ML20056E515
| ML20056E515 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/06/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056E512 | List: |
| References | |
| NUDOCS 9308240161 | |
| Download: ML20056E515 (2) | |
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3 UNITED STATES pj NUCLEAR REGULATORY COMMISSION a:
g s,4f WASHINGTON. D C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 181 TO FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO. 181 TO FACILITY OPERATING LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION. UNIT NOS. 1 AND 2 DOCKET N05. 50-280 AND 50-281
1.0 INTRODUCTION
By letter dated April 21, 1993, the Virginia Electric and Power Company (the licensee) proposed changes to the Technical Specifications (TS) for the Surry Power Station, Unit Nos. 1 and 2.
The changes would provide clarification of the design response time of the containment hydrogen analyzers and delete an unnecessary channel check for the analyzers.
Minor administrative changes are also included in the proposed change.
2.0 Proposed Technical Specification Chanaes The Basis Section of TS 3.7 is being revised to note that the containment hydrogen analyzers can provide continuous indication during accident conditions, and that each hydrogen analyzer is designed with the capability to obtain an accurate sample within 30 minutes after initiation of a safety injection.
Also, the discussion of the hydrogen analyzer heat tracing is being revised to delete the reference to the capability of the heat tracing to bring the hydrogen analyzer process piping to the appropriate operating temperature within 20 minutes.
TS Table 4.1-2A is being revised to delete the requirement in Item 20a to perform a channel check of the containment hydrogen analyzers every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Items 20b and 20c will be renumbered as 20a and 20b, respectively, and new Item 20b is being revised editorially for clarity.
TS Table 4.1-2A, Items 16 and 17, are being revised to add Section 4.3 under the FSAR Reference Section header in the table to reflect the Updated Final Safety Analysis Report section that discusses the reactor vessel overpressure mitigation system.
TS Table 4.1-2A, Item 18, is being revised to add a superscript that was inadvertently deleted by TS Amendment 84/83.
Superscript (b) notes the minimum differential pressure allowed for the Primary Coolant System periodic valve leakage testing discussed in Item 18.
TS Table 4.1-2A, Items 14a and b, 15 and 17, are being revised to designate their testing frequency as "Each Refueling Shutdown" for consistency in terminology.
9308240161 930E06 PDR ADOCK 05000280 p
. 3.0 EVALUATION The Surry Power Station utilizes two qualified hydrogen analyzers which are shared by units 1 and 2.
The purpose of the hydrogen analyzers is to provide continuous indication in the control room of hydrogen concentration in the containment atmosphere under accident conditions.
Under normal conditions, continuous monitoring of hydrogen concentration in the containment atmosphere is not required and the hydrogen analyzers are maintained in the standby mode.
Assurance that the hydrogen analyzers will function when needed is provided by the monthly functional check and the quarterly calibration which conforms with the Westinghouse Standard TS.
Therefore, it is unnecessary to perform a channel check every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during normal plant operations. The analyzers installed at the Surry station have the capability of obtaining an accurate sample of the containment atmosphere within 30 minutes after initiation of safety injection.
Therefore, the staff finds the proposed changes acceptable.
The other changes are administrative and are also 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 and change the 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 these amendments involve no significant hazards consideration and there has been no public comment on such finding (58 FR 30202). 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 1
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 these amendments will not be inimical to the common defense and security or to the health and safety of the public.
l Principal Contributor:
T. Farnholtz Date: August 6, 1993
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