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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20059L6211993-11-0505 November 1993 Application for Amend to License DPR-45 Revising TS Per Requirements of Revised 10CFR20 Regulations for Radiation Protection ML20247F9891989-03-28028 March 1989 Application for Amend to License DPR-45,revising Tech Spec Pages 2-2,2-3 & 2-4 to Add Definition of Controlled Area & Estimated Whole Body Dose for Duration for Safestor ML20235G8621989-02-15015 February 1989 Supplemental Application for Amend to License DPR-45, Revising 880222 Application by Changing Tech Spec 5.4.2.2.a to Propose Min Inventory of 150 Gallons Per Fuel Storage Tank ML20147B3271988-02-22022 February 1988 Application for Amend to Provisional License DPR-45,revising LACBWR Tech Specs.Proposed Safstor Tech Specs Encl for Review.Fee Paid ML20149H0771988-02-10010 February 1988 Application for Amend to License DPR-45,deleting Request to Convert License Into full-term Ol,Authorizing Safe Storage Condition as Described in Decommissioning Plan & Continuing to Maintain Possession Only Status During Safestor Period ML20149D7101988-01-29029 January 1988 Application for Amend to License DPR-45,changing Tech Spec Section 6.2.2.d Such That Individual Qualified in Radiation Protection Procedures Will Be Either Qualified Health Physics Technician or Shift Supervisor ML20236Q6301987-11-12012 November 1987 Application for Amend to License DPR-45,revising Administrative Section of Tech Specs Due to Permanent Shutdown of Plant on 870430.Fee Paid ML20235V6691987-09-30030 September 1987 Application for Amend to License DPR-45,revising Tech Specs by Eliminating Sections That Do Not Apply Due to Shutdown of Plant on 870430 ML20237L1481987-08-21021 August 1987 Revised Page 2 & Attachment 1, Dose Calculations, to Util 870821 Application for Amend to License DPR-45,requesting Exemption from Type a Containment Bldg Integrated Leak Rate Tests ML20237F7621987-08-21021 August 1987 Application for Amend to License DPR-45 & Request for Exemption from 10CFR50,App J Requirement to Perform Type a Containment Bldg Integrated Leak Rate Tests.Amend to Delete Requirements Re Type a Leak Rate Tests.Fee Paid ML20237J2901987-08-18018 August 1987 Application for Amend to License DPR-45,revising Tech Spec Sections 6.2.2.f,6.4.1,6.4.2,6.5.1.2 & Figure 6.2.2-1 to Reflect Permanent Shutdown.Fee Paid ML20205P8201987-03-24024 March 1987 Supplemental Application for Amend to License DPR-45, Creating Assistant General Manager for Operations Position & Changing Title of Director of External Affairs to Director of External Relations ML20207J8031986-12-19019 December 1986 Application for Amend to License DPR-45,changing Tech Specs to Reflect Replacement of Aging Nuclear Instruments & Provide Shutdown Functions for Reactor.Proposed Tech Specs & Proprietary GE Info Encl.Ge Info Withheld (Ref 10CFR2.790) ML20212B3501986-12-17017 December 1986 Application for Amend to License DPR-45,altering Requirement for Partial Scram on Low Oil Level or Low Gas Pressure in CRD Mechanism Accumulator & Instituting Limiting Condition for Operation as Tech Spec 4.2.7.1 ML20205M5721986-04-0707 April 1986 Application for Amend to License DPR-45,revising Tech Specs to Reflect Reorganization of Offsite Mgt Staff.Fee Paid ML20203B2771986-04-0707 April 1986 Application for Amend to License DPR-45,changing Tech Specs Re Reporting of Primary Coolant Iodine Spikes & Elimination of 800 H Per 12-month Period Cap for Exceeding Activity Limits,Per Generic Ltr 85-19.Fee Paid ML20202A9061986-04-0101 April 1986 Application for Amend to License DPR-45,changing Surveillance Requirements for HPCS Pumps.Functional Test Will Verify That Each Pump Operates at Flow Rate Greater than or Equal to 50 Gpm Design Flow Rate ML20153G0581986-02-21021 February 1986 Application for Amend to License DPR-45,revising Tech Specs to Clarify & Correct Description of Electrical Power Sys. Fee Paid ML20210B8611986-02-0404 February 1986 Application for Amend to License DPR-45,modifying Tech Spec Sections 4.2.3 & 2.6,to