Palo Verde Station, License Amendments 97, 85, 68, Would ... · spent fuel pool and relocate includes two changes to A copy of the related Safety Evaluation is also enclosed. The

August 7, 1995 5

Mr. William L. Stewart Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999 Phoenix, Arizona 85072-3999

SUBJECT: ISSUANCE OF AMENDMENTS FOR THE PALO VERDE NUCLEAR GENERATING STATION UNIT NO. I (TAC NO. M92329), UNIT NO. 2 (TAC NO. M92330), AND UNIT NO. 3 (TAC NO. M92331)

Dear Mr. Stewart:

The Commission has issued the enclosed Amendment No. 97 to Facility Operating License No. NPF-41, Amendment No. 85 to Facility Operating License No. NPF-51, and Amendment No. 68to Facility Operating License No. NPF-74 for the Palo Verde Nuclear Generating Station, Unit Nos. 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications in response to your application dated May 2, 1995.

These amendments would remove from the Technical Specifications (TS) plant elevations for the minimum water required in the spent fuel pool and relocate them to site procedures. This TS amendment also includes two changes to correct administrative errors in the TS.

A copy of the Issuance will notice.

related Safety Evaluation is also enclosed. The Notice of be included in the Commission's next biweekly Federal Register

Sincerely, Original Signed By Charles R. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Docket Nos. STN 50-528, STN 50-529 and STN 50-530

1 . 2. 3. 4.

Enclosures:

cc w/encls:

DOCUMENT NAME:

Amendment No. 97 to NPF-41 Amendment No. 85 to NPF-51 Amendment No. 68 to NPF-74 Safety Evaluation

See next page

PV92329.AMD

DISTRIBUTION Docket File PUBLIC PDIV-2 Reading EAdensam JHannon WBateman CGrimes, 011E22 BHolian CThomas CMcCracken

/?11 •

KPerkins, WCFO (4) HWong, RIV GHill (6), T5C3 OC/LFDCB, T9E1O OGC, 015B18 OPA, 02G5 ACRS (4), T2E26 LHurley, RIV EPeyton

OFC PDIV-2/LA PDIV-2/PM.. PDIV-2/PM -9tt )b OGC

NAME EPeyton CThomas: BHolian w* q

DATE 7/G/95 7/0/95 7/1 ¢/95 7 /iIi/ 9 5 7/2 Q 95

9508140048 950807 PDR ADOCK 05000528 P PDR

RECORD COPY

NF� �-- I

UNITED STATES 0 NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555-0001

August 7, 1995

Mr. William L. Stewart Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999 Phoenix, Arizona 85072-3999

SUBJECT: ISSUANCE OF AMENDMENTS FOR THE PALO VERDE NUCLEAR GENERATING STATION UNIT NO. 1 (TAC NO. M92329), UNIT NO. 2 (TAC NO. M92330), AND UNIT NO. 3 (TAC NO. M92331)

Dear Mr. Stewart:

The Commission has issued the License No. NPF-41, Amendment and Amendment No. 68 to Facili Verde Nuclear Generating Stati amendments consist of changes your application dated May 2,

enclosed Amendment No. 97 to Facility Operating No. 85 to Facility Operating License No. NPF-51, ty Operating License No. NPF-74 for the Palo on, Unit Nos. 1, 2, and 3, respectively. The to the Technical Specifications in response tw 1995.

These amendments would remove from the Technical elevations for the minimum water required in the them to site procedures. This TS amendment also correct administrative errors in the TS.

Specifications (TS) plant spent fuel pool and relocate includes two changes to

A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

harles R. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Docket Nos. STN 50-528, STN 50-529 and STN 50-530

Enclosures: I. 2. 3. 4.

Amendment No. 97 to NPF-41 Amendment No. 85 to NPF-51 Amendment No. 68 to NPF-74 Safety Evaluation

cc w/encls: See next page

Mr. William L. Stewart

cc w/encls: Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street Phoenix, Arizona 85007

T. E. Oubre, Esq. Southern California Edison Company P. 0. Box 800 Rosemead, California 91770

Senior Resident Inspector USNRC P. 0. Box 40 Buckeye, Arizona 85326

Regional Administrator, Region IV U. S. Nuclear Regulatory Commission Harris Tower & Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064

Chairman, Maricopa County Board of Supervisors

111 South Third Avenue Phoenix, Arizona 85003

Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street Phoenix, Arizona 85040

Mr. Curtis Hoskins Executive Vice President and

Chief Operating Officer Palo Verde Services 2025 N. 3rd Street, Suite 200 Phoenix, Arizona 85004

Roy P. Lessey, Jr., Esq. Akin, Gump, Strauss, Hauer and Feld El Paso Electric Company 1333 New Hampshire Avenue, Suite 400 Washington, DC 20036

Ms. Angela K. Krainik, Manager Nuclear Licensing Arizona Public Service Company P.O. Box 52034 Phoenix, Arizona 85072-2034

August 7, 1995-2 -

UNITED STATES NUCLEAR REGULATORY COMMISSION


ARIZONA PUBLIC SERVICE COMPANY. ET AL.

