ML17311A291
| ML17311A291 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/21/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17311A290 | List: |
| References | |
| NUDOCS 9409280142 | |
| Download: ML17311A291 (4) | |
Text
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ky*y4 UNITED STATES NUCLEAR REGULATORY COIVlMISSION WASHINGTON, D.C. 2055&0001 9409280142 9409pg PDR ADOCK 05000528 P
PDR SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
81 TO FACILITY OPERATING LICENSE NO.
NPF-41 AMENDMENT NO. 68 TO FACILITY OPERATING LICENSE NO. NPF-51 ND AMENDMENT NO.
53 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
1.0 INTRODUCTION
By letter dated August 5,
- 1993, the Arizona Public Service Company (APS or the licensee) submitted a request for changes to the Technical Specifications (TS) for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Appendix A to Facility Operating License Nos.
NPF-41, NPF-51, and NPF-74, respectively).
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 amendments change the phrase "Pressurizer Pressure - Wide Range" to "Reactor Coolant System Pressure Wide Range" in item 4 of TS Table 3.3-10" and item 4 of Table 4.3-7.
These amendments will clarify the instrumentation required and eliminate potential confusion between the reactor coolant system pressure instruments and the pressurizer pressure instruments.
- 2. 0 DISCUSSION AND EVALUATION The purpose of TS 3/4 3.3.6, "Post-Accident Monitoring Instrumentation,", is to ensure that sufficient information is available about selected plant parameters following an accident.
Currently, item 4 of Table 3.3-10, "Post-Accident Monitoring Instrumentation,"
and item 4 of Table 4.3-7, "Post-Accident Monitoring Instrumentation Surveillance Requirements,"
use the phrase "Pressurizer Pressure" to designate the wide-range pressure instrumentation required for post-accident monitoring.
The licensee proposes to change the phrase "Pressurizer Pressure" to "Reactor Coolant System Pressure" to be consistent with Regulatory Guide (RG) 1.97, "Instrumentation for Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and Following an Accident,"
and to agree with the as-built configuration and the field equipment identification.
The licensee stated that this change is administrative in nature because it only corrects the nomenclature of the instrumentation and does not change equipment, configuration, or operation.
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This amendment will clarify the instrumentation required and eliminate potential confusion between the reactor coolant system pressure instruments and the pressurizer pressure instruments and is, therefore, acceptable.
3.0 STATE CONSU TATION In accordance with the Commission's regulations, the Arizona State official was notified of the proposed issuance of the amendments.
The State official had no comments.
- 4. 0 ENVIRONMENTAL CONSIDERATION The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements.
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'ffsite, 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 considera-
- tion, and there has been no public comment on such finding (58 FR 50962).
Accordingly, the amendments meet 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 environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed
- above, that (I) 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:
L. Tran Date:
September 21, 1994
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