ML20072J746
| ML20072J746 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/23/1994 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072J750 | List: |
| References | |
| NUDOCS 9408290159 | |
| Download: ML20072J746 (9) | |
Text
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1 ARRFCp A.
A 7
E UNITED STATES
$ 't NUCLEAR REGULATORY COMMISSION l
g WASHINGTON, D.C. 20555-0001 i
l t
-LOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA PUBLIC SERVICE AUTHORITY I
DOCKET NO. 50-395 VIRGIL C. SUMMER NUCLEAR STATION. UNIT N0. !
l AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 116 l
License No. NPF-12 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by South Carolina Electric & Gas Company (the licensee), dated December 13, 1993, as supplemented by letter dated March 11, 1994, 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; 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 Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No.
NPF-12 is hereby amended to read as follows:
y 9408290159 940823 PDR ADOCK 05000395 p
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. (2)
T5chnical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.116
, 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 REG TORY COMMISSION W
/
N D id B. Matthews/ Dire tor Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 23, 1994
l ATTACHMENT TO LICENSE AMENDMENT NO. 116 TO FACIl.lTY OPERATING LICENSE N0. NPF-12 DOCKET NO. 50-395 Replace the following pages of the Appendix A Technical Specifications with j
the enclosed pages. The revised pages are indicated by marginal lines.
l Remove Paaes Insert Paaes 3/4 9-14 3/4 9-14 3/4 9-15 3/4 9-15 3/4 9-16 3/4 9-16 i
5-6 5-6 5-7 5-7 5-7a 5-7a 1
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REFUELING OPERATIONS 3/4.9.12 SPENT FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.12 The combination of initial enrichment and cumulative burnup for l
spent fuel assemblies stored in Regions 2 and 3 shall be within the acceptable domain of Figure 3.9-1 for Region 2 and Figure 3.9-2 for Region 3.
APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel pool.
ACTION:
j 1
a.
With the requirements of the above specification not satisfied, suspend all other movement of fuel assemblies and crane operations with loads in the fuel storage areas and move the non-complying fuel assemblies to Region 1.
Until these requirements of the above specification are satisfied, boron concentration of the spent fuel pool shall be verified to be greater than or equal to 2000 ppm at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable SURVEILLANCE REQUIREMENTS 4.9.12 The burnup of each spent fuel assembly stored in Regions 2 and 3 shall be ascertained by careful analysis of its burnup history prior to storage in Region 2 or 3.
A complete record of such analysis shall be kept for the time period that the spent fuel assembly remains in Region 2 or 3 of the spent fuel pool.
1 SUMMER - UNIT 1 3/4 9-14 Amendment No. -B7,116
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Note: The use of lineer interpolation between the mmimum burnups reported above is acceptable.
FIGURE 3.9-1 MINIMUM REQUIRED FUEL ASSEMBLY BURNUP AS A F OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 2 SOCIER - UNIT 1 3/4 9-15 Amendment No. 2 7 / >44~.110
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FIGURE 3.9-2 MINIMUM REQUIRED FUEL ASSEMBLY BURNUP AS A OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 3 SU'DIER - UNIT 1 3/4 9-16 Amendment No. 27 /, -M-116
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES ~
5.3.1 The core shall contain 157 fuel assemblies. Each fuel assembly shall consist of 264 Zircaloy-4 or ZIRLO(TM) clad fuel rods with an initial composition of uranium dioxide with a maximum nominal enrichment of 5.0 weight percent U-235 as fuel material. Limited substitutions of Zircaloy-4, ZIRLO(TM) and/or stainless steel filler rods for fuel rods, if justified by a cycle specific reload analysis using an NRC-approved methodology, may be used. Fuel assembly configurations shall be limited to those designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or cycle-specific reload analyses to comply with all fuel safety design bases. Reload fuel shall contain sufficient integral fuel burnable absorbers such that the requirements of Specifications 5.6.1.la.2 and 5.6.1.2 b are met.
A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core locations.
CONTROL R0D 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 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 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 For a temperature of 650*F, except for the pressurizer which is c.
680*F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is t
9407 100 cubic feet at a nominal Tavg of 586.8'F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
i SUMMER - UNIT 1 5-6 Amendment No. 27, 55, G2, 74, 105,116
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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 single assembly. The cells are grouped into 3 regions.
The spent fuel storage racks are designed and shall be maintained with a Keff less than or equal to 0.95 when flooded with unborated water, which includes conservative allowances for uncertainties and biases.. This is ensured by maintaining the following for each region:
a.
REGION 1 - designated for storage of fresh fuel assemblies and freshly discharged fuel assemblies.
1.
A nominal 10.4025 inch center-to-center distance between fuel assemblies placed in the storage rack.
2.
A maximum nominal enrichment of 5.0 weight percent U-235 with sufficient integral fuel burnable absorbers such that the maximum reference fuel assembly K. is less than or equal to 1.460 at 68'F.
b.
REGION 2 - designated for storage of discharged fuel assemblies.
1.
A nominal 10.4025 x 10.1875 inch center-to-center distance between fuel assemblies placed in the storage rack.
i 2.
A maximum nominal enrichment of 2.5 weight percent U-235 with no burnup and up to 5.0 weight percent U-235 with a minimum burnup of up to 21,600 MWD /MTU, as specified in Figure 3.9-1.
c.
REGION 3 - designated for storage of discharged fuel assemblies.
1.
A nominal 10.116 inch center-to-center distance between fuel assemblies placed in the storage rack.
2.
A maximum nominal enrichment of 1.4 weight percent U-235 with no burnup and up to 5.0 weight percent U-235 with a minimum burnup of up to 48,000 MWD /MTV, as specified in Figure 3.9-2.
5.6.1.2 The new fuel storage racks consist of 60 individual cells, each of which accommodates a single assembly. The new fuel pit storage racks are designed and shall be maintained with a Keff less than or equal to 0.95 when flooded with unborated water and less than or equal to 0.98 for low density optimum moderation conditions, including conservative allowances for uncertainties and biases. This is ensured by maintaining:
a.
A nominal 21 inch center-to-center distance between new fuel assemblies placed in the storage rack.
b.
A maximum nominal enrichment of 5.0 weight percent U-235 with sufficient integral fuel burnable absorbers such that the maximum reference fuel assembly K. is less than or equal to 1.460 at 68'F.
SUMMER - UNIT 1 5-7 Amendment No. 27,--74,116
DESIGN FEATURES DRAINAGE l
5.6.2 The spent Yuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 460'3".
CAPACITY 5.6.3 The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 1276 fuel assemblies, 242 in Region 1, 99 in Region 2, and 935 in Region 3.
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.
i SUMMER - UNIT 1 5-7a Amendment No. 27,116
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