Describe Replacement & Mod to Noninterruptible Bus 1C.Fee Paid ML20138J8471985-12-12012 December 1985 Application for Amend to License DPR-45,changing Tech Specs 4.2.4.2.5 & 5.2.17.5,to Increase Max Average Fuel Assembly Exposure Limit from 16,800 to 18,000 Mwd/Mtu in Operational Condition 1.Fee Paid ML20138J7651985-12-12012 December 1985 Application for Amend to License DPR-45,changing Tech Specs to Incorporate Use of Design AA Replacement Control Rods & Deleting Tech Spec 4.2.4.10.Fee Paid ML20132C6111985-09-17017 September 1985 Application for Amend to License DPR-45,revising 840711 Proposed Addl Tech Specs on Containment Ventilation Dampers to Clarify Actions Required When Both Dampers in Penetration Inoperable ML20133C2281985-09-16016 September 1985 Application for Amend to License DPR-45,revising Tech Specs to Delete Section 2.4.7 & Simplifying & Making More Stringent Conditions for Low Pressure Core Spray ML20126L0521985-07-26026 July 1985 Application for Amend to License DPR-45,granting Exemption from Full Amount of Available Onsite Primary Property Damage Insurance & Continuing 830912 Exemption from Excess Property Insurance Requirements,Per 850207 & 0712 Ltrs ML20129A8671985-06-25025 June 1985 Application for Amend to License DPR-45,revising Site Flooding Tech Specs to Require Plant to Be in Cold Shutdown Before Flooding Above Grade Floor of Plant Starts ML20054F2141982-06-0909 June 1982 Application to Amend License DPR-45 Adding Section 5.2.1.6, Containment Ventilation Isolation Valve Leakage Tests, to Tech Specs.Addl Tests Will Detect Excessive Degradation of Containment Ventilation Sys Dampers 1993-11-05
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20059L6211993-11-0505 November 1993 Application for Amend to License DPR-45 Revising TS Per Requirements of Revised 10CFR20 Regulations for Radiation Protection ML20127D3861993-01-13013 January 1993 Amend 67 to License DPR-45,revising TS by Deleting Requirement That Radioactive Effluent Release Rept Be Submitted Semiannually & Adding Requirement That Rept Be Submitted Annually ML20245J7171989-04-26026 April 1989 Amend 65 to License DPR-45,revising Tech Specs Re Storage of Fuel for Fire Pump Diesel Engines to Accommodate Installation & Use of New Diesel Fuel Tanks ML20247F9891989-03-28028 March 1989 Application for Amend to License DPR-45,revising Tech Spec Pages 2-2,2-3 & 2-4 to Add Definition of Controlled Area & Estimated Whole Body Dose for Duration for Safestor ML20235G8621989-02-15015 February 1989 Supplemental Application for Amend to License DPR-45, Revising 880222 Application by Changing Tech Spec 5.4.2.2.a to Propose Min Inventory of 150 Gallons Per Fuel Storage Tank ML20155F9081988-05-31031 May 1988 Amend 62 to License DPR-45,revising Tech Specs Per Util 870930 Request as Revised on 880222 ML20151G0571988-04-11011 April 1988 Amend 60 to Provisional License DPR-45,revising Tech Specs in Response to 871112 & 880129 Application ML20148C3791988-03-15015 March 1988 Amend 59 to License DPR-45,revising Tech Specs to Reflect Exemption from 10CFR50.54(o) & 10CFR50,App J Requirements to Perform Type a Containment Bldg Integrated Leak Rate Tests Per 10CFR50.12(a)(ii) ML20147B3271988-02-22022 February 1988 Application for Amend to Provisional License DPR-45,revising LACBWR Tech Specs.Proposed Safstor Tech Specs Encl for Review.Fee Paid ML20149H0771988-02-10010 February 1988 Application for Amend to License DPR-45,deleting Request to Convert License Into full-term Ol,Authorizing Safe Storage Condition as Described in Decommissioning Plan & Continuing to Maintain Possession Only Status During Safestor Period ML20149D7101988-01-29029 January 1988 Application for Amend to License DPR-45,changing Tech Spec Section 6.2.2.d Such That Individual Qualified in Radiation Protection Procedures Will Be Either Qualified Health Physics Technician or Shift Supervisor ML20149G0601988-01-0404 January 1988 Amend 58 to License DPR-45,revising Tech Specs to Show possession-only Status,To Reduce Fire Brigade from Five to Three Members & to Reassign Training Responsibilities for