ML20127B365

Requests Confirmation by 840305 Whether Reactor Core Referenced in License Section 2.1.2 as Basis for Reactor Safety Limits Actually Corresponds to Core in Actual Plant

ML20127B365
Person / Time
Site:	Grand Gulf, 05000000
Issue date:	03/02/1984
From:	Gilinsky V NRC COMMISSION (OCM)
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML19263A614	List: 05000000/LER-1984-002, :Since 840107,several Instances of Reactor Protection Sys Bus Breaker Trips Resulted in Loss of Shutdown Cooling.Trip on 840119 Caused by Failure of Circuit Board 05000000/LER-1984-010, :on 840210,reactor Protection Sys Motor Generator Set Output Breaker B Tripped While Transferring Power from Alternate Supply.Caused by Voltage Transient. Design Change Being Considered AECM-84-0133, Advises NRC of Completion of Operator Recertification Program,Per 831118 Commitment.Deficiencies in Training That Remain Open Will Be Closed in Near Future.One Licensed Reactor Operator Undergoing Remedial Training AECM-84-0204, Special Rept 84-017/0:on 840304,Fire Doors 1A401 & OC219 Blocked Open to Support Maint Activities.Fire Watches Established Until Doors Restored AECM-84-0226, Responds to 840323 Confirmation of Action Ltr Re Verifying Removal of Certain Individuals from Licensed Duties.Util Has Evaluated Licensed Operators to Determine If Deficiency Identified Applicable to Other Operators.Related Info Encl AECM-84-0239, Provides Info Re Plant Discrepancy Repts to Assure That Any safety-related Hardware or Procedural Deficencies Properly Dispositioned,Per 831205 Confirmatory Action Ltr.Procedural Revs Instituted.Related Info Encl ML19263A613 ML20126D262 ML20126D273 ML20126D322 ML20126D343 ML20126D352 ML20126D357 ML20126D360 ML20126D363 ML20126D376 ML20126D380 ML20126D392 ML20127A505 ML20127B023 ML20127B328 ML20127B331 ML20127B336 ML20127B341 ML20127B347 ML20127B352 ML20127B358 ML20127B363 ML20127B365 ML20127B370 ML20127B373 ML20127B377 ML20127B381 ML20127B384 ML20127B389 ML20127B408 ML20127B440 ML20127B520 ML20127B524 ML20127B530 ML20127B533 ML20127B542 ML20127B803 ML20127B808 ML20127B888 ML20127B893 ML20127B922 ML20127B927
References
FOIA-84-459 NUDOCS 8403200365
Download: ML20127B365 (1)

Text

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NUCLEAR REGULATORY COMMISSION 5s wassancion. o.c. rosss z g' 2-f-p N-

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MEMORM DUM TO:

HAROLD DENTON, DIRECTOR OFFICE OF NUCLEAR REACTOR REGULATION

SUBJECT:

GRAND GULF REACTOR SAFETY LIMITS I notice the Gr Gulf license references a reactor whose 2'#

nominal power i 32

!Et while the actual plant is supposedly rated ic 8

Et.

Additionally, the license p3 bases for the Power 2.stribution Limits in Section B 3.2.1-1

'apparently use 3c93 mit while the referenced Section 6.3 of OC#. 'd the Final Safet? Analyses Report indicates _3876-4.'t.

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makes me wonder whether the right reactor wcs use

/1' - j?f, consistently in the license subnittgLI..

,h h'o I would like the staff to confirn for ne by c.o.b. Monday, yl0 March 5, 1984, wh' ether the reacto-rore which is referenced V y,g 'S in license Sectier. 2.1.2 as the basis for the reactor SAFETY h h[d LIMITS, actually ccrryopends to -he core in the Grand Gulf reactor.

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d Victor Gilinsky cc:

Chnirman Pr.11e.dino Cor:dssioner Roberts Cocc.issioner Asselstine

~'C-Commissioner Bernthal S033-yg.yg y-,

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