ML20063P815

Proposed Temporary Changes to Tech Spec Re Maint of Secondary Containment for Period of Upcoming Refueling Outage

ML20063P815
Person / Time
Site:	Hatch
Issue date:	10/06/1982
From:	GEORGIA POWER CO.
To:
Shared Package
ML20063P813	List: ML20063P812 ML20063P815
References
TAC-48916, NUDOCS 8210150333
Download: ML20063P815 (8)

Text

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I ATTACHMENT 1 NRC DOCKET 50-321 OPERATING' LICENSE DPR-57 EDWIN 1. HATCH NUCLEAR PLANT UNIT 1 PROPOSED TEMPORARY CHANGES TO TECHNICAL SPECIFICATIONS Pursuant to 10CFR170.12 (c), Georgia Power Company has evaluated the attached proposed amendment to Operating License DPR-57 and has determined that: 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.

1 complex issues, involve ACRS review, or require an environmental impact statement;

c. The proposed ame'ndment does not involve a complex issue or more 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 surveillance requirements for a temporary change to the Unit 1 secondary containment boundary. The proposed change would allow the opening of both railroad airlock doors simultaneously in the Unit 1 reactor building to facilitate movement of material and personnel during the Unit 1 1982 refueling outage Mk.I torus modifications;

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

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ATTACIIMENT 2 1

NRC DOCKET 50-321- ,

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

PROPOSED TEMPORARY CHANGES TO TECHNICAL SPECIFICATIONS

, 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 3.7-12 3.7-12a 3.7-13 3.7-13 l

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIHLMtN15 C. Secondary Containment

• C. Secondary Containment l

1. Secondary Containment Integrity 1. Surveillance While Integrity Maintained

a. Integrity of the secondary con-

.tainment shall be maintained Secondary containmert surveillance during all modes of Unit 1 plant shall be performed as indicated operation except when all of the below:

following conditions are met:

(1) The reactor is subcritical and Specification 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 placing coolant 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 minimum margin below that stated in .

1/4-inch of water vacuum under Specification 3.3.A. calm wind ( 5 mph) conditions with each 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 each Unit 2 secondary containment filter train flow rate not more are 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 Unit 2 secondary containment is closed.

b. Integrity of the Unit 1 secondary containment shall be maintained during all modes of Unit 2 plant operations except Operational Condition 4 as defined in the Unit 2 Technical Specifications.

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

Amendment No. 3.7-12

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 shall below the refueling floor is be performed as indicated below:

not required provided all of the 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 filter below 2120F and the reactor trains in operation. Such tests coolant system is vented. shall demonstrate the capability to maintain a minimum 1/4-inch of (3) All hatenes between Unit 1 second- water vacuum under calm wind dary containment and Unit 2 secon- ( 5 mph) conditions with each fil-dary containment are closed and ter train flow rate not more than sealed. 4000 cfm.

(4) At least one door in each access b. If secondary containment integrity path between Unit 1 secondary shoud be required as stated in containment 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.2 refueling floor from Unit 1 perform surveillance as stated in secondary containment below the Specification 4.7.C.2.a.

refueling floor _are closed and sealed.

(6) At least one door in each access path separating Unit 1 secondary ,

containment above the refueling floor from Unit 1 secondary con-tainment below the refueling floor is closed.

b. Integrity of the Unit 1 secondary containment above the refueling floor shall be maintained during all modes of Unit 2 plant opera-tions except Operatioaal Condition 4 as defined in the Unit 2 Tech-nical Specifications.

c. Refueling operations may continue in Unit I secondary containment (above the refueling floor) provided all conditions in Specification 3.7.C.2.a are met.

Am:ndment No. 3.7-12a

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.C.3 Violation of Secondary 4.7.C.3 Surveillance After Integrity Violated Containment Integrity After a secondary containment vio-If Specification 3.7.C.1 cannot lation is determined the standby be met, procedures shall be gas treatment system will be operated initiated to establish conditions immediately after the affected zones listed in Specification 3.7.C.l.a are isolated from the remainder of through 3.7.C.l.d. the secondary containment. The ability to maintain the remainder of the secondary containment at 1/4-inch of water vacuum pressure under calm ( 5 mph) wind conditions shall 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 be valves 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 operating shall be operable except as stated cycle the operable isolation in Specification 3.7.D.2. valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and the closure times specified in Table 3.7-l.

Amendment No. 3.7-13 d

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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

) e 1 Totals l 4,000.00 .00 l 4,000.00 Note-If Ints does MOI agree witn your reCOfdS. p' ease return witn cheGM espid'ning dppdreht error

?lsi'gP y?,C5 ;"" "Y " n.= 362169 q;_ GeorgiaPower A Atlanta, Georgia 30302 Voucher 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 COMMISSION o.d:r ' WASHINGTON, DC

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