DOCKET NO. STN 50-528

PALO VERDE NUCLEAR GENERATING STATION. UNIT NO. I

AMENDMENT TO FACILITY OPERATING LICENSE

Amendment No. 97

License No. NPF-41

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

A. The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority dated May 2, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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 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 Facility Operating License No. NPF-41 is hereby amended to read as follows:

9508140051 950807 PDR ADOCK 05000528 p PDR

-2-

(2) Technical Soecifications and Environmental Protection Plan

The Technical Specifications contained in Appendix A, as revised through Amendment No. 97, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

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

FOR THE NUCLEAR REGULATORY COMMISSION

7' ,, •Al

Charles R. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment: Changes to the Technical Specifications

Date of Issuance: August 7, 1995

ATTACHMENT TO LICENSE AMENDMENT

AMENDMENT NO. 97 TO FACILITY OPERATING LICENSE NO. NPF-41


Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains marginal lines indicating the areas of change. The corresponding overleaf page is also provided to maintain document completeness.

REMOVE INSERT

3/4 1-11 3/4 1-11

40,000

30,000

MINIMUM BORATED WATER FROM THE 20,000 SPENT FUEL POOL

(GALLONS)

00

33,500

7,250

COLD SID VOLUME

200 400

AVERAGE REACTOR COOLANT SYSTEM TEMP., OF

75% I-

70% L-

RWT LEVEL INSTRUMENT READING (1) 65% I-

IL(2)

600,000 GAL. (565-F)

57,744 GAL. (I120-F)

COLD S/D VOL. PLUS MARGIN

600K

575K

550K MINIMUM USEFUL VOLUME (1)

525K REQUIRED IN THE RWT

- .- - - - - -- -- .. a SOCK

ESF VOL PLUS MARGIN (3)

200 400

475K

600 O

AVERAGE RCS TEMPERATURE, OF

(1) The tank level and volume shown are the useful level and volume above that in the tank which is required for vortex considerations.

(2) During Mode 5 and 6 one of these borated sources shall contain a minimum of 33,500 gallons.

(3) This volume is not required during Mode 6.

FIGURE 3.1-1 MINIMUM BORATED WATER VOLUMES

PALO VERDE - UNIT 1

600

BOO/6 -

3/4 1-11 Amendment No. 69,97

REACTIVITY CONTROL SYSTEMS

BORATED WATER SOURCES - OPERATING

LIMITING CONDITION FOR OPERATION

3.1.2.6 Each

a. The

1.

2.

3.

b. The

1.

2.

3.

of the following borated water sources shall be OPERABLE: spent fuel pool with: A minimum borated water volume as specified in Figure 3.1-1, and A boron concentration of between 4000 ppm and 4400 ppm boron, and A solution temperature between 60OF and 180*F.

refueling water tank with: A minimum contained borated water volume as specified in Figure 3.1-1, and A boron concentration of between 4000 and 4400 ppm of boron, and A solution temperature between 60OF and 1200 F.

APPLICABILITY: MODES 1, 2,* 3,* and 4*.

ACTION: a. With the above required spent fuel pool inoperable, restore the pool

to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours; restore the above required spent fuel pool to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours.

b. With the refueling water tank inoperable, restore the tank to OPERABLE status within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

SURVEILLANCE REQUIREMENTS

4.1.2.6 Each of the above required borated water sources shall be demonstrated OPERABLE:

a. At least once per 7 days by: 1. Verifying the boron concentration in the water, and 2. Verifying the contained borated water volume of the water source.

b. At least once per 24 hours by verifying the refueling water tank temperature when the outside air temperature is outside the 60*F to 120 F range.

C. At least once per 24 hours by verifying the spent fuel pool temperature when irradiated fuel is present in the pool.

See Special Test Exception 3.10.7.

