ML20038B531

Application to Amend License DPR-57 Revising Tech Specs to Update Table 3.7-4 Re Primary Containment Testable Isolation Valves.Torus Water Drain & Cleanup Sys Has Been Provided W/ Redundant Isolation Capabilities

ML20038B531
Person / Time
Site:	Hatch
Issue date:	12/02/1981
From:	Beckham J GEORGIA POWER CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20038B532	List: ML20038B531 ML20038B540
References
TAC-47443, NUDOCS 8112080375
Download: ML20038B531 (3)

Text

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Georg a Powe* Ccmpanv 333 Piedmont Avewe Af;crta Ga.>rg,a 303v8 Te!ephone 404 526-7020 Maing Addess Post o*f.ce Ba< 4545 At aria Gecrg'a 303C2 OM.

December 2, 1981 J T. Beckham, Jr. _

fg Vte Pres: cent a~j Ger:eraf Marag r fl Nuc: car Gere a* cn nN f- /

? . Y Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission h .ggI Jgg yy Washington, D. C. 20555 - ," ?g4ge , ,

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WC DOCKET 50-321 OPERATING LICENSE DPR-57 N k' ;f

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EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGES TO THE TECHNICAL SPECIFICATICNS REGARDING THE TORUS WATER DRAIN AND CLEAN-UP (G51) SYSTEM Gentlemen:

In accordance with provisions of 10 CFR 50.59, as required by 10 CFR 50.90, Georgia Power Company (GPC) proposes an amendment to the Technical ,

Specifications (Appendix A to the Operating License).

This amendment to the Unit 1 Technical Specifications would update the listing of Primary Containment Testable Isolation Valves (Table 3.7-4).

GPC is installing a Torus Water Drain and Clean-Up System (G51) on Plant Hatch Unit 1. Early in 1981, a portion of the system was installed during the Unit I refueling outage. At that time the Technical Specifications were amended to include a manual valve (G51-F016) and a blind flange (G51-D004) as the isolation valves for the Clean-Up System. During the recent Unit 1

" fuel reconstitution" outage, two air-operated valves were installed between G51-F016 and G51-D004. These valves, G51-F0ll and G51-F012, have not been connected to their air supply. Thus, both valves are closed and would require manual operation in order to be opened. Additionally, the switches which actuate the air supply to the valves have been tagged-out so that they will not be actuated until the proposed Technical Specification changes have been approved. -

The affected pages in the Plant Hatch Unit 1 Technical Specifications are attached and reflect the proposed changes. The changes do not constitute an unreviewed safety question per 10 CFR 50.59 because: 1) The probability of occurrence and the consequences of an accident or malfunction of equipment important to safety are not increased above those analyzed in the FSAR due to this change because the Torus Water Drain and Clean-Up System has been designed in accordance with 10 CFR 50, Appendix A, Section V, criterion 56 so that all portions of the system penetrating the torus are provided with redundant isolation capabilities; 2) the possibility of an accidentormalfunctionofadifferenttypethanthatanalyzedintheFSARlJOol

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,b 8112080375 811203 PDR ADOCK 05000321 P. PDR

r Georgia Powerkh Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 December 2, 1981 Page Two does not result from this change because no new modes of failure are introduced; and 3) the margin of safety as defined in Technical Specifications is not reduced due to this change because all portions of the system penetrating the torus are provided with redundant isolation capabilities.

Please note that Technical Specification 3.7.D " Primary Containment Isolation Valves" references Table 3.7-1 as being the listing of isolation valves required to be operable and to which the Limiting Conditions of Operation apply. Table 3.7-4, which is provided for information only, lists all Testable Primary Containment Isolation Valves. This amendment changes only Table 3.7-4; thus, it is an administrative change. Consequently, this proposed change constitutes a category 2 submittal for fee class determination. A check for the fee payment is enclosed. .

If you have any questions, please contact this office.

J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.

GEORGIA POWER COMPANY By: h dd- M %

g J. T. Beckham, M.

t y and subscribpefore me this 2nd day of [Mcember,1981.

[kO NMIf 3 ' '

((bm"ib Esp r$ ~Sht.5)[153 Notary Puolic DLT/mb Attachment xc: M. Manry R. F. Rogers, III l

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Georgia Power b

• - Georgia Power Company-Docket Number 50-321 Operating License DPR-57 Edwin I. Hatch Nuclear Plant Unit 1 Proposed Changes to Technical Specifications The proposed - changes to the Plant Hatch Unit 1. Technical Specifications would be incorporated as follows:

Delete Page Insert Pages 3.7-26 3.7-26 3.7-27 3.7 ,

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Table 3.7-4 (Concluded)

Primary Containment Testable-Isolation Valves Penetration Number Valve Designation Notes X-220. .P33-F006 & F014 (1) (2) (4) (5) (9)-

X-220 T48-F318 & F326 "

X220 T48-F332A & F333A "

X220 T48-F3328 & F333B X220 T48-F338 & F339 X-218A G51-F002 (1) (2) (4) (5)'(10)

X-218A G51-D001 (1) (2).(4) (5) (13)

X-218A G51-F0ll (1) (2) (4) (5) (10)

X-218A G51-F012 '(1) (2) (4) (5).(10) i 4

OO 3.7-26 hhk O g

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l Notes For Tables 3.7-2 through 3.7-4 '

- (1) Test duration for all' valves and penetrations listed will generally '

exceed one hour.

(2)- Test pressures.-are at_'least 50- psig for all valves and penetrations except MSIV's which are tested at 28 psig.

(3) - MSIV acceptable leakage limit is ll.5'scfh/ valve of air.

