Letter Sequence Other |
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Results
Other: ML19209A420, ML19246C410, ML19256G252, ML19257C541, ML19290B734, ML19320D502, ML19320D511, ML19320D518, ML19320D523, ML19320D526, ML20041G423, ML20052C092, ML20054K847, ML20054K849, ML20062G684, ML20062G693, ML20064L899, ML20082A625, ML20150F162
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MONTHYEARML19270G8051979-05-15015 May 1979 Summary of 790511 Meeting W/Util in Bethesda,Md Re Auxiliary Feedwater Sys.List of Attendees & Matl Discussed Encl Project stage: Meeting ML20150F1621979-05-22022 May 1979 Submits Formal Responses to 790510 Questionnaire Re Pressurizer Heater,Loss of Feedwater Event & Steam Generator Project stage: Other ML19225C9181979-06-0404 June 1979 Requests Status of Lll Electrical Staff Overpressure & Flooding Reviews Project stage: Request ML19246C4101979-06-11011 June 1979 Forwards NRC to Westinghouse Requesting Addl Info Re Small Break LOCA Analyses & Analysis Methods.Nrc Will Eventually Require Documentation Re Applicability of Westinghouse Results to Analyses at Facility Project stage: Other ML19209A4201979-09-21021 September 1979 Forwards NRC Requirements for Auxiliary Feedwater Sys & Requests That Plant Designs & Procedures Be Evaluated Against Applicable Requirements to Determine Degree of Conformity Project stage: Other ML19259D6551979-10-20020 October 1979 Forwards Response to NRC Requesting Commitments to Implement NUREG-0578 Recommendations.Design Differences Decrease Chance of TMI-type Accident Project stage: Request ML19290B7341979-10-29029 October 1979 Submits Partial Response to Re short-term & long-term Requirements for Auxiliary Feedwater Sys.Requests Extension Until 800131 for Remaining Requirements Project stage: Other ML19320D5181979-12-0707 December 1979 Seventy-Two Hour Test of Turbine-Driven Auxiliary Feed Pump Project stage: Other ML19256G1021979-12-17017 December 1979 Responds to NRC 791210 Request for Addl Info on TMI Lessons Learned Task Force Recommendations Re Auxiliary Feedwater Sys.Oversize Drawings Available in Central Files Project stage: Request ML19256G2521979-12-17017 December 1979 Forwards Modified Response to Previous Commitment to Implement NUREG-0578.Util Will Provide Alarms in Addition to Existing Position Indication for Power Operated Relief Valves for Both Units Project stage: Other ML19320D5261979-12-23023 December 1979 Seventy-Two Hour Test of Electrically-Driven Auxiliary Feed Pumps Project stage: Other ML19320D5231979-12-26026 December 1979 Seventy-Two Hour Test of Electrically-Driven Auxiliary Feed Pump Project stage: Other ML19320D5111979-12-28028 December 1979 Seventy-Two Hour Test of Turbine-Driven Auxiliary Feed Pump Project stage: Other ML19257C5411980-01-22022 January 1980 Forwards Small Break LOCA Operator Guidelines.Min RCS Subcooling Margin Set at 36 F Prior to Terminating Safety Injection Project stage: Other ML19260D8281980-02-0404 February 1980 Responds to NRC 790921 Request for Evaluation of Requirements for Auxiliary Feedwater Sys & Associated Schedule & Commitment for Implementation of Required Changes & Actions Project stage: Request ML19316A7831980-05-16016 May 1980 Forwards Request for Addl Responses to NRC Long & short-term Recommendations Re Auxiliary Feedwater Sys.Open Items Must Be Resolved Acceptably Before Safety Evaluation Can Be Issued.Responses Needed within 45 Days Project stage: Approval ML19320D5021980-07-0808 July 1980 Revised Tech Spec 15.3.4 for Steam & Power Conversion Sys Project stage: Other ML19320D4771980-07-0808 July 1980 Forwards Revised Tech Spec 15.3.4 for Steam & Power Conversion Sys & Four 72-h Test Repts for Auxiliary Feed Pump in Response to NRC 800516 Request for Addl Info Re Auxiliary Feedwater Sys Project stage: Request ML19350D3491981-04-0909 April 1981 Responds to 810127 Request for Response to Unresolved Items Identified in Safety Evaluation for Auxiliary Feedwater Sys, Including short-term Recommendation GS-1 Re Tech Specs & Recommendation Re Redundant Level Indications Project stage: Request ML20041G4231982-03-16016 March 1982 Submits Synopsis