AMENDMENT NO. ZZ, 69

I

PALO VERDE - UNIT 1 3/4 1-12





PALO VERDE NUCLEAR GENERATING STATION, UNIT NO. 2


Amendment No. 85

License No. NPF-51








-2-

(2) Technical Specifications and Environmental Protection Plan




' QCharles R.* Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation






Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT

3/4 1-11 3/4 1-11 3/4 6-19 3/4 6-19

MINIMUM BORATED WATER FROM THE SPENT FUEL POOL

(GALLONS)

40,000

30,000

20,000

10,000

0

-33,500

7,250

COLD SID VOLUME

0 200 400

AVERAGE REACTOR COOLANT SYSTEM TEMP., *F

80%

75% I-

70/ L-

RWT LEVEL INSTRUMENT READING (1) 65% F-

600,000 GAL. (565-F)

573,744 GAL. (120-F)


600K

575K

550K MINIMUM USEFUL VOLUME (1)

525K REOUIRED IN THE RWT

- ------------------------ -- - -.-t 5WK


200 400 600

475K

Ok

AVERAGE RCS TEMPERATURE, -F


(2) During Mode 5 and 6 one of these borated sources shall minimum of 33,500 gallons.


FIGURE 3.1-1 MINIMUM BORATED WATER VOLUMES

contain a

Amendment No. 66, 85

600

V

(2)


REACTIVITY CONTROL SYSTEMS



3.1.2.6 Each

a. The

1.

2.

3.

b. The

1.

2.

3.

of the following borated water sources shall be OPERABLE:

spent fuel pool with: A minimum borated water volume as specified in Figure 3.1-1, and A boron concentration of between 4000 ppm and 4400 ppm boron, and A solution temperature between 60OF and 1800 F.

refueling water tank with: A minimum contained borated water volume as specified in Figure 3.1-1, and A boron concentration of between 4000 and 4400 ppm of boron, and A solution temperature between 60*F and 120°F.



to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours;.restore the above required spent fuel pool to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours.





b. At least once per 24 hours by verifying the refueling water tank temnerature when the outside air temperature is outside the 60°F to 120 F range.

c. At least once per 24 hours by verifying the spent fuel pool temperature when irradiated fuel is present in the pool.


AMENDMENT NO. 1z, 55 I

w

I

I


CONTAINMENT SYSTEMS

3/4.6.3 CONTAINMENT ISOLATION VALVES


3.6.3 Each containment isolation valve shall be OPERABLE.*

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

1. With one or more of the isolation valve(s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:

a. Restore the inoperable valve(s) to OPERABLE status within 4 hours, or

b. Isolate each affected penetration within 4 hours by use of at least one deactivated automatic valve secured in the isolation position**, or

c. Isolate the affected penetration within 4 hours by use of at least one closed manual valve or blind flange**; or

d. Be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.

e. The provisions of Specification 3.0.4 do not apply.

SURVEILLANCE REQU I REMENTS

4.6.3.1 Each containment isolation valve shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair, or replacement work is performed on the valve or its associated actuator, control, or power circuit.

4.6.3.2 Each isolation valve used in containment isolation, containment spray, or containment purge shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on a CIAS, CSAS or SIAS test signal, each isolation valve actuates to its isolation position.

b. Verifying that on a CPIAS test signal, all containment purge valves actuate to their isolation position.

*Locked or sealed closed valves may be opened on an intermittent basis under administrative control.

"**The inoperable isolation valve(s) may be part of a system(s). Isolating the affected penetration(s) may affect the use of the system(s). Consider the technical specification requirements on the affected system(s) and act accordingly.

PALO VERDE - UNIT 2 Amendment No. ;-4,853/4 6-19

CONTAINMENT SYSTEMS

SURVEILLANCE REQUIREMENTS (Continued)

4.6.3.3 The isolation time of each power operated or automatic valve used in CIAS, CPIAS, or CSAS shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 The containment isolation check valves shall be demonstrated OPERABLE pursuant to 10 CFR 50, Appendix J, with the exception of those check valves footnoted as "Not Type C Tested."

4.6.3.5 The containment isolation valves used as safety/relief, normally open-ESF actuated closed, or required open during accident conditions shall be demonstrated OPERABLE as required by Specification 4.0.5 and the Surveillance Requirements associated with those Limiting Conditions for Operation pertaining to each valve or system in which it is installed. Valves secured*** in their actuated position are considered operable pursuant to this specification.

