ML20236X565
| ML20236X565 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/19/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20236X566 | List: |
| References | |
| DPR-70-A-196, DPR-75-A-179 NUDOCS 9808100103 | |
| Download: ML20236X565 (15) | |
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t UNITED STATES
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j NUCLEAR RE2ULATORY COMMISSION
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WASHINGTON. D.C. 200 6 4001 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWEP AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY EPERATING LICENSE Amendment No.196 License No. DPR-70 1.
Tne Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A. 'The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated October 25, 1996, as supplemented December 11, 1996, January 28, March 27, April 24, June 3, and June 12, 1997, 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;
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B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; t 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 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 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 pararraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
9808100103 */70619 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.196, are hereby iricorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
In addition, the license is amended by changes to Appendix C as indicated in the attachment to this license amendment, and paragraph 2.C.(10) of the Facility Operating License No. DPR-70 is amended to read as follows:
(10) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No.196, are hereby incorporated into this
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license.
Public Service Electric and Gas Comp;:ny shall operate the facility in accordance with the Additional Conditions.
3.
This licerse amendment is effective as of its date of issuance, to be implemented prior to entry into Mode 3 from the current outage.
FOR THE NUCLEAR REGULATORY COMMISSION i d$A U?h$rj John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:
1.
Page 1 to Appendix C of License
- DPR-70 2.
Changes to the Technical Specifications Date of Issuance: June 19, 1997 l
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- Page 1 of Appendix C is Ettached, for convenience, for the composite license to reflect this change.
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l ATTACHMENT TO LICENSE AMENDMENT NO.196 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 1.
Etm2E1 Insert Appendix C, page 1 Appendix C, page 1 2.
Revise Appendix A as follows:
Remove Paaes Insert Paaes 3/4 3-27 3/4 3-27 3/4 3-31 3/4 3-31 1
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APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-70 Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company, and Atlantic City Electric Company shall comply with the following conditions on the schedules noted below:
l Amendment Additional Condition Implementation Number Date 192 The licensee is authorized to relocate certain Technical The amendment i
Specification requirements to licensee-controlled shall be documents, implementation of this a:nendment shall implemented include the relocation of these technical specification within 60 days i
requirements to the appropriate documents, as described in from March 21, the licensee's application dated January 11,1996, as 1997.
I supplemented by letters dated February 26, May 22, June 27, July 12, December 23,1996, and March 17, 1997, and evaluated in the staff's safety evaluation attached to this amendment.
194 The licensee is authorized to upgrade the initiation circuitry The amenoment for the power operated relief valves, as described in the shall be licensee's application dated January 31,1997, as implemented prior supplemented by letters dated March 14, to entry into Mode April 8, and April 28,1997, and evaluated in the staff's 3 from the current safety evaluation attached to this amendment.
outage for Salem, Unit 1.
196 Containment Fan Cooler Units The amendment The licensee shall complete all modifications associated shall be with the amendment request concerning Containment Fan implemented prior Cooler Unit (CFCU) response time dated October 25,1996, to entry into Mode as described in the letters supplementing the amendment 3 from the current request dated December 11,1996, January 28, March 27, outage for Salem, April 24, June 3, and June 12,1997, prior to entry into Unit 1.
Mode 3 following refueling outage 12. All modifications made in support of this amendment request and described in the referenced submittals shall be in conformance with l
the existing design basis for Salem Unit 1, and l
programmatic controls for tank monitoring instrumentation i
shall be as described in the letter dated April 24,1997.
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Post modification testing and confirmatory analyses shall be as described in the letter dated March 27,1997. Future changes to the design described in these submittals may be made in accordanc3 with the provisions of 10 CFR 50.59.
l Further, the administrative controls associated with CFCU l
operability and containment integrity described in the letters
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dated March 27 and April 24,1997, shall not be relaxed or i
changed without prior staff review until such time as the license has been amended to include the administrative controls as technical specification requirements.
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Amendment No. MB, M4, 196 l
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TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE ITEMS INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1.
Manual a.
Safety Injection (ECCS)
Not Applicable Feedwater Isolation Not Applicable Reactor Trip (SI)
Not Applicable Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Service Water System Not Applicable Containment Fan Cooler Not Applicable b.
Containment Spray Not Applicable Containment Isolation-Phase "B"
Not Applicable Containment Ventilation Isolation Not Applicable c.
Containment Isolation-Phase "A"
Not Applicable Containment Ventila' tion Isolation Not Applicable t
d.
Steam Line Isolation Not Applicable 2.
Containment Pressure-High a.
Safety Injection (ECCS) s27.0(1) b.
Reactor Trip (from SI) s2.0 c.
Feedwater Isolation s10.0 d.
Containment Isolation-Phase "A" sl7.0(21/27.0(3) e.
Containment Ventilation Isolation Not Applicable 1
l f.
Auxiliary Feedwater Pumps s60 l
g.
Service Water System sl3.0(2)/45.0(3) h.
