ML20236L892

Requests Identified Addl Info Before 851206 Proposed Diesel Generator Amend May Be Approved

ML20236L892
Person / Time
Site:	Summer
Issue date:	11/09/1987
From:	Hopkins J Office of Nuclear Reactor Regulation
To:	Nauman D SOUTH CAROLINA ELECTRIC & GAS CO.
References
TAC-59451, NUDOCS 8711110103
Download: ML20236L892 (4)

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yMr.:DIA.'Nauman .. -S.LVargal ACRS :(10) . 1

,as T' MVice President,' Nuclear Operations? . .G. Lainas: 3 l A.;Adensam i

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P2 Anderson T H (P.O.' Box:764'(Mail CodeL167)1 '

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-J. Hopkins -l 1

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Dear'Mr;-Nauman:

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SUBJECT:

V.C.LSUMMER: NUCLEAR STATION DIESEL GENERATORS  ;

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l (TAC l NO.'. 59451)

The.NRC staff is reviewing your proposed diesel generator amendment submitted- }1

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>' by' letter dated December 6, 1985, and finds.that we. require additional linformationforourevaluation.'(see' enclosure).

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' This regtestsis covered by;0ffice of_ Management and Budget; Clearance Number.

W E315010011 which expires' September 30, 1989. Comments on burden and duplication .

i may b'e7 directed to the 0ffice' of Management and--Budget, Room l3208, New .

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.- -ExecutiveOffice~B'uilding,'Nashington,DC-20503..

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9 Sincerely',.

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Jon' B. 'Hopkins, Project Manager-  !

Project Directorate II-l' Division of Reactor Projects - I/II o Office.of Nuclear Reactor Regulation 1

Enclosure:

LAs Stated

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L South Carolina Electric & Gas" Company Virgil C. Summer Nuclear Station.

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Mr. William A. l Williams , Jr. .

Technical Assistant ' Nuclear. Operations-Santee. Cooper '

P.O.' Box 764~(Mail Code ~167)

'. Columbia, South Carolina.:i 29218 J. B. Knotts',,Jr., Esq.

Bishop, Liberman, Cook, Purcell .{

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-and Reynolds.

1200 17th. Street, N.W.- .

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Washington, D.-C. 20036 Resident Inspector / Summer NPS c/o U.S. Nuclear Regulatory Commission .,'

Route 1, Box 64. j Jenkinsville, South Carolina 29065 j Regional Administrator, Region II 1 U.S.: Nuclear Regulatory Comission, i 101 Marietta Street, N.W... Suite'2900  ;'

Atlanta, Georgia. 30323

. Clairman, Fairfield County Council P 0. Box 293

-l Winnsboro, South. Carolina 29180 .;

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. Attorney General' Box 11549 .

5 Columbia South Carolina 29211 1

, Mr. Heyward G. Shealy, Chief Bureau of Radiological Health-South Carolina. Department of Health and Environmental Control -

2600_ Bull Street 4

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Columbia, Seuth Carolina 29201 4

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Enclosure 1

.1. To action statement b.1. of Technical Specification (TS) 3.8.1.1, the following statement may be added: "If the EDG became inoperable due to any cause other than preplanned preventative maintenance." This optional j

statement was previously approved by the NRC staff in the. North Anna.TS and will help reduce the number of unnecessary starts.

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2. To action statements b.2. and c.2. of TS 3.8.1.1, a footnote should be

, added that states that, "This test is required to be' completed regardless c of when the' inoperable EDG is restored." This footnote is necessary to 'l make sure that, when one EDG is inoperable, the redundant EDG is tested 1 to ensure no common mode failure has occurred that affected both EDGs.

This footnote was approved by The NRC staff for the North Anna TS.

Therefore, add the footnote or explain its absence.

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3. Surveillance requirements 4.8.1.1.1.b and 4.8.1.1.2.e should remain at a-frequency of .once every 18 months. The change. to once every refueling is f a generic chaNe that is being evaluated by'the NRC staff independent of this TS surveillance by the NRC staff. Therefore, retain the original i frequency or further justify your proposed change.

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4. The NRC staff's view is that a loading band of 4150-4250 kw is sufficient i to avoid routine overloading of the EDG, and'that the proposed loading band of 3900-4100 kw deviates too far from the continuous load rating of l 4250 kw. Furthermore, the maximum load under loss of offsite power <

conditions is calculated to be 4441 kw. Therefore, the proposed loading band should be futher explained or changed. J

5. TS 4.8.1.1.2.e.6.c. ]

The NRC staff's view is that the original wording of " concurrent with" l should be retained instead of the proposed wording of "and/or." d Regulatory Guide 1.9 says that these trips should be bypassed on an 1 accident signal, and it is during an accident with loss of offsite power l that the loss of an EDG is least tolerable, since time to get water to 1 the reactor vessel may be critical. It is this mode that should be tested.

Therefore, the proposed wording should be changed er explained.

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6. TS 4.8.1.1.2.e.7.a l The two hour loading at the short time rating should be retained at the beginning of the test in accordance with position C.14 of Regulatory l Guide 1.9. The NRC staff's view is that this is especially necessary at j Summer because the maximum load under loss of offsite power condition's is l

.4441 kw which is into the short time rati . and will likely occur at the 1 beginning of the event. Therefore, you should further explain your i position or change it.

7. The NRC staff's view is that the original reporting requirements should be I retained. Therefore, you should further explain the proposed wording or l change it. Also, the NRC staff believes that the correct TS number is l 4.8.1.1.3.

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