Letter Sequence Request |
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Results
Other: ML19309H811, ML19318B896, ML20008E295, ML20010E854, ML20027D213, ML20038B135, ML20038B146, ML20039C398, ML20039C401, ML20039C419, ML20040H025, ML20069L742, ML20069L752
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MONTHYEARML19309H8111980-05-0808 May 1980 Forwards IE Info Notice 80-20, Loss of Decay Heat Removal Capability at Davis-Besse Unit 1 While in Refueling Mode. No Response Required Project stage: Other ML19318B8961980-06-0505 June 1980 Responds to IE Bulletin 80-12, Decay Heat Removal Sys Operability. Plant Design Does Not Provide for Automatic Actuation of ECCS Recirculation or Automatic Positioning of Containment Recirculation Sump Valves Project stage: Other ML20008E2951980-10-14014 October 1980 Responds to NRC Re Proposed Tech Spec Changes for All Facilities to Provide for Redundancy in Decay Heat Removal Capability.Plant Specs Already Address Concerns & Require No Changes Project stage: Other ML20010E8541981-08-14014 August 1981 Requests That Proposed Tech Specs for Redundancy of Decay Heat Removal Capability in All Modes of Operation & Related Safety Analysis Be Submitted within 60 Days.Model Tech Specs to Assist in Preparation of Submittal Encl Project stage: Other ML20038B1461981-11-16016 November 1981 Proposed Tech Specs Sections 15.3.1,15.3.3. & 15.3.8 to Ensure Redundancy of Decay Heat Removal Capability Under All Operating Conditions Project stage: Other ML20038B1351981-11-16016 November 1981 Tech Spec Change Request 72 for Amend to License DPR-24 & DPR-27,changing Tech Specs 15.3.1,15.3.3 & 15.3.8 to Ensure Redundancy of Decay Heat Removal Capability Under All Operating Conditions Project stage: Other ML20039C4011981-11-18018 November 1981 Comments on Util Tech Spec Change Request 72,proposing Revision to Tech Spec 15.3.1.A.2(a) Re Redundancy of Decay Heat Removal Sys.Elimination of Decay Heat Removal Capability Above 350 F Inappropriate Project stage: Other ML20039C4191981-12-0909 December 1981 Interim Deficiency Rept DER 81-39 Re Unit 1.Gas Stripper by C-E Has Undocumented Section of Pipe & Welds in Violation of ASME Code,Initially Reported 811112.Evaluation & Final Rept Expected by 820129 Project stage: Other ML20039C3981981-12-21021 December 1981 Forwards Region 3 Comments Re Util Tech Spec Change Request 72 Project stage: Other ML20040H0251982-01-22022 January 1982 Informs That 811116 Proposed Amend to Tech Specs Re Establishment of Redundancy of Decay Heat Removal Capability During All Modes of Operation Is Unacceptable.Application Should Be Modified Project stage: Other ML20052D8061982-05-0303 May 1982 Advises That Westinghouse Will Not File Reply Brief in Response to Wi Environ Decade Brief.Svc List Encl Project stage: Request ML20052E9091982-05-0303 May 1982 Revised Application for Amend to Licenses DPR-24 & DPR-27 Consisting of Changes to Tech Specs to Provide Addl Assurance of Availability of Redundant Reactor Decay Heat Removal Capabilities Project stage: Request ML20052E9201982-05-0303 May 1982 Proposed Changes to Tech Specs to Provide Addl Assurance of Availability of Redundant Reactor Decay Heat Removal Capabilities Project stage: Request ML20027D2131982-07-31031 July 1982 Tech Spec for Redundant DHR Capability,Point Beach,Units 1 & 2 Project stage: Other ML20069L7421982-11-0808 November 1982 Amend 66 & 71 to Licenses DPR-24 & DPR-27,respectively, Upgrading Tech Specs to Provide Redundancy of DHR Capability in All Modes of Operation Project stage: Other ML20069L7521982-11-0808 November 1982 Notice of Issuance & Availability of Amends 66 & 71 to Licenses DPR-24 & DPR-27,respectively Project stage: Other ML20069L7481982-11-0808 November 1982 Safety Evaluation Supporting Amends 66 & 71 to Licenses DPR-24 & DPR-27,respectively Project stage: Approval ML20081D3241983-10-25025 October 1983 Proposed Changes to Tech Spec 15.3.1.A Eliminating Provisions Beyond Basis for Required Operational RCS Components Project