Fire Brigade ML20236Q6301987-11-12012 November 1987 Application for Amend to License DPR-45,revising Administrative Section of Tech Specs Due to Permanent Shutdown of Plant on 870430.Fee Paid ML20235V6691987-09-30030 September 1987 Application for Amend to License DPR-45,revising Tech Specs by Eliminating Sections That Do Not Apply Due to Shutdown of Plant on 870430 ML20235B5551987-09-15015 September 1987 Amend 57 to License DPR-45,revising Tech Specs to Delete Requirements for Inservice Insp & Nuclear Instrumentation ML20237F7621987-08-21021 August 1987 Application for Amend to License DPR-45 & Request for Exemption from 10CFR50,App J Requirement to Perform Type a Containment Bldg Integrated Leak Rate Tests.Amend to Delete Requirements Re Type a Leak Rate Tests.Fee Paid ML20237L1481987-08-21021 August 1987 Revised Page 2 & Attachment 1, Dose Calculations, to Util 870821 Application for Amend to License DPR-45,requesting Exemption from Type a Containment Bldg Integrated Leak Rate Tests ML20237J2901987-08-18018 August 1987 Application for Amend to License DPR-45,revising Tech Spec Sections 6.2.2.f,6.4.1,6.4.2,6.5.1.2 & Figure 6.2.2-1 to Reflect Permanent Shutdown.Fee Paid ML20206G6141987-04-0808 April 1987 Amend 55 to License DPR-45,changing Tech Specs to Add New Reporting Requirements of 10CFR50.73 & Details to Requirements of Repts Required for Diesel Generator Failures ML20205P8201987-03-24024 March 1987 Supplemental Application for Amend to License DPR-45, Creating Assistant General Manager for Operations Position & Changing Title of Director of External Affairs to Director of External Relations ML20207J8031986-12-19019 December 1986 Application for Amend to License DPR-45,changing Tech Specs to Reflect Replacement of Aging Nuclear Instruments & Provide Shutdown Functions for Reactor.Proposed Tech Specs & Proprietary GE Info Encl.Ge Info Withheld (Ref 10CFR2.790) ML20212B3501986-12-17017 December 1986 Application for Amend to License DPR-45,altering Requirement for Partial Scram on Low Oil Level or Low Gas Pressure in CRD Mechanism Accumulator & Instituting Limiting Condition for Operation as Tech Spec 4.2.7.1 ML20214N3811986-09-10010 September 1986 Amend 54 to License DPR-45,updating Util Organization Chart for Tech Spec Figure 6.2.2-1 ML20209E9121986-09-0505 September 1986 Amend 53 to License DPR-45,revising Tech Specs to Add Operational Requirements on Containment Bldg Ventilation Inlet & Exhaust Dampers & Correcting Typo in Amend 50 ML20209D9611986-09-0202 September 1986 Amend 52 to License DPR-45,transfering Design Tech Spec Section 2.6, Electrical Power Supply to Bases of Operability Tech Spec Section 4.2.3, Electrical Power Sys ML20204J2451986-07-30030 July 1986 Amend 51 to License DPR-45,consolidating & Clarifying Operability & Surveillance Requirements for ECCS ML20203H3031986-07-15015 July 1986 Amend 50 to License DPR-45,revising Tech Spec Re Reactor Coolant Chemistry to Ensure That Facility Personnel Uniformly Interpret Necessary Actions to Be Taken ML20207G2601986-07-15015 July 1986 Amend 49 to License DPR-45,revising Tech Specs Re Change of Functional Testing Frequency for Installed Area Radiation Monitors to Quarterly & Calibr Frequency to Once Per 18 Months ML20141F4211986-04-14014 April 1986 Amend 48 to License DPR-45,modifying Tech Spec Sections 4.2.3 & 2.6 to Describe Replacement & Mod of Noninterruptible Bus 1C ML20205M5721986-04-0707 April 1986 Application for Amend to License DPR-45,revising Tech Specs to Reflect Reorganization of Offsite Mgt Staff.Fee Paid ML20203B2771986-04-0707 April 1986 Application for Amend to License DPR-45,changing Tech Specs Re Reporting of Primary Coolant Iodine Spikes & Elimination of 800 H Per 12-month Period Cap for Exceeding Activity Limits,Per Generic Ltr 85-19.Fee Paid ML20202A9061986-04-0101 April 1986 Application for Amend to License DPR-45,changing Surveillance Requirements for HPCS Pumps.Functional Test Will Verify That Each Pump Operates at Flow Rate Greater than or Equal to 50 Gpm Design Flow Rate ML20154S4701986-03-27027 March 1986 Amend 47 to License