ML20006E073
| ML20006E073 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/02/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006E072 | List: |
| References | |
| NUDOCS 9002160200 | |
| Download: ML20006E073 (2) | |
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l SAFETY. EVALUATION SY.'lHE.0FFICE OF.WUCLEAR. REACTOR. REGULATION
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RELATED T0 AMENDMENT NO.136 TO PROVISIONAL OPERATING LICENSE NO..DPR-16 GPU NUCLEAR CORPORATION AND 1
JERSEY CENTRAL POWER & LIGHT COMPANY-OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NC. 50-219
1.0 INTRODUCTION
Inaletter:datedDecember4,1989,GPUNuclearCorporation(GPUN),the licensee for Oyster Creek Nuclear Generating Station, proposed to revise Technical Specification (TS) 3.7.A to clarify operability requirements for i.itteries B and C and, in addition specify switchgear control power requirements associated-with each battery. The bases for Section 3.7 would
- also be clarified with respect to the 125 VDC System.
L 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 i
System. station-batteries. As addressed in-LER 89-020, the DC control power L
selector-switch for 460 VAC bus 182 had been improperly aligt.ed to non-safety E
related battery A.
The purpose of TSCR No.182 is-to clearly :specify the y
operability requirements'for batteries B and C and, in addition specify the
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switchgear-control power requirements associated with each battery.
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-2.0~ EVALUATION The licensee has modified Technical Specification 3.7.A.4 to indicate that u
batteries B and C and an assot.iated battery charger must be operable prior to D
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 guidence to plant personnel. Specification 3.7.A.4 has also been modified, in order.to
. provide clear guidance to phnt personnel, to include a statement concerning the source of DC control power for relevant bus switchgear addressed in
-1 Specification 3.7.A.I.
Neither proposed change alters the operability requirements or the manner in which the systems are operated. The bases has also been clarified with respect to the 125 VDC System.
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- The staff has reviewed the information provided by the licensee and has determined that the proposed changes clarify the operability requirements with respect to the 125 VDC System. Therefore, we conclude that the changes are acceptable.
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3.0 ENVIRONMENTAL CONSIDERATION
This amendment changes a requirement with respect to the installation or use of a facility component located within the restricted arer n defined in 1
10 CFR Part 20. We have determined that the amendment invcives no significant increase in the amounts, and no significant change in the types, of arty effluents that may be released offsite, and that there is no signif-icant increase in individual or cumulative occupational radiation exposure.
The staff has previously issued a proposed finding that this amendnent '
involves no significant hazards consideration and there has been no public coment ~on such finding. Accordingly, the amendnent meets the eli criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9)gibility Pursuant to 10 CFR 51.22(b), no environmental impact statement or environnental assessment need be prepared in connection with the issuance of this amendment.-
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety'of the public will not be endangered by operation in the proposed manner, and.(2) such activities will be conducted in compliance wit 1 the Commission's
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regulations, &nd (3) the issuance of the'amendnent will not be inimical to the common defense and security nor to the health and safety of the public.
. Dated: February 2, 1990 Principal Contributor:
A. W. Dromerick
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