Letter Sequence Request |
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Results
Other: 05000301/LER-1983-007-01, /01T-0:on 830523,higher than Normal Levels of I-131 in Primary Coolant Prompted Investigation of Fuel Assemblies.Probably Caused by Fretting at Bottom Spring Clip Grid Elevation Optimized Fuel assemblies,ZD3, ML20069D934, ML20077M425, ML20077M437, ML20093E118, ML20094A054, ML20095F318, ML20107D684, ML20108A768
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MONTHYEARML1201702131983-02-22022 February 1983
Incorporation of Westinghouse Model for Upper Plenum Injection in 1981 Evaluation Model Wreflood Code
Project stage: Request
ML20069D9341983-03-14014 March 1983
Proposed Tech Spec Change 87,revising Westinghouse 14x14 Optimized Fuel Assembly Design
Project stage: Other
ML20069D9271983-03-14014 March 1983
Application for Amend to Licenses DPR-24 & DPR-27,revising Limitations & Bases Re Use of Westinghouse 14x14 Optimized Fuel Assembly Design
Project stage: Request
05000301/LER-1983-007-01, /01T-0:on 830523,higher than Normal Levels of I-131 in Primary Coolant Prompted Investigation of Fuel Assemblies.Probably Caused by Fretting at Bottom Spring Clip Grid Elevation Optimized Fuel assemblies,ZD31983-06-0606 June 1983
/01T-0:on 830523,higher than Normal Levels of I-131 in Primary Coolant Prompted Investigation of Fuel Assemblies.Probably Caused by Fretting at Bottom Spring Clip Grid Elevation Optimized Fuel assemblies,ZD3
Project stage: Other
ML20077M4371983-08-31031 August 1983
Safety Evaluation for Point Beach Units 1 & 2 Transition to Westinghouse 14X14 Optimized Fuel Assemblies
Project stage: Other
ML20077M4251983-09-0606 September 1983
Revised Page Changes for Tech Spec Change Request 87 Re Utilization of Westinghouse 14X14 Optimized Fuel Assembly Design in Reactors
Project stage: Other
ML20077M3991983-09-0606 September 1983
Supplemental Info Supporting 830314 Application for Amend to Licenses DPR-24 & DPR-27,including Revised Page Changes to Tech Spec Change Request 87 & Safety Evaluation Re Utilization of Optimized Fuel Assembly
Project stage: Supplement
ML20093E1181984-07-13013 July 1984
Proposed Mods to Tech Spec Change Request 87 Figures, Covering Use of Westinghouse Optimized Fuel Assembly Design
Project stage: Other
ML20093E0941984-07-13013 July 1984
Suppls 840314 Application for Amend to Licenses DPR-24 & DPR-27,consisting of Tech Spec Change Request 87,covering Use of Westinghouse Optimized Fuel Assembly Design.Results of small-break LOCA Analysis & Mods to Tech Specs Encl
Project stage: Request
ML20094B9871984-08-0101 August 1984
Forwards Rev 1 to Process Control Program, Listing Vendor Procedures Governing Processing & Packaging of Solid Radwaste
Project stage: Request
ML20095F3181984-08-0707 August 1984
Requests Proprietary Responses to NRC Questions Re Optimized Fuel Assembly Design Be Withheld (Ref 10CFR2.790).Affidavit Encl
Project stage: Other
ML20095F2761984-08-17017 August 1984
Forwards Proprietary & Nonproprietary Responses to Request for Addl Info Re Tech Spec Change Request 87 Concerning Use of Westinghouse Optimized Fuel Assembly.Application for Withholding Proprietary Response (Ref 10CFR2.790) Encl
Project stage: Request
ML20108A7681984-10-0505 October 1984
Amends 86 & 90 to Licenses DPR-24 & DPR-27,respectively, Revising Tech Specs to Allow Use of Westinghouse Optimized Fuel Assemblies
Project stage: Other
ML20108A7771984-10-0505 October 1984
Safety Evaluation Supporting Amends 86 & 90 to Licenses DPR-24 & DPR-27,respectively
Project stage: Approval
ML20094A0541984-11-0101 November 1984
Provides Info Consistent W/Provision of 771102 Safety Evaluation Which Included Consideration & Approval of Using Fuel Assemblies Repaired by Replacement of Damaged Fuel Rod W/Inert Rod or by Removing Rod
Project stage: Other
ML20107D6841985-01-31031 January 1985
Cycle 11 Startup
Project stage: Other
1984-10-05
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,,.o O
O W P0afR COMPANY 231 W. MICHIGAN, P.O. 80X 2046, MILWAUKEE, WI 53201 August 1, 1984 Mr. !!. R.
Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention:
Mr. J. R. Millor, Chief Operating Reactors, Branch 3 Gentlement DOCKET NOS. 50-266 AND 50-301 RADIOACTIVE WASTE PROCESS CONTROL PROGRAM POINT BEACil NUCLEAR PLANT, UNITS 1 AND 2 Wisconsin Electric Power Company, licensco for Point Beach Nuclear Plant, Units 1 and 2, hereby filos Revision 1 of the Point Beach Nuclear Plant Radioactivo Wasto Process Control Program for NRC review.
The Process Control Program had previously been submitted as part of a modification to our Radiological Effluent Technical Specifications, dated October 7, 1983.
The onclosed Proccas Control Program is a list of Point Beach and vendor proceduros which govern the processing and packaging of solid radioactive wasto.
The proceduros have boon developed to assure complianco with stato and fodoral regulations relativo to wanto form, classification, transpor-tation and disposal.
Picano contact us if you have any questions concerning this submittal.
Very truly yours, un President R. W. Britt Enclosuro Copy to NRC Resident Inspector i
N Ln
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