DrIginai Signed by · 3. Amendment No. 48 to ibPR-68 4. Safety Evaluation 5. Notice cc: w/enclosures See next page 8112220a98 811 2 0 2 Disýybution: LDd'et File NRC PDR Local PDR

Docket Nos. 50-259 50-260 50-296

December 2, 1981

Mr. Hugh G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanooga, Tennessee 37401

/ �

Dear Mr. Parris:

The Commission has issued the enclosed Amendment Nos. 79 , 75 and 48 to Facility License Nos. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant, Unit Nos. 1, 2, and 3. These amendments consist of changes to the Technical Specifications in response to your request of May 15, 1981 (BFNP TS 163), as supplemented by your letter of July 13, 1981.

These amendments revise the administrative controls section of the Technical Specifications to reflect changes in the TVA and Browns Ferry Nuclear Plant organizations.

Copies of the Safety Evaluation and Notice of Issluance are also enclosed.

Sincerely,

DrIginai Signed by

L. L A. Ippolito I Kichard J. Clark, Project Manager Operating Reactors Branch #2 Division of Licensing

Enclosures: 1. Amendment No. 79 to DPR-33 2. Amendment No. 75 to DPR-52 3. Amendment No. 48 to ibPR-68 4. Safety Evaluation 5. Notice

cc: w/enclosures See next page

8112220a98 811 2 0 2

Disýybution: LDd'et File

NRC PDR Local PDR ORB#2 Reading D. Eisenhut S. Norris R. Clark OELD IE (4)

G. Deegan (12) 4. Se~ea-f I'U'-4

D. Brinkman ACRS (10) Clare Miles R. Diggs NSIC TERA ASLAB Gray File

A'�&�I

P PDR

S.... .... .............. . ....................... ........................ SUR A, ý i,........... ... . ............... I • .".' . .... ...... ..i...T.. ..... ... ... < • .• .. ........................ .........................

OT l/XD/ 81 1112,:)/81 ' 11 /81 1~ 81 ll/-36/81 D T . ....... I . .. .. ...-... . . P . ...... ... . .......R .....1.8...(.......0 ..... ....F. . . ..

NRG FORM 318 (10-80) NRCM 0240 O FFIC I AL R EC(rR D C OPY USGPO: 1981--33-5-960

MIr. -Hugh G. Parris.•

cc:

H. S. Sanger, Jr., Esquire General Counsel Tennessee Valley Authority

.. 400 Commerce Avenue E liB 33C Knoxville, Tennessee 37902

Mr. Ron Rogers Tennessee Valley Authority 400 Chestnut Street, Tower II Chattanooga, Tennessee 37401

Mr. Charles R. Christopher Chairman, Limestone County Commission

•P. 0. Box 188 Athens, Alabama 35611

-Ira L. Myers, M.D. State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36104

Mr. H. N. Culver 249A ;-D 400 Cc-Tmerce Avenue Tennessee Valley Authority Knoxville, Tennessee 37902

U. S. Environmental Protection Agency

Region IV Office Regional Radiation Representative 345 Courtland Street Atlanta-, Georgia 30308

Mr. Robert F. Sullivan U. S. Nuclear Regalatory Commission Route 2, Box 311 Athens, Alabama 35611

Mr. John F. Cox Tennessee Valley Authority W9-D 207C 400 C6fimerce Avenue Knoxville, Tennessee 37902

Mr. Herbert Abercrombie Tennessee Valley Arthority P. O. Box 2000 Decatur, Alabama 35602

Mr. Oliver Havens U.S. Nuclear Regulatory Commission Reactor Training Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411

Athens Public Library South. and Forrest -Athens, Alabama 35611

-" UNITED STATES NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555

TENNESSEE VALLEY AUTHORITY

DOCKET NO. 50-259

BROWNS FERRY NUCLEAR PLANT, UNIT NO. 1

AMENDMENT TO'FACILITY OPERATING LICENSE

Amendment No. 79 License No. DPR-33

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendments by Tennessee Valley Authority (the licensee) dated May 15, 1981, as supplemented by letter dated July 13, 1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;

B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;

C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering thehealth and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;

D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical. Specifications as indicated in the attachment to this 1-icense amendment and paragraph 2.C(2) of Facility License No. DPR-33 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

8112220604 811202 PDR ADOCK 05000529 P PDR

2

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Tihomas ýAChief Operating Reactors Branch #2 Division of Licensing

Attachment: Changes to the Technical

Specifications

Date of Issuance: December 2, 1981

ATTACHMENT TO LICENSE AMENDMENT NO. 79

FACILITY OPERATING LICENSE NO. DPR-33

DOCKET NO. 50-259.

Revise Appendix A as follows:

1. Replace the following pages with the identically numbered pages:

332 "335 336 337 346 358

'359 361 362 363 364

Marginal lines on the above pages indicate the areas being revised.

2. The overleaf pages are not being revised and should be retained.

.0 ~~lyIMM I ~1V co.;TLS~L

A,. The plant superintendent has on-site responsibilities for

thi safe operation of the facility and shall report to the Assistant

Director of Nuclear Power (Operations). In the absence of the

plant superintendent, an assistant superintendent will assume h i s r p onn n ts h il i t p c.

a. The portion of r1A manaaement which relates to the

operation of the plant is shown in Figure 6.1-1.

C. The functional organ'ization for the operation of the

station shall be as shown in Figure 6.1-2.

v. Shift manning requirements shall# as a minimum, be as

described in section 6.8.

E. Qualifications of the Browns Ferry Nuclear Plant

management and operating staff shall meet the minimum

acceptable levels as described in ANSI - N18.1,

Selection and Training of Nuclear Power Plant Personnel.

.dated March 8, 1971. The qualifications of the-Health Physics

Supervisor will meet or exceed the minimum acceptable levels as

described in Regulatory Guide 1.8, Revision 1, dated Sept. 1975.

