ML20071M930
| ML20071M930 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/27/1994 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071M932 | List: |
| References | |
| NUDOCS 9408050016 | |
| Download: ML20071M930 (12) | |
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3 UNITED STATES l
5i NUCLEAR REGULATORY COMMISSION k..-.,,/
WASHINGTON, D.C. 2055A001 f
PUBLIC SERVICE ELECTRIC & GAS COMPANY c
PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY I
ATLANTIC CITY ELECTRIC COMPANY l
DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 153 i
License No. DPR-70 s
1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Phil'adelphia Electric Company, Delmarva Power and Light l
Company and Atlantic City Electric Company (the licensees) dated j
May 3, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I, 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 endangering the health and safety of the public, and (ii) that such activities will be conducted l
in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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 r
the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-i tions 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:
i l
9400050016 940727 PDR ADOCK 05000272 P
. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 153, 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 after the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION flb Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance: July 27, 1994 1
0
ATTACHMENT TO LICENSE AMENDMENT NO.153 FACILITY OPERATING LICENSE NO. OPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 6-18 3/4 6-18 3/4 7-5 3/4 7-5 3/4 7-6 3/4 7-6 f
f 0
CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION i
3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
i ACTION:
With one hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
With both hydrogen analyzers inoperable, restore at least one analyzer to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next
.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 92 days, and at least once per Refueling by performing a CHANNEL CALIBRATION using sample gases containing:
a.
Two volume percent hydrogen (low span), balance Nitrogen, and b.
Six volume percent hydrogen (high span), balance. Nitrogen.
SALEM - UNIT 1 3/4 6-18 Amendment No.153
PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps
)
and associated manual activation switches in the control room and flow paths shall be OPERABLE with:
a.
Two feedwater pumps, each capable of being powered from separate vital busses, and 1
b.
One feedwater pump capable of being powered from an OPERADLE steam supply system.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
i a.
With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
SURVE1LLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Verifying that each non-automatic valve in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
2.
Verify the manual maintenance valves in the flow path to each steam generator are locked open.
SALEM - UNIT 1 3/4 7-5 Amendment No.153
r
'e PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (continued) h b.
At least once per 92 days on a STAGGERED TEST BASIS by:
1.
Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to 1275 psig on recirculation flow.
2.
Verifying that the steam turbine-driven pump develops a discharge pressure of greater than or equal to 1500 psig on recirculation flow when the secondary steam supply pressure is greater than 750 psig. The provisions of Specification 4.0.4 are not applicable.
c.
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 i
discharge pressure test signal.
2.
Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of each auxiliary feedwat'er actuation test signal.
6 SALEM - UNIT 1 3/4 7-6 Amendment No.153
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UNITED STATES l
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NUCLEAR REGULATORY COMMISSION k... *,#
WASHINGTON. D.C. 2055fH)001 PUBLIC SERVICE ELECTRIC & GAS COMPANY i
PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.134 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that A.
The application for amendment filed by the Public Service Electric &
j Gas Company, Philadelphia Electric Company, Delmarva Power and Light i
Company and Atlantic City Electric Company (the licensees) dated i
May 3, 1994, complies with the standards and requirements of the l
Atomic 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 regulations of the Commission; 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 set forth in 10 CFR l
Chapter I; 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.
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. DPR-75 is hereby amended to read as follows:
e
i
, (2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 134, 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 after the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
& f IA Charles L. Miller, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 27, 1994 i
o
ATTACHMENT TO LICENSE AMENDMENT N0.134 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 6-21 3/4 6-21 3/4 7-5 3/4 7-5 3/4 7-6 3/4 7-6 i
1 f
CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTRO' HYDROGEN ANALYZERS j
i LIMITING CONDITION FOR OPERATION 1
1 3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTION:
With one hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
With both hydrogen analyzers inoperable, restore at least one analyzer to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next l
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
l r
1 4
SURVEILLANCE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 92 days, and at least once per Refueling by performing a CHANNEL CALIBRATION using sample gas containing:
a.
Two volume percent hydrogen (low span), balance Nitrogen, and b.
Six volume percent hydrogen (high span), balance Nitrogen, l
I I
i 1
SALEM - UNIT 2 3/4 6-21 Amendment No.134 j
PLANT SYSTEMS, AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated manual activation switches in the control room and flow paths shall be OPERRBLE with:
a.
Two feedwater pumps, each capable of being powered from separate vital busses, and b.
One feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
a.
With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.
SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Verifying that each non-automatic valve in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
l 2.
Verify the manual maintenance valver in the flow path to each steam generator are locked open.
i l
SALEM - UNIT 2 3/4 7-5 Amendment No.134
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 92 days on a STAGGERED TEST BASIS by:
1.
Verifying that each motor-driven pump develope a discharge prescure of greater than or equal to 1275 psig on recirculation flow.
2.
Verifying that the steam turbine-driven pump develops a discharge pressure of greater than or equal to 1500 psig on recirculation flow when the secondary steam supply pressure is greater than 750 psig. The provisions of Specification 4.0.4 are not applicable.
c, 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 2 3/4 7-6 Amendment No.134
- - -.