ML20128H154
| ML20128H154 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/25/1985 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128H158 | List: |
| References | |
| NUDOCS 8507090433 | |
| Download: ML20128H154 (7) | |
Text
___
M UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION f;E O
WASHINGTON, D. C. 20555 PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELEGINIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELEGIRIC CUMPANY DOCKET NO. 50-272 SALEMNUCLEARGENERATINGSTATION,UNITNO.J AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-70 1.
The Nuclear Regulatory Comission (the Comission) 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 December 7,1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without enciangering the health and safety of.the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
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-70 is hereby amended to read as follows:
8507090433 850625 PDR ADOCK 0500C'272 P
FDR'
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 65, 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 issuance.
FOR THE NUCLEAR ret, TORY COMISSION arga$th e
Operating Reactors B h #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 25,1985 1
ATTACHMENT TO LICENSE AMENDMENT NO. 65 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
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CONTAINMENT SYSTEMS SURVEILLANCE REOLIIREMENTS (Continued) 4.6.3.1.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once.per 18 months by:
Verifying that on a Phase A containment isolation test a.
signal, each Phase A isolation valve 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.
Verifying that on a feedwater isolation test signal, each c.
3 feedwater isolation valve actuates to its isolation position.
d.
Verifying that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each Purge and Pressure-Vacuum y
Relief valve actuates to its isolation position.
' ~
Verifying that the Containment Pressure-Vacuum Relief e.
Isolation valves are limited to 160' opening angle.
4.6.3.1.3 At least once per 18 months, 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.
4.6.3.1.4 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.1.5 Each containment purge isolation valve shall be denonstrated 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 when 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 wnen the naasured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2d. for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60La.
4.6.3.1.6 A pressure drop test to identify excessive degradation of resilient valve seals shall be conducted on the:
Containment Purge Supply and Exhaust Isolation Valves at a.
least once per 6 nonths.
b.
Containment Pressure - Vacuum Relief Isolation Valves at
'least once per 3 months.
+
92'21% 6 1207 PDR ADOCK 05000272 P
PDR SALEM - UNIT 1 3/4 6-13 Amendment No. 65
/
UNITED STATES E
NUCLEAR REGULATORY COMMISSION 5
- p WASHINGTON, D. C. 20555
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELEGIRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. DPR-75 1.
The Nuclear Regulatory Comission (the Comission) 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 December 7, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, i
the provisions of the Act, and the rules and regulations of the l
Comission; C.
There is reasonable assurance (1) 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; i
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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 B, as revised through Amendment No. 39, 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 issuance.
F0 THE NUCLEAR 4 GULATORY COMMISSION
()
I brhos, J.
ven K. % #,
h Operating Reactors r nch #1 Division of Licensi g
Attachment:
Changes to the Technical Specifications Date of Issuance: June 25, 1985 8
.i ATTACHMENT TO LICENSE AMENDMENT N0. 39 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
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.i CONTAINMENT SYSTEMS
, SURVEILLANCE REQJ1REMENTS (Continued) 4.6.3.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
Verifying that on a Phase A containment isolation test a.
signal, each Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase 8 containment isolation test signal, each Phase 8 isolation valve actuates to its isolation position.
Verifying that on a feedwater isolation test signal, each c.
feedwater isolation valve actuates to its isolation position.
d.
Verifying that on a Containment Purge and Pressure-Vacuum Relief isolation test signal, each Purge and Pressure-Vacuum Relief valve actuates to its isolation position.
Verifying that the Containment Pressure-Vacuum Relief e.
Isolation valves are limited to 160' opening angle.
4.6.3.3 At least once per 18 sonths, 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 time of each power operated or automatic valve 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 when 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 when the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2d. for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60La.
4.6.3.6 A pressure drop test to identify excessim degradation of resilient valve seals shall be conducted on the:
Containment Purge Supply and Exhaust Isolation Valves at a.
least once per 6 months.
b.
Containment Pressure - Vacuum Relief Isolation Valves at l
least once per 3 months.
4 l
SALEM - UNIT 2 3/46i5 Amendment No. 39 l
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