AECM-83-0453, Forwards Summary of NUREG-0737 Tech Spec Status Per Generic Ltr 83-02.Two Required Changes Re Safety Relief Valve Challenges Will Be Submitted for Consideration by 830901

Forwards Summary of NUREG-0737 Tech Spec Status Per Generic Ltr 83-02.Two Required Changes Re Safety Relief Valve Challenges Will Be Submitted for Consideration by 830901

ML20077J589
Person / Time
Site:	Grand Gulf
Issue date:	08/15/1983
From:	Dale L MISSISSIPPI POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 AECM-83-0453, AECM-83-453, GL-83-02, GL-83-2, NUDOCS 8308170018
Download: ML20077J589 (3)

Text

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O MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi meMaMidd5 P. O. B O X 164 0, J AC K S O N, MIS SIS SIP PI 3 9 2 0 5 NUCLEAR PRODUCTION DEPARTMENT E '

U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attention: Mr. Harold R. Denton, Director

SUBJECT:

Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 License No. NPF-13 File 15180/0272

Reference:

Generic Letter 83-02 NUREG-0737 Technical Specifications AECM-83/0453 Attached is a summary of the technical specification status for Grand Gulf Nuclear Station (GGNS) requested in Generic Letter 83-02. Where deviations from or the absence of a specification is identified for CGNS, a change to the Operating License will be requested. The two required changes identified in the attachment will be submitted for your consideration by September 1, 1983.

Yours truly, k

g L. F. Dale Manager of Nuclear Services FGB/SHH: sap Attachment cc: Mr. J. B. Richard (w/c) Mr. T. B. Conner (w/o)

Mr. R. B. McGehee (w/o) Mr. G. B. Taylor (w/o) d$ Mr. Richard C. DeYoung, Director (w/a) ggo- Office of Inspection & Enforcement oo U. S. Nuclear Regulatory Conaission

@@ Washington, D. C. 20555 o

j 3:s: Mr. J. P. O'Reilly, Regional Administrator (w/a) l Office of Inspection and Enforcement

@8 50 U.S. Nuclear Regulatory Commission hQQf l l

$# Region II J

-@@ 101 Marietta St., N.W., Suite 2900 ma L Atlanta, Georgia 30303 Member Middle South Utilities System k

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1Attacharnt l'

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AECM-83/0453 IMPLEMENTATION

SUMMARY

OF in. _

GENERIC LETTER 83-03 TECHNICAL SPECIFICATIONS

1. . STA Training - The NRC.in SER Supplement 2~found the GGNS STA program to e b'e acceptable. .No additional action will be taken pending receipt of

,' further guidance from the NRC as indicated in the generic letter.

g 2. _ Limit Overtime.- GGNS Technical Specification 6.2.f is consistent with J .

the model specification ~provided in enclosure 2 of the letter and with the" policy of'the June'15, 1982 letter (Generic Letter 82-12).

'3l: ' Hydrogen Penetrations:- This item is not applicable to GGNS as internal

[ -recombiners are used.

'4. ' Containment Pressure Setpoint -- No action required by this letter. As

. noted in Supplement 1 to the GGNS SER, the containment pressure setpoint E that initiates containment isolation is approximately 2 psig, which is the' minimum value compatible with normal operating ~ conditions. This high drywell pressure setpoint is'found in Technical. Specification 3.3.2-2.

Containment Purge Valves

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5.' As noted in the letter, this item is being addressed separately on a plant by plant basis. The general-technical

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E specification requirements noted in the generic letter are addressed for GGNS'as fcllows:

a.. GGNS' Technical Specification 3.6.4 requires the containment and

'drywell isolation valves be- operable. Action statement b. requires penetrations with only one valve operable be isolated by.an automatic valve secured in the isolated position.

b. GGNS Technical Specifications do not currently restrict the use of

, these valves,to-safety related purposes-only.:.However, as-evaluated' F in Supplement 4 to the GGNS SER, the operability = issue of all but

,- the 6-inch containment purgeJisolation' valves'has been resolved. A proposed revision to License Condition 2.C.(19).in Supplement 4-L restricts the use of these purge isolation valves. ,

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! c. GGNS Technical. Specification 4.6.1.9.2 requires quarterly:

verification of operability for_ valves with resilient seats.:

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. d .' - .The allowable time period for;the 20-inch purge valves.to be~open '

i; ~during containment purge operations for GGNS;is'-1000 hours.per year-

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- in'accordance with Technical Specification 3.6.1.9.

6. -Radia' tion' Signal ~on Purge Valves; "As;noted by NRC Staff review in : .

'; Supplement 1 to'the:GGNS SER, thel containment'purgeLandLvent isolation

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l valves for GGNS-are; designed-to close~on'a high radiation. signal.

t g 7 7. SRV Challenges;- MP&LIcommitted, in our letter offJune 12, 1981 ~

L 1(AECM-81/0153),jto reporting SRV' challenges'andifailures.a:An amendment-request will be used to ' add the reporting requirements :to the Technical:

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~ . Specifications. . ] ,

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.- Attachsint 1 AECM-83/0453

8. RCIC Restart / Suction - CGNS Technical Specifications follow the model technical specifications with the exception of the " keep filled" instrumentr. tion. The " keep filled" instrumentation for the RCIC systen is not required at GGNS.

9.. Isolation Modifications - A request for amendment will be utilized to update Technical Specification 3.3.2. This update will reflect the minimum response times for the RCIC steam line high flow isolation.

10.. Interlock on Recirculation Pump Loops - This item applies only to non-jet pump plants; it is not applicable to CGNS.

11. Common Reference Level - As described in Supplement 2 to the GCNS SER, MP&L committed to modifications which were found to be acceptable to the NRC. GGNS Technical Specification Bases Figure B3/4 3-1 conforms to sample figure in the generic letter.

12. Manual Depressurization - No action was required by the letter.

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