ML20216A827
| ML20216A827 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/19/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20216A832 | List: |
| References | |
| NUDOCS 8706260394 | |
| Download: ML20216A827 (10) | |
Text
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D De + Gjku:Q'o, UNITED STATES
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' NUCLEAR REGULATCRY COMMISSION
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y PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY-
'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-4 Amendment No. 80 License No.~DPR-70 1.
The Nuclear Regulatory Comission.(the Comission 'or the NRC) has. found m.
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.3, 1986 and supplemented by letter dated October 10, 1986.
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 Comission; 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 Comission'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 Comission'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-70 is hereby
' amended to read as follows:
8706260394 870619 DR ADOCK O 22:
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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. 80, are hereby' incorporated in the i
. license.
The licensee shal.1 operate the facilid.y in accordance with-
.the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Walter R. Butler, Director.
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Project Directorate I-2 Division of Reactor Projects I/II i
Attachment:
Changes to.the Technical.
' Specifications Date of Issuance: June 19, 1987
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(2) Technical ~ Specifications and Environmental Protection Plan I
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 80, are hereby incorporated in the license. The licensee shall ope, rate the facility in accordance with
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the. Technical Specifications.-
1
' 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
s Walter R. Butler, Director Project Directorate I-2 Divisi<n of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications i
Date of Issuance: June 19, 1987 I
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ATTACHMENT.T0 LICENSE AMENDMENT NO.' 80 FACILITY OPERATING LICENSE NO. DPR-70
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DOCKET NO. 50-272 Revis' e. Appendix A ns follows:
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DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 ' The reactor containment building is designed and shall be maintained for j
a maximum internal pressure of 47 psig and an air temperature of 271*F.
5.3 REACTOR CORE FUE L ASSEMB LIES 5.3.1 The-reactor core shall contain 193 fuel assemblies with each fuel
-assembly normally containing 264 fuel rods clad with Ziracioy-4 except that limited substitution of fuel rods by filler rods consisting of Ziracloy-4 or stainless steel or by vacancies may be made if justified by a cycle specific reload analysis.
Each fuel rod shall have a nominal active fuel length of 143.7 inches. The initial core loading shall have a maximum enrichment of 3.35 weight l
percent U-235.
Reload fuel shall be similar in physical design to the core loading and shall have A maximum enrichment of 4.05 weight percent U.235.
CONTROL R00 ASSEMBLIES ~
j 5.3.2 The reactor core shall contain 53 fall length and no part length control j
rod assemblies. The full length control rcd assemblies shall contain a nominal 142 inches of absorber material.
The riominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent 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:
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SA LEM - UNIT 1 5 -4 Amendment No. 80 l
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.I WASHINGTON, D C. 20555.
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PUBLIC SERVICE' ELECTRIC & GAS COMPANY' PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY' ATLANTIC. CITY ELECTRIC COMPANY r
DOCKET N0. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE
' Amendment No. 54 License No. DPR-75 1.
The Nuclear.ReguYa' tory Comission;(the Comission or the NRC)'h'as found' 4
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 3. -1986 and supplemented by letter dated October 10, 1986, 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 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 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 m'
~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.
21 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-75 is hereby amended to read as follows:-
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, (2)' lechnical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in"the L
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.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
Walter R. Butler,-Director Project Directorate I-2 Division of Reactor Projects I/II
Attachment:
l Changes to the Technical.
Specifications -
Date of Issuance: ' June 19, 1987
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j (2) _ Technical Specifications and Environmental Protection Plan l
The. Technical Specifications contained in Appendices A and B, as
' revised through Amendment No. 54
, are hereby incorporated in the license. - The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This licen'se amendment is effective as' of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director-j Project Directorate I-2,
i Division of Reactor Projects I/II
Attachment:
~
Changes to the Technical Specificationt Date of Issuance: June 19, 1987
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ATTACHMENT TO LICENSE AMENDMENT NO. 54 i.
FACILITY OPEPATING LICENSE N0; DPR-75 DOCKET NO. 50-311 Revise Appendix A'as follows:
I Remove Page Insert Page.
'5-4 5-4'
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[ESIGN FEATURES -
- 0ESIGN PRESSURE AND TEMPERATURE
.5.2.2?.The: reactor containment building is. designed and shall be maintained for a maximum internal pressure of 47 psig and an air temperature of 271 F..
5.3 REACTOR. CORE-
. FUE L ASSEM8 LIES i
- 5.3.1 The reactor _ core shall contain.193l fuel assemblies-with each fuel l
assembly' normally'containing 264 fuel rods' clad with Ziracioy-4 except that
- limited substitution of fuel rods by filler' rods consisting'of Ziracloy-4'or stainless ' steel:.or by vacanc'ies may be made if justified by a cycle specific'
~ reload analysis.
Each -fuel rod shall have:a nominal active fuel length of 143.7 u.
inches. ~ The initici: core loading.shall have al maximum enrichment of 3.55 weight
.l l:
percent U-235.. Reload fuel shall be 'similar in physical design to the-core
' loading and shalli ave a maximum onrichment of 4.05 weight percent U.235.
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. CONTRO L1 ROD' ASSEMB LIES.'
5.3.2 The' reactor core shal1$contain 53 full length' and no part length control' W.
-rod assembliese.The' full length control rod assemblies shall contain a nominal'
'142 inches of' absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. All control rods
. shall be c1'ad with stainless steel tubing.
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~ 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 srecified 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 thL pressurizer which is 680'F.
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5.4.2~.The total water and steam volume of the reactor coolant system is 12,811 +-100 cubic feet at a -nominal Tavg of 581.0 F.
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SA LEM - UNIT 2 54 Amendment No. 54 1
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