ML19332F575

Application for Amend to License DPR-16,consisting of Tech Spec Change Request 182,modifying Tech Spec Section 3.7, Auxiliary Electrical Power.

ML19332F575
Person / Time
Site:	Oyster Creek
Issue date:	12/04/1989
From:	Fitzpatrick E GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML19332F573	List: ML19332F572 ML19332F575 ML19332F576
References
NUDOCS 8912150170
Download: ML19332F575 (4)

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GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION  !

Provisional Operating License No. DPR-16 Technical Specification  ;

Change Request No. 182 Docket No. 50-219 -

1 Applicant submits 6 by this Technical Specification Change Request No. 182 i to the Oyster Creek t!uclear Generating Station Technical Specifications, changes to pages. 3.7e1 and 3.7-3.

By .

Eugene E. Fitzp'af. rick Vice President and Director Oyster Creek Sworn and Subscribed to before me this k day of 1989.

L h). Nhw's A Notary Public of NJ DIAN A M. DeBLASIO N0nRY PUBLIC Of NEw ,

My Commissicli Expite_gJEpE 5751f/TSCR182 ,

8912150170 891204 ADOCK O KDR 2}9

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i UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the matter of ) Docket No. 50-219 l GPU Nuclear Corporation ).

p_ERTIFICATE OF SERVICE ,

This is to certify that a copy of Technical Specification Change Request {

No. 182 for Oyster Creek Nuclear Generating Station Technical Specifications, filed with the U.S. Nuclear Regulatory commission i on , has this day of , been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the -

United States mail, addressed as follows:

The Honorable Christopher Connors i Mayor of Lacey Township ,

818 West Lacey Road i Forked River, NJ 08731 Bv WPK

' Eugene E. Fit'zpatrick I

Vice President and Director Oyster Creek I

l-I r 5751f/TSCR182

OYSTER CREEK NUCLEAR CENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 182 Applicant hereby requests the Commission to change Appendix A to the above captioned license as indicated below. Pursuant to 10CFR50.91, an analysis concerning the determination of no significant hazards consJderations is miso presented:

1. Egglion to be Chanorld Section 3.7 ' Auxiliary Electrical Power"

2. Extent of_qhpngg Revise Specification 3.7. A to clarify operability requirements for batteries B cnd C and, in additiLn specify switchgear control power requirements associated with each battery. The bases for Section 3.7 has also been clarified with respect to the 125 VDC System.

3. Chances Reauested The requested changes are shown on the attached Technical Specification pages 3.7-1 and 3.7-3.

4. Discussion In the process of reviewing the existing OCNGS Technical Specifications, GPUN has identified the need to modify Section 3.7 as it relates to the 125 VDC System station batteries. As addresned in LER 89-020, the DC control power selector switch for 460 VAC bus 182 had been improperly aligned to non-safety related battery A. The purpose of TSCR No. 182 is to clearly specify the operability requirements for batteries B and C and, in addition specify the switchgear control power requirements associated with each battery.

Specification 3.7.A.4 has been modified to indicate that batteries B and C and an associated battery charger must bs operable prior to the reactor becoming critical. The proposed change does not alter the intent of the existing specification but, rather references the term

" operable" which is defined in the Technical Specifications and provides clear guidance to plant personnel. Specification 3.7.A.4 has also been modified, in order to provide clear guidance to plant personnel, to include a statement concerning the source of DC control power for relevant bus switchgear addressed in Specification 3.7.A.1. Neither proposed change alters the operability requirements or the manner in which the systems are operated.

5751f/TSCR182

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5. Determination:

GPU Nuclear has determined that operation of the Oyster Craek Nuclear Generating station in accordance with the proposed technical specifications does not involve a significant hazard. The change does not:

1. Involve an increase in the probability or consequences of an accident previously evaluated. The proposed change provides guidance with respect to the requirements applicable to the station batteries. There are no changes to plant configuration, availability of safety systems, the manner in which safety systems are initiated or plant operation. An a result, an increase in the probability nr consequences of an accident previoasly evaluated is not involved.

2. Create the possibility of a new or different kind of accident from any accident previously evalunted. The proposed criange does not alter the plant configuration, nor does it change the availability of safety systems or the manner in which they respond to initiating events. As auch, the possibility of a new or different kind of accident from any previously evaluated is  ;

not created.

3. Involve a significant reduction in a margin of safety. The operability requirements of the existing Technical specifications are not altered by the proposed change. In addition, safety system availability, initiation and response are not altered.

Therefore, the margin of safety is not reduced.

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5751f/TSCR182 ,

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