DPR-45,modifying Tech Spec to Allow Use of Control Rods of ASEA-ATOM Plate Design or Current Allis Chalmers Tube Sheath Design ML20140F3531986-03-25025 March 1986 Amend 46 to License DPR-45,increasing Max Average Exposure of Any Fuel Assembly Not on Periphery of Core to 18,000 Mwd/Mtu ML20153G0581986-02-21021 February 1986 Application for Amend to License DPR-45,revising Tech Specs to Clarify & Correct Description of Electrical Power Sys. Fee Paid ML20210B8611986-02-0404 February 1986 Application for Amend to License DPR-45,modifying Tech Spec Sections 4.2.3 & 2.6,to Describe Replacement & Mod to Noninterruptible Bus 1C.Fee Paid ML20141F6951986-01-0606 January 1986 Amend 45 to License DPR-45,authorizing Addition of New Paragraph 4.1.6 to Tech Specs,Requiring Reactor Shutdown When Plant in Conditions 1,2 or 3 & Mississippi River Level Expected to Exceed 640 Ft ML20138J8471985-12-12012 December 1985 Application for Amend to License DPR-45,changing Tech Specs 4.2.4.2.5 & 5.2.17.5,to Increase Max Average Fuel Assembly Exposure Limit from 16,800 to 18,000 Mwd/Mtu in Operational Condition 1.Fee Paid ML20138J7651985-12-12012 December 1985 Application for Amend to License DPR-45,changing Tech Specs to Incorporate Use of Design AA Replacement Control Rods & Deleting Tech Spec 4.2.4.10.Fee Paid ML20133F6461985-10-0808 October 1985 Amend 44 to License DPR-45,adding Paragraph 4.2.23 to Tech Specs Requiring Demineralized Virgin Water Tank to Be Operable W/Min Water Level of 1 Ft & Surveillance Requirement to Verify Min Water Level Every Wk ML20132C6111985-09-17017 September 1985 Application for Amend to License DPR-45,revising 840711 Proposed Addl Tech Specs on Containment Ventilation Dampers to Clarify Actions Required When Both Dampers in Penetration Inoperable ML20133C2281985-09-16016 September 1985 Application for Amend to License DPR-45,revising Tech Specs to Delete Section 2.4.7 & Simplifying & Making More Stringent Conditions for Low Pressure Core Spray ML20126L0521985-07-26026 July 1985 Application for Amend to License DPR-45,granting Exemption from Full Amount of Available Onsite Primary Property Damage Insurance & Continuing 830912 Exemption from Excess Property Insurance Requirements,Per 850207 & 0712 Ltrs ML20129A8671985-06-25025 June 1985 Application for Amend to License DPR-45,revising Site Flooding Tech Specs to Require Plant to Be in Cold Shutdown Before Flooding Above Grade Floor of Plant Starts ML20126E5021985-06-0707 June 1985 Amend 43 to License DPR-45,incorporating New Requirements for Operability & Surveillance Testing of RCS Safety Valves ML20125D1681985-06-0505 June 1985 Amend 42 to License DPR-45,removing Specific Quantity Limitations for Radioactive Byproduct,Source,Or SNM Used for Sample Analysis or Instrument Calibr ML20128K9511985-05-28028 May 1985 Amend 41 to License DPR-45,changing Tech Specs Re Exclusion Area,Coolant Water Purity Limits & Containment Airlock Door Seals ML20205A0011985-04-11011 April 1985 Errata to Amend 36 to License DPR-45,adding Tech Spec Page 5-2 Re Section 5.1.6 on Channel Check,Test & Calibr & Containment Testing ML20062D9591982-07-30030 July 1982 Amend 29 to License DPR-45,changing Tech Specs Re Containment Integrity & High Radiation Areas ML20054F2141982-06-0909 June 1982 Application to Amend License DPR-45 Adding Section 5.2.1.6, Containment Ventilation Isolation Valve Leakage Tests, to Tech Specs.Addl Tests Will Detect Excessive Degradation of Containment Ventilation Sys Dampers 1993-11-05
[Table view] |
Text
e w.- .h D A/R LAND 8 [k COOPERAT/VE
- P.O. BOX 817 a 2615 EAST AV SOUTH . LA CROSSE. WISCONSIN 54601 (608) 788 4 000 December 12, 1985 In reply, please refer to LAC-11318 DOCKET NO. 50-409 Director of Nuclear Reactor Regulation Attn: Mr. John Zwolinski, Chief Operating Reactor Branch #5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)
PROVISIONAL OPERATING LICENSE NO. DPR-45 APPLICATION FOR AMENDMENT TO LICENSE
REFERENCE:
(1) '10 CFR 50, Section 50.90 (2) 10 CFR 170.12 (3) LACBWR Technical Specifications (4) DPC Letter, Linder to Ziemann, LAC-6274 dated May 9, 1979.