4.6.3.6 The manual containment isolation valves (normally closed/post accident closed valves) shall be demonstrated OPERABLE pursuant to Surveillance Requirement 4.6.1.1.a of Specification 3.6.1.1.

***Locked, sealed, or otherwise prevented from unintentional operation.

AMENDMENT NO.73PALO VERDE - UNIT 2

I

I

I

3/4 6-20





PALO VERDE NUCLEAR GENERATING STATION, UNIT NO. 3


Amendment No. 68

License No. NPF-74








-2-

(2) Technical Specifications and Environmental Protection Plan




PCharles R. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation






Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT

3/4 1-11 3/4 1-11 3/4 8-17 3/4 8-17

40,000

30,000

MINIMUM BORATED WATER FROM THE 20,000 SPENT FUEL POOL

(GALLONS) 10,000

0

33,500

7,250

COLD S/D VOLUME

0 200 400

AVERAGE REACTOR COOLANT SYSTEM TEMP., 'F

80% F

L5

70% 1-

RWT LEVEL INSTRUMENT READING (1) 65% 1-

600,000 GAL. (565*F)

573,744 GAL. (120-F)


6OWK

575K

550K MINIMUM USEFUL

VOLUME (1) 525K REQUIRED IN THE

RWT

- - - - -------------------- J 500K


200 400

475K

600 Ok

AVERAGE RCS TEMPERATURE, -F


(2) During Mode 5 and 6 one of these borated sources shall contain a

minimum of 33,500 gallons.


FIGURE'3.1-1 MINIMUM BORATED WATER VOLUMES

Amendment No. 44,68

600

V,

IIx (2)

I I




3.1.2.6 Each of the following borated water sources shall be OPERABLE: a. The spent fuel pool with:

1. A minimum borated water volume as specified in Figure 3.1-1, and 2. A boron concentration of between 4000 ppm and 4400 ppm boron, and 3. A solution temperature between 60*F and 1800F.

b. The refueling water tank with: 1. A minimum contained borated water volume as specified in

Figure 3.1-1, and 2. A boron concentration of between 4000 and 4400 ppm of boron, and 3. A solution temperature between 60*F and 120*F.



to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours; restore the above required spent fuel pool to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours.





b. At least once per 24 hours by verifying the refueling water tank temperature when the outside air temperature is outside the 60OF to 120OF range.

c. At least once per 24 hours by verifying the spent fuel pool temperature when irradiated fuel is present in the pool.


AMENDMENT NO. 2, 42 1PALO VERDE - UNIT 3 3/4 1-12

ELECTRICAL POWER SYSTEMS

3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES

CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES


3.8.4.1 Primary and backup containment penetration conductor overcurrent protective devices associated with each containment electrical penetration circuit shall be OPERABLE. The scope of these protective devices excludes those circuits for which credible fault currents would not exceed the electrical penetration design rating.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

With one or more of the above required containment penetration conductor overcurrent protective devices inoperable:

a. Restore the protection device(s) to OPERABLE status or deenergize the circuits(s) by tripping the associated backup circuit breaker or racking out or removing the inoperable device within 72 hours and declare the affected system or component inoperable and verify the backup circuit breaker to be tripped or the inoperable circuit breaker racked out at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers tripped, or

b. Be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.


4.8.4.1 The above noted primary and backup containment penetration conductor overcurrent protective devices (except fuses) shall be demonstrated OPERABLE:

a. At least once per 18 months:

1. By verifying that the medium voltage (4-15 kV) circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers of each voltage level, and performing the following:

(a) A CHANNEL CALIBRATION of the associated protection relays, and

(b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed.

PALO VERDE - UNIT 3 Amendment No. 6.7,683/4 8-17

ELECTRICAL POWER SYSTEMS

SURVEILLANCE REQUIREMENTS (Continued)

(c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested. 2. By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers. Circuit breakers selected for functional testing shall be selected on a rotating basis. Testing of these circuit breakers shall consist of injecting a current with a value equal to 300% of the setpoint (pickup) of the long-time delay trip element and 150% of the setpoint (pickup) of the short-time delay trip element, and verifying that the circuit breaker operates within the time delay band width for that current specified by the manufacturer. The instantaneous element shall be tested by injecting a current for a frame size of 250 amps or less with tolerances of +40%/-25% and a frame size of 400 amps or greater of ±25% and verifying that the circuit breaker trips instantaneously with no apparent time delay. Molded case circuit breaker testing shall also follow this procedure except that generally no more than two trip elements, time delay and instantaneous, will be involved. Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.*

b. At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.