F. Retraininq and replacement tra-ining of station-personnel

shall be in accordance with ANSI - N18.1, Selection and

Traininq of Nuclear Power Plant Personnel, dated March

8, 1971. The minimum frequency of the retraining

proqzam shall be every two years.

0. An industrial security Program shall be maintained for

the life of the glant.

F. The Safety Engineer shall have the following qualifications:

a. Must have a sound understanding and thorough technical

knowledge of safety and fire protection practices,

procedures, standards, and other codes relating to

electrical utility operations. Must be able to read

and understand engineering drawingS. Must possess an

analytical ability for problem solving'and data analysis.

Must be able to communicate well both orally and in

writing and must be able to write investigative reports

and prepare written procedures. Must have the ability

to secure the cooneraticn of management, employees and

groups in the implementation of safety programs. Must

be able to conduct safety presentations for supervisors

and employees.

b.. Should have experience in safety engineering work at this

level or have 3 years experience in saiety and/or fire

protection engincering. It is desirable that the

itncu-bent be a graduate of an accredited college or

university with a degree in inductriall, mechanical,

electrical, or safety engineering or fire protection

engineering. 332

Amendment No. 79

6.0 Aj3tMNI-T,%A7IVE CONTROLS

B. "Plant Operations Review Committee (PORCI

1. Membership

The PORC shall consist of the plant superintendent, or his representative, electric maintenance section supervisor; mechanical maintenance section supervisor, instrument maintenance section supervisor, health physics supervisor, operations section supervisor, engineering section supervisor, and quality assurance supervisor. An assistant plant supervisor may serve as an alternate committee memeber when his supervisor is absent.

The plant superintendent will serve as chairman of the PORC. His representative will serve as chairman in the absence of the plant superintendent.

2. Meetina Freaue cy

The PORC shall meet at regular monthly intervals and for special meetings as called by the chairman or as requested by individual members.

3. Qorum

Superintendent or his representative, plus five of the seven other members, or their alternate, will constitute a quorum. A member will be ccnsidered present if he is in telephone communication with the committee.

335

Amendment No. 79

6.0 ADMINISTRATIVE CONTROLS

The PORC serves in an advisory capacity to the plant superintendent and as an investigating and reporting body to the Nuclear Safety Review Board in matters related to safety in plant operations. The plant superintendent has the final responsibility in determining the matters that

should be referred to the Nuclear Safety Review Board.

The responsibility of the committee will include:

a. Review all standard and emergency operating and maintenance instructions-and any proposed revisions thereto, with principal attention to

provisions for safe operation.

b. Review proposed changes to the Technical Specifications.

C. Review proposed changes to equipment or systems having safety significance, or which may constitute "an unreviewed safety question," pursuant to 10 CFR 50.59.

d. Investiqate reported or suspected incidents involving safety questions, violations of the

Technical Specifications, and violations of

plant instructions pertinent to nuclear safety.

e. Review reportable occurences, unusual events,

operating anomalies and abnormal performance of plant equipment.

f. Maintain a general surveillance of plant activities to identify possible safety hazards.

g. Review plans for special fuel handling, plant

maintenance, operations, and tests or experiements which may involve special safety

considerations, and the results thereof, where

applicable.

h. Review adequacy of quality assurance program

and recommend any appropriate changes.

i. Review implementatinq procedures of the Radiological Emergency. Plan and the industrial Security Program on an annual basis.

-336

Amendment No. 79

• -..-,.I •"CONr~t ROL.S

* |(,vi,.w I(dL4UdCy. of employee traininq proqrans

.ind t' commend chanqe.

t. Au.hotr i ýt_

Tne PORC shall be advisory to the plant

superintendent.',

6. Records

Minutes shall be kept for all PORC meetings with

copies sent to Director, Nuclear. Power; Assistant Director of Nuclear Power (Operationsl; Chairman, NSRB

7. Procedures

written administrative procedures for committee

operation shall be prepared and maintained

describinq the method for submission and content of

presentations to the committee, review. and approval

by members of committee actions, dissemination of

minutes, agenda and scheduling of meetings.

337

Amendment No. X, 79

U A, 1X4 1tJ. .;TIrIT V COITPOLS

6.'q Actions to be Taken in the Event of eortbl Occurrence

in Plant Operation (Ref. Section 6.7)

A. Any reportable occurrence shall be promptly reported to

the Assistant Director, Nuclear Power' (Operations) and shall be

promptly reviewed 1>y PORC. This jcmmittee shall prepare

a separatc report'for each reportable occurrence. This

report shall iniclude an evaluation of the cause of the

occurrence and recommendations for appropriate action to

prevent or reduce the probability of a repetition of the

occu rrence.

B. Copies of all such reports shall be submitted to the

Assistant Director, Nuclear Power (Operations), the Manager of Power, and the

Chairman of the NSRB for their review.

C. The plant superintendent shall notify the NRC as

specified in Specificationf6.7 of the circumstances of

any reportable occurrence.

6.5 Action to be Taken in the Event a Safetyis Exceeded

If a safety limit is exceeded, the reActor shall be shut down

and reactor operatioSn shall not be resumed until authorized

by the N RC. A prompt report shall b-1 mzide to the Assistant

Director, Nuclear Power (Operations), and the Chairman of the NSRB. A

complete analysis of the circumstances leading up to dcnu

resulting from the situation, together with recommendations

to px.Žvent a recurrence, shall be prepared by the POFC. Thi s

report shall be submitted to the Assistant Director, Nuclear Power (Operations),

the Manager of Power, arid the NORB. Notification of such occurrences

•iII be made to the NRC by the plant spperintendent within 24

hours.

6.6 -tistion op at. -rinq :corTds

A. Records and/or 10gs shall be kept in a in•inner convenie2nt

for review as indicated below:

I. All normal plant ol.*xration including such items ýE

power level, fuel exposure, and nhutdo-,ns

2. Princi-pal maintenance activities

3. Peeportable o-currences

346

Amendment No. 79

... ' AD,4t .1 *T A'1 IVE (:fr!4TROLS

6.8 Minimum Plant Staffing

The minimum plant staffing for monitoring and conduct of

operations is as follows.

