ML20034G571
| ML20034G571 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/04/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034G570 | List: |
| References | |
| NUDOCS 9303100121 | |
| Download: ML20034G571 (3) | |
Text
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NUCLEAR REGULATORY COMMISSION
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT N0.162
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TO FACILITY OPERATING LICENSE NO. DPR-16 GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-219
1.0 INTRODUCTION
Pursuant to 10 CFR 50.90, GPU Nuclear Corporation (GPUN/ licensee), operator of the Oyster Creek Nuclear Generating Station, submitted on August 12, 1992, a Technical Specification (TS) Change Request No. 202. This is a change request to Appendix A of the Facility Operating License No. DPR-16.
The change request proposes to revise the low condenser vacuum reactor scram function in TS Table 3.1.1, Function A.6, to represent the as-built condenser vacuum trip system.
2.0 EVALUATION Figure 1, reproduced from the licensee's submittal, represents the logic diagram for the reactor trip initiated by low condenser vacuum. A low vacuum in any condenser section (A, B, and C) actuates two independent vacuum trip systems, VT-1 and VT-2, which in turn operate four switches RSCS-11, RSCS-12, RSCS-21, and RSCS-22.
RSCS-11 AND RSCS-21, input to reactor protection system RPS I, and RSCS-12 and RSCS-22 input to RPS II. The existing TS Table 3.1.1, Function A.6, specifies a minimum of two operable trip systems and two operable instrument channels per operable trip system.
This had been interpreted to mean that RPS I, and P,PS II, and RSCS-11, RSCS-21, RSCS-12, and RSCS-22 must be operable.
However, this interpretation does not ensure that a low vacuum in any one of the three condenser sections will initiate a reactor trip.
During actual condenser transients, the licensee observed that vacuum in the three condenser sections did not fluctuate equally.
Similar uneven condenser pressure variation was also observed in the licensee's RELAP5 M002 computer simulations.
To overcome this limitation, the licensee proposes to change TS Table 3.1.1, Function A.6 to require a minimum of one operable trip system (VT-1 or VT-2) and three operable instrument channels (bellows) per operable trip system.
9303100121 930304 PDR ADOCK 05000219 P
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i The licensee does not take credit for the low condenser vacuum reactor trip in I
the Final Safety Analysis Report (FSAR) Chapter 15 analysis nor for any other transient analysis in the FSAR because this-low condenser vacuum reactor trip is provided as a backup to turbine trip to protect the condenser and turbine and not for reactor protection.
Based on the above evaluation, the staff concludes that the proposed changes to the TS do not involve an unreviewed safety issue or change the plant safety i
and, therefore, the changes are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New Jersey State official was notified of the proposed issuance of the amendment.
The State official-had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no i
significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commis.; ion has previously issued a proposed finding that the i
amendment involves no significant hazards consideration, and there has been no public comment on such finding (57 FR 42775). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or j
environmental assessment need be prepared in connection with the issuance of the amendment.
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5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, i
that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
S. Mazumdar
Attachment:
Figure 1 Date:
March 4, 1993
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'Fioure 1 Low Condenser Vacuum Scram Function f.
I condenser condenser condenser.
A B
C 1
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II~
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!I bellows instrument 1A 1B 1C 2A 23 2C channel u
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vacuum vacuum trip trip l
system system one two i
t c
RSCS-11 RSCS-21 RSC5-12 RSCS-22 p
p u.
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or or '
i reactor reactor protection protection system system div 1 div II T
t Signal Key and Sensing line Mechanical / Hydraulic F
Electric reactor i
scram i