*This surveillance requirement, otherwise due January 12, 1991, will be performed prior to the end of the second refueling outage or by June 15, 1991.

PALO VERDE - UNIT 3 AMENDMENT NO. 253/4 8-18

UNITED STATES

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

RELATED TO AMENDMENT NO. 97 TO FACILITY OPERATING LICENSE NO. NPF-41,

AMENDMENT NO. 85 TO FACILITY OPERATING LICENSE NO. NPF-51.,

AND AMENDMENT NO. 68 TO FACILITY OPERATING LICENSE NO. NPF-74

ARIZONA PUBLIC SERVICE COMPANY, ET AL.

PALO VERDE NUCLEAR GENERATING STATION, UNIT NOS. 1. 2. AND 3

DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530

1.0 INTRODUCTION

By application dated May 2, 1995, the Arizona Public Service Company (APS or the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License Nos. NPF-41, NPF-51, and NPF-74, respectively) for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3. The Arizona Public Service Company submitted this request on behalf of itself, the Salt River Project Agricultural Improvement and Power District, Southern California Edison Company, El Paso Electric Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority. The proposed changes would remove from the Technical Specifications (TS) plant elevations for the minimum water required in the spent fuel pool currently referenced in the TS Figure and relocate them into site procedures. This TS amendment also includes two changes to correct administrative errors in the TS.

2.0 BACKGROUND

TS 3.1.2.6 provides a curve, Figure 3.1-1, of average reactor coolant system (RCS) temperatures versus the volume of water required in the spent fuel pool (SFP). From this curve, the amount of water required at the highest average RCS temperature is 33,500 gallons. Also, TS 3.1.2.6 stipulates that both the SFP and the refueling water tank (RWT) shall be operable and shall be available as borated water sources during MODES 1 through 4.

The plant elevations shown in Figure 3.1-1 do not correctly correspond to the volumes of water required in the SFP. The elevations shown in the figure are incorrectly based on a siphon breaker hole elevation of 132'-6" instead of 133'-6". If the SFP is utilized as a borated water source, line PCN-038-HCCA3 is used to draw water from the SFP. This line has a siphon breaker hole at plant elevation 133'-6". The purpose of this siphon breaker is to prevent the SFP level from dropping below the level required for shielding purposes. Therefore, the only water available for boron injection is the volume in the SFP that is above the siphon breaker hole.

9508140053 950807 PDR ADOCK 05000528 P PDR

-2-

The elevations, therefore, do not correctly correspond to the volumes of water noted on the figure. The volumes of water remain unchanged; only the conversion of these volumes to plant elevation is incorrect. Site procedures are now in place to verify the required minimum borated water volumes using the correct plant elevations.

Description of Proposed Changes

Figure 3.1-1 in TS 3.1.2.6

Figure 3.1-1, "Minimum Borated Water Volumes," is revised to remove the plant elevations for PVNGS Units 1, 2, and 3. The plant elevations that correspond to the minimum required water volumes for the SFP will be relocated into site procedures.

Reference to Table 3.8-2 in TS 3.8.4.1

Table 3.8-2 was removed from TS 3.8.4.1 in Unit 3 amendment number 57; however, the reference to the table was not removed at that time due to an administrative oversight.

Technical Specification (TS) 4.6.3.1

This TS revision adds the word "containment" to TS 4.6.3.1 in Unit 2. This addition is for clarification purposes and ensures consistency among the three TSs for Units 1, 2, and 3.

3.0 EVALUATION

The licensee's changes are administrative in nature and do not involve any modifications to plant equipment or affect plant operation. Plant elevations corresponding to the required volumes of water do not need to be maintained in the TSs. The required volume of water in the SFP is noted on Figure 3.1-1 and will remain unchanged. Once the plant elevations are removed from the TS and relocated to site procedures, changes to the correlation between plant elevation and water volume will be controlled in accordance with the provisions of 10 CFR 50.59. The staff has reviewed these TS changes to the SFP; they meet the requirements of SRP 9.1.3 and therefore are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Arizona State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change a surveillance requirement. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no

-3-

significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (60 FR 35060). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: C. Thomas

Date: August 7, 1995

Documents

Palo Verde Station, License Amendments 97, 85, 68, Would ... · spent fuel pool and relocate includes two changes to A copy of the related Safety Evaluation is also enclosed. The