ML20082P302
| ML20082P302 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/22/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082P306 | List: |
| References | |
| NUDOCS 8312080190 | |
| Download: ML20082P302 (10) | |
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UNITED STATES 8)b b
' NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY
~AT[ ANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.55 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated December 3, 1982, complies with the standards and require-ments 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 confonnity 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; D.
The issuance of this amendment will not be inimical to the cocanon
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defense and security or to the health and safety of the public; l
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.
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Accordingly, the license is amended by changes to the Technical Specifications 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:
(2) Technical Specifications The Technical Snecifications contained in Appendices A and B, as revised through Amendment No. 55, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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teven /Y Var lga, ief Operating Reactor Branch No. 1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 22, 1983 l
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,e ATTACHMENT TO LICENSE AMENDMENT NO.55 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 1
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DESIGN FEATURES E.;
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555 DESIGN PRESSURE AND TEMPERATURE 5
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X 5.2.2 The reactor containment building is designed and shall be main-NE l"i tained for a maximum internal pressure of 47 psig and an air temperature of 271*F.
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2555 5.3 REACTOR CORE 5
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FUEL ASSEMBLIES
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5.3.1 The reactor core shall contain 193 fuel assemblies with each 5
fuel assembly containing 264 fuel rods clad with Zircaloy -4.
Each L'.
fuel rod shall have a nominal active fuel length of 143.7 inches and contain a maximum total weight of 1766 grams uranium.
The initial 7
core loading shall have a maximum enrictnent of 3.35 weight percent U-235.
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Reload fuel shh11 be similar in physical design to.the initial core m
loading and shall have a maximum enrichment of'4.0E weight percent U-235 4
5, CONTROL ROD ASSEMBLIES l-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 of absorber material shall be 80 percent silver,15 percent indium and 5 E
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percent cadmium.
All control rods shall be clad with stainless steel tubing.
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5.4 REACTOR COOLANT SYSTEM 5'
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DESIGN PRESSURE AND TEMPERATURE
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5.4.1 The reactor coolant system is designed and shall be maintained:
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I SALEM - UNIT'1 5-4 Amendment No. 55
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DESIGN FEATURES a.
In accordance with the code requirements specified in Section 4.1 of the FSAR with allowance for nornal 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 + 100 cubic feet at a nominal T,yg of 576.7'F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE
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CRITICALITY 5.6.1 The new and spent fuel. storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between ned fuel assemb'.ies and a nominal 10.5 inch center-to-center distance between spent fuel assemblies placed in the storage racks to ensure a kT$di quivalent e
to < 0.95 with the storage pool filled with caborated water.
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5,0795 includes a conservative allowance of 2.2% ak/k for uncertainIIIs.f DRAINAGE 5.6.2 The spent fuel storage pool is designed ahd shall bE maintained to prevent inadvertent draining of the pool below elevation 124'8".
CAPACITY I
5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1170 fuel assemblies.
8' Each assembly is limited to 4.05 weight percent U-235.
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SALEM - UNIT 1 5-5 Amendment No. 55 r--
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.i NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 i
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PUBLIC SERVICE ELECTRIC AND 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.22 '
License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated December 3, 1982, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended 'the Act) and the Commission's rules and regulations set for v 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 l
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 a'mendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 22, 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION jd f
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pSte%venA.Varg. Jai hief Operating Reac Branch No. 1 Division of Licensing
Attachment:
Changes to the Technical Specifications
- Date of Issuance: November 22, 1983 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 22 FACILITY OPERATING LICENSE NO. DPR-75 DOCKET NO. 50-311 1
Revise Appendix A as follows:
Remove Pages Insert Pages 5-4 5-4 5-5 5-5 l
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DESIGN FEATURES DESIGN 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 FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 143.7 inches and contain a maximum total weight of 1766 grams uranium.
The initial core loading shall have a maximum enrichment of 3.35 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.05 weight percent U.235.
I CONTROL ROD ASSEM LIES 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 of absorber material l
shall be 80 percent silver,15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless stvel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
a.
In accordance with the code requirements specified in Section 4.1 of the FSAR, with allowance for normal degradation pt suant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and For a temperature <>f 650*F, except for the pressurizer which is c.
680*F.
j 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,yg of 581.0*F.
SALEM - UNIT 2 5-4 Amendment No.
22
f DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 The new and spent fuel storage racks are designed and shall be maintained with:
a.
Ak equivalent to less than or equal to 0.95 when flooded with unb8f$ted water, which includes a conservative allowance of 2.2%
delta k/k for uncertainties.
b.
A nominal 21 inch center-to-center distance for new fuel storage racks and 10.5 inch center-to-center distance for spent fuel storage racks.
i DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 124'8".
CAPACITY r
5.6.3 The fuel storage pool is designed and shall be maintained with a storage l
capacity limited to no more than 1170 fuel assemblies.
Each assembly is l
limited to 4.05 weight percent U-235.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
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SALEM - UNIT 2 5-5 Amendment !!o. 22
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