ML18087A557
| ML18087A557 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/15/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18087A558 | List: |
| References | |
| NUDOCS 8211080111 | |
| Download: ML18087A557 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 12 LiceQse No. DPR-75
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated October 7, 1982, complies with the standards and requirements of the Atbmic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and reguiations of the Cammi ss ion; C.
There is. reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
- The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public;
- and
- E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- s211oso111 s210 i's PDR* ADOCK 05000311 P
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 12, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuanca..
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 15, 1982 FOR THE NUCLEA,~GULATORY COMMISSION.
(.raJA~
' e Varga, C 1 f.
Operating Reactors Br nch No. 1 Division of Licensi
_J
---~---
ATTACHMENT TO LICENSE AMENDMENT NO. lZ FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Page Insert Page 3/4 6-15 3/4 6-15
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolat~on valve specified in Table 3.6-l shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 nonths by:.-*
- a.
Verifying that on a Phase A containment isolation test signal, each Phase A isol~tion val~e actuates to its isolation position.
b:
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
- c.
Verifying that on a feedwater isolation test signal, each feedwater isolation valve actuates to its isolation position.
- d.
Verifying that *on a Containment Purge and Pressure-V.acuum Relief isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates to its isolation position.
4.6.3.3 At least once per 18 11onth, verify that on a main steam isolation test signal, each main steam isolation valve specified in Table 3.6-1 actuates to its isolation position.
4.6.3.4 The isolation ti11e of each power operated or automatic valv_e of
- Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.5 Each containment purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing of the valve, except ~he.n the valve is being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that
\\then the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.l.2d. for all other Type Band C penetrations, the combined lea_kage rate is less than or equal _to 0.60La:
4.6.3.6 A pressure drop test to identify excessive degradatioo of resilient valve seals shall be ccn:lucted cm fhe :
- a.
O:mtaiment Purge SuR>ly and Exhaust Isolatiai valves at least~
per 6 m:mths.
b.*
a:mtainment Pressure - Vacuum Relief Isolation Valves at least once pel: 3 months.
. *The provision.. of Surveillance Requi~ement 4.6.3.6.b is not applicable during the remainder of the first fuel cycle.
- SALEM - UNIT 2*
3/4 6-15 Amendment No. fl 12