ML20105B996

From kanterella
Revision as of 19:14, 23 September 2022 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Submits Addl Info Re Revised TS Change Request 142 to Licenses DPR-24 & DPR-27,submitted Via 900907 & s, Incorporating Upgraded Testing Requirements for safety- Related Batteries,Per NRC 920519 Meeting Request
ML20105B996
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 09/11/1992
From: Link B
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20105B997 List:
References
CON-NRC-92-109 VPNPD-92-306, NUDOCS 9209220006
Download: ML20105B996 (4)


Text

.

Wisconsin 1

J Electnc POWER COMPAtH rv w wwxv; n > ,. m vwww a u ; mu:w tw VPNPD-92-306 NRC-92-109 September 11, 1992 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, D.C. 20555 Gentlemen, DQCKETS 50-266 AND 50-301 REVISED TECHNICAL SPECIFICATION CHANGE REOUEST 142 FIFTH SAFETY-RELATED BATTERY AND DATTJa.Y SERVICE AND PEREOEMAILCE TFaSTING POItLT_Jrr\CH NUCLEAR PLANT, UNITS 1 ANDl By letter dated September 7, 1990, as modified in a letter dated May 10, 1991, Wisconsin Electric Power Company, licensee for the Point Deach Nuclear Plant, Units 1 and 2, submitted a license amendment application for DPR-24 and DPR-27, respectively. This application requested amendments to incorporate upgraded testing requirements for the safety-related station batteries and to reflect a fifth safety-related battery that is being installed at Point Beach. In a meeting at Point Beach Nuclear Plant on May 19, 1992, with members of your staff, we committed to provide additional information supporting our request for a 24-hour allowed outage time in the Limiting Conditions for Operation (LCOs) for the safety-related batteries.

Presently, Technical Specification Section 15.3.7, " Auxiliary Electrical Systems," requires all four existing safety-related station batteries to be operable in order to make one or both reactors critical. During operation, one safety-related battery may be taken out of service for a limited period of time.

Batteries DOS and D06 were installed as part of the original plant DC systems. .These batteries have an allowed outage time, defined in the LCO, of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Safety-Related Batteries D105 and D106 were installed as part of the post-TMI modifications to provide an uninterruptable power supply to the third and fourth instru-mentation channels. At the time of installation, D105 and D106 were not considered as critical to the operation of PBNP as Batteries DOS and D06. Therefore, a 72-hour LCO was established for Batteries D105 and D106, effective March 1, 1985, by Amendments 92 and 97 to DPR-24 and DPR-27, respectively.

9209220006 920911 ADOCK 05000266 (D\

V\

l PDR P PDR ws,n una,nm n <w-wa s - _. - - -

- -. - . . . . ~ . . - . - - - . . _ _ - . - - - . - . _--.-.-

e Document Control desk

_. September 11, 1992 Page 2 Due to system upgrades and added instrumentation since the installation of D105 and D106, these batteries have taken on increased importance to the safe and reliable operation of PBNP.

Therefore, in Technical Specification Change-Request 142, we proposed a 24-hour LCO for Safety-Related Station Batteries D105 ,

and D106. This LCO time is consistent with the licensing bases for PBNP while allowing sufficient flexibility for continued safe operation of PBNP if any one safety-related battery in operation is declared out-of-service.

We are-installing a fifth safety-related battery at PBNP. The fifth safety-related battery is a swing battery which can be used in place of any of the four existing safety-related station batteries. This-will allow us to remove a battery from service to perform the service and performance testing propescd in Technical Specification Change Request 142, while maintaining the necessary degree of redundancy. As a swing battery, we expect it will be available under normal circumstances to take the place of any one of the four other safety-related batteries should one of the other batteries be declarea out of service. Based on our initial assessments, we expect it will take, under controlled conditions, a minimum of two hours to tie in the swing safety-related battery to any one of the four existing DC distribution systems.

Performance of the proposed service or performance tests on -

station safety-related battery will required removing the battery from service for a period of at least two days. In addition, other planned evolutions, such as performing an equalizing charge on a single cell or entire battery will necessitate removing-the affected battery from service for an extended period cf time. The fifth safety-related battery will be utilized to assure that four safety-related batteries remain in service during planned evolutions.