Containment Fan Coolers s60.0 (7)
SALEM - UNIT 1 3/4 3-27 Amendment No.196 I
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l TABLE 3.3-5 (Continued)
TABLE NOTATION 1
f (1)
Diesel generator starting and sequence loading delays included.
Response time limit includes opening of valves to establish SI path and attainmer.t of discharge pressure for centrifugal charging pumps, SI and RHR pumps.
l (2)
Diesel generator starting and sequence leading delays not included.
Offsite power available. Response time lindt includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
1 (3)
Diesel generator starting and sequence loading delays included.
Response time limit includes cpening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
(4)
On 2/3 in any steam generator.
(5)
On 2/3 in 2/4 steam generators.
l (6)
The response time is the time the isolation circuitry input reaches the isolation sotpoint to the time the Is71ation valves are fully
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shut.
(7)
The response time includes the time to automatically align the service water flow to the CFCUs following an accident coincident with a loss of offsite power, and also includes the time delays associated with isolation of the Turbine Generator Area service water header.
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SALEM - UNIT 1 3/4 3-31 Amendment No.196 l
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cmeg UNITED STATES g-y UCLEAR RE'IULATORY COMMIGCION t
o%......j WASHINGTON, D.C. 205d500C1 PUBLIC. SERVICE ELECTRIC & 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.179 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlcntic City Electric Company (the licensees) dated October 25, 1996, as supplemented December 11, 1996, January 28, March 27, April !4, June 3, and June 12, 1997, complies with the l
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;
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B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the
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Comission; '
j C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health end '
safety of the public, and (ii) that such activities will be conducted in compliance with the Commission'.s regulations set t eth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common l
defense and security or t.o the health and safety of the public; and
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of l
the Comission's regulations and all applicable requ'irements have been i
satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and l
paragraph 2.C.(2) of Facility Or2 rat!ng License No. DPR-75 is hereby cmended to read as follows:
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TABLE 3.3-5 I
l ENGINEERED SAFETY FEATURES RESPONSE ITEMS
)
I INITIATING SIGNAI AND FUNCTION 1
RESPONSE TIME IN SECONDS 1.
Manual l
i a.
Safety Injection (ECCS)
Not Applicable 1
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Feedwater Isolation Not Applicable i
Not Applicable Containment Isolation-Phase "A" Not Applicable f
Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Service Water System Not Applicable Containment Fan Cooler
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Not Applicable
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b.
Containment Spray Not Applicable f
Containment Isolation-Phase "B" Not Applicable l
Containment Ventilation Isolation Not Applicable c.
Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation Not Applicable I
d.
Steam Line Isolation Not Applicable 2.
Containment Pressure-High a.
Safety Injection (ECCS) s27.0(1) b.
Reactor Trip (from SI) s2.0
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c.
Feedwater Isolation s10.0 i
d.
Containment Iscir.clon ' tase "A" sl7.0(2)/27.0(3) e.
Containment Ventilation Isolation Not Applicable f.
Auxiliary Feedwater Pumps s60 g.
Service Water System s13.0(2)/45.0(3) h.
Containment Fan Coolers s60.0 (7) l SALDi - UNIT 1 3/4 3-27 Amendment No.196 i
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TABLE 3.3-5 (Continued)
TABLE NOTATION (1)
Diesel generator starting and sequence loading delays included.
Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps, SI and RHR pumps.
(2)
Diesel generator starting and sequence loading delays not included.
Offsite power available. Response time lindt includes op+ning of valves to establish SI path and attainment of discharga pressure for centrifuga1 charging pumps.
(3)
Diesel generator starting and sequence loading delays included.
Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
(4)
On 2/3 in any steam generator.
(5)
On 2/3 in 2/4 steam generators.
(6)
The response time is the time the isolation circuitry input reaches the isolation setpoint to the time the Isolation valves are fully shut.
(7)
The response time includes the time to automatically align the service water flow to the CFCUs following an accident coincident with a loss of offsite power, and also includes the time delays associated with isolation of the Turbine Generator Area service water header.
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9ALEM - UNIT 1 3/4 3-31 Amendment No.196
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4 UNITED STATES y
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20686-0001
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PUBLIC SERVICE ELECTRIC & 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.179 License No. DPR-75 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated October 25, 1996, as supplemented December 11, 1996, January 28, March 27, April 24, June 3, and June 12, 1997, 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; r 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) t. hat such activities will be conducted 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 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:
I
. (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 179, are hereby incorporated in the license.
The licensee shall o the Technical Specifications. perate the facility in accordance with In addition, the license is amended by changes to Appendix C as indicated in the attachment to this license amendment, and paragraph 2.C.(26) of the Facility Operating License No. DPR-75 is amended to read as follows:
(26) Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No.179, are hereby incorporated into this license.
Public Service Electric and Gas Company shall operate the facility in accordance with the Additional Conditions.
3.
This license amendment is effective as of its date of issuance, to be implemented prior to entry into Mode 3 from the current outage.