1. A licensed senior operator shall be present at the site

at all times when-there is fuel in the reactor.

2. A licensed operator shall be in the control room

whenever there is fuel in the reactor.

3. A licensed senior operator shall be in direct charge of

a reactor refueling operation; i.e., able to devote full

time to the refueling operation.

4. A health physics technician shall be present at the

facility at all times there is fuel in the reactor.

5. Two licensed operators shall be in the control room

during any cold startups, while shuttinq down the

reactor, and during recovery from unit trip.

6. Either the plant superintendent or an assistant pl2nt superintendent shall have acquired the experience and

training normally required for examination by the NRC

for a Senior Reactor Operator's License, whether or not

the examination is taken. In addition, either the

operations supervisor or the assistant operations

supervisor shall have an SRO license.

358.

Amendment No. 1T< 79

I (THIS PAGE INTENTIONALLY LEFT BLANK)

359

Amendment No. 79

%, -"

, Manager

of

Power Operations

Division of

Nuclear Power

Nuclear

Plants

a--

BROWNS FERRY NUCLEAR PLANT FINAL SAFETY

ANALYSIS REPORT

TVA Office of Power Organization for

Operation of Nuclear Plants

F.GTTR. 6L 1-1Amendment No. 79

Manager

of

Power

361

0

I I'~s

I BI -ECC-TOR

I I L. . . . _

I F

MEDICAL L - I

I IIEALT I I PYsI CS I

L__ _

0'

7 ~ TEST ')';IT :: ::. " '; + .. J .. '..

. L. r .., y" Tri .'

rF "SECURITY I

r - --. --"

4I POWER I S1IORES

T RA I I ' :G~ SIlP[ v I SOR I

L - -----

- Indicates functional reportln-

Figure 6.1-2

(

I P*I'. LI

(

Quality Assurance and

Audit Staff 1 -'a

Manager

of

Power Operations

Division

of

Nuclear Power

Nuclear Plant

Superintendent

Nuclear Safety

Review Board

Plant Operations

Review Conmitte

363Amendment No. 79

Manager of

Power

I

REVIEW AND AUDIT

FUNCTION

FIGURE 6.2-1

UPZAXT rXVM POCRkN OUM7IZATI0 BOO P73k? NIXLK PLAJN?

Assistant Power Plant Has been delegated the responsibilit': Superintendent for overall. ndministration oF the

plant fire protection and prevention program in accordance with approved standards and practices as adopted for plant needs.

Safety Engineering Supervisor

P lan~t Opeations iiuperviaor

]

I1

Plant hmrmency Director (or-Duty Shift zomineer)

Provides conaultation to planl. magment on all fire ssety matters; coordinates and evaluates testing, mintarance, aM repair of a~l

fir1e-relat equipment mid systes; conducts periodic safety and tire Inspections to identify deficiencis and recmmnds corrective actions; conducts fire trining-and evaLuates fire drills; provides on-the-scene advice to fire brigade leaders duing fire emergencies as epplionbi. Interpret and evaluate requirementa for control

of t'ansieent fire loads. Reviews pre-fire plans and mergency planning docuents. Participates in establishing mitual aid agreoents. Provides surveillance of cuttisng, welding and Opflaw work controls. Coordinates fire safety matters as required vith Sfoety Enginering Services.

Responsible for OpraiaiMP aRn training the pleat tire brlgade; proe.ur: needed firefiehtiew eiuisiaent ano cuppliep. coordInates arranreqnts for mtual aid reir"ws work plano for fire potentials anad Initates as late cntrols; reviews and . .al t.. the status Of fire protection and detection systoss; Lad remains cogninet of systemas roanvd fr•m service Lot Interim controls placed In effect.

I

Plant Fire nritade .•ela"r

(Ass•i.nd Annt. ihift En.r. €n1hnty)

rPlart Fire Arind.e MNserm .a (Assir'Od Plant)

Ptnet Fir. Watches

Responsible for Iaplementation of amermency plans If needed onshift; Provides control aol sinXle point of contact for all conting• cies; attends Fire Rriemde Leader Course every 5 years; conducts n•-shift briefin$s of fire bripade and initiates Periodic fire drills; end controls valding. euttin,. amd ceon flame work.

Hesr-lble fer ontrol snA rerforeae• of fire NbodýArinpf dunn. nrcetenrl..5; Cond-si n-shirt hniefinom Cf hrlpsde aeel-cre; roviowi rronrc plans ^n -e0-y rlinniý. d-.,nts; raaatin conizrant or Diant rtre toad status. fire -ysteas and e'rilosent n work activities havin. fIre Potentials; senm attends Fire Brioade leaer Course eve&ry Years.

Responsible ro r s)cnt firef"i'ht.in activities; atten• Tlant fire trainilng curses evrh ye•a•r; a&Mi are repetuiible for knowirP brirain asaj.;res.nto in re-rdane. with plant fre plan.

J Oniucts roving fire ratrols on a regularly assined basis; responsible for detectine and reportine fire hasarda and initiating first aLid firef•aNtin If needed; and will be .lteed On clock m*is6teTr until all .l•aned lixed fire I et s are Inatalle4 and operable.

3 64Fliwee b.3-1

Amendment No. 79

-H

I !

i

I

I

-"%UNITED STATES NUCLEAR REGULATORY COMMISSION



DOCKET NO. 50-260


AMENDMENT TO FACILITY OPERATING LICENSE



A. The application for amendments by Tennessee Valley Authority (the licensee) dated May 15, 1981, as supplemented by letter dated July 13, 1981, complies with the standards and requirements *of the Atomic Energy Act of 1954, as amended (the'Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;

B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission;

C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the *public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;

D. The issuance of this amendment will not.be inimical to the common defense and security or to the health and safety of the public; and

E. The issuance of this amendment is in accordance w ith 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is. amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facility License No. DPR-52 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 75, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.