stage: Request ML20081D3121983-10-25025 October 1983 Application to Amend Licenses DPR-24 & DPR-27,changing Tech Spec 15.3.1.A to Eliminate Provisions Beyond Basis for Required Operational Components of Rcs.Class II Fee Encl Project stage: Request ML20086M6131984-02-0202 February 1984 Safety Evaluation Supporting Amends 82 & 86 to Licenses DPR-24 & DPR-27,respectively Project stage: Approval ML20086M6031984-02-0202 February 1984 Amends 82 & 86 to Licenses DPR-24 & DPR-27,respectively, Clarifying Limiting Condition for Operation of Steam Generators & Other DHR Equipment,Indicating Conditions Only Applicable When Fuel Loaded in Core Project stage: Approval 1981-12-09
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IHeconsin Electnc amcoumr 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 October 25, 1983 CERTIFIED MAIL 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:
DOCKETS 50-266 AND 50-301 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 93 LIMITING CONDITIONS FOR OPERATION REACTOR COOLANT SYSTEM POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with the provisions of 10 CFR 50.59, Wisconsin Electric Power Company, Licensee for Point Beach Nuclear Plant, Units 1 and 2, hereby submits an application for amendments to Facility Operating Licenses DPR-24 and DPR-27.
The purpose of these amendments is to incorporate changes to Point Beach Technical Specification 15.3.1.A which eliminate provisions which are beyond the basis for the required operational components of the reactor coolant system.
The attached proposed Technical Specification page includes the following changes identified by margin bars:
Specifications 15.3.1.A.1, 15.3.1.A.2, and 15.3.1.A.3 are revised to be applicable only when one or more fuel assemblies are in the reactor vessel.
As required by 10 CFR 50.91(a) (1), Licensee has determined that these proposed changes do not involve a significant hazards consideration.
The Commission has provided guidelines concerning the application of the standards by providing certain examples (48 FR 14870).
One of the examples of actions involving no significant hazards consideration relates to purely administrative changes to the technical specifications to achieve consistency.
The proposed amendments provide consistency between the intent of the limiting conditions for operation of the reactor coolant system and the technical specification basis.
The basis for the specifications to which the changes are proposed is to provide a means of removing Q,./J wlc A= K pI 8311010136 831025
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PDR ADOCK 05000266 P
PDR
Mr. H.
R. Denton October 25, 1983 heat from the core due to power operation or decay heat generation.
Therefore, the identified specifications are applicable only when one or more fuel assemblies are in the reactor vessel.
The proposed change climinates the restrictions in the existing limiting operating conditions which are beyond the scope of the basis for technical specifications and provides the needed flexibility to perform required hydrostatic testing of the reactor coolant system.
Licensee has determined that this license amendment application constitutes a Class II approval request as defined in 10 CFR 170.22.
A duplicate review for the second Point Beach unit constitutes a Class I approval.
Accordingly, we have enclosed herewith a check in the amount of $1,600 for these license approval fees.
As further specified in the Commission's regulations, enclosed are three signed originals and forty copies of this license amendment application.
Please contact.us if you have any additional questions concerning this subject.
Very truly yours, h
Vice President-Nuclear Power C. W. Fay Enclosure (Check No. 754051)
Copies to NRC Resident Inspector C.F.
Riederer, PSCW Subscribed and sworn to before me this 3 5-#1(, day of October 1983.
& T&[
- n. __
Notary'Puh%1c, State of Wisconsin My Commission expires % f,IfTY.
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