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ATTACHMENT 1

NRC DOCKET 50-321OPERATING' LICENSE DPR-57

EDWIN 1. HATCH NUCLEAR PLANT UNIT 1PROPOSED TEMPORARY CHANGES TO TECHNICAL SPECIFICATIONS

Pursuant to 10CFR170.12 (c), Georgia Power Company has evaluated theattached proposed amendment to Operating License DPR-57 and has determinedthat: 4

a. The proposed amendment does not require evaluation of.a new.Safety Analysis Report and rewrite of the facility license;

b. The proposed amendment does not require evaluation of several.complex issues, involve ACRS review, or require an environmental1

impact statement;

The proposed ame'ndment does not involve a complex issue or morec.than one environmental or safety issue;

d. The proposed amendment does involve a single safety issue, namely,the addition of limiting conditions of operation and surveillancerequirements for a temporary change to the Unit 1 secondarycontainment boundary. The proposed change would allow theopening of both railroad airlock doors simultaneously in the Unit 1reactor building to facilitate movement of material and personnelduring the Unit 1 1982 refueling outage Mk.I torus modifications;

The proposed change to Operating License DPR-57 is therefore ae.Class III amendment.

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ATTACIIMENT 21

NRC DOCKET 50-321- ,

OPERATING LICENSE DPR-57EDWIN-I. HATCH NUCLEAR PLANT UNIT 1

PROPOSED TEMPORARY CHANGES TO TECHNICAL SPECIFICATIONS i

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The proposed temporary changes to the Technical Specifications,

(Appendix A to Operating License DPR-57) would be incorporated as follows:!

Remove Page Insert Page,

3.7-12 3.7-123.7-12a--

3.7-13 3.7-13|

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIHLMtN15

C. Secondary Containment * | C. Secondary Containment

1. Secondary Containment Integrity 1. Surveillance While IntegrityMaintained

a. Integrity of the secondary con-.tainment shall be maintained Secondary containmert surveillanceduring all modes of Unit 1 plant shall be performed as indicatedoperation except when all of the below:following conditions are met:

(1) The reactor is subcritical andSpecification 3.3.A is met. a. A Preoperational secondary contain-

ment capability test shall be(2) The reactor water temperature is conducted after isolating the

below 2120F and the reactor secondary containment and placingcoolant system is vented. the standby gas treatment system

filter trains in operation. Such

(3) No activity is being performed tests shall demonstrate the capa-which can reduce the shutdown bility to maintain a minimummargin below that stated in 1/4-inch of water vacuum under.

Specification 3.3.A. calm wind ( 5 mph) conditions witheach filter train flow rate not

(4) The fuel cask or irradiated fuel more than 4000 cfm.is not being moved in the re-actor building. b. Secondary containment capability

to maintain a minimum 1/4-inch(5) All hatches between Unit 1 of water vacuum under calm wind

secondary contairment and ( 5 mph) conditions with eachUnit 2 secondary containment filter train flow rate not moreare closed and sealed. than 4000 cfm shall be demonstrated

at each refueling outage, prior to(6) At least one door in each refueling.

access path between Unit 1. secondary containment and Unit2 secondary containment isclosed.

b. Integrity of the Unit 1 secondarycontainment shall be maintainedduring all modes of Unit 2plant operations except OperationalCondition 4 as defined in the

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Unit 2 Technical Specifications.

*For secondary containment during 1982refueling outage, see page 3.7-12a.

Amendment No. 3.7-12

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

2 Secondary Containment Integrity 2. Surveillance While Integrity Maintained

During 1982 Refueling Outage Only

a. Unit 1 secondary containment Secondary containment surveillance shallbelow the refueling floor is be performed as indicated below:not required provided all ofthe following conditions are met: a, A preoperational secondary contain-

ment capability test shall be per-(1) The reactor is subcritical and formed after isolating the Unit 1

Specification 3.3.A is ret. secondary containment above the re-fueling floor and placing the

(2) The reactor water temperature is standby gas treatment system filterbelow 2120F and the reactor trains in operation. Such tests

coolant system is vented. shall demonstrate the capabilityto maintain a minimum 1/4-inch of

(3) All hatenes between Unit 1 second- water vacuum under calm winddary containment and Unit 2 secon- ( 5 mph) conditions with each fil-dary containment are closed and ter train flow rate not more thansealed. 4000 cfm.

(4) At least one door in each access b. If secondary containment integritypath between Unit 1 secondary shoud be required as stated incontainment and Unit 2 secondary Specification 3.7.C.1 perform sur-containment is closed. veillance as stated in Specifica-

tion 4.7.C.l.a. If secondary con-(5) All hatches sepwating Unit 1 tainment is subsequently required

secondary containment above the as stated in Specification 3.7.C.2refueling floor from Unit 1 perform surveillance as stated insecondary containment below the Specification 4.7.C.2.a.refueling floor _are closed andsealed.

(6) At least one door in each accesspath separating Unit 1 secondary

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containment above the refuelingfloor from Unit 1 secondary con-tainment below the refueling flooris closed.

b. Integrity of the Unit 1 secondarycontainment above the refuelingfloor shall be maintained during'

all modes of Unit 2 plant opera-tions except Operatioaal Condition4 as defined in the Unit 2 Tech-nical Specifications.

c. Refueling operations may continuein Unit I secondary containment(above the refueling floor) providedall conditions in Specification3.7.C.2.a are met.

Am:ndment No. 3.7-12a

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

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3.7.C.3 Violation of Secondary 4.7.C.3 Surveillance After Integrity ViolatedContainment Integrity

After a secondary containment vio-If Specification 3.7.C.1 cannot lation is determined the standbybe met, procedures shall be gas treatment system will be operatedinitiated to establish conditions immediately after the affected zoneslisted in Specification 3.7.C.l.a are isolated from the remainder ofthrough 3.7.C.l.d. the secondary containment. The

ability to maintain the remainderof the secondary containment at1/4-inch of water vacuum pressureunder calm ( 5 mph) wind conditionsshall be confirmed.

D. Primary Containment Isolation Valves D. Primary Containment Isolation Valves

1. Valves Required to be Operable 1. Surveillance of Operable Valves

During reactor power operation, Surveillance of the primary con-all primary containment isolation tainment isolation valves shall bevalves listed in Table 3.7-1. and performed as follows:all reactor coolant system instru-ment line excess flow check valves a. At least once per operatingshall be operable except as stated cycle the operable isolationin Specification 3.7.D.2. valves that are power operated

and automatically initiatedshall be tested for simulatedautomatic initiation and theclosure times specified inTable 3.7-l.

Amendment No. 3.7-13

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Endr rsement of accorppanying check is considered a receipt in full settlement of the following s' ems I,

Vendor Number 921900 Check Number 923165 Voucher Number (' Dist Date intnice Date Your Number Our No Gross Amount Discount Net Amount ,

10-82 10-04-82 100482400000 4,000.00 .00 4,000.00

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Totals | 4,000.00 .00 | 4,000.00Note-If Ints does MOI agree witn your reCOfdS. p' ease return witn cheGM espid'ning dppdreht error

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GeorgiaPower A?|si'gP y?,C ;"" "Y " n.= 362169 q;_5Atlanta, Georgia 30302Voucher Number Date (Mt p NdMri H

10-05-82 923165

Amount

Pay .$4.000 and 00/100 Dollars $4,000.00

$c U.'S.' NUCLEAR REGULATORY COMMISSIONo.d:r ' WASHINGTON, DC

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{Th2 First National Bank of Atlanta, Atlanta, Georgia ~ utnonzed * 'aEre:BN

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