'=ThmsX poltChief

Operating. Reactors Branch #2 Division of Licensing


Specifications


ATTACHMENT TO LICENSE AMENDMENT NO. 75


"DOCKET NO. 50-260


1. Replace the following pages with the identically numbered pages:

332 335

"* - 336 337 346 358 '359 361 362 363 364

Marginal lines on the above pages indicate the areas being revised.

2. The overleaf pages are not being revised and should be retained.

61.0 &0M1It~1X-4A1wrV! CO.-;TUOLS

The plant superintendent has on-site responsibilities for

thi safe operation of the facility and shall report to the Assistant

Director of Nuclear Power (Operations). In the absence of the plant superintendent, an assistant superintendent will assume hiA. rPmnn.q1.hlitien.

. The portion of TA manaoement which relates to the operation of the plant is shown in Figure 6.1-1.

C. The-,-functional organization for the operation of the stationý_shall be as shown in Figure 6.1-2.

0. Shift manning requirements shall, as a minimum, be as


z. Qualifications of the Browns Ferry !4uclea-r Plant management and operating staff shall meet the minimum acceptable levels as described in ANSI - N18.1, Selection and Training of Nuclear Power Plant Personnel., dated March 8, 1971. The qualifications of the Health Physics Supervisor will meet or exceed the mininum acceptable levels as described in Regulatory Guide 1.8, Revision 1, dated Sept. 1975.

F. Retraining and replacement training of station personnel shall be in accordance with ANSI - N18.1, Selection and Traininq of Nuclear Power Plant Personnel, dated MarCh 8, 1971. The minimum frequency of the retraining proqzam shall be every two years.

0. An Industrial Security Program shall be maintained for the life of the plant.

H. Thd Safety Engineer shall have the following.qualffications:

a. Must have a sound understanding and thorough technical knowledge of safety and fire protection practices, procedures, standards, and other codes relating to electrical utility operations. Must be able to read and understand engineering drawings. Must possess an analytical ability for problem solvingand data analysis. Must be able to communicate well both orally and in writing and must be able to write investigative reports and prepare written procedures. Must have tOe ability to secure the coooeration of management, employees and groups in the implementation of safety programs. Must be able to conduct safety presentations for supervisors and employees.

b.. Should have experience in safety engineering work at this level or have 3 years experience in safety and/or fire protection enaincering. It. is desirable that the incumbent be a graduate of an accredited college or university with a degree in inductrials mechanical, electrical, or safety engineering or fire protection engineering. 332

Amendment No. ,.K 75

6.n ADMINIT'TRJ7.IVE CONTROLS

B. Plant Operations Review Committee IPORCI

1. Membership

The PORC shall consist of the plant superintendent, or his representative, electric maintenance section supervisor; mechanical maintenance section supervisor, instrument maintenance section supervisor, health physics supervisor, operations secf6n supervisor, engineering section supervisor, and quality assurance supervisor. An assistant plant supervisor may serve as an alternate committee memeber when his supervisor is absent. The plant superintendent will serve as chairman of the PORC. His representative will serve as chairman in the absence of the plant superintendent.

2. Meeting Frequency

The PORC shall meet at regular monthly intervals anr for Special meetings as called by the chairman or as requested by individual members.

3. uoruo

Superintendent or his representative, plus "five of the seven other members, or their alternate, will constitute a quorum. A member will be c-cnsidered present if he is in telephone communication with the committee.

335

Amendment No. 75


The I(HC serves in an advisory capacity to the plant superintendent and as an investigating and

reporting body to the Nuclear Safety Review Board

in matters related to safety in plant operations." The plant superintendent has the final responsibility in determining the matters that

should be referred to the Nuclear Safety Review Board.


a. Review all standard and emergency operating and maintenance instructions-and any proposed revisions thereto, with principal attention to provisions for safe operation.


C. Review proposed changes to equipment or systems having safety significance, or which may constitute "an unreviewed safety question," pursuant to 10 CFR 50.59.

d. Investiqate reported or suspected incidents involving safety questions, violations of the

Technical Specifications, and violations of

plant instructions pertinent to nuclear safety.

e. Review reportable occurences, unusual events,

operating anomalies and abnormal performance of plant equipment.


g. Review plans for special fuel handling, plant

maintenance, operations, and tests or experiements which may involve special safety

considerations, and the results thereof, where applicable.

h. Review adequacy of quality assurance program and recommend any appropriate changes.

i. Review implementatinq procedures of the Radiological Emergency. Plan and the Industrial Security Program on an annual basis.

.336

Amendment No. 75

j. )t(qvi#*w j.L.4u•dcy. of employee traininq proqraus

.and trrcommend chanqe.

S. Authority

Tne roýC shall be advisory to the plant

ruperintendent.',.

6. Records

.minutes shall be kept for all PORC meetings with

copies sent to Director, Nuclear Power; Assistant

Director of Nuclear Power (Operationsl; Chairman, NSRB

7. Procedures

written administrative procedures for committee operation shall be prepared and maintained describinq the method for submission and content of

presentations to the committee, review and approval Iy members of committee actions, dissemination -of

minutes, aqenda and scheduling of meetinqs.

337

Amendment No. X, 75

Amendment No. 75

6.4 Actipns to be Taken in the Event of aReportablc Occurrence

in Plant Operation(Ref. Section 6.7)

A. Any reportable occurrence shall be promptly reported to

the Assistant Director, Nuclear Power (Op erations) and shall be

promptlyreviewed by PORC. This committee shall prepare

a separatcý-reportsfdr each reportable occurrence. This

report shall include an evaluation of the cause of the

occurrence and recommendationis for appropriate action to

prevent or reduce the probability of a repetition of the

occu rrence.


Assistant Director, Nuclear Power (Operations), the Manager of Power, and thie

Chairman of the NSRB for their review..

