ML20236G838
| ML20236G838 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/30/1987 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20236G842 | List: |
| References | |
| CON-NRC-87-106 VPNPD-87-459, NUDOCS 8711030312 | |
| Download: ML20236G838 (3) | |
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' Wisconsin lectnceomcowe 23 i W. MICHlGAN AO. 80X 2046, MILWAUKEE, WI 53201
'(414) 221-2345 10;CFR 50.90 VPNPD-87-459 NRC-87-106 October', 30, 1987-y CERTIFIED MAIL U. S. NUCLEAR REGULATORY COMMISSION Document Control Desk Washington, D. C.
20555 Gentlemen:
DOCKETS 50-266'AND 50-301 TECHNICAL SPECIFICATION CHANGE REQUEST 121 EMERGENCY DIESEL GENERATOR OPERABILITY l'
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POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2' In accordance with.the requirements of 10 CFR 50.59.andl50.'90,-
j Wisconsin. Electric Power Company (Licensee) hereby~ submits an-
-j application for amendment to Facility _ Operating Licenses DPR-24 Units 1 and 2.
. The and DpR-27 for Point Beach Nuclear ~ Plant, amendments would allow a one-time extension to the emergency, diesel generator operability requirements of Technical
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Specification 15.3.7.B.1.e.
The Technical' Specification page identifying the proposed change is attached.-
l The purpose of the proposed changesisito allow a one-time-1
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extension to the existing requirements of Technical
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Specification 15.3.7.B.l.e,which-permits-one' emergency diesel y
generator (EDG) to be inoperable for up'to.seven days.
This extension would be necessary t'ofpermit the: repair or.
replacement of emergency diesel generator component parts with s
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an improved design.-
j The provisions of Technical Specification 15.3.7.B. lie associated with testing of the operable diesel: generator will-When the affected diesel is taken out of
-remain unchanged.
service, the operability of the other diesel will.be. ensured by-performing the exercise test prior to removing the diesel from.
a service and daily thereafter until the affectedJdiesel is Additionally, Technical / Specification returned to service.
15.3'.0.C applier, in order to meetothefrequirement'of Technical ~
l Specification 15.3.7.B.1.e that associatedDengineered safety-L features be operable.
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NRC Document Control Desk October 30, 1987 page 2 Specifically, we plan to measure the backlash of the No. 1 idler gear in order to assess the need to replace the idler i
gear and stub shaft.
These measurements can be completed through an access port without disassembly.
The measurements i
would require the affected diesel generator to be out of service for approximately one day.
Should replacement of the idler gear and stub shaft be necessary,.bowever, the steps required to gain access include removal of the turbocharger assembly, decoupling and separating the generator, and removal l
of the engine's flywheel.
The amount of time for which the affected diesel generator would be out of service to complete the replacement has been estimated to be'approximately seven days.
This assumes working two 10-12 hour shifts per day and includes minimal contingency for unanticipated problems or delays.
If the replacement takes longer than seven days, we would be in violation of Technical Specification 15.3.7.B.l.e, which allows power operation of one or both reactors with one diesel generator inoperable for a period not exceeding seven days.
Therefore, we are proposing that the specific time period of diesel generator inoperability be extended one time l
per diesel generator to ten days for the purpose of replacing
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the No. 1 idler gear and its stub shaft and, if necessary, other engine components.
We propose that these amendments be in effect for a finite period to end December 31, 1988.
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We have evaluated this amendment request in regards to the criteria of 10 CFR 50.92 and have determined that this amendment will not result in a significant hazards l
consideration.
The first criterion of 10 CFR 50.92 concerns changes involving a significant increase in the probability or consequences of an l
accident previously evaluated.
The probability of occurrence of an event which would entail a demand on an emergency diesel generator is independent of the operability of the emergency diesel generator.
In addition, the consequences of such an event, although dependent on the operability of the emergency diesel generators, are independent of the amount of time the emergency diesel generators are in a specific operational status.
This is because the testing provisions of Technical Specification 15.3.7.8.1.e to ensure operability status of the operating diesel generator will not be changed.
Operability of the other diesel generator will be demonstrated on a daily basis.
Therefore, the probability or consequences of previously evaluated accidents are not increased by altering the amount of time one emergency diesel generator is inoperable.
NRC Document Control Desk October 30, 1987 Page 3 The second criterion involves creating the possibility of a new or different kind of accident from any accident previously evaluated.
The change in the amount of time for which an-emergency diesel is inoperable does not. result in the new or l
different kind of accident.
The existing specification already permits, and the plant is analyzed for, a limited-unavailability of one EDG.
The third criterion concerns a significant reduction in a margin of safety.
The margins of safety provided in the Point' Beach safety analyses are not dependent on the amount of time the EDG's are in a specific-. operational status.
Therefore, the proposed change to extend this unavailability for a period not exceeding ten days for each EDG does not reduce the margin of safety.
In addition to the above evaluation, in accordance with 10 CFR 50.92, the following emergency diesel generator reliability data for the period 1983 through June 1987 are provided.
Emergency diesel generator GO1 had 174 start demands with one failure to start.
Of the GO1 start demands, 164 were load demands with no failures to load.
Emergency diesel generator GO2 had 173 start demands with no failures to start.
Of the GO2 start demands, 164-were load demands with no failures'to load.
We have enclosed a check in the amount of $150 for the application fee as prescribed in 10 CFR 170.
Please contact us j
t if you have any questions concerning this request.
Very truly yours, I
p NJ y l
C. W./ Fay l
Vice President
.f Nuclear Power Enclosures (Check 974664)
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Copies to NRC Regional Administrator, Region III j
NRC Resident Inspector l
R.
S. Cullen, PSCW j
I Subscribed and sworn to before me this 3o #1 day of () c f o bev, 1987.
Ca u d ta Notary Public, State"6f Wisconsin My Commission expires 5/27!76
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