(5) DPC Letter, Linder to Crutchfield, LAC-7572 dated June 1, 1981.
(6) NRC Letter, Crutchfield to Linder, dated November 6, 1981.
(7) DPC Letter, Linder to Crutchfield, LAC-8109 dated February 23, 1982.
(8) NRC Letter, Crutchfield to Linder, dated March 11, 1982.
Gentlemen:
Dairyland Power Cooperative (DPC) hereby requests the following change to the LACBWR Technical Specifications. In accordance with the provisions of Reference 1, this application to amend Provisional Operating License No.
DPR-45 for the La Crosse Boiling Water Reactor is being filed with three (3) signed original applications, together with thirty-seven (37) copies.
Technical Specification 4.2.4.2.5 currently states:
4.2.4.2.6 The maximwn average exposure of any fuel assembly not on the periphery of the core shall be limited to 16,800 FfdD/FffU.
Y\
APPLICABILITY: Operational Condition 1.
DPC requests that this Technical Specification be changed to read:
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$l 218 h 9 ,jd6 P g
.,- 'S
- e Mr. Jchn Zrolinski, Chief .
Daceabar 12, 1985
.Oparcting Raccter Branch #5 LAC-11318
( 4.2.4.2.5 The maximum average exposure of any fuel aasombly not on the pariphery of the core ahati be timited to 18,000 NWD/MTU.
APPLICABILITY: Opertional Condition 1.
i' Suggested, revised pages for the LACBWR Technical Specifications showing this change along with the appropriate corresponding changes to the s surveillance requirement (Specification 5.2.17.5) and the Specifications Bases 3 are' attached to this letter.
The justification for this change is the continued exceptionally good
[ performance of the Type III (Exxon) fuel in the LACBWR. The first reload of Type III fuel was used.in LACBWR Fuel Cycle 5 which began on March 9, 1978.
As of the end'of Cycle 9, eighty-two (82) Type III fuel assemblies had been discharged from the LACBWR core. The core for the current fuel cycle (Cycle
- 10) contains only Type III fuel. No indication of fuel clad degradation has been observed in any of this fuel nor has there been any indication of Type III fuel degradation in the continuously monitored off-gas or in the routinely
, monitored. reactor coolant activities. The fuel performance during Fuel Cycles 5 and 6 and most of Cycle 7 is discussed in detail in References 4, 5 and 7.
l This data base of Type III fuel perforamnce is updated to the present by the Table of_" Fuel Performance in the LACBWR", the tables listing fuel assemblies discharged..the figures showing BOC and EOC core configurations and the figures showing LACBWR power history and reactor coolant and off-gas
- radioactivity attached to this letter.
l Near the end of Fuel Cycle 7, a temporary change to Technical
!- Specification 4.2.4.2.5 was granted which allowed nonperipheral fuel assemblies to be exposed to 17,200 MWD /MTU. Four Type III fuel assemblies i completed this cycle in nonperipheral core positions with exposures above
, 16,800 MWD /MTU. The highest exposure in a nonperipheral position was 17,196 MWD /MTU. At the end of Cycle 7, all of the fuel in the core was given a
-detailed visual examination using high resolution underwater television equipment. One failed' fuel rod was observed in a Type I (A-C) fuel assembly
, and this single ruptured fuel rod was the cause of the small increase which j had been observed in the off-gas and reactor coolant activities near the end 5 .of Cycle 7. The remaining 71 fuel assemblies were subjected to a dry sipping test, which is a very sensitive method of detecting very small clad defects, with no indications of leaking fuel rods observed.
