ML20244B542

Proposed App a Tech Specs,Pages 3.7-26 & 27 Re Primary Containment Isolation Valves & Page 3.6-9a Re Safety Relief Valve Tail Pipe Pressured Switches

ML20244B542
Person / Time
Site:	Hatch
Issue date:	05/04/1981
From:	GEORGIA POWER CO.
To:
Shared Package
ML16341B613	List: ML20244B542
References
TAC-43822, TAC-43823, NUDOCS 8105080268
Download: ML20244B542 (8)

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ATTACHENT 1 f

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NRC DOCKET 50-321 I

I OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED _ CHANCES TO TECHNICAL SPECIFICATIONS j,

Pursuant to 10 CFR 170d2 (c), Georgia Power Company has evaluated the l

attached proposed amendtents to Operating License DPR-57 and has q

determined that:

j a)

The proposed amendment does not require' the evaluation of a new Safety Analysis Report or rewrite of the facility license; b)-

The proposed amendnent does 'not contain several complex issues, does not involve ACRS

review, and does not require an environmental impact statement; c)

The proposed amendrnent does not involve a complex issue, en environmental issue or more than one safety issue; d)

The proposed amendment does involve a single safety issue, namely, the addition of two valves and two flanges to the table of Primary Containment Isolation Valves; e)

The proposed change is therefore a Class III amendment.

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i ATTACHMENT 2

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NRC DOCKET 50-321 1

i OPERATING LICENSE DPR-57 l

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EDWI.N I. HATCH NUCLEAR PLANT UNIT 1 j

PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS j

The proposed change to Technical Specifications (Appendix A to Operating License CPR-57) would be incorporated as fo11cws:

l Remove Pa g Insert Page 3.7-26 3.7-26.

3.7-27 3.7-27 i

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I Table 3,7-4 (Concluded)

I Primary Containment Testable Isolation Valves l

J Penetration I

NJmber Valve Designation Notes l

i X-220-P33-F006 & F014 (1) (2) (4) (5) (9)

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l X-220 T48-F318 & F326 X220 T48 F332A & F333A i

X220 T48-F3328 & F3338 X220 T48-F338 & F339 X-218A G51-F002-(1) (2) (4) (5) (10)

X-218A G51-0001 (1) (2) (4) (5) (13)

X-218A.

G51-F016 (1) (2) (4) (5) (14)

X-218A G51-0004 (1) (2) (4) (5) (13)

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i 3.7-26

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l Notes For Tables 3.7-2 throuch 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 11.5 scfh/ valve of air.

(4)

The total acceptable leakage for all valves and penetrations other than the MSIV's is 0.6 La-(5)

Local leak tests on all testable isolation valves shall be performed each msjor refueling shutdown but in no case at intervnls greater I

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 I

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 fsolation valves.

Inboard valve is not tested in the direction required for isolation but will have j

equivalent or more conservative leakage results.

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i (10)

Identifies isolation valves that are tested by applying pressure i

between the isolation valve and a manually operated valve such that the isolation valve is tested in the direction required for isolation.

(11)

Identifies isolation valves that are tested by applying pressure l

between the isolation valves and other system valves.

Isolation valves not tested in the direction required for isolation will have f

equivalent or more conservative results.

(12)

The RHR system remains water filled post-LOCA.

Isolation valves are tested with water.

f (13)

Identifies blind flange that is Lested by apolying pressure between j

the flange and a manually operated valve such that the flange is i

tested in the direction requiltd for isolation.

(14)

Identifies an isolation valve that is tested by applying pressure between the manually operated isolation valve and a blind flang e.

The isolation va'1ve is not tested in the direction required for isolation but will have equivalent or more conservative results.

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3.7-27

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ATTACHMENT 3 NRC DOCKET 50-321 l

OPERATING LICENSE OPR-57

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EDWIN I. HATCH NUCLEAR PLANT UNIT 1 l

PROPOSED CHANCES TO TECHNICAL SPECIFICATIONS Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the i.

attached ' proposed amendments to Operating License DPR-57 and has determined that:

j a)-

The proposed amendment does not require the evaluation of a new Safety Analysis Reoort or rewrite of the facility license, 1

b)-

The proposed amendment does not contain several complex issues,

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does not involve ACRS review and does not require an r

environmental impact statement;

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c)

The proposed amendment does not involve a complex issue, an environmental issue or more than ~one safety issue; j

.J d).

The proposed amendment does involve a single safety issue,

'j namely, the deletion of, surveillance requirements - for verifying j

operability of Safety Relief valve tail pipe pressure switches, j

e)

The proposed change is. therefore a Class III amendment.

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'e NRC: DOCKET.50-3211 klC f" OPERATING LICENSE DPR-57

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'EDWIN:I; HATCH' NUCLEAR PLANT UNIT 1 l

' ', '. PROPOSED CHANGES TO TECHNICAL' SPECIFICATIONS

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' Thel proposed; changeto Technical' Specifications (( Appendix A to. Operating.

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,LLicense DPR-57) would'be incorporated as follows:

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LI.MITING CONDITIONS FOR OPERATION SURVEILI.ANCE REQUIREMENTS

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Jee Pu=es I. Jet Pu::res 4

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.i Whenever both recirculating rumps

.j Whenever the reactor is in the

~are operating vich the reactor in Starr & Hot standby or Run Mode.

j vith both recirculating ptusps the Start & Hot Standby or Run Mode, operating. all jet pumps shall be-jet pump operability shall be checked operable. If it is decernised that daily by verifying that the followins d

a fat pu=p is inoperable, an orderly conditions.do not occur. simultaneously, shutdovu shall be initiated and the reactor shall be in the Cold Shut-

1. The two recirculation loops have dovu-Condition with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

a flov imbalance of 1.5% or more

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vhen the pumps are operated at the same speed.

