ML20063H321

Proposes to Modify TS 15.3.7.B.1.g,per 940112 Telcon W/Nrc Re Util Proposed DG Testing Requirement When One DG Inoperable,W/Regard to 930226 TS Change Request 156.Proposed TS Pages Encl

ML20063H321
Person / Time
Site:	Point Beach
Issue date:	02/08/1994
From:	Link B WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20063H327	List: ML20063H321 ML20063H334
References
CON-NRC-94-011, CON-NRC-94-11 VPNPD-94-017, VPNPD-94-17, NUDOCS 9402170319
Download: ML20063H321 (3)

Text

_ _

4

. . t Wisconsin Electnc  ;

POWER COMPAtW 231 W Michgan. PO Box 2046, Mnwoukee. WI 53201-2046 (414)221-2345 ~ ,

i VPNPD 017 10CFR50.4 NRC Oll 10CFR50.90  :

February 8, 1994

! Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION j Mail Station P1-137 '

Washington, DC 20555 Gentlemen:

I l DOCKETS 50-266 AND 50-301 l l RESOLUTION OF DIESEL GENERATOR TESTING CONCERNS i TECHNICAL SPECIFICATION CHANGE REOUEST 156 l

MODIFICATIONS TO TECHNICAL SPECIFICATIONS.

SECTION 15.3.7. SECTION 15.4.6. AND TABLE 15.4.1-2. '

! POINT BEACH NUCLEAR PLANT. UNITS 1 AND'2 f l

On February 26, 1993, we submitted. Technical Specification l Change Request 156, " Modifications.toLTechnical Specifications i Section 15.3.7, Section 15.4.6, and Table 15.4.1-2." The?

proposed changes added operating conditions, limiting conditions.

for operation (LCOs), zand surveillance requirements for the 120 VAC j vital instrument bus system inverters 1and the diesel fuelEoil. '

t system. This change request also prop'osed a surveillance fo'r the diesel generator room exhaust fans,and a revision to eliminate the diesel generator daily-testing requirement when one diesel generator is inoperable. We also proposed a change to the basis for Section 15.3.7 to support the above: changes and to remove ~an administrative error.

We submitted a letter dated November 30, 1993, addressing several unresolved issues associated with our original submittal. On January 12, 1994, a telephone conference was held between personnel from the Nuclear Regulatory Commission-(NRC) Office of Nuclear l

Reactor Regulation (NRR) and Wisconsin Electric Power Company (WE) .

The conference call was conducted to discuss our proposed diesel 1 generator testing requirement when one diesel generator is inoperable.

.j.

9002170319 940208 150053 9 . bh g

PDR ADOCK 05000266 ,? IC P

PDR Li A subsMiny oHIinvasia Emgr Caporathn : \

l i

Document Control Desk  !

February 8, 1994 i Page 2 In our November 30, 1993 letter, we proposed that, if one diesel generator is inoperable for reasons other than preplanned preventive maintenance or testing, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> either start the other diesel generator to ensure operability or. ensure the cause for failure of the inoperable diesel generator is not common to the other diesel generator. This proposed specification is consistent with the recommendations contained in Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requ!.rements for Testing During Power operation," dated September 27, 1993.

During our January 12, 1994 telephone conference, you disagreed with our proposal to test the operable diesel generator only once during the 7-day LCO period. You also disagreed with our proposal to waive the initial 24-hour diesel generator test if a common mode failure mechanism was proven not to exist or if the diesel generator inoperability wau due to preplanned maintenance or testing because of the design of the Point Beach Nuclear Plant (PBNP) emergency AC power system.

Although we still believe that the testing requirements proposed in our previous submittals provide an adequate safety margin, we are modifying our request based on discussions with your staff. We therefore propose to modify Specification 15.3.7.B.1.g to read:

15.3.7.B.1.g One diesel generator may be inoperable for a period not exceeding 7 days provided the-ether-d-lesel generat-or in tected= daily to encure operability and the-engineered cafety fcaterec accooieted with thic diccc1 genereter-shall be operabicKEhsishiihssFsd shfstyJfshtisEssTsss6dlit'EdNithithafopefsbieIdlesal senskaEbr7sisi6peribfssandjjereXtisst!sd? sit!hihytnsli rdqttifedssurvbillancMtsst?lritsrvaish sThs?dthsri" ~

dieselfg$nefstskisha ihibsT Athrtisd[ticWshsuFd" "

bperabilityNithin824dioursibsforeNrfsf tienfshEFy' in,tMthis,%C, OTa_hd,isve.i 7 ~

- n. ph,u_2sho_ur.si_t_hir_bh_f w .w ti_sr,! ~ ~~

This LCO shall not be allowed in conjunction with e.

or f. above.

We have reviewed the safety evaluation and the no significant hazards consideration forwarded to you in our February 26, 1993, ,

submittal. Because the above specification is more restrictive j than our original proposal, we believe the conclusions contained i therein remain valid.

l 1

Document Control Desk j February 8, 1994 i Page 3  ;

I A complete set of marked-up Technical Specifications pages which includes our proposed revision to Specification 15.3.7.B.1.g is enclosed.

Please contact us if you have any questions.

Sincerely, ,

/ /

dd6 Bob Link abEOif'gf,ll 7 Vice President Nuclear Power DAW /jg Enclosures cc: NRC Regional Administrator NRC Resident Inspector Public Service Commission of Wisconsin Subscribed and sworp before me on this 8"h day of IE bru A e v 1994.

b < , . . h), , . Mi/;

• Notdry()Public, State of Wisconsin V

My commission expires 10 -27 ~ h .

i l

I I

l

.