ML20065H690

Application to Amend Licenses DPR-24 & DPR-27,revising Spent Fuel Pool Poison Surveillance Specimen Location & Clarifying Conditions for Operating power-operated Relief Valves

ML20065H690
Person / Time
Site:	Point Beach
Issue date:	09/30/1982
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20065H692	List: ML20065H690 ML20065H723
References
TAC-48929, TAC-48930, NUDOCS 8210050222
Download: ML20065H690 (3)

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lHsconsm Elecinc w.ecwne 231 W. MICHIGAN, P.O. BOX 2044. MILWAUKEE, WI 53201 September 30, 1982 CERTIllED MAIL Mr. H. R..Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555

Dear Mr. Denton:

k DOCKET NOS. 50-266 AND 50-301 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 83 SPENT FUEL POOL POISON SURVEILLANCE LOCATION AND POWER-OPERATED RELIEF VALVE OPERABILITY In accordance with the requirements of 10 CFR Part 50.59, Wisconsin Electric Power Company (Licensee) hereby submits its application for amendments to Facility Ooorating Licenses DPR-24 and DPR-27 for the Point Beach Nuclear Plant, Units 1 and -

2, respectively. The purpose of thesa amendments is to authorize a change to the Point Beach Technical Specifications permitting locating of the spent fuel pool poison surveillance specimen in a position adjacent to the spent fuel _ pool divider wall and clarifi-cation of the limiting conditions for operation of the power-operated relief valves (PORV) and PORV indication.

Presently Specification 15.5.4.4 states that each spent fuel assembly storage location immediately adjacent to a spent fuel pool wall shall be restricted to storage of fuel assemblies having la cooling time of one year or more. As a part of the surveillance program established to verify the long-term acceptability of the borated silicon rubber neutron absorber sheets, Licensee has also committed to keeping a freshly discharged fuel assembly on each side of the poison surveillance samples. Poison surveillance ,

sample location slots were provided in both the north and south halves of the spent fuel pool, however, in the south spent fuel pool the surveillance sample poison location slot ~is adjacent to the spent fuel pool divider wall. This wall separates the north and south halves of the spent fuel pool. Unless the Technical Specifi-cation cnange proposed in this letter is approved, Licensee would have to maintain the poison surveillance samples in the north pool location or relocate the poison sample location in the south pool.  ;

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.210050222 DR ADOCK 0500026 20v20

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Mr. H. R. Denton September 30,'1982 I 1

The latter option would require temporarily relocating all the i

_ stored spent fuel assemblies into the north pool so that a diver _

could enter the south pooloto relocate the poison surveillance i F . sample storage-slot. This would result in personnel radiation j exposure which may be avoided if the following changes were -l

approved. .

We hereby propose that Specification 15.5.4.4Lbe revised to read:' J I

"Except for the two storage locations. adjacent to the j designated slot'for the spent.fuelistorage rack neutron r L

i absorbing material surveillance specimen irradiation,  !

spent fuel assembly storage locations immediately [

. adjacent to the spent fuel pool perimeter or divider .

walls shall not be. occupied by fue1Eassemblies which have been subcritical-for less than one year." l 3_

A revised spent fuel pool gamma heating evaluation has  ;

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been completed for the case of . tan) three-day decay fuel assemblies l Pl aced in storage locations immediately adjacent to the spent I

fuel pool divider wall. The analysis model gave a calculated l 4 concrete temperature of 206*F. Bechtel Power Corporation, the ~!

! contractor who conducted this analysis for Wisconsin Electric, J

concluded that the divider wall will not incur any structural -l damage or reduction of capacity as a result of having two three-day j decay fuel elements stored in the adjacent spent fuel storage- 1 rack locations.

Specification 15.3.1.A.4 requires that if a.PORV is i inoperable, the PORV shall be restored to operation within one i hour or the associated' block valve shall be shut. The basis for j l this specification defines a PORV as being operable .f leakage ,)

, past the valve doesn't exceed Specification 15.3.1.D limits and  ;

i the PORV has met its most recent channel test. The limiting i conditions for operation in Specification 15.3.1.A.4, however,

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do not differentiate between having the PORV inoperable because of i~ leakage or because of failure to satisfy the. channel functional .

test. In the latter case, placing-the control switch for the PORV  !

in the closed position disables the. control circuitry for the -

-j PORV operation and would. assure that the valve remained. shut regard- ,

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less of the status of pressure signals to the automatic control- 'i circuitry. This-would preclude having.to unnecessarily cycle l closed the associated block valve. If for any reason the PORV 4 were leaking, both temperature and flow indicators would' indicate .!

the leakage and, under these circumstances, the associated-  !

block valve.could then.be closed.-'A revision to this specifica-  ;

. tion has been provided withithe attached proposed Technical- .i

' Specification pages. [

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Mr..H. R. Denton September 30, 1982 i F

A-similar argument can be made for not closing the  :

. block valve if the PORV position indicator is inoperable.  !

Table 15.3.5-5, item 1, presently requires the block valve .

associated with a PORV to be shut if an inoperable PORV valve position indicator cannot be restored to operation within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. Again, placing the PORV control switch in the closed I position will ensure the PORV remains shut regardless of the' status of the PORV control' circuitry or position indication and precludes unnecessary cycling of the PORV block valves.

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If leakage past the PORV somehow develops, other sensors will indicate this leakage and, at that time, the block valve can be  :

shut. We also request that the time. period allowed.to correct a defective PORV or block' valve position indication be extended to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. This relaxation would permit Licensee more i flexibility in scheduling corrective maintenance prior to having i to'take the action specified in-column 3.of Table 15.3.5-5.

' In accordance with the schedule of amendment approval fees for reactor facility licenses as listed in 10 CFR Part'170.22,  ;

Licensee has determined that this license amendment approval for  !

i Point Beach Nuclear Plant Unit 1 should be classified as.a Class'III amendment in that the proposed Technical Specification j changes do not involve any significant= hazards considerations.  ;

l The amendment approval for Point Beach Unit 2 is a duplicate of  !

the Unit 1 request and is, therefore, classified as a Class I approval. Accordingly, a check in the amount of $4,400 is< enclosed as payment for the applicable Class III and I approval fees.- [.

As further specified in the Commission's regulations, we enclose herewith three signed originals and, under' separate 1 cover, 40 copies of this application for license amendments. ';

Please contact us if you have any questions concerning this submittal.

Very truly yours,

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b$ I Assistant Vice resident -

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C. W. Fay i Attachment (Check No. 695113) t

. Subscribed ~and sworn to before me i.

this 30% day _ of September 1982.  :

UP ha  :

Notary PdUlic, State of Wisconsin f My Commission expires *

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Copy to.NRC Resident Inspector-

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