ML20038B135

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Tech Spec Change Request 72 for Amend to License DPR-24 & DPR-27,changing Tech Specs 15.3.1,15.3.3 & 15.3.8 to Ensure Redundancy of Decay Heat Removal Capability Under All Operating Conditions
ML20038B135
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 11/16/1981
From: Burstein S
WISCONSIN ELECTRIC POWER CO.
To: Clark R, Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20038B136 List:
References
TAC-42114, TAC-42115, NUDOCS 8111240759
Download: ML20038B135 (3)


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Waconsin Electnc eomcouew a 231 W/ MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 ng'!

1 November 16,.1981 f'

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m' Mr. H. R. Denton, Director -

Office of, Nuclear Reactor Regulation 6 - YI U.'S.; NUCLEAR REGULATORY COMMISSION lb h .A Q-

[ . Washington, D. C.( 20555-g g~9 3 i98> <hd x , .

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7[ 7%' Attentio'n: J4r. R./AY Clark,' Chief'_ y ~

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~~. Operating; Reactors Branchf3

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' Gentlemen: ,

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.# d ' DOCKET NOS. 50-266 AND.50-301 I

- ..- [ TdCHNICAL SPECIFICATIONoCHAMGE-REOUEST.NO. 72

] 7- -> REDUNDANT DECAY HEAT REMOVAL ~-

.# 4 / POINT . BEACH' NUCLEAR : PLANT, UNITS 1 AND 2

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In hecordance- with Tthe requdstwin Mr. Robert A.

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Clark's-

, lghter ~ d,hted' A'ug'ust '14, 1981, Wisc~onsin Electric Power Company (Licensee)b reque,st;s amendments' to Facility Operating Licenses ,

DPR-24'and DP" ~' forsthe Point Beach' Nuclear # Plant,. Units 1tand 2, resperdtid fne purpose . of these' amendments 'is to incorporate .

certainj%an s .Into the Technical Specifications to ensure -

redund'aficy.of decay heattremoval capability'under all operating a f ,qonditions. 'y%

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,.g In a letter. dated June 11, 198.0',A he'NRC requested O, Licensee to review the Point Beach Nuclear Plant Technical Specifications to ensure that redundancy of decay heat removal was provided under all operating conditions [ We responded, by 3 ' letter; dated October 14, 1980, that~the' existing Technical

- SpedificationsE did address this concern and she Specifications ~

~F required no changes.f Specific references to the Specifications: . .

were provided to support Licensee's~determinationa' In Mr. Clark's

' August 14 letter, the NRC. agreed that for conditions corresponding '

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/ to normal power operation, hot shut-down and refueling shut-down,

  1. --.the Technical Shecifications'brovided-for redundancy in decay'

.i hea't-remofel bapability. .However, for conditions corresponding -l to.operaticna.1"modesr4 and 5,^that is at' reactor coolant tempera- R

'tures betwees 350*F and 140 F, the NRC again request'ed proposed Technical-Specification changes be submitted. _

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Mr. H. R. Denton November 16, 1981 In response to this request, Licensee.has proposed the attached Technical Specification changes. Specific changes on each of the attached pages have been indicated by margin bars. A discussion of these changes follow. >

1. Specification 15.3.1.A.1.b has been changed by substituting the terminology " rated power" for-

" thermal power". Thetspecification, currently written as "l% of thermal'p'ower", does not define a specific core thermal output.

2. A new Specification 15.3.1.A.2 has been provided, modeled after the standardized technical speci-fications, to require redundant operable decay heat removal methods when reactor coolant tempera-tures are between 350 F and 140*F. A section has also been included to clarify the decay heat removal requirements when the reactor coolant temperature is less than 140 F and to specify a permissible operating condition to permit periodic maintenance of the residual heat removal system.
3. The Basis for Specification 15.3.1.A has been modified to include a discussion of, and basis for, the new Specification 15.3.1.A.2.
4. Specification 15.3.3.A.2 has been reworded. As presently written, this Specification requires the reactor to be placed in a cold shut-down condition if a residual heat removal pump is out of service for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This action results in putting tfe reactor coolant system in a condition without redundant decay heat removal capa-bility. Therefore, the Specification has been rewritten to permit keeping the reactor in a hot standby condition with reactor coolant temperatures between 500*F and 350'F so that the steam generators may be used for redundant decay heat removal while the residual heat removal syrtem is repaired.

I 5. Specification 15.3.8.A.4 has been changed so that it is consistent with new Specification 15.3.1.A.2.

Reference is made to the entire residual heat removal loop rather than simply the pump. This specific change was suggested by the NRC_ Staff. A sentence has also been added to permit securing the operating residual heat removal loop for up to one hour in an eight hour period when flow would interfere with refueling operations.

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i Mr. H. R. Denton November 16,-1981 c ,

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i -In accordance with the provisions of 10 CFR Part 170.22,.we have determined.that since,these TechnicalsSpeci-

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, ' fication changes involve a.singlo' issue, redun' dant decay. ,

heat removal, for which an'NRC position bas been previously identified,this license. amendment application should be classified as a. Class III amendment. The duplicate amendment'

' for the second Point Bea'chiunit may be classified asja Class I '

amendment. Therefore, we~have enclosed herewith:a check drawn .

i in:the amount of $4,400 for the amendment approval fee. ,

As specified in the CommissioiUs regulations, w'e are

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providing three signed origincls and, tinder separate cover, forty

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copies of this license amendment' application and attachments.

l Should you have any questions concerningithe, contents of this -

application, please notify us so that we.may address your Concerns.

Very truly yours,

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G' tar.4 i Executive Vice President Sol Burstein Enclosures (Check No. 646108)

Copy to NRC Resident Inspector i

.I Subscribed and' sworn to before me this /(ch day of November 1981.  ;

dC4%48&n $P +

, Notary Ptiblic, State of Wisconsin My Commission expires /, //2N/ .

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