ML20070K059
| ML20070K059 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/11/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K061 | List: |
| References | |
| NUDOCS 9103180291 | |
| Download: ML20070K059 (12) | |
Text
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NUCLE AR REGULATORY COMMISSION
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,c, UNITED STATES l
WASHINGTON. D. C 20665 gw j e...+
PURLIC SERVICE.ElFCTRIC.A-GAS COMPANY D4II, AOEL DWI A-FL ECTRIC. COMP ANY I
DElNARVA. POWER AND-1,1GWT. COMPANY ATLALTIC CITY ELECTRIC 00kPANY DOCKET NO, 50-272 sal,FN GENERATlWG. STAT 10N.UhlT.NO, 1 i
AWENDWENT TO FACILITY.0PERATING. LICENSE Amendment No. 119 License No. DPR-70 1.
The Nuclear Regulatory Comission (the romission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric A Gas Company, Philadelphia Electric Company, Iselmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated December 27, 1990 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 1:
B.
The facility will operate in conformity with the application, the l
provisions of the Act,.ind the rules and regulations of the l
Comissioni C.
There is reasonable assurance: (i)thattheactivitiesauthorizedby this amenoment 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 set forth in 10 CFR Chapter li 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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regult.tions anc t.ll applicable requirements have been l
satisfiec.
l E.
Accoroingly, the license is awndec by changes to the Technical Specifica-tiens 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:
9103180291 910311 DR ADOCK 0500 2
2 (2) Technical Specifications and Environrnental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment f;o. 119, 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 its date of issuance and shall be impicuented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/S/
Walter R. Butler, Director Project Directorate 1 2 Division of Reactor Projects. 1/11 Attachme.it:
Changes t3 the Technical SpecifD.stions Date of Issuance: March 11, 1991 n
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2 (2) T,echnical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.119, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications, i
3.
This license amendment is effective as of its date of issuance ano shall l
be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY 00MMISSION 1
WhdC AJiAL Walter R. Butler, Director i
Project Directorate I-2 Division of Reacter Projects - I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: March 11.1991 I
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ATTACHMENT TO LICENSE AMENDMENT NO.119 FACILITY OPERATING LICENSE NO. OPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 7-6 3/4 7-6 8 3/4 7-2 B 3/4 7-2 r.,-
e PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (continued) 4.
Verify the manual maintenance valves in the flow path to each steam generator are locked open, b.
At least once per 18 months during shutdown by:
1.
Verifying that each automatic valve in the motor driven pump flow path actuates to its correct position on a pump discharge pressure test signal, 2.
Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of each auxiliary feedwater actuation test signal.
' SALEM UNIT 1 3/4 7 6 Amendment No,119
1 PLANT SYSTEMS BASES maximum number of inoperable safety valves per operating U
steam line 109 - Power Range Neutron Flux High Trip Setpoint for 4 loop operation 76 Maximum percent of RATED THERMAL POWER permissible by P 8 Setpoint for 3 loop operation, Total relieving capacity of all safety valves per steam X
line in Ibs/ bout Y
Maximum relieving capacity of any one safety valve in Ibs/ hour 3 /4. 7.1. 2 AUXILIARY TEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled dovn to less than 350'F from normal operating conditions in the event of a total loss of off site power.
Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 440 gpm at a pressure of 1150 psig to the entrance of the steam generators.
The steam driven auxiliary feedvater pump is capable of delivering a total ft+dwater flow of 880 gpm at a pressure of 1150 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350'F when the Residual Heat Removal System may be placed into operation.
The flow path to each steam generator is ensured by maintaining all manual maintenance valves locked open.
A spool piece consisting of a length of pipe may be used as an equivalent to a locked open manual valve.