C. The plan-, superintendent shall notify the NRC as

specified in Specification 6 . 7 of the circumstances of


6.5 Action to be Taken in the Event a safetvyLi.mit is Exceeded

If a safety limit is exceeded, the reactor shall bc shut down

and reactor operation shall not be resumed until authorized

by the 1JRC. A prompt report shall be inade t.o thte Assistant


complete a;ialysis of the circumstances lealing up to d.LnU


to pi event a recurrence, shall be prepared by the PORC. This


the Manager of Power, arid the NSRB. Notification of such occurrences

•i1l be made to the NRC by the plant superintendent within 24

hours.

6.6 5•tittion o0 ratirico:'cords

A. Records and/or loqs shall be kept in a in.uiner conveni.2nt

for review ds indicated below:

1. All normal plant oL.!ratiun including such items ýc

power level, fuel exposure, and .hittdo•-nS

2. Princiýpal maintenance activities

3. Reportable oc"currences

346

1

,�.') I il , 't! •-A. I VE_:f(-fTl--JLs


The minimum plant staffing for monitoring and conduct of



at all times when- there is fuel in the reactor.

2. A licensed operator shall be in the control room

whenever there is fuel in the reactor.


a reactor refueling operation; i.e., able to devote full

time to the refueling operation.


facility at all times there is fuel in the reactor..

5. Two licensed operators shall be in the control room

durinq any cold startups, while shuttinq down the

reactor, and durinq recovery from unit trip.

6. Either the plant superintendent or an assistant plnt.

superintendent shall have acquired the experience and

traininq normally required for examination by the NRC


the examination is taken. In addition, either the

operations supervisor or the assistant operations

supervisor shall have an SRO license.

358.

Amendment No. -es 75

(THIS PAGE TiTENT•IONALLY LEFT BLANI)

359

Amendment No. 75

I

Manager

of

Power

lianager

of

Power Operations

Division of

Nuclear Power

Nuclear

Plants

361Amendment No. 75


ANALYSIS REPORT



FIGURE 6.1-1

a -- a r

I I� I � ii=un

I � II Z�-, I S ii � I �.fl c

I II I

Amendment No. 75

1.4J

��1 I j

� I 62C

-� x:; I a ra. I C. I �

Ze

r

C *1'� J.J 1" 0 Ca. C, Is

- N w 0 - C A.; U W C I*'

Id-I &

'C � CI 4-' C U

-4

C a-.

Quality Assurance and

Audit Staff I---

Nuclear Plant

Superintendent

Plant Operations

Review Comnitte

363Amendment No. 75

a.--

REVIEW AND AUDIT| FUNCTION

FIGURE 6.2-1

i I

N-'

il1-711M TilW PINRPJN ~OWMrflA?? -PM POW MlWPAR "lART

Has been delegated the responsibil itfor overall ndminfistration oF the plant fire protection and prevention program in accordance wit1' approved standards and practices as adopted for pl'ant needs.

HSafety Engineering Supervisor

-d Plan~t Dprations %lpsrvisor

-I plant ftergency, Director tOn.-Dtw Marft butimeer)

pr*Vides cooAwltationk tU p.lsn' manamgnt on a&l fire safety meLttara cooedlaat" and oevluates testirie, manitenance. and repair Of sall fire-related squiposot and systaem.; conducts periodlc safety and fire Loapectionsa to id~tMf deficiencias and recomin5d correetive

aioscnducts fty. training, ad evaLuates fixe duills; prolides oa-the-beena advice to fire brigade leaders duting firs emergencies as applmmible. Interpret and evaluate requlirements for control of transient fire loads. Rafiewa pre-fire plane and mnrgency Planning documents. Partlcipates In establIsIaL mutual aid agreemets. prorrihea surveillance of cutting. velding. and openflaew work CootroLa. Coordinates tire Safety mattere an requited ,ib safety &Dsineering Servicea.

I GPResosble for OPPenisimi' and tratiningt the Plant tire brnead.; Proewrineeded riretightimi equigpesnt amd qOppliv6e; eordI"eteg sfra~wenta for mutual Rid, revewes work nians for ?Ire potentaias s&M Initiates appropriate controls; reviews and evaluates ith states or tlvz protection and detectOA systems; and ranging cognimeot of syetems eQMMed from aservice Sol Interim controla placed in affect.

J Uscalesble for Implementation of .wrgescy giant if needed on.. shirt. provides control &el single point of contact for all co~itingenelese attands Fire lIgatin leade~r Cours. every 5 YVas4, conducts on-shift biiefiiss of fire brip~ade and initiates

daiode fire 4rilis; and controls vedldt,. euttim. and owen flame work.

Sesrenalbi -tt-t r Anei n pr*feonn ot fir. fteiedn,, "M CIT stpwroeie.; C~.W~ts

shit tr~ein~ethrlp.Aei eassist; rt-9es prrtie ian a, erey panni., 6deR~iets;

remains Cnnnifant or giant fire load statue, fire sstemss and mduiveoet &ad work act 1eities liavin fire notentlals; amd attends Fire Dricade, [e~.r Cureaevrt" 5 years.

Reeneshlefnrplet trelW'htAlnn aetinitles; attndplnt tire trikint,, roirses ench .' Years;

Wd ^rer ermneible fc.r ltovrein tirinae mats.ln. 0@nto in mirr.1nce with p'lant fire plan.

I Plant 'ire flrigelan d er

Plant Fire Prniad. iimbers (AR.1 "'d Plant)

Plant Pit. Uat.chearorelstt. retIna fire patrols On a wecularly asasirnd basis.

r Pree imible for detecting &Md eportin tire hazalda and Iitlatiatw first aid fi~reiahtia, if seeded: and will be Cslaced on clock registers until all slaifted 'iced fire mwt -s are installed and overebl&.

rVid're b-3-1

Amendment No. 75

9.

