ML20205B816

Amend 120 to License NPF-42,revising TS to Support Mod to Plant to Increase Nominal Fuel Enrichment to 5% Percent Weight Percent U-235

ML20205B816
Person / Time
Site:	Wolf Creek
Issue date:	03/22/1999
From:	Thomas K NRC (Affiliation Not Assigned)
To:
Shared Package
ML20205B817	List: ML20205B816 ML20205B825
References
NUDOCS 9903310372
Download: ML20205B816 (8)

Text

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NUCLEAR REEULATORY COMMISSION

• \\;, w ]2 WASHINGTON, D.C. 20056-0001 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION a

DOCKET NO. 50-482 6MENDMENT TO FACILITY OPERATING LICENSE I

Amendment No.120 i

License No. NPF-42 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to the Wolf Creek Generating Station (the facility)

Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation) dated March 20,1998, as supplemented by letters dated May 28, June 30, August 28, September 4, November 20, and December 8, 1998, 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, as amended, 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 Se conducted in compliance with the Commission's regulations; D.

The issuance of this license 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.

9903310372 990322 PDR ADOCK 05000482 P

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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. NPF-42 is hereby amended to read as follows:

2.

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 120, and the Environmental Protection Plan contained in 4

Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3 3.

The license amendment is effective as of its date of issuance to be fully implemented no later than December 31,1999, except that the racks in the cask loading pit may be installed at a future time after the completion of the next refueling outage. While the 3

spent fuel pool reracking modification is in progress, both the technical spec,idations issued through Amendment No.119, and those technical specifications being amended by Amendment No.120 will be applicable.

4 FOR THE NUCLEAR REGULATORY COMMISSION WW Kristine M. Thomas Project Manager Prcject D: rectorate IV 2 i

Division of Licensing Poject Management Office of Nucleai Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

March 22, 1999 i

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ATTACHMENT TO LICENSE AMENDMENT NO. ' 120 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT 3/4 9-15 3/4 9-15 3/4 9-16 3/4 9-16 i

B 3/4 9-3 B 3/4 9-3 5-7 5-7 t

l l

REFUELING OPERATIONS 3/4 9,12 SPENT FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.12 Spent fuel assemblies stored in either the Spent Fuel Pool or cask loading pit shall be l

subject to one of the following conditions:

a.

Spent fuel assemblies regardless of bumup can be placed in Region 1.

b.

Spent fuel assemblies within the bumup-enrichment range shown in F 3.9-1 for Region 2 fuel can be placed in Region 2 or 3.

c.

Spent fuel assemblies within the bumup-enrichment range shown in Figure 3.9-1 for Region 3 fue! shall be placed in Region 3.

APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel poc! or cask loading l

pit.

l ACTION:

f 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 l

areas and move non-complying fuel assemblies to Region 1. Until the requirements l

of the above specification are satisfed boron concentration of the spent fuel pool shall l

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 />.

l l

b.

The provisions of Specification 32.3 and 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS l

l 4.9.12 The bumup of each spent fuel assembly stored in Regions 2 or 3 shall be ascertained l

by analysis of its bumup history and independently verified prior to storage in Regions 2 or 3. A l

complete record of such analysis shall be kept for the time period that the spent fuel assembly remains in Regions 2 or 3 of the spent fuel pool or cask loading pit.

i WOLF CREEK-UNIT 1 3/4 9-15 Amendment No.120

FIGURE 3.9-1 i

MINIMUM REQUIRED FUEL ASSEMBLY BURNUP AS A FUNCTION OF i

INITIAL ENRICHMENT TO PERMIT STORAGE IN REGIONS 2 AND 3 55000

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50000 9

ACCEPTABLE BURNUP DOMAIN g

FOR REGlotl 2 AND 3 STORAGE N

45000

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UNAC ::EPTAB LE BUftNUP D OMAIN E

FOR ltEGION 2 OR 3 ST01tAGE 5000 0

1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 FUEL ASSEMBLY INITIAL ENRICHMENT (w/o U-235)

WOLF CREEK-UNIT 1 3/4 9-16 Amendment No. 46:61,120

m. _ _ _ _

REFUELING OPERATIONS BASES 3/4.9.9 CONTAINMENT VENTILATION SYSTEM The OPERABILITY of this system ensures that the containment purge penetrations will be automatically isolated upon detection of high radiation leve s within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the upture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the safety analysis.