FOR THE NUCLEAR REGULATORY COMMISSION fus/M.L000 n
John F. Stolz, Dire r
Project Directorate I-2 Division of Reactor Projects - I/II l
Office of Nuclear Reactor Regulation Attachments:
1.
Pacfe I to Appendix C of License
- DPR-75 2.
Changes to the Technical Specifications l
Date of Issuance: June 19, 1997 i
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- Page 1 of Appendix C is attached, for convenience, for the composite license to reflect this change.
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l ATTACHMENT TO LICENSE AMENDMENT NO.179 '
l FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 1
1.
Remove Insert Appendix C, page 1 i
Appendix C, page 1 i
2.
Revise Appendix A as follows:
Remove Paaes
. Insert Paaes 3/4 3-28 3/4 3-32 3/4 3-28 3/4 3-32 1
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APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. DPR-75 Public Service Electric and Gas Company, Philadelphh Electric Company, Delmarva Power and Light Company, and Atlantic City Electric Company shall comply with the following conditions on the schedules noted below:
Amendment Additional Condition Implementation Number Date 175 The licensee is authorized to relocate certain Technical The amendment l
Specification requirements to licensee-controlled shall be i
documents, implementation'of this amendment shall implemented include the relocation of these technical specification within 60 days I
requirements to the appropriate documents, as described in from March 21, the licensee's application dated January 11,1996,as 1997.
1 supplemented by letters dated February 26, May 22, I
June 27, July 12, December 23,1996, and March 17, 1997, and evaluated in the staff's safety evaluation' attached to this amendment.
177 The licensee is authorized to upgrade the initiation circuitry The amendment for the power operated relief valves, as described in the shall be l
licensee's application dated January 31,1997, as implemented prior supplemented by letters dated March 14, to entry into Mode April 8, and April 28,1997, and evaluated in the staff's 3 from the current safety evaluation attached to this amendment.
outage for Salem, Unit 2.
179 Ccotainment Fan Cooler Units The amendment All modifications made in support of the amendment shall be request concerning Containment Fan Cooler Unit (CFCU) implemented prior response time dated October 25,1996, as described in the to entry into Mode letters supplementing the amendment request dated 3 from the current December 11,1996, January 28, March 27, April 24, outage for Salem, l
June 3, and June 12,1997, shall be in conformant.e with Unit 2.
the existing design basis for Salem Unit 2, and programmatic controls for tank monitoring instrumentation shall be as described in the letter dated April 24,1997.
Post modification testing and confirmatory analyses shall be as described in the letter drted March 27,1997. Future changes to the design described in these submittals may be made in accordance with the provisions of 10 CFR 50.59.
Further, the administrative controls associated with CFCU operability and containment integrity described in the letters dated March 27 and April 24,1997, shall not be relaxed or l
changed without prior staff review until such time as the l-license has been amended to include the administrative controls as technical specification requirements.
Amendment No. M, W,179
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TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIAT7NG SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS l
1.
Manual a.
Safety Injection (ECCS)
Not Applicable Feedwater Isolation Not Applicable Reactor Trip (SI)
Not Applicable Containment Isolation-Phase "A" Not Applicable Containment Ventilation Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable Service Wate: System Not Applicable Containment Fan Cooler Not Applicable b.
Containment Spray Not Applicable Containment Isolation-Phase "B" Not Applicable Containment Ventilation Isolation Not Applicable c.
Containment Isolation-Phase "A" Not Applicable Containment ventilation Isolation Not Applicable d.
Steam Line Isolation Not Applicable 2.
Containment Pressure-High a.
Safety Injection (ECCS) s 27.0(1) b.
Reactor Trip ffrom SI) s 2.0 c.
Feedwater Isolation s 10.0 d.
Containment Isolation-Phase "A" s 17.0(2,/27.0(3) e.
Containment Ventilation Isolation Not Applicable f.
Auxiliary Feedwater Pumps s 60 g.
Service Water System s 13.0(2)/45.0(3) h.
Containment Fan Coolers s 60.0(7) l SALEM - UNIT 2 3/4 3-28 Amendment No.179
TABLE 3.3-5 (Continued)
TABLE NOTATION (1)
Diesel generator starting and sequence loading delays included.
Response time lindt includes opening of valves to establish SI path and attaimnent of discharge pressure for centrifugal charging pumps, SI and RHR pumps.
(2)
Diesel generator starting and sequence loading delays not included.
Offsite power available. Response time limi?. includes opening of valves to establish SI path and attaimaent of discharge pressure for cent ! fugal charging pumps.
(3)
Diesel generator starting and sequence loading delays included.
Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
(4)
On 2/3 in any steam generator.
(5)
On 2/3 in 2/4 steam generators.
(6)
The response time is the time the isolation circuitry input reaches the isolation setpoint to the time the Isolation Valves are fully shut.
(7)
The ro pense tirce includes the time to autenatically align the service water flow to the CFCUs following an accident coincident with a loss of offsite power, and also includes the time delays associated with isolation of the Turbine Generator Area service water header.
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SALEM - UNIT 2 3/4 3-32 Amendment No.179 1
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