ML20236H198

Rev 1 to TS Change Request 230 to License DPR-16,deleting Requirements That Biennial EDG Insp & Station Battery Capacity Tests Be Done While Plant Is Shutdown & Increasing Per Cent of Rated Power to Be Reached During Diesel Testing

ML20236H198
Person / Time
Site:	Oyster Creek
Issue date:	06/29/1998
From:	Roche M GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20236H163	List: ML20236H160 ML20236H198 ML20236H218
References
NUDOCS 9807070119
Download: ML20236H198 (5)

Text

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GPU NUCLEAR CORPORATION ,

OYSTER CREEK NUCLEAR GENERATING STATION l Facility Operating License No. DPR-16 l l

4 Technical Specification Change Request No. 230, Revision 1 Docket No. 50-219 l

l Applicant submits, by this Technical Specification Change Request No. 230, Revision 1, to the Oyster Creek Nuclear Generating Station Operating License, a change to pages 3.7-2,4.7-1,4.7-2, 4.7-3 and 4.7-4. j BY bc krY Michael B. Roche Vice President and Director Oyster Creek Sworn and Subscribed to before me this _ /// LL. day of Ox'A l

, 1998.

v vdcuih f [th A Notary Public of NJ GERALDINE E. LEVIN NOTARYMALC0FIEWSWEY MycomammienEmpbes,_ /_. -Y 9 'o I

9807070119 990629 PDR ADOCK 05000219 P PDR

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TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR) No. 230 (Rev.1)  !

l GPU Nuclear requests that the following changed replacement pages be inserted into

{ existing Technical Specifications r >

l Replace existing pages 3.7-2,4.7-1,4.7-2,4.7-3 and 4.7-4 with the attached revised replacement pages 3.7-2,4.7-1,4.7-2,4.7-3 and 4.7-4.

i II. REASON FOR CHANGE L

Oyster Creek's current Technical Specifications (TS) include a requirement that the emergency diesel generators (EDG) be given a thorough inspection at least once

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every 24 months during shutdown. Inspecting the diesels and . servicing them, if  ;

necessary, is prudent and recommended by the vendor. GPUN has made the '

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inspection part of the facility's maintenance program.

Removing the phrase "during shutdown" from specification 4.7.A.3 would permit l l scheduling such activities during operating periods. Current specifications permit l the reactor to remain in operation for a period of seven days with one EDG out of j service, provided certain conditions are met. Specification 3.7.C.2 will be revised to 1 reflect that an EDG would be made inoperable for the biennial inspection. The  ;

inspections would permit greater availability of the EDGs during planned L

shutdowns.

i L Specifications 3.7.C.2 and 4.7.A.1 currently require that the diesels be started and j loaded to not less than 20% power during the biweekly tests. Since that specification was written the diesels have been upgraded and that figure is no longer adequate. The proposed value is 80% of rated load that is appropriate for the diesel upgrade and consistent with the surveillance criteria.

Specification 4.7.A.5 requires that the diesel starting batteries be tested and monitored the same as the station batteries. A new provision would permit the l

battery capacity test to be skipped if the diesel startmg batteries were replaced durmg the previous biennialinspection.

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' Finally, several wording changes have been made to enhance clarity. -In specification 4.7.A.5 a lower case "b" in a reference to specification 4.7.B las been corrected. In addition, in specification 4.7.B.3.b the word " volts" has been deleted.

That specification concems specific gravity and specific gravity is not measured in volts. In addition the Basis of Specification 4.7 has been modified to reflect the  ;

change to 80% loading of the diesel during the biweekly test and to clarify a statement about battery capacity.