I I

I

I

i

-O UNITED STATES NUCLEAR REGULATORY COMMISSION



DOCKET NO. 50-296


AMENDMENT TO FACILITY OPERATING LICENSE



A* The application for amendments-by Tennessee Valley Authority (the licensee) dated May 15, 1981, as supplemented by letter dated July 13, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (theAct), and the Commission's rules and regulations set forth inlO CFR Chapter I;

B. The facility will operate in conformity With the applicationr_the provisions of the Act, and the rules and regulations of.he Commission;

C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;

D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and

E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C(2) of Facili ty License No. DPR-68 is hereby amended to read as follows:

(2) Techni cal S peci fications

The Technical Specifications contained in Appendices A and B, asrevised through Amendment No. 48, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

2



Thomashief Operating Reactors Branch #2 Division of Licensing


Specifications


ATTACHMENT TO LICENSE'AMENDMENT NO 48


DOCKET NO. 50-296-


1. Remove the following pages and replace with the identically'numbered pages:

362 365 366 367 376

,388 389 391 392 393 394

2. Marginal lines on the above pages indicate the areas being changed.

a.-

I

Amendment No. /, 48 6

The plant superintendent has on-site responsibilities for

the safe operation of the facility and shall report to the Assistant

Director of Nuclear Power (Operations). In the absence of the

plant superintendent, an assistant superintendent will assume his annhite.

B. The portion of r;A manaqement which relates to the

operation of.the plant is shown in Figure 6.1-1.

C. The functional organization for the operation of the

station shall be as shown in Figure 6.1-2.

O. Shift manning requirements shall, as a minimum, be as


E. QUalifications of the Browns Ferry Nuclear plant

management and operating staff shall meet the minimum

acceptable levels as described in AM;SI - N18.1,

selection and Training of Nuclear power Plant Personnel.

dated March 8, 1971. The qualifications of the Ilealth Physics

supervisor will meet 'or exceed the mininum acceptable levels as

-described in Regulatory Guide 1.8, Revision 1, da'ted Sept. 1975.

F. Retraining and replacement training of station personnel

shall te in accordance with ANSI - N18.1, Selection and

Traininq of Nuclear Power Plant Personnel, dated March

8, 1971. The minimum frequency of the retraining

proqxam shall be every two years.

G. An industrial Security Program shall be maintained for

the life of the plant.

H. The Safety Engineer shall have the following qualifications:

a. Must have a sound understanding and thorough technical

knowledge of safety and fire protection practiceS,

procedures, standards, and other codes relating to

electrical utility operations. Must be able to read

arid understand enginpering drawings.

362

6.n Aý)MINIFTrA7IVE CONTROLS

E. Plant Operations Review Committee fPORCI

1. Membership

The PORC shall consist of *the plant superintendent, or his

representative, electric maintenance section supervisor, mechanical

maintenance section supervisor, instrument maintenance section supervisor, health physics supervisor, operations secti6n

supervisor, engineering section supervisor, and quality assurance

supervisor. An assistant plant supervisor may serve as an alternate committee memeber when his supervisor is absent.

The plant superintendent will serve as chairman of the PORC. His representative will serve as chairman in the absence of the plant superintendent.

2. Meetinc Frequentc The PORC shall meet at regular monthly intervals

and for special meetings as called by the chairman or as requested by individual members.

3. Q orum

Superintendent or his representative, plus

five of the seven other members, or their alternate. will constitute a quorum. A member will be considered present if he is in telephone communication with the committee.

365

Amendment No. /, 48


4.

The PORC serves in an advisory capacity to the plant superintendent and as an investigating and reporting body to the Nuclear Safety Review Board in matters related to safety in plant operations. The plant superintendent has the final responsibility in determining the matters that. should be referred to the Nuclear Safety Review Board.


a. Review all standard and emergency operating and maintenance instructions and any proposed revisions thereto, with principal attention to provisions foe safe operation.


c. Review proposed changes to equipment or systems having safety significance, or which may constitute "an unreviewed safety question," pursuant to 10 CFR 50.59.

d. Investiqate reported or suspected incidents involving safety questions, violations of the Technical Specifications, and violations of plant instructions pertinent to nuclear safety.

e. Review reportable occurences, unusual events, operating anomalies and abnormal performance of plant equipment.


g. Review plans for special fuel handling, plant maintenance, operations, and tests or experiements which may involve special safety considerations, and the results thereof, where applicable.

h. Review adequacy of quality assurance program and recommend any appropriate changes.

i. Review implementating procedures of the Radiological Emergency Plan and the Industrial Security Proqram on an annual basis.

.366

Amendment No. /, 48

. I0OV.:j-.,rMTV oN•. - V rROLS

j. H,'vi,:w ,,glegfudcy o employee traininq proqrams

,,nd• recommend chanqe.

C5. Authority

Tne POPC shall be advisory to the plant

qsuperintendent.',

6. Records

Minutes shall be kept for all PORC meetings with

copies sent to Director, Nuclear Power; Assistant

Director of Nuclear Power (Operationsl; Chairman, NSRB

7. Procedures

written administrative procedures for committee operation shall be prepared and maintained describinq the method for submission and content of

presentations to the committee, review and approval

ty members of committee actions, dissemination of

minutes, aqenda and scheduling of meetings.

367

Amendment No. X, 48

I

1.

,,.0 _LJJN I•Tw,'rI V? .-. CO.NTROLS ED. U LI Yj'_q0iL M

6.4 A~ctioDns to be Taken in the Event of a Reportable Occurrence

in Plant n Oeration (Ref. Section 6.7)

A. Any reportab.le occurrence shall be promptly reported to

the Assistant Director, Nuclear Power (operations) and shall be

promptly reviewed by PORC. This committee shaLl prepare

a separate report foi- each reportable occurrence.. This

report shall include an evaluation of the cause of the

occurrence and recommendations for appropriate action to

prevent or reduce the probability of a repetitiofn of the

occu rrence.


Assistant Director, Nuclear Power (Operations), the Manager of Power,

and the

Chairman of the NSRB for their review.

C. The plant superintendent shall notify the NRC as

specified in Specification 6.7 of the circumstances of


6.5 Action to be Taken in the Event a Safety Lim__it is Exceeded

If a safety limit is exceeded, the reactor shall be shut down

and reactor operation shall not be resumed until authorized

by the URC. A prompt report shall be made to the Assistant


complete analysis of the circumstances Lea-ing up to dUIU


to prevent a recurrence, shall be prepared by -the PORC. This


the Manager of Power, arid the ISRB Notification of such occurrences

will be made to the NRC by the plant superintendent within 24

hours.

