ML17312B694
| ML17312B694 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/11/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17312B693 | List: |
| References | |
| NUDOCS 9710010245 | |
| Download: ML17312B694 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
NPF-41 AMENDMENT NO.
106 TO FACILITY OPERATING LICENSE NO.
NPF-51 AND AMENDMENT NO.
85 TO FACILITY OPERATING LICENSE NO.
NPF-74 ARIZONA PUBLIC SERVICE COMPANY ET AL.
PALO VERDE NUCLEAR GENERATING STATION UNIT NOS.
1 2
AND 3 DOCKET NOS.
STN 50-528 STN 50-529 AND STN 50-530
- l. 0 INTRODUCTION By application dated December 27.
1996.
as supplemented by letter dated August 22, 1997. the Arizona Public Service Company (APS or the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License Nos.
NPF-41, NPF-51, and NPF-74, respectively) for the Palo Verde Nuclear Generating Station, Units 1, 2, and: 3.
The Arizona Public Service Company submitted this request on behalf of itself. the Salt River Project Agricultural Improvement and Power District. Southern California Edison Company.
El Paso Electric Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power,, and Southern California Public Power Authority.
The proposed changes would revise Technical Specification (TS) 3/4.6.1.3.b and the associated Bases sections (3/4.6.1.4.
3/4.6.1.6 and 6.16) to reflect an increase in the peak containment internal pressure for the design basis LOCA from 49.5 psig to 52 psig.
The August 22.
1997.
supplemental letter provided additional clarifying information that did not change the staff's original no significant hazards consideration determination that was published in the Federal Reeister on May 21, 1997 (62 FR 27794).
2.0 nAI UATION Technical Specification 3.6.1.3.b provides the limits on containment air lock leakage based on the calculated peak containment internal pressure for the design basis LOCA.
The limits on leak rates for containment air locks are required to meet the restrictions for containment integrity and containment leak rate.
The licensee indicated that a reanalysis using the 2.5 psig initial positive containment pressure limit resulted in a change to the calculated peak containment pressure for the design basis LOCA from 49.5 psig to 52.0 psig.
The proposed change is still below the containment design pressure of 60.0 psig.
In addition, it maintains at least a 10 percent margin 97i0010245 9709ii PDR ADQCK 05000528 P
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above the accepted peak calculated containment pressure following a LOCA as per NRC Standard Review Plan (SRP), Section 6.2. 1.1.A, "PWR Dry Containment, Including Subatmospheric Containments."
With this change, the containment will still meet the affected General Design Criteria 16. 38, and 50 of 10 CFR
- 50. Appendix A.
Further, the change will not invalidate the Acceptance Criteria "a" through "i" specified in Section 6.2.1.1.A of the SRP.
The licensee also stated that this change does not impact the radiological consequences of a LOCA as previously analyzed in Chapters 6 and 15 of the Updated Safety Analysis Report (UFSAR).
UFSAR Section 15.6.5.6 "Analyses of Effects and Consequences
- Large Break LOCA." states that "it is assumed that the containment leaks at the maximum rates allowed by the Technical Specifications. i.e.. O.l vol.X/d for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and half of that rate thereafter."
The dose calculation assumes that under accident conditions, the release of radionuclides to the containment is instantaneously mixed with containment air within'the containment free air volume.
This, results in a constant radioactivity per volume (curies/cc) independent of containment internal pressure.
Since radioactivity is assumed to be mixed in the containment free air volume. the volume percent leaked per day is equivalent to the fraction of radioactivity which leaks from the containment per day.
Therefore, the increase in the peak calculated containment internal pressure does not impact the radiological consequences associated with the design basis LOCA as analyzed in Chapters 6,and 15 of the UFSAR.
Based on the above.
the staff finds the proposed change for the peak containment internal pressure for the design basis LOCA to be acceptable as this value remains below the containment design pressure and still meets the 10 percent margin.
Further, it does not impact the radiological consequences of a LOCA previously analyzed.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Ar,izona State official was notified of'he proposed issuance of the amendments.
The State official had no comments.
- 4. 0 ENVIRONMENTAL C NSIDERATION The amendments change a requirement with respect to the use of a facility component located within the restricted area, as defined in 10 CFR Part 20.
The NRC staff has determined that the amendments involve no 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 Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration.
and there has been no publ'ic comment on such finding (62 FR 27794).
Accordingly, the amendments meet the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
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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 amendments will not be inimical to the common defense and security or to the health and safety of. the public.
Principal Contributor:
R. Goel Date:
September 1'1, 1997
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