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III. SAFETY EVALUATION JUSTI'FYING CHANGE 1

l The Bases of Oyster Creek TS 3.7 " Auxiliary Electrical Power" states that the objective is to "assum an adequate supply of power with at least one active and one standby source of power available for operation of equipment required for a safe plant shutdown.". The Bases also cite the probability analysis in the Oyster Creek l FDSAR Appendix L which is based on one diesel and shows that even with only one diesel, the probability of requiring engineered safety features at the same time as

. the second diesel fails is quite small. Since that analysis was performed, the reliability of the diesels has been enhanced and, although not analyzed for accident conditions, an additional source of AC power has been installed.

l Specification 3.7. " Auxiliary Electrical Power" describes four active and two -

! standby (EDG) sources of power excluding the plant's main generator. Two active sources (e.g. two 230kV lines or one 230kV line and one 34.5kV line) must be available during plant operation. In addition, if one diesel generator becomes inoperable during plant operations, the other diesel must be tested periodically and none of the engineered safety features fed by the operable diesel can be out of

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service. If the proposed activity were approved, EDO inspection could be done  !

! with the reactor online, making one diesel inoperable. However, two active

! sources of power would be required and the Limiting Condition for Operation

(LCO) for the diesel generators must be met or exceeded.

l In September 1992, the NFC issued NUREG-1433 which reflects the generic

! requirements for General Ele tric plants. The STS include definitions, LCOs and i surveillance requirements. This document does not include a specification j

! concerning theinspection ofEDGs.

j. Upon approval of this request, GPU Nuclear could inspect, and service if required,

! the EDGs during reactor operations. Such an inspection would be planned well in advance, ensuring that there would be no conflicting work and all components l requimd to be operational would be in service. Inspecting the EDGs while the l reactor is on line obviates the need to inspect them when the unit is shutdown.

While other tests and activities relative to the EDGs will continue to take place

! during shutdown, the percentage of time that they are available during shutdown will significantly increase. As a result, shutdown risk would be mduced.

l. He provision permitting the skipping of the diesel starting battery capacity test is l predicated on the starting battery having been replaced in the previous biennial L

inspection of the diesel. A new battery would have been tested and qualified prior to installation. He battery capacity would not have degraded significantly in less than two years.

The increase from a minh cnn of 20% loading of the diesel during testing to an 80%

loading brings the specification into line with the current operations of the diesels and is consistent with the surveillance criteria. The Basis for Specification 4.7 has

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• been revised accordingly. Finally, two wording changes were made to enhance understanding and a minor typographical error has been corrected. These changes are administrative in nature. As such, they have no effect on safety.

i s. IV. NO SIGNIFICANT HAZARDS CONSIDERATION i

GPU Nuclear has determined that this TSCR poses no significant hazard as defined by the NRC in 10 CFR 50.92.

1. State the basis for the determination that the proposed activity will or will not increase the probability of occurrence or the consequences of an accident.

'Ihe proposed activity deletes the requirement to inspect EDGs during shut l down from the Technical Specifications and permits skipping diesel starting l battery capacity tests for recently installed batteries. The minimum loading

!- during the testing of the diesels has been increased from 20% to 80%. In addition, wording changes were made to enhance clarity and a minor typographical error was corrected. During reactor operations other power sources are available to compensate for one diesel being out of service. The inspections and testing will continue to be done with the same intervals and-l the 80% loading is a more stringent requirement. Therefore, these changes l do not affect the design or performance of the EDGs or their ability to perform their design function.

l l' 2. State the basis for the determination that the activity does or does not create a possibility of an accident or malfunction of a different type than any previouslyidentified in the SAR.

l' The EDGs are not the source of any accident described in the SAR. These changes do not modify the design or performance of the EDGs and do not affect plant functions or actions. Current specifications permit one diesel generator to be inoperable for up to 7 days and this change will not impact that time frame. Therefore, the proposed change does not create the l possibility of an accident or malfunction of a different type than those '

previously identified.

3. State the basis for the determination that the margin of safety is not reduced.

The proposed changes are designed to improve EDG reliability and availability during shutdown periods by providing flexibility in the scheduling and performance of maintenance. The surveillance intervals are unchanged and operability requirements are not modified. The proposed

I activity does not aiter the basis of any technical specification that is related to the establishment or maintenance of a nuclear safety mrrgin. Therefore, the margin of safety is not significantly reduced by this acticen.

. V. IMPLEMENTATION

! GPUN requests that the amendment authorizing this change be effective upon l

issuance.

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