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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l%scwasin Electnc eomcome 231 W. MICHIGAN, P.0, BOX 2046, MILWAUKEE, WI 53201 August 17, 1984 Mr. H.
R.
Denton, Director Office of Nuclear Reactor Regulation U.
S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention:
Mr.
J.
R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 s\\
OPTIMIZED FUEL ASSEMBLY DESIGN TECHNICAL SPECIFICATION CHANGE REQUEST NO. 87 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 On March 14, 1983, Wisconsin Electric Power Company applied for License Amendments and Technical Specification Changes to permit use of the Westinghouse Optimized Fuel Assembly design (OFA) at our Point Beach Nuclear Plant Units 1 and 2.
Additional information and other editorial Technical Specification Changes were contained in a subsequent letter dated September 6, 1983.
In another letter dated July 13, 1984, we provided the results of the OFA small-break LOCA analysis and submitted other licensing changes related to the use of OFA fuel.
In a letter dated August 1, 1984, the NRC staff requested additional information concerning the OFA fuel design.
The purpose of this letter is to provide that additional information.
Enclosed with this letter are the following items:
1.
Responses to the request for additional information
- Proprietary edition 2.
Responses to the request for additional information
- Non-proprietary edition 3.
A copy of Westinghouse Electric Corporation's letter CAW-84-78 dated August 7, 1984, requesting withholding from public disclosure, in accordance with 10 CFR 2.790, of that material identified as proprietary in Enclosure 1.
4.
A copy of Westinghouse affidavit, AW-76-60 in support of the application for proprietary treatment.
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d Mr. H.-R.~Denton August 17, 1984 The enclosed material -is submitted for your information in support of Technical. Specification Change Request No. 87.
As
' discussed in enclosures-3 and 4, it is requested that the infor-mation1be treated as proprietary.information of Westinghouse Electric Corporation.. Correspondence with respect to the affidavit or application.for withholding should reference AW-84-78 and should be addressed:to R. A..Wiesemann, Manager of Regulatory and Legislative Affairs, Westinghouse Electric Corporation,.
P.' O. Box 355, Pittsburgh,. Pennsylvania 15230.
As discussed. iniour previous correspondence, we are planning.to insert the initial region of OFA fuel into Point Beach Unit 2 during the fall 1984 refueling outage.
This outage is presently scheduled for five weeks beginning on September 28, 1984.
Your continued efforts to complete your review and approval
-of our license applicationsto meet this schedule will be appreciated.
Very truly yours,
(/
Vice Preside t-Nuclear Power C. W.
Fay Enclosure Copy to NRC Resident Inspector (w/o encl.)
1 l
O
, ' ID ENCLOSURE 3