.During the refueling for Cycle 8, ten (10) Type III fuel assemblies 4
discharged at the end of Cycle 6 were returned to the LACBWR core in n peripheral positions. During Cycles 8 and 9 considerably higher burnups were
. achieved in Type III assemblies in the peripheral locations. Three fuel assemblies have been discharged with~ exposures greater than 20,000 MWD /MTU (EOC-9) and a total of 18 Type III assemblies have achieved greater than i 18,000 MWD /MTU (including those presently in the core). These fuel exposures have been accomplished with no significant indications of any fuel cladding
! failure. The infrequent high values in the alpha activity in the reactor coolant (see attached figures) and the relatively low and relatively constant
- ~ levels of fission product activity in the off-gas and reactor coolant are due to tramp fissionable material remaining in the system from the earlier i- failures-in the Type I and II (A-C) fuel. We believe that this impeccable j
- performance of'the Type III fuel to greater than 20,000 MWD /MTU on the i
, WP3.7 ,
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- = ,
g g.
Mr. Jahn' Zw311nski, Chief - Drestber 12, 1985 Operating Reactor Branch.f5 LAC-11318 periphery of the LACBWR core and to 17,200 MWD /MTU in nonperipheral locations in Cycle 7 indicates that it can achieve at least 18,000 MWD /MTU without failure in nonperipheral locations in the core. Continued restrictions on rate of power escalation and rate of control rod withdrawal and judicious reload planning to limit power density increases in fuel will contribute to the expected good fuel performance.
~
Finding of no significant hazards We have reviewed'the hazards consideration referenced in 10 CFR 50 Sections 91 and 92 and have determined that with these criteria no significant hazards result from this proposed amendment. 10 CFR 50.92 (c)(1-3) provide the questions for review of significant hazards considerations. They are repeated here for reference.
10 CFR 50.92 (c)
(1) ~ Involve a significant increase in the probability or consequences of an' accident previously evaluatad; or
.(2) Create the possibility of a new or different kind of accident from
'any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
The proposed small increase in allowed fuel exposure in -fuel assemblies not on the periphery of the core will not involve a significant increase in the probability or consequences of an accident previously evaluated. The greater fuel exposure will not cause a precipitous deterioration of the fuel clad. Any deterioration that might occur is expected to develop slowly and would be apparent at an early stage from increases in the reactor coolant and off-gas radioactivity. The current Technical Specification limits for these activities provide assurance that LACBWR fuel assemblies will not exhibit unacceptable degradation during future operation. All other fuel related Technical Specifications such as MAPLHCR (Spec. 4.2.4.2.1), MCPR (Spec.
4.2.4.2.3) and MLHCR (Spec. 4.2.4.2.4) will be conservatively met during-operation with the higher fuel exposure.
The increase in exposure limit for fuel assemblies not on the periphery of the core can not by itself create the possibility of a new or different kind of accident from any accident previously evaluated. No systems or
' method of operation are being changed by this revision. It also will not involve a significant reduction in a margin of' safety since the Technical
. Specification limits for off-gas and' reactor coolant activities and for fuel power densities have not been changed and these specifications control the margin of safety for consequences of anticipated accidents.
The information submitted in this application for license amendment has been reviewed by the LACBWR Committees as prescribed in LACBWR Technical Specifications.
A copy of the proposed revised pages of LACBWR Technical Specification is attached. A check for $150 accompanies this letter to cover the required application fee per Reference 2.
WP3.7 t
i Mr. J hn Zwolinski, Chisf Dectabsr 12, 1985 Op2rsting Racetor.Brench f5 LAC-11318 DPC requests approval of this request as soon as possible. The present Technical Specification limit of 16,800 MWD /MTU assembly average exposure for fuel assemblies not on the periphery of the core would require an unnecessarily early termination of the present fuel cycle about the middle of February, 1986.
If there are any questions concerning this submittal, please contact us.
Sincerely, D RYLAND POWER COOPERATIV James W. Taylor General Manager JWT:SJR:sks Enclosure cc: Mr. John Stang' NRC Resident Inspector Mr. James Keppler, Region III Mr. Clarence Riederer, Chief Engineer Wisconsin Public Service Commission P. O. Box 87854 Madison, WI 53707 STATE OF WISCONSIN )
)
COUNTY OF LA CROSSE )
Personally came before me this [d day of , 1985, the above named, James W. Taylor, to me known to be the person who executed the foregoing instrument and acknowledged the same.
I M& '
Notary Publi La Crosse' County Wisconsin My commission expires February 21, 1988 WP3.7 . _ _ - _ _ _ - _ _ - - _ _ _ -