(4) The total acceptable leakage for all valves and penetrations' other.

than the MSIV's is 0.6 La-1 (5) Local leak tests on all testable isolation valves shall be performed each major refueling shutdown but in no case at intervals greater than-2 years.

- (6) Local leak tests on all' testable penetrations shall be performed-each ~

major refueling shutdown but in no case at intervals greater than 2 years.

(7) The personnel air lock shall be tested at intervals .not to exceed 6 months.

(8). .The personnel air lock door seals are tested at' 10 psig after. each opening.

I (9) Identifies isolation. valves that. are tested by applying . pressure

between the inboard and outboard isolation valves.. Inboard valve is not tested in the direction required ~ for . isolation ~ but will have-equivalent or more conservative leakage results.

(10) Identifies isolation valves that are tested by applying pressure

. between the isolation valve and a manually operated valve mich .that

, the isolation valve is tested in the direction re' *a for 3

. isolation.

' (11) identifies isolation valves that are tested by applying pr% sure between the isolation valves and other system valves. Isolation

~

valves not tested in the direction required for isolation will have equivalent or more conservative results.

. (12) The RHR system remains water filled post-LOCA. Isciation valves are tested with water.

l J. (H) Identifies blind flange that is tested by applying pressure between

{ the flanm and a manually operated valve such that the flange is tested in the direction lequired for isolation.

q P 3.7-27 J_r____---______-_______--_-_-____________

. Georg a Pener Campa y -

333 PMmont Aunos 4 Asanta GKw 30308 Te'ephone 404 SN 7023

. Ma Lng A1 ress Post c" ice Box JM5

- Arama Ges;a 30302 December 2, 1981

• • i J. T. seekham, Jr.

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vce Pres rec ae Gema: va,ager .j; eear ocezen - g, q

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Director of Nuclear Reactor Regulation fg ggI  ;

U. S. MJclear Regulatory Commission r)-

Washington, D. C. 20555 - ,, g /gg ,

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NRC DOCKET 50-321 Q' N' f U OPERATING LICENSE OPR-57 N

EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS REGARDING THE TORUS WATER DRAIN AND CLEAN-UP.(G51) SYSTEM Gentlemen:

In accordance with provisions of 10 CFR 50.59, as required by C CFR 50.90, Georgia Power Company (GPC) proposes an amendment to the TecicQal Specifications (Appendix A to the Operating License).

This amendment to the Unit 1 Technical Specifications would update the listing of Primary Containment Testable Isolation Valves (Table 3.7-4).

GPC is installing a Torus Water Drain and Clean-Up System (G51) on Plant Hatch Unit 1. Early in 1981, a portion of the system was installed during the Unit I refueling outage. At that time the Technical Specifications were amended -to include a manual valve (G51-F016) and a blind flange (G51-D004) as the isolation valves for the Clean-Up System. During the recent Unit 1

" fuel reconstitution" outage, two air-operated valves were installed between G51-F016 and G51-D004. These valves, G51-F0ll and G51-F012, have not bean connected to their air supply. Thus, both valves are closed and would require manual operation in order to be opened. Additionally, the switches which actuate the air supply to the valves have been tagged-out so that they will not be actuated until the proposed Technical Specification changes have been approved.

The affected pages in the Plant Hatch Unit 1 Technical Specifications are attached and reflect the proposed changes. The changes do not constitute an unreviewed safety question per 10 CFR 50.59 because: 1) The probability of occurrence and the consequences of an accident or malfunction of equipment important to safety are not increased above those analyzed in the FSAR due to this change because the Torus Water Drain and Clean-Up System has been designed in accordance with 10 CFR 50, Appendix A, Section V, criterion 56 so that all portions of the system penetrating the torus are provided with redundant isolation capabilities; 2) the possibility of an accident or mal. function of a different type than that analyzed in the FSAR 0

h01.s

,b 8112080375 811202 PDR ADOCK 05000321 P PDR 4

i GeorgiaPbwer d Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 December 2, 1981 Page Two does not result from this change because no new modes of failure are introduced;- and 3) the margin of safety as defined in Technical Specifications is not reduced due to this change because all portions of the system penetrating the torus are provided with redundant isolation capabilities.

Please note that Technical Specification 3.7.D " Primary Containment Isolation Valves" references Table 3.7-1 as being the listing of isolation valves required to be operable and to which the Limiting Conditions of Operation apply. Table 3.7-4, which is provided for information only, lists all Testable Primary Containment Isolation Valves. This amendment changes only Table 3.7-4; thus, it is an administrative change. Consequently, this proposed change constitutes a category 2 submittal for fee class determination. A check for the fee payment is enclosed.

If you have any questions, please contact this office.

J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.

GEORGIA POWER COMPANY By: d # hv g J. T. Becknam, M.

Sw rn t and subscribed efore e this 2nd day of December, 1981.

' tiotary Pubhc. Geoma. State at Large b . 13 My Commission Empires Sept. 20,1983 Notary Puolic DLT/mb Attachment xc: M. Manry R. F. Rogers, III

,--m. .- . _ . - . _ . . _ _ , . . . . . . _ _ _ _ _ . . _ . . . _. - _ . . _ _ _ , . _ . _ _ _ _ - - _ _ _ . , _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _

Georgia Powerkn Georgia Power Company Docket Number 50-321 Operating License DPR-57 Edwin I. Hatch Nuclear Plant Unit 1 Proposed Changes to Technical Specifications The proposed changes to the Plant Hatch Unit 1 Technical Specifications would be incorporated as follows:

Delete Pace Insert Pages 3.7-26 3.7-26 3.7-27 3.7-27 9