ML20236R894

Confirmation of Action Ltr Re Util Commitments to Make Corrections to Diesel Generator Loading,Uhs Max Temp & Svc Water Flow Balance,Per 871105 Meeting in Rockville,Md

ML20236R894
Person / Time
Site:	Crystal River
Issue date:	11/17/1987
From:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Wilgus W FLORIDA POWER CORP.
References
CAL, NUDOCS 8711240089
Download: ML20236R894 (2)

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<r DdeketNoN50-302L LicenseLNo. DPR-721

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,, Florida Power l Corporation:

' l.Mr.DWLS.!Wilgus .

"Vice President Nuclear' Operations-

. ATTN: 'Mana'ger, Nuclear. Licensing:

P. O.: Box.219 .

l Crystali River, FL : ' 32629 Gentlemen:..

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SUBJECT:

CONFIRMATION'0FcACTION LETTER 1 i

EThis l refers to"a meeting 'between - Florida Power Corporation and the NRC on 1 - . November 5,1987, in Rockville, Maryland. Three concerns, raised during a,

>, frecent10perational-Safety . Team Inspection, were discussed including: 1) Dies'el-

"- ~ Generator DG. Loading. 2) Ultimate Heat Sink Maximum Temperature,.and 3) SW Flow

u. Balance'. As a result of=that meeting, it is our understanding that FPC will' Ltake the1following corrective actions in.the respective time frames:

J 41.5 ~ Priorito entry into mode. 4.following its current refueling outage,'the j

. maximum DG' loading will be analyzed -to be within the 3300 KW/30 minute 4 i cumulative L rating ' of the ~ machine' and an' appropriate Technical l

~. Specification change will' be requested. . In addition, the DG's will-be 1 Ltested'at a 1oad not.to exceed 3250 KW for at least 5 minutes. This test, L

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o i or; additional n tests, - will . be1used to empirically determine, where

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, ' possible ; the accuracy of. the' figure . arrived at for the maximum' loading. j

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Also, the issue concerning maximum' air temperature to the. turbocharger Lwill be resolved.

LPrior to ' entry :into mode 3 following. the current refueling outage,

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additional > flow testing' of. the Nuclear Services Closed Cycle Cooling l System (SW) will be conducted to demonstrate adequate flow to'all critical ]

Jcomponents under emergency conditions, i l

3.  : Prior to exceeding a. seawater temperature. of 85'F appropriate changes l will be .madeLto ' procedures, Technical Specifications and/or equipment in

. ordere to. support operation with. a higher Ultimate Heat Sink design If final l resolution is.not achieved prior to 85 F, the plant

_ temperature.

shall be reduced in power commensurate with the design capabilities of the various support cooling systems.

• 4p FPCEwill- aggressively pursue long-term corrective actions to the DG 7

l loading' ist,ue, e.g., upgrade of existing DGs, addition of a third DG or replacemmt with larger DGs such that prior to the next refueling outage the. issue is resolved or commitments are in place to ensure prompt resolution'of the issue thereafter.

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• ,,,',1 ?If your' understanding of our: discussion. is different from that' above,; please inform this'. office; promptly..

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.J. tielson Grace W .. .. _

. Regional Administrator

.- .; CAL'502302-87-01' cc: -P. F. McK'ee, Director,'

' Nuclear . Plant Operations-a E. C.:Simpson, Director,.

Nuclear Site Support-bec: J.Taflor,E001 i

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NRC Resident; Inspector.

' Document: Control Desk.-

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