ML20076E173
| ML20076E173 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/08/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076E170 | List: |
| References | |
| NUDOCS 9108160008 | |
| Download: ML20076E173 (3) | |
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UNITED STATES g
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V-WNGTON, D. C. M%
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SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 159 TO FACILITY OPERATING LICENSE N0. OPR-32 AND A!!ENDMENT NO.158 TO FACILITY OPERATING LICENSE NO. 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 November 3,(1989, as supplemented April 27, 1990, Virginia Electric and Power Company the licensee) requested changes to Section 3.12.C of the Surry Units 1 and 2 Technical Specifications.
The proposed changes would provide an allowed outage time and action statement for inoperable control rods.
2.0 EVALUATION Section 3.12.C.2 of the current Technical Specificati"is allows no more than one inoperable control rod when the reactor is criti-In this case, a control rod is considered inoperable if it cannot be moved by the drive mechanism, is misaligned by a certain amount, or has a rod drop time greater than 2.4 seconds. The proposed change would require the reactor to be brought to hot shutdown conditions within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> when more than one rod is inoperable.
This is acceptable since p' acing the reactor in hot shutdown obviates concerns about the development of undesirable xenon or power distributions and f, hours allows sufficient time to shut down the unit in a controlled manner without challenging the safety systems.
However, in order to be consistent ufth the Standard Technical Specifications, the staff also requested that the shutdown margin be verified within I hour and that boration be initiated if the required shutdown margin was not met.
By letter dated April 27, 1990, the licensee agreed to this additional request and the staff, therefore, finds the proposed change acceptable.
Section 3.12.C.3 of the current Technical Specifications also allows the reactor to remain critical for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> when more than one control rod is out of service because of a single failure external to the individual drive mechanism provided that immediate attention is directed toward making the necessary repairs, in the event the affected rods cannot be returned to service within the 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor must be brought to hot shutdown conditions. The proposed change would further require the rods to be trippable in this out-of-service condition.
In this case, the affected rods must be restored to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the unit must be placed in hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This is consistent with Standard Technical Specifications and is acceptable.
9108160000 910808 PDR ADOCK 050002GO P
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3.0
SUMMARY
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Based on the above evaluation, the staff concludes that the requested changes additionalmodificationrequestedbythestaff,inconjunctionwiththe to the Surry 1 and 2 Technical Specifications are acceptable.
l 4.0 STATE CONSULTAY10N in accordance with the Commission's regulations, the Virginia State official f
was notified of the proposed issuance of the amendments. The State official l
had no comment.
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5.0 ENVIRONMENTAL CONSIDERATION
These amendments change a requirement with respect to installation or use of a
- i facility component located within the restricted area as defined in 10 CFR t
Part 20._ The NRC staff has determined that the amendments involve no significant l
increase in the amounts and no significant change in the types, of any effluents thatmaybereleasedoffsite,andthatthereisnosi0nificantincreasein individual or cumulative occupational radiation exposure. The Commission has areviously issued a proposed finding that these amendments involve no significant i
lazards consideration and there has been no public connent on such finding (55FR21982).
Accordingly, these amendments meet the eligibility criteria i
51.22(b)gorical exclusion set forth in 10 CFR 51.22(c)(9).
for cate Pursuant to 10 CFR i
no environmental-impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
6.0 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 (2) such activities will not be endangered by operation in the proposed manner be conducted in compliance with the Connission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
i Principal Contributor: L. Kopp Date: August 8, 1991 l
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s DATED:' August 8, 1991
- AMENDHENT NO.159 TO FACILITY OPERATING LICENSE NO. OPR SURRY UNIT 1
[
AMENDMENT NO.158 TO FACILITY OPERATING LICENSE NO. OPR SURRY UNIT 2 i
' Docket File
'NkC & Local PDRs PDII-2 Reading S. Varga, 14/E/4 G. Lainas, 14/H/3
-H. Berkow D. Miller B. Buckley Opr.WF D. Hagan, 3302 MNBB E. Jordan, 3302 MNBB i
B. Grimes, 9/A/2 L. Kopp 8/E/23
[
R. Jones, 8/E/21 G. Hill-(8), P-137 Wanda Jones, MNBB-7103 i
C. Grimes,-11/F/23 ACRS (10) f GPA/PA OC/LFMB PD Plant-specific file [ Gray file]
i M. Sinkule, R-II Others as-required i
I cc:
Plant Service list 5
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