6.6 nt..ration OPratinq P*hCords

A. Records and/or logs shall be kept in a intiiier convt'ni.nt

for review as indicated below:

1. All normal plant operation including such ite:7 as

power level, fuel exposure, and shuti.,c ;ns

2. principal maintenance ac'tivities

3. Feportable co-cuirrr-ecs

376

Amendment No.X, 48

6.f) AUM•?I1.;-:PA-IIVE CONTROLS


The minimum plant staffing for monitorinq and conduct of



at all times when'there is fuel in the reactor.

2. A licensed operator shall be in the control room whenever there is fuel in the reactor.


a reactor refueling operation; i.e., able to devote full time to the refueling operation.


facility at all times there is fuel in the reactor.

5. Two licensed operators shall be in the control room durirnq any- cold startups, while shutting down the reactor, and during recovery from unit trip.

6. Either the plant superintendent or an assistant plant

superintendent shall have acquired the experience and

training normally required for examination by the NRC


the examination is taken. In addition, either the operations supervisor or the assistant operations supervisor shall have an SRO license.

388

Amendment No. /, 4 48 "

I

-9

(THIS PAGE INTENTIONALLY LEFT BLANK)

389

Amendment No. 48


ANALYSIS REPORT



FIGURE 6.1-1

391 Amendment No. 48

I L n

I ~'z~sE J

MEI~DICAL I

IHEALTH I.I PHYS ICS I

"U.UERA. O TEST UN~IT

SECURITY I

-4 POWER I I STORES I L JkT2A 1I'-IG

S'I'Rv I SOR I

(

-I

-J

I

(

-Indicates functional reporting

rigure 6.1-2

ENG I I: E I P I MG-

Manager

of'

Power

, Manager

of

Power Operations

Division

of

Nuclear .Power

Nuclear Plant

Superintendent

Plant Operations

Review Committe

393

Amendment No. 48

Nuclear Safety

Review Board

REVIEW AND AUDIT

FUNCTION

FIGURE 6.2-1

M-M FrM •PWA• PtAnA

Has been delegated the responsibility for overall administration of the plant fire protection and prev-ention program in accordance with approved-standards and practices as adopted for plant needs.

H Safety Engineering Supervisor

I riaMt Operatiaos .qiuevsor I

-1 Plant asergency Director (on-Duty 3hift w-•reer)

Provide$ conssMIt&tIn to plSA" NgmWn ent on Oi fire safety atters;

coordinates snd evituaes testing, eaintanahce, en repair of sal

fire-relAted eqliphent TAn systeMS; conducts periodic safety and

fire Inspections to identify deficiencies and reccUMM.d. corrective

actiomn; conducts fire training end evaluates fire dris; provides

on-tbe-scene a4vice to fire brigade leaders during fire emergencies

as "pplaoble. Interpret end evaluate requirement•t fo control

of tranlegt fire oeds. Reviews pro-fire plans end ergefncy

pleaning ocment. Pas-rticipates in esxtblitiing mutual. id

egreements. Provides surveiflhnce of cutting, welding, and open

ame rk contr- a. Coordinate fire safety matters as reqU••d

with Safety Engineering Services.

Rvipo slble for orsItiin. arid training the plant ftire brigade; procure:

needed firefighting ealPsent "Ad .,urpli•s; coordinates arrsosaents

for vsutl aid; reviev work .plan, for fire Potentials ant initiates

aPpropriate controls; review. ant .vhi,,atehsb status of fire protection and detecon systes; and rensain cognizant of systin

rcoved lfrom service sd interim, controls placed in effect.

Responsible for Implemntation of emerency Plans if needed onshift; -provides control end single point of contact for all

contingencies; attends Tire Arigade leader Course every 5 yearst

conducts on-shift brlefirgs of fire brigade sad initiates

Periodic fire drills; and controls velditn. cutting. sd oPeen

flams work.

P'lant Virt friesde •eader

(Assirtned Anst. Shift Flwr. On-Duty)

Plant Fire nrigede Mesbers (As€inn ., Plant)

-A Plant ?Ie Watches

Responsible for cntrol end aTerforToe. of rtre -rivae durim fire meerr#ecls; cond•wts n-.

shift hrtefinrs nf hrirsae snetr.; rvievse pry

fire p)Lsne saw .. rerncf Pianninn, dnrsseeta; reai.ns concizant of okant fire toed sIttus, fire

systes. and equipment and work activities havim

fire Potent&lst; and attends rire Brlade 1ader Course every 5 Years.

Responsthie for plant rirerihtln, etivitles:

attend plant fire training rafrses each .' years;

and are renpn.nihie T.r Wnoeinr bri.tai asl,.rn i In anrrdanev with plant ri- pn,,.

fr~osucts roving fire Petrols on a recularly asslened basis. responsible for detecting and reporting 'fire hatards and

Initiating first aid firefighting If needed. and vill ts Placed on clock registers until all Planned fIed fire

stal are Instlled and operable.

% Figure 6. .3

Amendment No. 48

.1

I D

L7_Ig

I -

I

II

I

I

0• UNITED STATES 0 ,NUCLEAR REGULATORY COMMISSION


SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

SUPPORTING AMENDMENT NO. 79 TO FACILITY OPERATING LICENSE NO. DPR-33

AMENDMENT NO. 75 TO FACILITY OPERATING LICENSE NO. DPR-52

AMENDMENT NO. 48 TO FACILITY OPERATING LICENSE NO. DPR-68


BROWNS FERRY NUCLEAR PLANT, UNIT NOS. 1, 2 AND 3

DOCKET NOS. 50-259, 50-260 AND.50-296

1.0 Introduction

By letter dated May 15, 1981 (TVA BFNP TS 163) and supplemented by letter dated July 13, 1981, the Tennessee Valley Authority (the licensee or TVA) requested changes to the Technical Specifications (Appendix A) appended to Facility Operating License Nos. DPR-33, DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Unit Nos. 1, 2 and 3. The proposed amendments 4pd revised Technical Specifications would revise the administrative coinirols section of the Technical Specifications to reflect changes in the TVA and Browns Ferry Nuclear Plant (BFNP) organizations.

