ML18079A950

Submits Request for Addl Info Supporting FSAR Review & for Info Sizing Design Basis for Refueling Water Storage Tank . Requests Info by 790904.Forwards 781028 Deficiency Rept

ML18079A950
Person / Time
Site:	Salem
Issue date:	08/02/1979
From:	Parr O Office of Nuclear Reactor Regulation
To:	Mittl R Public Service Enterprise Group
Shared Package
ML18079A951	List: ML18079A950 ML18079A952
References
NUDOCS 7909240034
Download: ML18079A950 (4)

Text

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Distribution w/e11cl~e:

Docket File:or.E'2

0. Parr NRC poq A. *oromerick Local PDR M. Rushbrook LWR #3 File R. Mattson D. Vassallo S. Hanauer D~ ~ass J. Knight S. Varga R. Tedesco F. *t~illiams

• R. DeYoung V. Moore

~~. Kreger M. Ernst R. Denise OELD IE ( 3)

SCC:

JBuchanan TAbernathy

.l\\CRS ( 16)

Docket No. 50-311 AUG 2 2 1979 Mr. R. L. Mittl~.General Manager Licensing and Environment Engineering and Construction Department Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE S.ALEM UNIT 2 FINAL SAFETY ANALYSIS REPORT (FSAR)

As a result of our continuing* review of the Salem FSAR, we find that we need additional information to complete our evaluation. The specific information required is listed in the Enclosure.

Our review schedule is based on the assumption_that this additional information will be available for our review by September 4, 1979. If you cannot meet this

.date, please inform us within seven days after receipt of this letter so that we may revise our schedule accordingly.

Please contact us if you desire any discussion or clarification of.the enclosed request.

Enclosure:

Request for Additional Information.

cc w/enclosure:

See next page Sincerely,

/fe Ortgfpal.. S}gnecf bl W

0. D. Parr Olan D. Parr, Chief Light Water Reactors Branch No. 3 Division of Project Management 790924003'-f um #3_:19f) u,m Jt~Bc eFl'ICI:.. ~* -."JJ¥trC:f'/ij:, *****a*?r*r:;~********** ************************** ********:***************'. *************************.. :*******************

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• U.S. CilOVERNMllNT PRINTING OP'fl'ICE: t 171

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Mr. R. L. Mittl, General Manager cc: Richard Fryling, Jr., Esq.

Assistant General Counsel Public Service ElectriG & Gas Company 80 Park Place Newark, New Jersey 07100 Mark Wetterhahn, Esq.

Conner, Moore & Caber 1747 Pennsylvania Avenue, N.W.

Suite 1050 Washington, D.C.

20006 Mr. Leif J. Norrholm.

U. S. Nuclear Regulatory Commission.

Region I Drawer I Hancocks Bridge, New Jersey 08038 AUG 2 2 1979

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION SALEM NUCLEAR GENERATING STATION, UNIT 2 6.0 ENGINEERED SAFETY FEATURES 6.30 A recent design deficiency report submitted for the Seabrook Station (attached) identified in adequacy in the RL~ST capacity. The deficiency is related to the remaining capacity in the RWST, following transfer from the injection to the recirculation mode, and the required operator actions along with the time needed to perform these actions relative to this remaining tank capacity.

To pro vi de _a~s~r_anc~ _~~a.!: _a.~i~~]~t_- -~ro~ l_el!1_ ~~s __ not ~)5_i ~:t_ _for 5aJ_em __ 2.: w_e~._r:~q~_{~. ~

that you provide the sizing design basis for the RWST including the following specific information:

1.

Provide the information and justification on each of the following RWST design criterion.

a.

Injection requirements (LOCA)

b.

Instrumentation error

c.

Working allowance

d.

Transfer allowance

e.

Single failure allowance

f.

Unuseable volume

2.

Each of the following questions on RWST capacity and volume is to be answered in terms of useable volume unless otherwise specified.

Provide the total tank volume, the technical specification minimum required volume, the low level alarm setpoint for initiation of switchover procedures, the tank volume at back-up automatic switchover, and the low-low tank/level volume.

Provide the volume remaining in the tank followfog injection to recirculation switchover procedure ustng normal operation and operation with worst single failure.

Include total lack of operator response to first low-level alarm with no response until sec6nd (audio-visual) alarm is heard as a scenario for single failure.

Justify your proposed worst single failure.

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3.

Provide time requirements for manual and automatic functions at switchover.

Examine the time required to perform operator procedures and the time allotted from one RWST setpoint to the next for both small and large breaks.

Justify that there is enough time to complete the procedures.

Include single failure analysis, especially lack of operator response.

Fcir both.small and large breaks, provide the amount of time remaining after low-low level alarm is no manual action has been taken.

4.

Identify the specific functions that the operator must perform during switchover procedures.

Include action to be taken if low-low level alarm is reached with no manual operator action. Provide assessment of time and RWST volume used by each operator action, Justify that the time is enough to recognize, initiate, and complete each function.

5.

Show that there is sufficient allowance in the RWST to prevent vortex formation and air entrapment in RWST suction pipi.ng.

Reference a te.st showing that the minimum amount of remaining RWST volume (after switchover with worst si,ngle failure) is eno.ugh to prevent vortextng problems.

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