ML20195K075

Amend 16 to License NPF-42,revising Tech Specs 5.3.1 & 5.6.1.1 to Allow Storage of Fuel Assemblies of Up to 4.5% U-235 from Current Limit of 3.5% U-235

ML20195K075
Person / Time
Site:	Wolf Creek
Issue date:	06/17/1988
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20195K042	List: ML20195K040 ML20195K075 ML20195K080
References
NUDOCS 8806290336
Download: ML20195K075 (8)

Text

.-

'o f g UNITED STATES y g NUCLEAR REGULATORY COMMISSION 5 E WASHINGTON, D. C. 20655

%...../

KANSAS GAS & ELECTRIC COMPANY KANSAS CITY POWER AND LIGHT COMPANY KANSAS ELECTRIC POWER COOPERATIVE, INC.

WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 License No. NPF-42

1. The Nuclear Pegulatory Comission (the Comission) has found that:

A. The application for amendment to the Volf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation, dated February 26, 1988, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the rules

, and the Comission's Atomic and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confomity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 license amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

!!k P

Och 0 $2

2. Accordingly: the license is amended by changes to the Technical Specifi-cations as indicated in.the attachment to this license arendment and Paragraph 2.C.(2) of Facility Operating License No. NPF a? is hereby amended to read as follows:

?. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 16 , and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. KG8E shall operate the facility in accordance with the Technical Specifications and the Environmental Protecticn Plan.

3. The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY C0tHISSION I

I y, nA s Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Reculation Attachnent:

Charces to the Technical Specifications Date of Issuance: June 17,1988

. ATTACHFENT TO LICENSE AMENDMENT N0.16 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revise Appendix A Technical Specifications by renoving the pages identified i below and inserting the enclosed pages. The revised pages are identified by l amendment number and contain marginal linec indicating the area of change. i The corresponding overleaf paces are also provided to maintain documen e completeness.

REMOVE PAGES INSERT PAGES 3/4 9-16 3/4 9-16 5-6 5-6 5-7 5-7 5-8 5-8

REFUELING OPERATIONS 3/4.9.12 SPENT FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.9.12 Spent fuel assemblies stored in Region 2 shall be subject to the following conditions:

a. The combination of initial enrichment and cumulative exposure shall be within the acceptable domain of Figure 3.9-1, and

b. No spent fuel assemblies shall be placed in Region 2, nor shall any storage location be changed in designation from being in Region I to being in Region 2, while refueling operations are in progress.

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 ppe 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.

l SURVEILLANCE REQUIREMENTS 4.9.12 The burnup of each spent fuel assembly stored in Region 2 shall be ascertained by analysis of its burnup history and independently verified, prior to storage in Region 2. A complete record of such analysis shall be kept for the time period that the spent fuel assembly remains in Region 2 of the spent fuel pool.

WOLF CREEK - UNIT 1 3/4 9-15

DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 .The core shall contain 193 fuel assemblies with each fuel assembly j containing 264 fuel rods clad with Zircaloy-4. Each fuel rod shall have a nominal active fuel length of 144 inches. The initial core loading shall have a maximum nominal enrichment of 3.10 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.50 weight percent U-235.

l CONTROL ROD ASSEMBLIES l

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 rods shall be hafnium, 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 volume of the Reactor Coolant System, including pressurizer and surge line, is 12,135 1 100 cubic feet at a nominal T,yg of 557*F.

b.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

I l

WOLF CREEK - UNIT 1 5-6 Amendment No. 3,16

DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY

5. 6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. A k,,f equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a conservative allowance of 2.6%

Ak/k for uncertainties , described in Section 4.3 of the FSAR.

This is based on new fuet with an enrichment of 4.50 weight percent l U-235 in Region 1 and on spent fuel with combination of initial enrichment and discharge exposures, shown in Figure 5.6-1, in Region 2, and

b. A nominal 9.236 inch center-to-center distance between fuel assemblies placed in the storage racks. (

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

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 2040 feet.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1344 fuel 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.16

.{

l l

50 . . ...

40 ..

1 Acceptable m -- .

i 3, ..

1 x 30 ;_-

N ..

v  :

a ..

3 ..

g 20 f1 2 ..

m ..

[

Unacceptable 10 21 ..

0 ':::::::::l:::::::::  :::::.:::l:::::::::

1.0 2.0 3.0 4.0 5.0 ENRICHMENT (w/o) rIGURE 5.6-4 WOLF CRIM MIMIMUM REQUIRTD FUEL ASSEMBLY SURnUP A$ A F4 ACTION OF IWi7tAL ENRICHMENT FOR STORAGE IN REGION 2 WOLF CREEK - UNIT 1 5-8 Amendment No.16

_ . _ _ - . . - _ _ . - _ . - - . - - - _ - - - _ . . . . . - - . _ - - - _ - . - . - - - . - . .