The manual valves in the flow path are: 1AF1, 11AF3, 12AF3, 13AF3, 11AF10, 12AF10, 13AT10, 14AF10, 11AF20, 12AF20, 13AF20, 14AF20, 11AF22, 12AP22, 13AF22, 14AF22, 11AF86, 12AF86, 13AF86, and 14AF86, 3 /4. 7.1. 3 AUXILIARY FEED STORACE TANK The OPERABILITY of the auxiliary feed storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with steam dischargo to the atmosphere concurrent with total loss of off site power, The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
SALEM UNIT 1 B 3/4 7 2 Amendment No.119
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UNITED STATES NUCLEAR REGULATORY COMMISSION l
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PUBLIC. SERVICE. ELECTRIC.4. GAS COMPANY l
PHILADELP_HIA ELECTRIC COM_PANY 1
DFLMARVA POWER AWD LIGWT. COMPANY ATLAWTIC. CITY.[LECTRIC COMPANY I
j DOCKET WO.-50-311 SA1EM. GENERATING STATION.-UNIT-WO.-?
j WENDWENT T0. FACILITY-OPERATlWG. LICENSE Amendment No. 99 License No. OPR-75
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The Nuclear Regulatory Conission (the Comission or the NRC) has found i
that:
1 i
A.
1he application for turdment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company,(Delmarva Power and Light l
Company and Atlantic City Electric Company the licensees) dated i
December 27, 1990 complies with the standards and requirements.of i
the Atomic Energy Act of 1954, as amended (the Act), and the Comission's i
rules and regulations set forth in 10 CFR Chapter I; D.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l
Comission; C.
There is reasonable assurance: (1)thattheactivitiesauthorizedby i
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 set forth in-10 CFR Chapter 11 D.
The issuance of-this amendment will not be inimical to the comon I
defense ar.d security or to the health and safety of the public; and i
i E.
The issuance of this amendment is in 7.ccoraance with 10 CFk Nrt $1 of the Comission's regulations ano all applicable requirements have been satisfied.
j 2.
Accordingly,-the. license is amended by changes to-the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-75 is hereby 4
l amended to read as follows:-
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 99 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 its date of issuance and shall be impicnented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMIS$10H
/S/
Walter R. Buticr, Director Project Directorate 12 Division of Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 11, 1991 nA
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[ TAC.N05.79367/79368]
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications cantained in Appendices A and B, as revised through Amendment No. 99, 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 its date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ltl(2 k
<Att Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: March 11, 1991 l
l l
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ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. OPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 7-6 3/4 7 6 8 3/4 7-2 8 3/4 7 2 1
. - ~
PLANT SYSTf,tyi SURVEILIANCE REQUIRbtENTS (Continued) 4.
Verify the manual maintenance valves in the flow path to each steam generator are locked open.
b.
At least once per 18 months during shutdown by:
1.
Verifying that each automatic valve in the motor driven i
pump flow path actuates to its correct position on a pump discharge pressure test signal.
4 2.
Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of each auxiliary feedwater actuation test signal.
SALEM UNIT 2 3/4 7 6 Amendment No. 99
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PIANT SYSTEMS i
BASES 4
~
maximum number of inoperable safety valves per operating U
steam line 109 - Power Range Neutron Flux High Trip Setpoint for 4 loop operation 76 Maximum percent of RATED THERMAL POWER permissible by P 8 Setpoint for 3 loop operation i
X Total relieving capacity of all safety valves per steam line in 1bs/ hour Maximum relieving capacity of any one safety valve in-Y Ibs/ hour a
3/4.7.1.2 AUXILI ARY FEEDWATER SYSTEM The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350'F from normal operating conditions in the event of a total loss of offsite power.
Each electric driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 440 gpa at a pressure of 1150 psig to the entrance cf the steam generators.
The steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 880 gpa at a pressure of 1150 psig to the entrance of the steam generators.
This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temperature to less than 350*F when the Residual Heat Removal System may be placed into operation.
The flow path to each steam generator is ensured-by maintaining all manual maintenance valves locked open.
A spool piece consisting of a length of pipe may be used as an equivalent to a locked open manual valve. The manual valves in the flow path are: 2AF1, 21AF3, 22AF3, 23AF3, 21AF10, 22AF10, 23AF10, 24AF10, 21AF20, 22AF20, 23AF20, 24AF20, 21AF22, 22AF22, 23AF22, 24AF22, 21AF86, 22AF86, 23AF86, and 24AF86.
l 3/4.7.1.3 AUXILI ARY FEED STORAGE TANK i
The OPERABILITY of the auxiliary feed storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with steam discharga to the atmosphere concurrent with total loss of offsite power. The contained water volume limit includes an allowance for water not usable because of tank discharge line-location or other physical characteristics.
SALEM. UNIT-2 B 3/4 7 2
__' Amendment No. 99
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