If however, one of the remaining four batteries should be determined to be operable during testing or other planned evolutions, there would be insutficient time under the two-hour LCO recommended in NUREG-0452, " Standard Technical Specifications for Westinghouse Pressurized Water Reactors," to complete corrective actions prior to commencing shutdown of both PBNP units. For example, jumpering out of a single defective cell takes approximately 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. Cleaning, reassembly, and retorquing of intercell connections takes approximately four hours. These times do not account for the call-in response time for maintenance

l. personnel if the work must be performed on an emergent basis on a

, backshift. Therefore, we believe the adoption of a two-hour LCO l

may result in the PBNP units undergoing unnecessary transients. A 24-hour LCO for all in-service safety-related batteries, consistent 4

i

-se . m,a 4,. '=m

, g ,y & , -,y a, -r,,. , ,w-,- * + , g-w--.m. - - - -.-i w= +--g---ne , w

hi-1

- J Document Control Desk September.11, 1992 Page 3 with our licensing basis for DOS and D06, is appropriate and assures the safe and reliable operation of the Point Beach' Nuclear Plant.

We have made two administrative changes-to the proposed Technical Specifications and bases. The changes are related to_the designation of-the fifth safety-related battery and battery performance testing. The fifth safety-related battery has be6n designated D305. Our original submittal indicated this battery-would be designated D205. The D205 designation is being given to the new nonsafety-related. batteries for Units 1 and 2.

In a letter dated May 16, 1990, the NRC staff indicated that battery service testing should be performed in addition-to performance discharge testing. This position was based on the assumption that the performance-test did not completely envelope the worst case duty cycles (service test) for Batteries DOS and D06. However, calculations demonstrate that the performance discharge tests will completely envelope the worst case duty cycles for Batteries DOS, D06, D105, and D106 after the turbine bearing emergency lube oil pumps are removed from the DOS and D06  :

batterjes. The turbine bearing emergency lube oil pumps will'ba removed from Batteries DOS and D06 and rawered from nonsafety-related batteries being installed at PBNP. This installation will-be cctpleted by December 31, 1992. We discussed this: issue with Dr. Saba Saba and other NRC personnel at our meeting-at PBNP on May 19, 1992. IEEE Standard 450, Section 5.2, allows a performance test to be used in lieu of-a service test based on the assumption that the performance test completely envelopes the service test.

We have changed the bases for Technical Spec.ification Section 15.3.7 to indicate that the performanca test entirely envelopes the i service test.

- Tnese-changes are administrative in nature and-do not alter the conclusions contained in our evaluation and determination of no j significant hazards contained in our September.7, 1990, submittal '

as modified by our May 10,.1991, letter. A complete copy of the revisca Technical Specification pages with these proposed _-changes included is attached.

u< sre committef to complete the. installation of the fifth safety-

' elated battery by December 31, 1992, and presently plan to perform tne installation during the upcoming Unit 2 outage schedulad for September 26 through November 12, 1992. We request that the _

l proposed-amendments be issued and made effective upon completion of L installation and testing of the' fif th safety-related battery, but no later-than December 31, 1992.

.m - . A ,-

- . . . - . . . - - . - . - - . - . - . - . . . . . . - - - - - . ~- _.. . . - - - . . . = . .

-Document' control Desk September 11, 1992 l Page 4 :l

'i i

If yc,u have any questions, or require additional information, l please contact us, l l

Sincorcly, .

s

. . , - /

13ob Link Vice President  !

Nuclear Power l 1

, -l l TGM/jg l l

Attachment I

cc: NRC Regional Administrator, Region III  !

NRC Resident Inspsator L. L. Smith, PSCW l

l l

Subscribed and sworn to before me thin l'/t4 day of vfle o f-j

, 1992.

I 1

[7A &t t-40 9 , 7Y1 ewue<% j Notary Public,V State of Wisconsin  !

-1

'4y commission expices C-2-9c, i

I l-l l

l l

I l

l i

l a