ML20041F974

Amend 28 to License DPR-45 Modifying Tech Specs to Reflect Changes in Allowable Max Average Exposure of Fuel Assembly Not Having Periphery of Core for Cycle 7

ML20041F974
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/11/1982
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20041F971	List: ML20041F970 ML20041F974 ML20041F977 ML20041F981
References
NUDOCS 8203170609
Download: ML20041F974 (8)

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UNITED STATES y y 3,

NUCLEAR REGULATORY COMMISSION g

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DAIRYLAND POWER COOPERATIVE

• • L-DOCKET NO. 50-409 LA CROSSE BOILING WATER REACTOR AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 2s License No. DPR-45 1.

The Nuclear Regulatory Ccmmission (the Comission) has found that:

A.

The application for amendment by Dairyland Power Cooperative (the licensee) dated February 23, 1982, as supplemented March 4, 1982, 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; B.

Th? 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 compliarce with the Commission's regulations; D.

The issuance of this amencment 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 ac rdance with 10 CFR -Part 51 of the CoMission's regulations and o.1 applicable requirements have been satis fied.

8 8203170609 820311 DR ADOCK 05 0

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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

,e No. DPR-45 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A issued October 21, 1959, with Authorization No. DPRA-5, as revised thrcugh Amendment No. 23, are hereby incor-porated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This licente amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY C0h 'SSION l

Dennis M. Crutchfield, Chssf Operating Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 11, 1982 t

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ATTACHMEtJT TO LICEl:SE AMEliDME!1T !!0. 28 PROVISI0tiAL OPERATII G LICEllSE fi0. OPR-45 LA CROSSE BOILING WATER REACTOR (LACBWR) s Revise Appendix A by replacing the following pages with the enclosr.d pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change.

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PAGES 32a.

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32aa 32hh 32ii 4

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-*for pagination purposes only; there are no changes to the technical s

specification provirions I

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REACTORf C00LAfiT SYSTEM w

4.2.2.22k ACTIVITY s

LIMITING CONDITION FOR_ OPERATION _

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'l 4.2.2.22 The activity" of the:

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Reactor coolant shall be limited to:

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4 0.2 sci /gramDOSEEQU{VALENTI-131, 2.

1 100/E i/ gram, and

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5.0 x 10 Ci/c. ram c.ross alpha activit.y.

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b.

O'f-gts emissien, measured at the 150 cu f t. off-gas holdas t' ri effluent monitor, shall be li:.ited to < 750 Ci/d (P/P.)

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+ A. (1-0.015t') (P/P ), where:

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(P/P j = fraction of RATED THEPJ4AL POWER between' 33 MWt r

and 165 MWt, l

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2.

A.7 = trasp4 activity, Ci/d, not,to exceed 1500, at THEPJiAL

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POWER (P ) as deter:ained upon init.ial power escalation aftereabhrefueling.

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= do./J "ter the dete'--inatien of A..d th the limitatien

! hat : 0 60.

4 Activity.f ues shcil be ncrmali:ed for 'ccrrelatien with

re.'icus cycles due :: changes ir. cni:ering, scnlin; z. > ! :.- g.- : - ye:e

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,N, tiriu for Cvcie 6 core conficuration with reactor coeration extended be3.c q,0C

..;/PT. Tea; assd.;if a.ecace exps.re in the retaining A:

" core 11 fuel assemblies *.

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7 9:se c;ivalent 0.0 2uC?/ cat i31 Gross Alpha Activity 0.9x10fpCi/ gram N

Off-gas 2L 570'. Ci/aay

• ? off-gas activity limits for Cycle 7. reactor operation with raaximum averace fuel assembly exposure greater th'an 16,800 i:WD/!iTU shall be wherever it' y substituting 571 Ci/ day for the 750 Ci/ day figure deterhined b aopearsi'nf$ection4.2'.2.22.

k~end en! *ic. N, l[.,lE, 2[

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APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3 and 4.

ACTION:

a.

In OPERAT10NAL CONDITION 1, 2 or 3, with the activity of the reactor coolant-i

>0.2 uti/crem DOSE EQU1 VALENT 1-131.but < 4.0 vCi/ cram, entry te'OTE:.;i10NAL CONDITICN 1, 2, 3 cr is ce rti t t e t anc operaticn may centin've for u; 10 4E nours provided that coeretion under these conditions shall not exceet 500 heurs in eny censecutive 12-ncr.th ceriod.

Sh0pic the total coeretin; tire at a primrry cociant specific activity >0.2 uti/ cram DOSE EQU1V'LErii 1-131 exceed 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive 'six-r.onth period, the licensee shaii report the number cf hours of cperation above this limit to'the NP.C within 30 days.

2.

> 0.2 uti/ gram DOSE EOU1VALEST l-13i for more than 45 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> durinc one centinuous time interval er > 4.0 tCi/crar be in at leist HOT Sh*JTDOWN with the main steam line isolation valve closed wit.hin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Amendment No. 11, 3 6, )9~, 28 m-.-

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POWER DISTRIBUTION LIMITS MAXIMUM AVERAGE 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 16,8 00 MWD /MTU

• APPLICABILITY:

OPERATIONAL CONDITION 1.

ACTION:

With the maximum average fuel assembly exposure of any non-peripheral assembly greater than 15,900 MWD /MIUt be in at least HOT SHUTDOWN with the m.ain steam 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 9

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 16,8 00* MWD /MTU by calculation at least once per 31 EFPD.

t For Cycle 7 reactor operation, this limit is increased to 17,200

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Amendment !!o. 11, 16, 20, 26, 28

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i POWER DISTRIBUTION LIMITS BASES FOR SECTIONS 4.2.4.2 XND 5.2.17 Maximum Average Fuel Assembly Exposure - (Continued)

Pellet-clad interaction is a well known and documented contrib-uting factor to fuel rod failures.

The presence of pellet cladding interaction 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 f actor in contributing to fuel rod f ailure.

A limit of 17,200 MWD /MTU fuel element average exposure for Cycle 7 is substantiated by examinations of LACBWR fuel assemblies and by operating experience with the improved Type III (Exxon) fuel design.

(References 8, 9, 10 and 11).

During future operation the rate of withdrawal of control rods when the THERMAL POWER is above 25% of RATED THERMAL POWER will be reduced from that experienced during operation prior to Cycle 5 which will also significantly reduce the stresses in the fuel clad.

Additional r.urveillance and limitations on coolant and off-gas activity will assure that operation does not continue with c.rossiv. 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.

.LC EafeQ Evalcaticr. Repert, Lc :cr, Reid t'o Maf;ett, 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.

Anendrent No. 11, 16,' 20, 26, 28

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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", Dairyltad Power Cooperative, LAC-3929, May 17, 1976.

7.

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

Subject:

PJJLEGR Lin.its for Type I (Allis-Chalmers) Fuel, dated June 22, 197.7.

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.

i;1.

DPC Letter, LAC-8131, Linder to Crutchfield, dated I' arch 4,1982.

(Next page is page 33)

Amendment No. 20, 26, 28

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