of Items Discussed During 820302 Telcon Re Automatic Initiation Features of Auxiliary Feedwater Sys Project stage: Other ML20052C0921982-04-27027 April 1982 Tech Spec Change Request 76 Consisting of Tech Spec Pages 15.3.4-1,-2 & -2.a Re Auxiliary Feedwater Pump Project stage: Other ML20052C0861982-04-27027 April 1982 Application for Amend to Licenses DPR-24 & DPR-27,consisting of Tech Spec Change Request 76.Amend Would Incorporate NRC Changes to Limit Unavailability of Auxiliary Feedwater Pumps Project stage: Request ML20054K8491982-06-30030 June 1982 Proposed Tech Spec Changes Re Periodic Testing of Auxiliary Feedwater Sys Automatic Actuation Logic Project stage: Other ML20054K8471982-06-30030 June 1982 Forwards Revision to Tech Spec Table 15.4.1-1 Re Periodic Testing of Auxiliary Feedwater Sys Automatic Actuation Logic.Nrc Review of Tech Spec Change Request 76 Should Include Addl Change Project stage: Other ML20062G6931982-07-27027 July 1982 Notice of Issuance & Availability of Amends 62 & 67 to Licenses DPR-24 & DPR-27,respectively Project stage: Other ML20062G6841982-07-27027 July 1982 Amends 62 & 67 to Licenses DPR-24 & DPR-27,respectively, Changing Tech Specs to Modify Limiting Conditions for Operation Re Auxiliary Feedwater Pump Operation Project stage: Other ML20064L8991983-02-11011 February 1983 Advises That Installation of Addl Supports for Auxiliary Feedwater Sys Piping & Components Rescheduled to June 1983, Due to Conflicts W/Other Plant Mods Project stage: Other ML20082A6251983-11-11011 November 1983 Advises That Auxiliary Feedwater Sys Operability Mods Completed Per Tech Spec Revs Proposed in 820427,0505 & 0630 Ltrs Project stage: Other 1979-09-21
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t-7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION
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e."
DOCKET NOS. 50-266 AND 50-301
_,l WISCONSIN ELECTRIC POWER COMPANY NOTICE OF IS'SUANCE OF AMENDMENTS TO FACILITY i.
OPERATING LICENSES The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 62 to Facility Operating License No. DPR-24, and Amendment No. 67 to Facility Operating License No. DPR-27 issued to Wisconsin Electric Power Company (the licensee), which revised Tech-nica1' Specifications for operation of Point Beach Nuclear Plant, Unit Nos.1 and 2 (the facilities) located in the Town of Two Creeks, j
Manitowoc County, Wisconsin. The amendments are effective 60 days from i
date of issuance.
I The amendments modify the limiting conditions for operation of the Technical Specifications with respect to the auxiliary feedwater pump opera tio n.
The application 'for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.
Prior public notice of these amendments was not. required since the amendments do not involve a significant hazards considera tion.
W cortifica E u
8208130135 820727 DR ADOCK 05000266 l
PDR t
7590-01
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The Commission has determined that the issuance of these amendments l
-will not result in any significant environmental impact and that pursuant to 10 CFR $51.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with issuance of these auendments.
For further details with respect to this action, see (1) the applica-tion for amendments dated April 27, 1982, as supplemented June 30, 1982, (2) Amendment Nos. 62 and 67 to License Nos. DPR-24 and DPR-27, and (3) the Commission's letter dated July 27, 1982. All of these items are available for public inspection at the Commission's Public Document Room,1717 H Street, N.W., Washington, D.C. 20555, and at the Joseph Mann Library, 1516.16th Street, Two Rivers, Wisconsin 54241. A copy of items (2) and (3) may be obtained upon request addressed to the U. S.
Nuclear Regulatory Commission, Washington, D.C.
20555, Attention:
Director, Division of Licensing.
Dated at Bethesda, Maryland, this 27th day of July,1982.
FOR THE NUCLEAR REGULATORY COMMISSION
&[
Y' Robert A. Clark, Chief
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Operating Reactors Branch #3 Division of Licensing M
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