ML20195B435
| ML20195B435 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 10/28/1988 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20195B431 | List: |
| References | |
| NUDOCS 8811020018 | |
| Download: ML20195B435 (7) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 6I WASHINGTON, D. C. 20655
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SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY DCCKET NO. 50-395 VIRGIL C. SUMNER N'JCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. NPF-12 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by South Carolina Elec'.ric & Gas Company (the licensee), dated March 8,1988 and suppleranted by submittals dated August 31. 1988 and September 30, 1988, complies with the standards anc requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFP. 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 Comission'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 amendrent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2, Accordir. gly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this licenst amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-12 is hereby amended to read as follows:
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i (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 74
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of its date of issuance, and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULA'ORY CDP. MISSION N
Elinor G. Adensam, Director Project Directorate !!-1 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of issuance:
October 28, 1989
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ATTACHMENT TO LICENSE dMENDMENT NO. 74 TO FACILITY OPERATING LICENSE NO. NPF-12 a
DOCKET NO. 50-395 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of chsnge.
Remove Pages inseat Pages 3/4 9-15 3/4 9-15 3/4 9-16 3/4 9-16 5-6 5-6 5-7 5-7 5-7a delete 4
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4.25 FUEL ASSEMBLYINITIAL ENRICHMENT,wi.% U 235 FICURE 3.9-1 MINIMUM REQUIRED FUEL ASSEMBLY EXPOSURE AS A FUNCTION OF INITIAL EhRICHMENT TO PERMIT STORAGE IN R5GION 2
.s SUMER - UNIT 1 3/4 9-15 Amendment No. T//. 74
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4.25 FUEL ASSEMBLY INITIAL ENRICHMENT,wT. % U 235 FIGURE 3.9-2 MINIMoM REQUIRED FUEL ASSEMBLY EXPOSURE AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 3 SUMER - UNIT 1 3/4 9-16 Amendment No. 2/, 74
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly normally containing 264 fuel rods clad with Zircaloy-4. except that limited substitution of fuel rods by filler rods consisting of Zircaloy-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 144 inches.
The initial core loading shall have a maximum enrichment of 3.2 weight percent U-235 Reload fuel shall be similar in physical design to the initial i
co. loading and shall have a maximum enrichment of 4.25 weight percent U-235.
I CONTROL R00 ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length control rod assemblies.
The full length control rod assemblies shall contain a nominal 142 inches o' 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 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 5.2 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 9407 1 100 cubic feet at a nominal T of 586.8*F.
avg
- 5. 5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
SUM 4ER - UNIT 1 5-6 Amendment No. 11, 55, fi 74
DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY
- 5. 6.1.1 The spent fuel storage racks consist of 1276 individual cells, each of which accommodates a t, ingle fuel assembly.
The cells are grouped into 3 regions.
Region 1 is designated for storage of freshly discharged fuel assemblies with enrichments up to 4.25 weigh percent U-235.. The cells in l
Region 2 are reserved for accommodating fuel assemblies with initial enrichments of 4.25 weight percent U-235 and a minimum burnup of 19,000 MWD /MTU.
Both
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Regions 1 and 2 are poisoned.
Region 3 cells are capable of accommodating fuel assemblies with initial enrichments of 4.25 weight percent U-235 and a minimum burnup of 39,750 MWD /MTU.
The spent fuel storage racks are designed and shall be maintained with:
A K,ff equivalent to less than or equal to 0.95 when flooded with a.
unborated water, which includes a conservative allowance for uncertainties as described in Section 4.3 of the FSAR.
b.
Nominal center-to-center distance between fuel assemblies of 10.4025" in Region 1, 10.4025" x 10.1875" in Region E, and 10.116" in Reginn 3.
5.6.1.2 The new fuel storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that K,ff will not exceed 0.98 when fuel having a maximum enrichment of 4.25 weight percent U-235 is in place and v.irious densities of unborated water l
are assumed including aqueous foam moderation.
The K,ff of 10.98 includes the l
conservative allowance for uncertainties described in Section 4.3 of the FSAR.
DRAINAGE 5.6.2 The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 460'3".
SLM4ER - UNIT 1 5-7 Amendment No. 21, 74
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