ML20034G583
| ML20034G583 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/05/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034G582 | List: |
| References | |
| NUDOCS 9303100161 | |
| Download: ML20034G583 (5) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.174 TO FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO.173 TO FACILITY OPERATING LICENSE N0. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281
1.0 INTRODUCTION
By letter dated September 4,1992, ,rginia Electric and Power Company (the licensee) requested changes to the Technical Specifications (TS) to reinstate and also increase the allowable outage time for surveillance testing of the non-essential service water isolation actuation logic and incluae operability requirements and an action statement for the actuation logic.
In ddition, the licensee has requested to reformat the surveillance requirements to parallel the operability requirements.
2.0 BACKGROUND
TS Amendments Nos. 130/130, dated August 16, 1991, incorporated operability and surveillance requirements for the new canal level monitoring system as Item 5 to TS Table 3.7-2, " Engineered Safeguards Action Instrument Operating Conditions," and Item 40 to TS Table 4.1-1, " Minimum Frequencies for Check, Calibration, and Test of Instrument Channels." Those amendments allowed one train of non-essential service water actuation logic to be blocked for a period not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. However, TS Amendments Nos. 165 and 164, dated December 30, 1991, which are meant to incorporate related criteria documented in a report entitled, " Evaluation of the Surveillance frequencies and the Out of Service Times for the Engineered Safety Features Actuation System," and Supplements (WCAP 10271), inadvertently eliminated the 2-hour permissible bypass condition for performance of the non-essential service water isolation actuation logic surveillance tasting. Amendments Nas. 165 and 164 allowed other actuation logic to be blocked for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for testing. The proposed TS changes would extend the allowed outage time from 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for the non-essential service water actuation logic testing, which was approved for other actuation logic in Amendments Nos. 165 and 164, include the operability requirements for the actuation logic (Table 3.7-2, Item 5.b), and provide clarity and consistency fr - " % 3.7-2 and 4.1-1.
9303100161 930305 PDR ADOCK 05000280 P
i 3.0 EVALUATION The proposed changes to TS Table 3.7-2 add Item 5.b to indicate the total number of channels, minimum operable channels, channels to trip, and Operator Action 14.
The action statement requires the unit to be placea in hot shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the minimum channels operable requirement is not met, and allows one channel of the actuation logic to be bypassed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for surveillance testing. The 8-hour allowed outage time slightly increases actuation logic unavailability; however, it is not significant. The staff has evaluated these changes and has determined that they are consistent i
with requirements previously approved by the staff in TS Amendments 165/164, and staff safety evaluations related to WCAP 10271, dated February 22, 1989, and April 30, 1990. The proposed changes to TS Table 4.1-1 (Item 40 and Footnote), provide additional clarity and consistency.
4.0
SUMMARY
The staff has reviewed the licensee's proposed revisions to TS Tables 3.7-2, and 4.1-1 and has found them to be consistent with the UFSAR, staff reports on WCAP 10271, and previous Amendments Nos. 165/164. Therefore, the staff finds the proposed revisions 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 amendments. The State official had no comments.
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6.0 ENVIRONMENTAL CONSIDERATION
Pursuant to 10 CFR 51.32, an environmental assessment has been published (58 FR 11874) in the Federal Reaister on March 1, 1993. Accordingly, the Commission has determined that the issuance of this amendment will not result in any environmental impacts other than those evaluated in the Final Environmental Statement.
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 matter, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or the health and safety of the public.
hincipal Contributors:
F. Rinaldi, PDI-2 B. Buckley, PDII-2 Datt;; March 3, 1993
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4 UNITED STATES 3
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20s5t4001
%...e f 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N05. 50-280 AND 50-281 NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES The U.S. Nuclear Regulatory Comission (Commission) has issued Amendment No. 174 to Facility Operating License No. DPR-32 and Amendment No. 173 to facility Operating License No. DPR-37, issued to the Virginia Electric and Power Company (the licensee), which revised the Technical Specifications for operation of the Surry Power Station, Units 1 and 2, located in Surry County, Virginia. These amendments are effective as of the date of issuance.
The amendments modified the Technical Specifications to provide specific operability requirements for the actuation logic and, as part of the associated action statement, reinstate the permissible bypass condition.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.
Notice of Consideration of Issuance of Amendment and Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER on October 20, 1992 (57 FR 47884), No request for a hearing or petition for leave to intervene was filed following this notice.
5 The Comission has prepared an Environmental Assessment related to the action and has determined not to prepare an environmental impact statement.
Based upon the environmental assessment, the Comission has concluded that the f
issuance of this amendment will not have a significant effect on the quality of the human environment (58 FR 11874).
For further details with respect to the action see (1) the application for amendments dated September 4, 1992, (2) Amendment No.174 to License No.
DPR-32 and Amendment No.173 to License No. DPR-37, (3) the Commission's i
related Safety Evaluation, and (4) the Commission's Environmental Assessment.
All of these items are available for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC f
20555 and at the local public document room located at the Swem Library, College of William and Mary, Williamsburg, Virginia 23185. A copy of items (2), (3) and (4) may be obtained upon request addressed to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Document Control i
Desk.
l Dated at Rockville, Maryland this 5th day of March 1993 FOR THE NUCLEAR REGULATORY COMMISSION bt C.bW Bart C. Buckley, Se r Project Manager Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
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