2.0 Discussion and Evaluation

The proposed changes only-involve Section 6.0 (the Administrative Controls section) of the Technical Specifications. A thorough discussion and justification for each change was provided by TVA in their submittals referenced above. We have reviewed the changes and have concluded they are acceptable. A summary description of the changes is outlined below.

The proposed changes:

a. Reflect that TVA's Division of Power Production has been separated into-two divisions--the Division of Nuclear Power and the Division of Fossil and Hydro Branch. The former Nuclear Generation Branch is now the Division of Nuclear Power.

b. Following the March 22, 1975 fire an overall fire restoration coordinator position was established. The position was abolished when the restoration was completed. Reference to this position in the Technical Specification was deleted by Amendment Nos. 71, 68 and 43 issued June 18, 1981 except for one reference in Section 6.1.H.

c. There are about 1,000 people regularly at the BFNP associated with normal operation of the plant. In addition, there is in the order of 400 additional field service personnel at theplant to handle major maintenance and prepare for the modifications and overhaul work performed during refueling outages. During outages, the total work

8112220609 811202 i PDR ADOCK 05000259 P PDR

2

force on site can approach 3,000 people. Initially, BFNP had one assis'tant plant superintendent. In January 1981 a second assistant plant superintendent was added. Recently, a third assistant plant superintendent was authorized. Section 6.1 of the Technical Specifications is being revised to reflect this change. One assistant superintendent will be responsible for engineering and operations, another will be responsible for maintenance, and the third is responsible for health physics, safety, security, training and administrative services. The health physics organization is placed under the Health and Safety Services, Assistant PlantiSuperintendent. Thus, the Health Physics Supervisor reports to an'aisistant superintendent and is independent from plant operations. This is in accordance with the recommendations of Regulatory Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposure at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable" and NUREG-O731,-"Criteria for Utility Management and Technical Competence" and is acceptable. The quality assurance supervisor still reports directly to the plant superintendent; there is no change in this area.

d. Secti.on 6.2.B of the Technical Specifications lists the duties, functions and membership of the Plant Operations Review Committee (PORC). With the new organization, new section supervisors have been added and the titles for some groups have been revised. Section 6.2.B is being changed to revise the membership of the PORC consistent with thgeew plant organization.

e. The fire protection and prevention program was formerly under the Operations Supervisor. The change assigns responsibility for this program to the assistant plant superintendent for health and safety services.

None of the organizational changes outlined above will have an adverse effect on the nuclear or environmental safety of the Browns Ferry Nuclear Plant. We conclude the proposed changes are acceptable.

3.0 Environmental Considerations

We have determined that these amendments do not-authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that these amendments involve an action which is insignificant from the standpoint of environmental impact, and pursuant to 10 CFR Section 51.5(d)(4) that an environmental impact statement, or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of these amendments.

4.0 Conclusion

We have concluded based on the considerations discussed above that: (1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not

N.

3

involve a significant decrease in a safety margin, the amendments do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

Dated: December 2, 1981

`590-01

UNITED STATES NUCLEAR REGULATORY COMMISSION

DOCKET NOS. 50-259, 50-260 AND 50-296

- TENNESSEE VALLEY AUTHORITY

NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY

OPERATING LICENSES

The U.S. Nuclear Regulatory Commission (the Commission) has issued

Amendment No. 79 to Facility Qperating License No. DPR-33, Amendment No. 75

to Facility Operating License No. DPR-52, and Amendment No. 48 to Facility

Operating License No. DPR-68 issued to Tennessee -Valley Authority (the

licensee), which revised Technical Specifications for operation of the

Browns Ferry Nuclear Plant, Unit Nos. 1, 2 and 3 (the .facility) located

in Limestone County, Alabama. The amendments are effective as of the date

of issuance.

The amendments revise the administrative controls section of the

Technical Specifications to reflect changes in the Tennessee Valley Authority

and Browns Ferry Nuclear Plant organizations.

The application for the amendments complies with the standards and require

ments of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's

rules and regulations. The Commission has made appropriate findings as required

by the Act and the Commission's rules and regulations in 10 CFR Chapter I,

which are set forth in the license amendments. Prior public notice of these

amendments was not required'since the amendments do not involve a significant

hazards consideration.

The Commission has determined that the issuance of these amendments will

not result in any significant environmental impact and that pursuant to 10 CFR

8112220616 811202 PDR ADOCK 05000259 P PDR

7 )-Ol

2

§51.5(d)(41 an environmental impact statement, or negative declaration and

environmental impact appraisal need not be prepared in connection with issuance

of these amendments.

For further details with respect to this action, see (1) the application

for amendments dated May 15, 1981., as supplemented by letter dated July 13,

1981, (2) Amendment No. 79 to License No. DPR-33, Amendment No. 75 to License

No. DPR-52, and Amendment No. 48 to License No. DPR-68, and (3), the Commission's

related Safety Evaluation. All of these items are available for public

inspection-at the Commission's Public Document Room, 1717 H Street, N.W.,

Washington, D.C. and at the Athens Public Library, South and Forrest, Athens,

Alabama 35611. A copy of items (2) and (3) may be obtained upon request

addressed to the U.S. Nuclear Regulatory Commission, Washington, D.C.3-20555,

Attention: Director, Division of Licensing.

Dated at Bethesda, Maryland, this 2nd day of December 1981.


1ChiefIppolit o, Operating Reactors Branch #2 Division of Licen.sing,

Documents

DrIginai Signed by · 3. Amendment No. 48 to ibPR-68 4. Safety Evaluation 5. Notice cc: w/enclosures See next page 8112220a98 811 2 0 2 Disýybution: LDd'et File NRC PDR Local PDR