ML20093D131
| ML20093D131 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/27/1984 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20093D133 | List: |
| References | |
| NUDOCS 8410110108 | |
| Download: ML20093D131 (12) | |
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,M 8 bJ UNITED STATES 7 i NUCLEAR REGULATC,Y COTAMISSION
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SOUTH CAROLINA ELECTRIC & GAS COMPANY 3
SOUTH CAROL'INA PUBLIC SERVICE AUTHORITY DOCKET NO. 50-395 VI2GIL C. SUMMER NUCLEAR STATI'05, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No. NPF-12 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Virgil C. Sumer Nuclear Stationi Unit No.1 (the facility) Facility Operating License No. NPF-12 filed by the South Carolina Electric & Gas Company acting for itself and South Carolina Public Service Authority (the licensees), dated January 23, 1984, complies with the standards and requirements of the Atomic Energy Act of.1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity 54th the application,-as amended, the provisions of the Act, and the repulations of the Commission; C.
There is reasonable assurance: (i)3 fiat 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to lhe common-defense and security or to the health and safety of the public; E.
The issuance of this license amendment is in accordance with 10CFR Part
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51 of the Commission's regulations and all appTicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C(2) of Facility Operating Licen'se No. NPF-12 is hereby amended to read as follows:
(2) Technical Specifications
- The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, are hereby incorporated into this license.
4 South Carolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This license amendmant is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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- <w Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Enclosure:
Technical Specification Changes Date of Issuance: September 27, 1984 E
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e ATTACHMENT TO LICENSE AMENDMENT t:0. 27 FACILITY OPERATING LICENSE N0. NPF-12 DOCKET NO. 50-395 Replace the following pagse of the Appendix "A"'fechnical Specifications with the enclosed pages. The revised pages are identified by Amend ent number and contain vertical lines indicating the areas of change. Corresponding overleaf pages are also provided to maintain document completeness.
Amended Overleaf Page Page 3/4 9-14 3/4 9-15 3/4 9-16 B3/4 9-3 5-6 5-5 5-7 5-8 5-7a s*
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.s REFUELING-OPERATIONS 3/4.9.12 SPENT FUEL' ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.12 The combination of initial enrichment and cumulative exposure.for 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:
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.E,4-are not applicable -
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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.
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a SUMMER - UNIT 1 3/4 9-14 Amendment No. 27
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4 FUEL ASSEMBLY INITIAL ENRICHMENT, WT. % U-235 FIGURE 3.9-1 MINIMUM REQUIRED FUEL ASSEMBLY EXPOSURE AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 2 SUMMER ~- UNIT 1 3/4 9-15 Amendment No. 27 s
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3 FUEL ASSEMBLY INITIAL ENRICHMENT, WT. % U-235 FIGURE 3.9-2 HINIMUM REQUIRED FUEL ASSEMBLY EXPOSURE AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 3 SUWiER - UNIT 1 3/4 9-16 smendment No. 27
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s i.d.:ui.IhG GPERATIONS BASES 3/4.9.12 SPENT FUEL ASSEMBLY STORAGE The restrictions placed on spent fuel' assemblies stored in Regions 2 and 3 of the spent fuel pool ensure inadvertent criticality will not occur.
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' UNIT 1 B 3/4 9-3 Amendment No. 27 i
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LI UtD RELEASES SOUTH CAROLIN A ELECTRIC & GAS CD.
@ F AIRFIELD PUMPED STOR AGE F ACILITY PENSTOCKS vlRGil C. SUMMER NUCLEAR STATION l
(Al LlOulO WASTE PROCESSING SYSTEM
Release ?OinCS
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(Al UNPROCESSED STEAM GENER ATOR BLOWOOWN
- 18) TURBtNE BUILDING FLOOR O R AINS GASEOUS RELE ASES:
h SITE BOUNDARY FOR GASEOUS RELEASES FIGURE 5.1-4 S UF"'E : - UNIT 1 5-5
DESIGN FEATURES.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 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 144 inches and contain a maximum-total weight of 1766 grams uranium..The initial core loading shall'have a maximum enrichment of 3.2 weight percent U-235.
Reic d fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.3 weight percent U-235.'
CONTROL ROD 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 E' ' -
DESIGN PRESSURE AND TEMPERATURE
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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 650aF, except for the pressurizer which is' 1
680*F.
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VOLUME 5.4.2 The total' water and steam volume of the reactor coolant system is
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9407 100 cubic feet at a nominal T f 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.
i t-l' SUMMER -~ UNIT 1 5-6 Amendment No.27
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 fuel assembly.
The cells are grouped into 3 regions.
Region 1 is designated for storage of freshly discharged fuel assem-blies with enrichments up to 4.3 weight percent U-235.
The cells in Region 2 are reserved for accommodating fuel assemblies with initial enrichments of 4.3 weight percent U-235 and a minimum burnup of 20,000 MWD /MTU.
Both regions 1 and 2 are poisoned.
Region 3 cells are capable of accommodating fuel assem-blies with initial enrichments of 4.3 weight percent U-235 and a minimum burnup of 42,000 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 2, and 10.116" in. Region 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
will, n t exceed 0.98 when fuel having i'liiaxinmm-enrichment of 4.3, weight eff percent U-235 is in place and various densities of unborated water are assumed '
including aqueous foam moderation. The K,ff of 5,0.98 includes the conservative allowance for uncertainties described in Section 4.3 of the FSAR.
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ORAINAGE 5.6.2 The spent fuel pool is designed and shall be maintained to prevent" inadvertent draining of the pool below elevation 460'3".-
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SUMMER - UNIT 1 5-7 Amendment No. 27
-0ESIGN FEATURES 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 maiatained within the cyclic or transient limits of Table 5.7-1.
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SUMMER UNIT 1 5-7(a)
Amendment No.27
O TABLE 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS
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CYCLIC OR DESIGN CYCLE E COMPONENT TRANSIENT LIMIT
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--4 Reactor Coolant System 200 heatup cycles at 5 100 F/hr -
Heatup cycle - T from < 200 F 3y9 and 200 cooldown cycles at to 2 550*F.
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< 100*F/hr.
Cooldown cycle - T avg from
> 550*F to < 200 F.
200 pressurizer cooldown cycles Pressurizer cooldown cycle at < 200*F/hr.
temperatures from > 650*F to
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< 200*F.
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i 80 loss of load cycles, without
> 15% of RATED THERMAL POWER to immediate turbine or reactor trip.
0% of RATED THERMAL POWER.
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40 cycles of loss of offsite Loss of offsite A.C. electrical A.C. electrical power.
ESF Electrical System.
400 reactor trip cycle.,.
100% to 0% of RATED THEP"AL POWER.
10 inadvertent auxiliary,spppy Spray water temperature differential actuation cycles.
[
> 320*F.
i P'ressurized to > 2485 psig.
50 leak tests.
5 hydrostatic pressure tests.
Pressurized to > 3107 psig.
200 large stepload decrease with,
Load decreases of more than 10%
steam dump RATED THERMAL' POWER occurring in 1 minute or less.
Break in a > 6 inch steam line.
Secondary System 1 steam line break.
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5 hydrostatic pressure tests.
Pressurized to > 1350 psig.
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