ML20076E116
| ML20076E116 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/01/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076E119 | List: |
| References | |
| NUDOCS 9108150190 | |
| Download: ML20076E116 (11) | |
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UNITED STATES i M(2$h L.ti NUCf EAR REGULATORY COMMISSION 1
WASHINGTON, D.C. 20566 q 7,:.....f
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PUBLIC SERVICE ELECTRIC,j,,CA,S_,C,0,M,PgY THILADELPHI A ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY 4
ATLANTIC-CITYELECTRICC0ftPANY A
DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION. tJNIT NO.1 AMENDMENT TO FACILITY OP, ERA,T_I!!,G, LICE!15,E -
- Amendment No.128 License.No. OPR-70 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, Phi _ladelphia Electric Company, Delmarva Power-and Light Company and: Atlantic City Electric Company (the licensees) dated November 19, 1990, as supplemented April _1, 1991, May 20, 1991 and June 14, 1991, complies with the standards and requirements of the i
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; 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 comr:liance with the Comission's _ regulations set forth in 10-CFR Chapter:1; D.
The issuance of this amendment will not be inimical to the comon defense-and secur_ity 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 licens'e 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:
9108150190 910001 DR ADOCK 050 2
2 (2) -Technical Specifications and Environmental Protection Plan The Technical Specifications contained ir Appendices A and B, as revised throbgh Amendment No.128, 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 of issuancet FOR THE NUCLEAR REGULATORY COMMISSION (i(b
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Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - I/II
Attachment:
Changes to the Technical Specifications Date of-Issuance:
August 1, 1991 l
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ATTACHMENT _ Tp,LJCE!1,SLMiE!;p!!E!g,!1pd2,8,,,
FACILITY OPERATING LICENSE NO. OPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Pages Insert Pages 5-4 5-4 5-5 5 5-6 5-6
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I DESIGN TEATURES
.....................................a..n......................................
DESIGN PREC Q*J 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'r.
5.3 REACTOR CORE FUEL. ASSEMBLIES 5.3.1~ The reactor core shall contain 193 fuel assemblies with each fuel assembly normally containing 264' fusi rods clad with Ziracloy-4 except that limited substitution of fuel rods.by filler rods consisting of Ziracloy-4 or.
stainless-steel or by va:ancies 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.
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 i
nominal 142 inches of absorber material. The nominal values of absorber material shall=bc 80. percent silver, 15 percent indium and 5 percent cadmium.
All control: rods shall be clad with etainless 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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i SALEM - UNIT 1 5-4 Amendment No.128
DESIGN FtATURES a.
In accordance with the code requirements 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 poig, and c.
For a temperature of 650'F, except for the pressuriser which is 680'F.
VOf ?JME 5.4.2 The total water and steam volume of the reactor coolant system is 12,811 1 100 cubic feet at a nominal Tavg of 576.7'F.
5.5 METEOPOLOGICAL 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 oew and spent fuel storage racks are designed and shall be maintained withs A reff equivalent to less than or equal to 0.95 with the otorage a.
rack filled with unborated water.
This value of keff includes a conservative allowance of:
1.
2.2% delta k/k uncertainty for all standard and V5H fuel assemblies, and 2.
An additional 0.7% delta k/k uncertainty for standard and V5H fuel assemblies containing Integral Fuel Burnable Absorber (IFBA) pins.
b.
A nominal 10.5 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks.
c.
A nominal 21.0 inch center-to-center distance between fuel assemblies placed in the new fuel storage racks.
d.
Standard or Vantage 5H fuel assemblies with maximum enrichment of 4.55 w/o U235 and a Kint less than or equal to 1.453 in the core geometry at 68'~r with no soluble boron.
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".
I I
SALEM - UNIT 1 5-5 Amendment No.128
DESIGN TEATURES CAPACITY 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.
5.7 COMPONENT CYCLIC OR TRANSirNT 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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I SALEM - UNIT 1 5-6 Amendment No.120 l.
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) i NUCLEAR REGULATORY COMMISSION 1 \\ !)h wAssiNotoN. o e ar.'6
%,.....f PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA,F,0,WER,ApD,,LJ,GH,T,,C,0M,PArq A,T L Af4T I C,,CJ,T Y_EL E CT R I C COMP ANY DOCKET NO.,50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. ?
AfiEt:Ct'ENT T0_ _ FACILITY OPERAT!flG LICEllSE Amendment No.107 License No. OPR-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 Comaany,(Delmarva Power and Lig Company and Atlantic City Electric Company the licensees) dated November 19, 1990, as supplemented April 1, 1991, May 20, 1991, and June 14, 1991 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 1; 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: (1) tnat the activities authorized by this amendment can be conducted without endangering the hccith 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 rot 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 applicabic requirements have been satisfied.
2.
Accordingly, the license is anended 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 flo. OPR-75 is hereby amended to read as follows:
L l
2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No 107. 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 of the date of i ssuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
42/
b v
Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of issuancc: August 1, 1991 l
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i ATTACHt4ENT TO,L1,CEN,SE,/pEtlDi'.Elli tt0.107 FACILITY OPERATit'C LICENSE NO OPR-75 t
DOCKET N_0,.,,5,0,,3)],
Revise Appendix A as follows:
Remove Pages insert Pages 5-4 5-4
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55 5-5 S
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- _ - - - - ~
DESIGN FEATURES
.............................r................................................
DESIGN PRESSURE AND TEMPERATURL 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 GKk AMIlEAU 5.3.1 The reactor core shall contain 193 fuel assemblies with each fuel assembly r.ormally containing 2(4 fuel rods clad with giracioy-4 except that limited substitution of fuel rods by filler rods consisting of Ziracioy-4 of etainless 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.
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 inchen 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 clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM DESIGN FEATURE ANJ 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 pursuart to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and t
c.
For a temperature of 650*F, except for the pressurizer which is 680*F.
VOLUME i
i 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,y of 581.0'F.
l b
SALEM - UNIT 2 5-4 Amendment No.107
t DESIGN TEATURES 5.5 METroROLootcAL TOWER LOCAT1og 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STOP. ACE Chl11Ghld%1 l
5.6.1 The new and spent fuel storage racks are designed and shall be I
maintained with:
A Kef f equivalent to less than or equal to 0.95 with the storage a.
rack filled with unborated water.
This value of koff includes a conservative allowance of:
1.
2.2% delta k/k uncertainty for all standard and V5H fuel assemblies, and 2.
An additional 0.7% delta k/k uncertainty for standard and V5H fuel assemblies containing Integral ruel Burnable Absorber (ITDA) pins.
b.
A nominal 10.5 inch center-to-center distance between fuel assemblies placed in the spent fuel storage racks.
c.
A nominal 21.0 inch center-to-center distance between fuel assemblies placed in the new fuel storage racks, d.
Standard or Vantage 5H fuel assemblies with maximum enrichment of 4.55 w/o U235 and a Kinf less than or equal to 1.453 in the core geometry at 68'r with no soluble boron.
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".
CAL' ACITY 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 assemblics.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT i
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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.
I SALEH - UNIT 2 5-5 Amendment No.107 l
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