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f Arnendment No. 71 3.6-9a 4

.e LIMITZMG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS v

4.6.H.

Relief / Safety Valves (Contin'ued) i 5.

Operability of Tail Pipe Pressure Switches i..

1 a.

Functional Test:

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2. At each scheduled outage greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during i

l which entry is made into the

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L primary containment, if not F"

performed within the previous; 31 days.

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Calibration and verify.ing the l

setpoint to be 3015 psig at least once per-18 months.

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Jet Pumos I. Jet Pumos Whenever the reactor is in the Whenever both. recirculating pumps Start & Hot Standby or Run Mode are operating with the reactor in with both recirculating pumps the Start & Hot Standby or Run ibde, operating,. all jet pumps shall be jet pump operability shall be checked operable.

If it'is determined that daily by' verifying that the following a fet punp is inoperable, an orderly conditions do not occur simultaneously.

shutdown shall be initiated and the reactor shall be in the Cold Shut-

1. The two< recirculation loops have down condition with 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

a flow imbalance of 15% or~ more when the pumps are operated at-the same speed.

t Amendment No. 71' 3.6-9a

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E' Georgia Power Company f.

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Telechone 404 526 fiS26 Maihng Address-l Post omce Sox 454$

. Manta oeorga 30302

' May 4,1981 GeorgiaPower-l the SOUtherft electfC systern Vice Presioent and oeneral Manager Nuclear Generafion c,

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Director of Nuclear, Reactor Regulation U. S. Nuclear Regulatory Commission

-6N Washington, D. C.

20555 6

bRC DOCKET 50-321 OPERATING LICENSE OPR-57 EDWIN I. HATCH-NUCLEAR PLANT UNIT 1

- REQUEST FOR - CHANGE TO ' TEC.HNICAL - SPECIFICATIONS Gentlemen:

Pursuant to 10 CFR - 50.90 as required by 10 CFR 50.90(c)(1), Georgia'-

Power Company hereby requests changes to the Technical' Specifications j

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(Appendix A to the Operating License).

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Two changes are requested.

The first' change would add two ; valves and I

two ; flanges to Table :3.7-4, primary containment isolation - valves.

These valves and flanges are part of the Torus Drainage and Purification System, a portion of which will be installed during the current refueling outage.

This system includes a new torus penetration.

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' The' second change would. delete surveillance requirement 4.6.H.5 for j

verifying operability of the. Safety Relief Valve Tail Pipe pressure j

switches.

The present. switches are being ' replaced with qualified switches per I&E ' Sulletin 79-919.

The qualified switches are incapable of being -

j adjusted to the presently.specified setpoint of 20 5 psig.

Since these i

2 switches do not perform a safety function, we propose ' to ' delete their

.I surveillance requirements from the Technical' Specifications.

Should this

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not be acceptable, we alt'ernately propose to change the setpoint to 30 5

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1 psig to accommodate installation of' the qualified switches.

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' The Plant Review Board anJ the Safety Review Board have reviewed and approved.these proposed changes to the Unit 1 Technical' Specifications and j

have deterfulned that neither change involves _an unreviewed safety j

question, j

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For the first ' change, the probability of occurrence and the I

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consequences of an accident or malfunction of equipment important to safety l

are not increased because the Torus Orainage -and Purification. System has been ' designed in - accordance,with 10 CFR 50, Appendix A,

Section V,

I criterion 56 such that all portions of the systen penetrating the torus are j

provided with redundant Isolation capabilities.

No new modes of failure are introduced by this change.

The margin of safety as defined.in the R,

Technical Specifications is not reduced because all portions of the system. ge,/

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penetrating the torus are provided with redundant isolation capabilities, j

l The addition of these primary containment isolation valves will not result 3/ 3 i

in a violation of the requirements of 10 CFR 100.

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. Director of. Nuclear Reactor Regulation U.1 Si NJClear Regulatory Commission May 4, 1981-L y LPage Two 1

m For the second - change,: the probability' of. occurrence and L the.

. consequences of an accident or malfunction of. equipment. important to safety are not. increased because'. the pressure ' switches are used for monitoring functions -only.

No new' modes of failure are introduced 1 because : the pressure switches will-perform a monitoring function' only.. The margin -. of..

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safety:as-defined :in the Technical: Specifications 'is unchanged.because the-9 switches do not perform a safety. function..

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B We have determined each of. these changes to be' a. Class III amendment.

Enclosed with the proposed changes are_ a determination of. amendment class,.

1 instructions; for : incorporation of the' proposed ' changes tinto the' Technical ~

Specifications, and payment of applicable fees.

. Since-these changes are' needed prior to unit startup, your. timely;

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review and approval would' be appreciated.. Please contact this office iif j

.further information is desired.

W. A. Widner states that he is _Vice President of Georgia Power Company and 1s' 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.

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' GEORGIA POWER COMPANY

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By:

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W. A. Widner.

Sw rn t and subscribed before me this 4th day of May,1981.

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Netary Public. Georgia. State at Large g L-f My Commission Expires Sept. 20,1983 Notary Public RES/mb g

Enclosures-1 xc:.,M. Manry

.g R. F. Rogers, III o

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