ML20070R926
| ML20070R926 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/16/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070R920 | List: |
| References | |
| GL-93-05, GL-93-5, NUDOCS 9405230138 | |
| Download: ML20070R926 (2) | |
Text
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t UNITED STATES f,I**(
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NUCLEAR REGULATORY COMMISSION "f
WASHINGTON, D.C. 20555 0001 s.'... /
SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
+
RELATED TO AMENDMENT NOS.182 AND 163 TO FACILITY OPERATING LICENSE NOS. NPF-4 AND NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY QLD DOMINION ELECTRIC COOPERATIVE NORTH ANNA POWER STATION. UNITS N0. 1 AND NO. 2 DOCKET NOS. 50-338 AND 50-339
1.0 INTRODUCTION
By letter dated February 25, 1994, the Virginia Electric and Power Company (the licensee) proposed a change to the Technical Specifications (TS) for the North Anna Power Station, Units No. I and No. 2 (NA-l&2).
Specifically, the change would modify the surveillance frequency of the nozzles in the Quench Spray and Recirculation Spray Systems (QSRSS) at NA-l&2.
As documented in Generic Letter (GL) 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," dated September 27, 1993, the NRC has completed a comprehensive examination of surveillance requirements in TS that require testing at power.
In addition, several changes in surveillance intervals for tests performed during shutdown were recommended.
Specifically, GL 93-05 recommended a reduction in nozzle test frequency for stainless steel spray systems.
Consistent with GL 93-05, the licensee is requesting a change to the surveillance frequency from 5 years to 10 years for the spray nozzles in the QSRSS at NA-1&2.
2.0 DISCUSSION 1
NVREG-1366, " Improvements to Technical Specifications Surveillance Requirements," dated December 1992, evaluated testing of spray nozzles in pressurized water reactors' Containment Spray Systems with stainless steel piping. The W REG concluded that the corrosion of stainless steel piping is negligib1" dJring the extended surveillance interval, since the spray systems are maint 6ed dry and there are no additional mechanisms that could reasona:.;y cause blockage of the spray systems' nozzles.
NVREG-1366 concluded that the surveillance interval could be increased from 5 to 10 years without any decrease in plant safety.
In confirmation of that conclusion, no clogging of the nozzles in the spray systems during the surveillance tests performed to date has been observed at NA-l&2.
i 3.0 TECHNICAL SPECIFICATION CHANGES I
The surveillance intervals for the spray nozzles in the QSRSS in TS 4.6.2.1.d and 4.6.2.2.d, respectively, are being changed from 5 to 10 years for both NA-l 1&2.
9405230138 940516 PDR ADOCK 05000338 p
0
. In addition, an editorial change is being made to Specification 4.6.2.2.1.c.2 for both NA-1&2.
4.0 EVALVATION The proposed changes to the surveillance requirements for the QSRSS nozzles are consistent with the intent of GL 93-05.
NUREG-1366 concluded that the corrosion of stainless steel piping is negligible during the proposed extended surveillance interval, since the spray systems are maintained dry and there are no additional mechanisms that could reasonably be postulated to cause blockage of the spray systems' nozzles.
Therefore, the proposed reduced testing of the spray systems' nozzles remains adequate to ensure operability of the nozzles to mitigate the consequences of a Design Basis Accident.
Based on the above, the staff finds the proposed changes to be acceptable.
5.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendment. The State official had no comment.
6.0 ENVIRONMENTAL CONSIDERATION
These amendments change a requirement with respect to 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 offsite, and that there is no significant increase in individual or cumulative l
occupational radiation exposure. The Commission has previously issued a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding (59 FR 17608). Accordingly, these 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
L. Engle Date: May 16, 1994