4/4.9.12 SP The racks for the Spent Fuel Pool and cask loading pit are designed for storage of both new fuel and irradiated fuel. Prior to storage of fuel assemblies in either the Spent Fuel Pool or cask loading pit, overall pool storage Regions shall be prepared in accordance with administrative controls. The restrictions placed on fuel assemblies stored in the spent fuel pool and cask loading pit ensure inadvertent criticality will not occur. Region 1 is designed to accommodate new fuel with a maximum nominal initial enrichment of 5.0 weight percent U-235, or spent fuel regardless of the discharge fuel bumup. Region 2 and Region 3 are designed to accommodate fuel of various initial enrichments which have accumulated minimum bumups within the acceptable domain according to Figure 3.9-1, in the accompanying LCO.

3/4.9.13 EMERGENCY EXHAUST SYSTEM - FUEL Bull. DING The limitations on the Emergency Exhaust System ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere. Operation of the system with the heaters operating to maintain low humidity for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup cf moisture on the adsorbers and HEPA filters. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses. ANSI N510-1975 and N510-1980 will be used as procedural guides for surveillance testing.

WOLF CREEK-UNIT 1 B 3/4 9-3 Amendment No. EE;M;69;95,120

DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies.

Each assembly shall consist of a matrix of Zircaloy or ZIRLO clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (%) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods in accordance with a) proved applications of fuel rod configurations, may be used. Fuel assem)1ies shall be limited to those fuel designs that have been analyzed with applicable NRC approved codes and methods and shown by test or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.

CONTROL ROD ASSEMBLIES 5.3.2 The 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. All control rod assemblies shall be hafnium, silver-indium-cadmium, or a mixture of both types. 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 specif1ed 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 65(?F. except for the pressurizer which is 680*F.

.YDLutf 5.4.2 The total volume of the Reactor Coolant System. including p'ressurizer and surge line. is 12.135 t 100 cubic feet at a nominal T.,, of 557 F.

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5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

i WOLF CREEK - UNIT 1 5-6 Amendment No. 3.15.19.18.51.110

l DESIGN FEATURES i~

5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

With a k,,, equivalent to less than or eqesi to 0.95 when flooded with unborated l

water, which includes an allowance for uncertainties as described in Section 4.3 of the USAR. This is based on new fuel with maximum nominal enrichment of 5.0 l

weight percent U-235 in Region 1 and on spent fuel with combination of initial enrichment and discharge exposures, shown in Figure 3.9-1, for Regions 2 and 3, l

and b.

With a nominal 8.99 inch center-to-center distance between fuel assemblies placed l

in the storage racks.

c.

For fuel with nominal enrichments greater than 4.6 weight percent U-235, the combination of enrichment and integral fuel bumable absorbers shall be sufficient so that the requirements of Specification 5.6.1.1.s are met. Integral fuel bumable absorbers are not required for Region 1 locations on the periphery of the pool, adjacent to a concrete wall.

5.6.1.2 The k, for new fuel for the first core loading stored dry in the spent fuel storage racks shall not excr d 0.98 when aqueous foam moderation is assumed.

DRAINAGE 5.6.2 The fuel storage poolis designed and shall be maintained to prevent inadvertent draining l

of the pool below elevation 2040 feet.

CAPACITY 5.6.3 The spent fuel storage poolis designed and shall be maintained with a storage capacity limited to no more than 2363 fuel assemblies. The cask loading pit is designed and shall be maintained with a storage capacity limited to no more than 279 assemblies.

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.

WOLF CREEK-UNIT 1 5-7 Amendment No. 46,6+,120