ML20073A053
| ML20073A053 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/08/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073A048 | List: |
| References | |
| NUDOCS 9409200096 | |
| Download: ML20073A053 (3) | |
Text
{{#Wiki_filter:9 e '*h ye 1 UNITED STATES ^ .j {' NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20686-0001 I SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 155 AND 136 TO FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLEAR GENERATING STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated June 17, 1994, as supplemented by letter dated July 13, 1994, the Public Service Electric & Gas Company (the licensee) submitted a request for changes to ~the Salem Nuclear Generating Station, Unit Nos. I and 2, Technical Specifications (TS). The requested changes would revise the surveillance requirements for the Power Operated Relief Valve (PORV) and the PORV Block Valve position indicators (Table 4.3-11,. Surveillance Requirements for Accident Monitoring Instrumentation). The'PORV position indication surveillance frequency would be changed from quarterly to every refueling outage. The PORV Block Valve position indication surveillance frequency would . remain quarterly, but would not be required if the PORV Block Valve was shut to isolate a malfunctioning PORV. 2.0 EVALUATIQB The current TS surveillance requires that, every 92 days, in Modes 1, 2, and 3, the PORVs be demonstrated OPERABLE by the performance of a channel functional test. The Salem TS define a channel functional test as: "A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions." In order to perform the required channel functional test of the~ PORV position-indication, the PORV Block Valve is closed and the PORV is stroked through one complete cycle of full travel. Generic Letter 90-06,'provided guidance to the licensees concerning the improvement in reliability of the PORVs. Included in that guidance is a position that " Stroke testing of the PORVs should not be performed during power operation". Other methods of testing the position. g920oo9694o90g 'p ADOCK 05000272 PDR g
l. 4 E indication could be used but this would require either modification of the l circuit or manually closing the contacts of the limit switches. The licensee i has chosen not to modify the circuit in order to utilize the first method and the location of the PORVs makes the latter method unacceptable due to ALARA l and personnel safety considerations. l The revised Westinghouse Standard Technical Specifications, NUREG-1431, Section 3.3.3, Post Accident Monitoring (PAM) Instrumentation, does not include PORV or PORY Block Valve position indication as one of the required post accident monitoring instruments. PAM instrumentation that is to be included in Table 3.3.3-1 is all Regulatory Guide 1.97 Type A variables and all Regulatory Guide 1.97, Category 1, non-Type A variables. At Salem, the PORV and PORV Block Valve position indication channels have been classified as a Type D, Category 2 variable. The licensee has proposed to keep the PORV position indication channel functional test in the TS, but to avoid having to cycle the PORV while at power, the channel functional test will be done every refueling outage. The staff finds this change acceptable. For the PORV Block Valve, in order to perform the position indication 4 functional test, the valve is operated through one complete cycle.
- However, i
the licensee has proposed to keep the position indication channel functional i test quarterly, but to include a footnote that would exempt the valve from the ) channel functional test if the valve was closed to isolate a PORV as required 4 by Technical Specification 3.4.3 (Unit 1) and 3.4.5 (Unit 2). This will bring the functional test requirements of Table 4.3-11 into agreement with the surveillance requirements of TS 4.4.3.2 and TS 4.4.5.2 for Salem 1 and 2, l respectively. The staff finds this change acceptable. l
3.0 STATE CONSULTATION
l t accordance with the Commission's regulations, the New Jersey State official u notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The 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 occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (59 FR [ 39596). Accordingly, the amendments meet the eligibility criteria for s
.,= I 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. 1
5.0 CONCLUSION
The Commission has con.euded,-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,- l and (3) the issuance of the amendments will not be inimical-to the common - l defense and security or to the health and safety of the public. Principal Contributor: J. Stone Date: September 8, 1994 l I L 1 a = _ - - _ -}}