ML20140F353

Amend 46 to License DPR-45,increasing Max Average Exposure of Any Fuel Assembly Not on Periphery of Core to 18,000 Mwd/Mtu

ML20140F353
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/25/1986
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20140F350	List: ML20140F346 ML20140F353 ML20140F357
References
NUDOCS 8603310376
Download: ML20140F353 (7)

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1. 'g UNITED STATES jr, .g a

NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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DAIRYLAND POWER COOPERATIVE

, DOCKET NO. 50-409 LA C9.0SSE BOILING WATER REACTOR

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AMENDMENT TO PROVISIONAL OPERATING LICENSE 4 %nendment No.45 License No. DPR-45

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

A. The application for amendment by Dairyland Power Cooperative

(the licensee) dated December 12, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; I B. The facility will operate in conformity with the application, I 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

i. conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the common i defense and security or to the health and safety of the public; and i- E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comnission's regulations and all applicable requirements have been satisfied.

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B603310376 860325 I PDR ADOCK 05000409 p PM 4

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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 Provisional Operating License No. DPR-45 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A issued October 31, 1969, with Authorization No. OPRA-6, as revised

.through Amendment No. 46, are hereby incorporated in the' license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

ISSION FORTH{NUCLEARREGULATOYC John kk1

. Zwolinski, Director BWR P ject Directorate #1 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: March 25,1986 f

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4 ATTACHMENT TO LICENSE AMENOMENT NO.46 PRpVISIONAL OPERATING LICENSE NO. DPR-45 DOCKET NO. 50-409 J

Revise Appendix A Technical Specifications b.y removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 32aa 32aa 32g9 32gg 32hh 32hh 3211 3211 I

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POWER DISTRIBUTION LIMITS MAXIMUM AVERACE FUEL ASSEMBLY EXPOSURE LIMITING CONDITION FOR OPERATION 4.2.4.2.5 the maximum average exposure of any fuel assembly not on the periphery of the core shall be limited to 18,000 MWD /MTU. l APPLICABLILITY: OPERATIONAL CONDITION 1.

ACTION:

With the maximum average fuel assembly exposure of any nonperipheral assembly greater than 18,000 MWD /MTU, be in at least HOT SHUTDOWN with the main steam l line isolation valve closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENT , 5.2.17.5 The maximum average exposure of each fuel assembly not on the periphery of the core shall be determined to be less than 18,000 MWD /MTU by l calculation at least.once per 31 EFPD.

Amendment No. M, J$, 29, 2$,7$,46

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POWER DISTRIBUTION LIMITS BASES FOR SECTION 4.2.4.2 AND 5.2.17 LINEAR HEAT GENERATION RATE - (Continued)

For Type I and Type II (A-C) fuel, the orginial design LINEAR HEAT GENERATION RATE specified by the fuel manufacturer was conservatively reduced to 11.94 kw/f t to account for the e.f fects of densification, power spikes and manufacturing factors. For Type III (ENC) fuel, tLe design LINEAR REAT GENERATION RATE of 11.52 kw/ft is also calculated with design conservatisas that are larger than the calculated axial densification effects plus manufacturing tolerances and power spike effects, Reference 6 and 7.

The daily requirement for surveillance of the core LHGR above 25% of RATED THERMAL POWER is sufficient since power distribution shifts are very slow when there have not been significant power or control rod changes. The surveillance of core LHGR after power increases 1 15% of RATED THERMAL POWER will assure that significant increases in LHGR are determined.

4.2.4.2.5 and 5.2.17.5 Maximus Average Fuel Assembly Exposure i

References:

8, 9, 10, 11 and 12.

Fuel cladding integrity is a function of many parameters including fuel exposure, pellet clad interaction, THERMAL POWER, rate of change in power density, coolant chemistry, etc. Therefore, limiting fuel exposure to 18,000

• '7D/MTU in the non peripheral fuel assemblies which experience higher than average power densities and rate of change of power will give additional assurance that the condition of the fuel during operation will be satisfactory. It is not necessary to limit exposure in the peripheral core locations since operating experience at LACBWR has shown that the 28 peripheral fuel assemblies have a much lower rate of failure than the 44 interior fuel assemblies. This trend has been attributed to the. lower power density at these locations, and the minimal effects of control rod movements which cause local power peaking in the fuel rods near the tips of the control rods. The outer control rods are fully withdrawn at the beginning of cycle (BOC) and remain withdrawn during normal cycle operations.

Amendment No. AA, M, A$, Ah,46

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POWER DISTRIBUTION LIMITS BASES FOR SECTIONS 4.2.4.2 AND 5.2.1.7_

Maximum Average Fuel Assembly Exposure -(Continued)

Pellet-clad interaction is a well known and documented contributing factor to fuel rod failures. The presence of pellet cladding f uteraction has been identified in post-irradiation examinations of fuel rods removed from LACBWR fuel assemblies. Fuel rods removed from fuel assemblies with average exposure up to 14,700 MWD /MTU have been examined. The strength, ductility, and condition of the cladding in these rods was found to be adequate as determined by mechanical tests. The examination further confirmed that power history of the rods is of prime importance, though not the only factor in contributing to fuel rod failure. During operation the rate of withdrawal of control rods, when the THERMAL POWER is above 25% of RATED THERMAL POWER, is reduced from that experienced during operation prior to Cycle 5 which also significantly reduces the stresses in the fuel clad.

Minor clad defects that may occur would be expected to develop very slowly and the consequences of such failure would be minimal. Surveillance and limitations on coo'-st and off-gas activity will assure that operation does not continue with m;.nificant quantities of failed fuel.

References:

1. " Technical Evaluation Adequacy of La Crosse Boiling Water Reactor Emergency Core Cooling System", Report SS-942, Gulf United Nuclear Corporation, May 31, 1972.

2. " Review of Densification Effects in La Crosse Boiling Water Reactor",

Report SS-1085, Gulf United Nuclear Corporation, May 15, 1973.

3. NRC Safety Evaluation Report, Letter, Reid to Madgett, dated August 12, 1976.'

4. "ECCS Analysis for Type II and Type III Fuels for the La Crosse Boiling Water Reactor" Exxon Nuclear Company, Inc., XN-NF-77-7, March 1977.

5. " Transient Analysis for LACBWR Reload Fuel", Response to Question 4, Nuclear Energy Services, Inc. Report 81A0025, February 18, 1977.

Amendment No.11, J6, 26, 26, 28, 46

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POWER DISTRIBUTION LIMITS BASES FOR SECTIONS 4.2.4.2 AND 5.2.17 _

References - (Continued)

6. " Description of Exxon Type III Nuclear Fuel for Batch 1 Reload in the LACBWR**, Dairyland Power Cooperative, LAC-3929, May 17,1976.

7. Exxon Nuclear Co. Letter, J. A. White to C. W. Angle,

Subject:

MAPLHGR Limits for Type I (Allis-Chalmers) Fuel, dated June 22, 1977.

8. DPC Letter, LAC-6846, Linder to Ziemann, dated April 1,1980.

9. DPC Letter, LAC-7572, Linder to Crutchfield, dated June 1, 1981.

10. DPC Letter, LAC-8109, Linder to Crutchfield, dated February 23, 1982.

11. DPC Letter, LAC-8131, Linder to Crutchfield, dated March 4, 1982.

12. DPC Letter, LAC-11318. Taylor to Zwolinski, dated December 12, 1985. l i

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Amendment No. 20., 26, 28,46

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