ML20079A178
| ML20079A178 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/23/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079A170 | List: |
| References | |
| NUDOCS 9412300189 | |
| Download: ML20079A178 (4) | |
Text
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t UNITED STATES 4
S NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20666-0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.195 TO FACILITY OPERATING LICENSE N0. OPR-32 AND AMENDMENT NO.195 TO FACILITY OPERATING LICENSE N0. DPR-37 4
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION. UNIT NOS. 1 AND 2
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DOCKET NOS. 50-280 AND 50-281 l
1.0 INTRODUCTION
1 Pursuant to 10 CFR 50.90, the Virginia Power and Electric Company (the licensee), by letter dated October 11, 1994, submitted proposed changes to the Surry Power Station, Units 1 and 2 Technical Specifications (TS).
The proposed changes would revise the surveillance frequencies of the hydrogen analyzers Channel Functional Test from once per 31 days to once per 92 days, and change the surveillance frequency of the Channel Calibration from one per 4
92 days on a staggered basis to once per 18 months.
2.0 TS CHANGES The surveillance test requirements for hydrogen analyzers in the TS Table 4.1-j 2A Item 20.a. and b. are being changed as follows:
the frequency of the Channel Functional Test is changed from once per 31 days to once per 92 days, and the frequency of the Channel Calibration is changed from once per 92 days on a staggered test basis to once per 18 months.
Defined terms are capitalized on the pages affected oy this change.
These terms include Channel Calibration, Channel Functional Test, Power Operation, and Cold Shutdown.
3.0 EVALUATION The staff's SER dated April 22, 1983, requires continuous indication of the containment hydrogen concentration in the control room within 30 minutes of the initiation of safety injection. A hydrogen analyzer is dedicated to each Surry unit having the capability to be cross-connected to the opposite unit.
The containment hydrogen monitors are capable of providing continuous indication of the containment hydrogen concentration in the control room within 30 minutes of the initiation of safety injection.
The analyzers are maintained in a standby mode during normal operation and are used to alert the control room operator to take planned manual actions to activate the hydrogen recombiners following a loss-of-coolant accident.
These analyzers have no automatic safety function. Although a channel check is not performed in the 9412300189 941223 PDR ADOCK 05000280 P
J standby mode, the analyzers have alarms to indicate electronic system or power failures. NUREG-1366, " Improvements to Technical Specifications Surveillance Requirements," dated December 1992, provided a comprehensive examination of surveillance requirements in technical specifications that require testing at power.
In performing this study, the NRC staff found that, while the majority of the testing at power is important, safety can be improved, equipment degradation decreased, and an unnecessary burden on personnel resources eliminated by reducing the amount of testing that the TS require during power operation. The study also indicated that only a small fraction of the TS surveillance intervals warranted relaxation.
The proposed change being addressed in this safety evaluation falls into this latter category.
The licensee also stated that, based on their surveillance test experience, the hydrogen analyzers have been shown to be stable with repeatable results.
The proposed reduced testing of the hydrogen analyzers remains adequate to ensure operability of the analyzers when required.
Based on all of the above, the staff finds the proposed changes conform with the provisions of NUREG-1366 and Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," dated September 27, 1993, and are, therefore, acceptable.
4.0 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 comment.
5.0 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. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, l
of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation t
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 55893).
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 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 not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, i
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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.
Principal Contributor:
B. Buckley Date: December 23, 1994 4
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DATED.
December 23, 1994 AMENDMENT NO.
AMENDMENT N0,195 TO FACILITY OPERATING LIC 195
_D.11ttibMLo NSE NO. DPR S Docket File!1 PUBLIC 1
PDII-2 R 2
S. Varga,eading OGC 14/E/4 G. Hill C. Grimes (,4) ll/F/23 ACRS (4)
OPA OC D. /LFDCB Verelli, R-II
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December 23, 1994 DATED:
AMENDMENT NO. 195 TO FACILITY OPERATING LICENSE NO. DPR SURRY UNIT 1 AMENDMENT N0. 195 TO FACILITY OPERATING LICENSE NO. OPR SURRY UNIT 2 Distribution Docket File PUBLIC PDII-2 Reading S. Varga, 14/E/4 OGC G. Hill (4)
C. Grimes, ll/F/23 ACRS (4)
OPA OC/LFDCB D. Verelli, R-II t
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