ML17310B185
| ML17310B185 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/06/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17310B184 | List: |
| References | |
| NUDOCS 9404140300 | |
| Download: ML17310B185 (6) | |
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UNITED'STATES NUCL'EAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RE AT D 0 AMENDMENT NO. 73 TO FACILITY OPERATING LICENSE NO.
NPF-41 M NDMENT NO.
59 TO FACILITY OPERATING LICENSE NO.
NPF-51 ND AMENDMENT NO. 45 TO FACILITY OPERATING LICENSE NO. NPF-74 ARIZONA PUBLIC SERVICE COMPANY ET AL.
A 0 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 December 2,
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.
Specifically, the proposed changes would revise the Palo Verde TS 3/4.6.1.2 by deleting the schedular requirements for Type A (overall integrated containment leakage rate) tests to be performed at 40 2 10 month intervals and instead reference Type A testing in accordance with Appendix J to 10 CFR Part 50.
The proposed amendment would also include several editorial/administrative changes.
2.0 BACKGROUND
Currently, the Palo Verde TS requires a set of three containment integrated leakage rate (Type A) tests be performed specifically at 40 2 10 month intervals during each 10-year service period, with. the third test of each set performed during the shutdown for the 10-year plant inservice inspection.
Appendix J to 10 CFR Part 50 requires that a set of three Type A tests be conducted at approximately equal intervals during the 10-year service period with the third test of each set conducted to coincide with the shutdown for the 10-year plant inservice inspection outage.
While the Palo Verde TS leakage rate testing requirements essentially duplicate the requirement in Appendix J, the TS specifically requires the Type A tests to be performed at 40 i 10 month intervals.
The licensee stated that this TS requirement to conduct Type A tests at 40 i 10 month intervals is too restrictive for units with 18-month fuel cycle.
Therefore, the licensee proposes to revise the TS to delete the detailed surveillance schedule for the Type A tests, and instead reference performance of Type A testing in accordance with Appendix J to 10 CFR Part 50.
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3.0 TECHNICAL SPECIFICATION CHANGES Technical Specification Surveil,lance Requirement 4.6.1.2.a would be revised to remove the specific requirement that the Type A tests be performed at 40 + 10 month intervals with the third test of each set conducted during the shutdown for the 10-year plant inservice inspection.
The revised requirement would read:
- "Type A (Overall Integrated Containment Leakage Rate) testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions."
Technical Specification Surveillance Requirements 4.6.1.2.b and 4.6.1.2.c would be deleted.
The licensee stated that these Type A test requirements are also specified in Appendix J to 10 CFR Part 50 and need not be reiterated in the Technical Specifications.
However, Surveillance Requirement 4.6.1.2.c.3 is not specified in Appendix J to the same level of detail.
This surveillance requirement concerns the accuracy of supplemental testing.
Section III.A.3(b) of Appendix J states the requirements for the accuracy of supplemental testing in terms of a fraction of L,, while Surveillance Requirement 4.6.1.2.c.3 is related to a specific test and its success criteria.
Although the requirement is not specified in the same level of detail in Appendix J as in the technical specification surveillance requirement, the staff finds the deletion of this surveillance requirement acceptable because:
(1) the requirement for a supplemental test and general requirements for the accuracy of the test are specific'd in Appendix J, and (2) it is not necessary for the technical specifications to contain the level of detail specified in section 6.6.1.2.c.3.
In fact, the new Combustion Engineering Standard Technical Specifications are consistent with the licensee's proposal in this respect.
The remaining Surveillance Requirements would be renumbered for continuity.
Consistent with this renumbering, the reference in TS 4.6. l.l.c is revised from "Specification 4.6.1.2.d" to "Specification 4.6.1.2.b."
- 4. 0 EVALUATION Satisfactory leakage results are a requirement for the establishment of containment operability.
Neither the general frequency nor the required number of Type A tests would be changed by the proposed changes.
Also, the maximum allowable leakage rate at the calculated peak containment pressure would not be changed.
Only the detailed 40 2 10 month test interval would be changed to provide more flexibility. Type A, B, and C tests would continue to be performed in accordance with Appendix J to 10 CFR Part 50.
Type A test acceptance criteria would not be changed and combined leakage of penetrations subject to Type B and C tests would be maintained within the required limits.
Also, the proposed changes do not impact the design basis of the containment and would not change the response of containment during a design basis accident.
Finally, the testing method, acceptance
- criteria, and the Bases to the TS are not changed by the proposed revisions to the TS.
Therefore, based on all of the above, the staff finds the proposed changes to be acceptable.
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- 5. 0 STATE CONSULTATION:
In accordance with the Commission's regulations, the Arizona State official was notified of the proposed issuance of the amendment.
The State official had no comments.
6.0, NVIRONMENTAL 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 changes 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
- 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 considera-
- tion, and there has been no public comment on such finding (59 FR 616).
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.
7.0 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:
L. Tran Date:
April 6, 1994
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