ML20141H402
| ML20141H402 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/17/1997 |
| 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 | |
| ML20141H407 | List: |
| References | |
| DPR-70-A-198, DPR-75-A-181 NUDOCS 9707230133 | |
| Download: ML20141H402 (10) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20666-0001 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY j
DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.198 License No. DPR-70 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, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated June 18, 1996, as supplemented August 19, 1996, April 28, 1997, and June 11, 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; 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 i
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.
i 2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and i
paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby I
amended to read as follows:
9707230133 970717 PDR ADOCK 05000272 P
PDR I
i
1 l (2) Technical Specifications and Environmental Protection Plan i
The Technical Specifications contained in Appendices A and B, as i
revised through Amendment No.198, 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.(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.198, are hereby incorporated into this license.
Public Service Electric and Gas Corr.pany 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 within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Jopn.F.Stolz, Director
)
P@ ect Directorate I-2 v Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachmenta
~1.
Page I to Appendix C of License
- DPR-70 2.
Changes to the Technical Specifications Date of Issuance: July 17, 1997 1
- Page -1 of Appendix C is attached, for convenience, for the composite license to reflect this change.
a ATTACHMENT TO LICENSE AMENDMENT NO. 198 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 1.
Remove Insert Appendix C, page 1 Appendix C, page 1 2.
Revise Appendix A as follows:
Remove Paaes Insert Paaes 5-4 5-4 4
=
j 1
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:
Amendment Additional Condition Implementation Number Date 192 The licensee is authorized to relocate certain Technical The amendment shall Specification requirements to licensee-controlled documents.
Le implemented implementation of this amendment shallinclude the relocation of within 60 days from these technical specification requirements to the appropriate March 21,1997, documents, as described in the licensee's.*pplication dated January 11,1996, as supplemented L; 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 autnorized to upgrade the initiation circuitry for the The amendment shall povver operated relief valves, as described in the licensee's be implemented prior application dated January 31,1997, as supplemented by letters to entry into Mode 3 dated March 14, April 8, and April 28,1997, and evaluated in the from the curre.1 staff's safety evaluation attached to this amendment.
outage for Salem, Unit 1.
196 Containment Fan Cooler Units The amendment shall The licensee shall complete all modifications associated with the be implemented prior amendment request concerning Containment Fan Cooler Unit to entry into Mode 3 (CFCU) response time dated October 25,1996, as described in from the current the letters supplementing the amendment request dated outage for Salem, December 11,1956, January 28, March 27, April 24, June 3, and Unit 1.
June 12,1997, prior to entry into 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 the existing design basis for Salem Unit 1, 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 dated 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 changed without prior staff review until such time as the license has been amended to include the administrative controls as technical specification requirements.
198 The licensee shall perform an evaluation of the containment liner The amendment shall anchorage by Novernber 30,1997, for the loading induced on the be implemented containment liner during a Main Steam Line Break event to confirm within 30 days from the assumptions provided in the Preliminary Safety Analysis Report July 17, 1997.
and Updated Final Safety Analysis Report.
Amendment No. Ma, M4, M6,198
i DESIGN FEATURES
......................................c.......................................
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment is designed and shall be maintained for a maximum internal pressure of 47 psig.
Containment air temperatures up to 351.3*F are acceptable providing the containment pressure is in accordance with that described in the UFSAR.
5.3 REACTOR CORE 4
FUEL ASSEMBLIES 5.3.1 The reactor shall contain at least 193 fuel assemblies.
Each assembly i
shall consist of a matrix of zircaloy or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material.
Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel
~
designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies. The full length control rod assemblier shall contain a nominal 142 inches of absorber material. The nominal values t absorber material shall be 80 percent silver, 15 percent indium and 5 p reent cadmium.
All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN FEATURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
4 SALEM - UNIT 1 5-4 Amendment No.198 l
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3066Hooi
\\..../
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 N0. 2 3
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.181 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 &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated June 18, 1996, as supplemented August 19, 1996, April 28, 1997, and June 11, 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; 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 Chapter 1; 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'-
(2) Techs.. cal Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.181, are hereby incorporated 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.(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 througn Amendment No.181, 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 within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
)
/
I John'
. Stolz, Director ctDirectorateI-2'j)
Pro Di ision of Reactor Projects - I/II 4
Office of Nuclear Reactor Regulation Attachments:
1.
Page 1 to Appendix C of License
- DPR-75 2.
Changes to the Technical Specifications Date of Issuance: July 17, 1997
- Page 1 of Appendix C is attached, for convenience, for the composite license to reflect this change.
V l
ATTACHMENT TO LICENSE AMENDMENT NO.181 l
FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 1.-
Remove Insert Appendix C, page 1 Appendix C, page 1 i
2.
Revise Appendix A as follows:
Remove Paaes Insert Paaes 5-4 5-4
APPENDIX C ADDITIONAL CONDITIONS OPERATING LICENSE NO. OPR-75 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:
Amendment Additional Condition Implementation Number Date 175 The licensee is authorized to relocate certain Technical The amendment shall l
Specification requirements to licensee-controlled documents.
be implementerl implementation of this amendment shallinclude the relocation of within 60 days from these technical specification requirements to the appropriate March 21,1997.
documents, as described in the licensee's application dated January 11,1996, as supplemented by letters dated February 26, l
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.
177 The licensee is authorized to upgrade the initiation circuitry for the The amendment shall power operated relief valves, as described in the licensee's be implemented prior application dated January 31,1997, as suppitmented by letters to entry into Mode 3 dated March 14, April 8, and April 28,1997, and evaluated in the from the current staff's safety evaluation attached to this amendment.
outage for Salem, Unit 2.
179 Containment Fan Cooler Units The amendment shall All modifications made in support of the amendment request be implemented prior concerning Containment Fan Cooler Unit (CFCU) response time to entry into Mode 3 dated October 25,1996, as described in the letters supplementing from the current the amendment request dated December 11,1996, January 28, outage for Salem, March 27, April 24, June 3, and June 12,1997, shall be in Unit 2.
conformance with 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 dated 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 changed without prior staff review until such time as the license has been amended to include the administrative controls as technical specification requirements.
181 The licensee shall perform an evaluation of the containment liner The amendment shall anchorage by November 30,1997, for the loading induced on the be implemented containment liner during a Main Steam Line Break event to confirm within 30 days from the assumptions provided in the Preliminary Safety Analysis Report July 17, 1997, and Updated Final Safety Analysis Report.
Amendment No. 4M, 97, W9,181
I 1
DESIGN FEATURES i
DESIGN PRESSURE AND TEMPERATURE j
5.2.2 The reactor containment is' designed and shall be maintained for a maximum internal pressure of 47 psig.
Containment air temperatures up to 351.3*F are acceptable providing the containment pressure is in accordance with that described in the UFSAR.
5.3 ' REACTOR CORE FUEL ASSEMBLIES I
5.3.1 The reactor shall contain at least 193 fuel assemblies.
Each assembly shall consist of a matrix of zircaloy or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material.
Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values ut absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless eteel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN FEATURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
a.
In accordance with the code requirement specified in Section 4.1 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650*F, except for the pressurizer which is 680*F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12,811 1 100 cubic feet at a nominal T,, of 581.0'F.
SALEM - UNIT 2 5-4 Amendment No.181
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