ML20082Q485
| ML20082Q485 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/05/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082Q482 | List: |
| References | |
| NUDOCS 9109120193 | |
| Download: ML20082Q485 (3) | |
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Sf f ETY EV,AL,UAT10N BY _THE,0((j,CE,0F_N,tg,E A,R, pE ACTOR REGUL,ATJON R,EL,AT,E,D,,TO AliENDMENT NO.153 TO F ACILIT Y OP,ER,ATJpG,,LJ C,EFSE, NO., pf,R,-J 6 GPU NUCLEAR CORc0 RAT 10N AND JEF,SEF llfM(Al]MQQQRPAp,Y OYSTEP CREEK NUCLEAR CENERATING STATION 00C KE~ p0,.,,50,,2J 9 1.0 Jp,T,R,0 DUCT ION The licensee, GPU Nuclear Corporation (GPUN), by letters dated August 14, 1990 and Jane 18, 1991, proposed changes in Sections 3.4.A 3, 3.4.A.4, 3.4.D.2, and the associated Bases of the Technical Specification (TS) for the Oyster Creek Nuclear Generating Station (OCNGS). The proposed changes would revise the TS to incorporate the 10 CFR 50.46 loss-of-coolant accident (LOCA) anal basis for the Average Planar Linear Heat Generation Rate (APLHGR)ysis that is the limits provided in the TS Section 3.10, " Core Limits." The Limiting Conditions for Operation (LCOs) and Bases were changed as appropriate. The NRC staff has reviewed the safety implications of the proposed TS changes, and this evaluation presents a summary of the review.
2.0 EVALUAT1_0N A specific listing and evaluation of the proposed changes are given below:
(1) TS 3.4.A.3:
Part (b) is the only new addition in this section, which
"'n~dlcates that when one of the core spray loops becomes inoperable during i
the run mode, the average plarar linear heat generation rate (APLHGR) of all the rods in any fuel assembly, as a function of average planar exposure, at any axial location shall not exceed 90 percent of the limits given in Specification 3.10.A.
The action to bring the core to 90 percent of the APLHGR limits must be completed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> af ter the system has been determined to be inoperable. This proposed change of lowering the APLHGR is conservative relative to the existing specification and, therefore, acceptable.
Furthermore this proposed change is conservative in assuring that the peak clad temperature will remain below 2200 F under 10 CFR 50.46 Appendix K requirements when one core spray is out of service.
In the associated Bases, the licensee attempted to justify the use of the existing specification which allows reactor operation up to a period of 7 days when one of the core spray loops becomes inoperable during the run mode. The NRC staff acknowledges that the associated Bases are consistent with the current specification.
However, we note that a break in the pipe between reactor vessel and the core spray check valve in one loop while the other loop is inoperable has the potential to lead to an 9109120193 910905 PDR ADOCK 05000219 P
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uenitigated LOCA.
Furtherriore, the normal allowed time of reactor oper ation in such a degraded emergency core cooling system (ECCS) configuration is typically less than 7 days for other plants.
Realizing the potential vulnerabilities that may exist in this particular segment of the plant, the licensee is examining the core damage frequency contribution of core spray line breaks separate from other LOCAs in the Individual Plant Examination (IFE) for the OCNGS.
The results from this analysis can provide a technical basis for evaluating this issue via the licensee's IPE submittal. The UFC staff also recommends that due to the enhanced importance of the segment of the pipings between reactor vessel and core spray check valve in the core spray loops, this particular segment of the pipings be closely monitored for potential degradation.
(2) TS 3.4.A.4:
This section has been revised to indicate that in the event of an inoperable core spray main punp, the other core spray main pump in the loop is demonstrated daily to be operable, and the APLHGR of all the rods in any fuel assembly, as a function of average planar exposure, at any axial location shall not exceed 90 percent of the limits given in Soecification 3.10.A.
The action to bring the core to 90 percent of the APLHGR limits must be completed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> af ter the component has been determined to be inoperable. The proposed changes are conservative and the value of 90 percent is based upon the use of approved models, meet applicable criteria and are acceptable.
(3) TS 3.4.D.2:
This section has been revised to indicate that the symbol
'22' be changed to "less than." This is merely an editorial change, and has no safety implications.
The proposed change is acceptable.
As a result of our review, which is presented in the evaluation above, the NFC staff concludes thet the pronosed Technical Specification changes are acceptable.
3.0 STATE CONSULTATION
in accordance with the Concission'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
Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental assessment and finding of no significant impact have been prepared and published in the Federal Register on August 6, 1991 (56 FR 37372). Accordingly, based upon the environmental assessment, the NRC staff has determined that the issuance of the amendment will not have a significant effect on the quality of the human environment.
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5.0 CONCLUSION
The Commission 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, (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:
M. Razzaque Date:
September 5, 1991
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