Letter Sequence Other |
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Results
Other: ML18086B727, ML19249B547, ML19269F078, ML19309E488, ML19337A621, ML19338E953, ML19344F186, ML19350D332, ML19350D336, ML19352A999, ML20002E376, ML20004C837, ML20004E532, ML20005B917, ML20009F141, ML20010E585, ML20030C831, ML20030C845, ML20031G095, ML20049H841, ML20052G353, ML20053D878, ML20065T584, ML20069E650, ML20077K670, ML20085A749
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MONTHYEARML19225B2971979-06-13013 June 1979 Notifies of Review of Util 770728 Submittal Re TAC 10042 & 10043,degraded Grid Voltage.Forwards Request for Addl Info Project stage: RAI ML19247A7701979-07-0303 July 1979 Discusses Util Re Degraded Grid Voltage Generic Issues.Forwards Request for Addl Info Re Trip Setpoint Time Delay,Voltage Monitor Verification of IEEE Requirements & Channel Functional Tests Project stage: RAI ML19249B5471979-08-24024 August 1979 Submits Tech Spec Mod Change Request 45 to 770728 License Amend Request Re Tables 15.3.5-1 & 15.4.1-1,& Addl Info Per NRC .Revised Tables Encl Project stage: Other ML19254D0751979-10-0101 October 1979 Requests Addl Info Re Loss of Offsite Power on 731013 to Aid in Review of Offsite Power Sys Adequacy.Requests Response within 90 Days Project stage: Approval ML19254D0781979-10-12012 October 1979 Forwards Response to 790808 Request for Addl Info Re Adequacy of Station Distribution Sys Voltages.Results of Verification Testing Described Will Be Submitted Separately After Completion of Tests Project stage: Request ML19269F0781979-11-16016 November 1979 Four ROs on 710413,0205,731013 & 740427 Re Partial & Total Losses of Offsite Power.Caused by Wiring Errors & Weather Conditions.No Voltage or Frequency Problems Occurred Project stage: Other ML19309E4881980-04-17017 April 1980 Notifies of Changes to Undervoltage Relaying for Protection Against Degraded Grid Voltage on 4160 Volt Safeguard Busses. Action Responds to NRC Request to Upgrade Circuitry Upon Review of Facility 790824 & 1012 & s Project stage: Other ML19344F1861980-09-0808 September 1980 Forwards Requests for Addl Info Re Adequacy of Station Electric Distribution Sys Voltages to Continue Review. Response Requested within 45 Days of Ltr Receipt Project stage: Other IR 05000266/19800141980-09-22022 September 1980 IE Insp Repts 50-266/80-14 & 50-301/80-14 on 800801-31. Noncompliance Noted:Failure to Comply W/Asme Section XI Code Requirements for Valve Inservice Testing,Exceeding Tech Specs Due to Improper Valve Testing on Containment Sys Project stage: Request ML19337A6181980-09-22022 September 1980 Proposed Change 45,modifying 770728 Request to Amend Licenses DPR-24 & DPR-27 to Incorporate Tech Spec Changes. Changes Modify Trip & Time Delay Setting for Undervoltage Protection Circuitry Project stage: Request ML19337A6211980-09-22022 September 1980 Tech Spec Change for Item 7 of Table 15.3.5-1 & Item 3a of Table 15.3.5-3 Re Time & Trip Delay Settings for Undervoltage Protection Sys Project stage: Other ML19338E9531980-09-26026 September 1980 Requests Addl 90 Days to Provide Info Re Adequacy of Station Distribution Sys Voltages Per Project stage: Other ML20002E3761981-01-21021 January 1981 Responds to NRC Requesting Addl Info Re Adequacy of Electrical Distribution Sys.All safety-related Sys Supplied from Either 480 Volt or 4160 Volt Sys.Electrical Sys Diagram Encl Project stage: Other IR 05000266/19800221981-01-21021 January 1981 IE Insp Repts 50-266/80-22 & 50-301/80-22 on 801201-31. Noncompliance Noted:Failure to Obtain New Baseline Data Following Interruption in Refueling Activities Project stage: Request ML0710202641981-02-25025 February 1981 Memo from Thomas Murley to Stephen Hanauer Re Diesel Generator Loading Problems Related to SIS Reset on Loss of Offsite Power Project stage: Request ML19345G4961981-03-26026 March 1981 Forwards Request for Addl Info for Review of Util Re Adequacy of Station Electric Distribution Sys Voltages. Requests Response within 60 Days Project stage: RAI ML19350D3321981-03-31031 March 1981 Amends 47 & 52 to Licenses DPR-24 & DPR-27,respectively, Reflecting Mods to Plant Equipment for Addl Assurance of Proper Functioning of safety-related Electrical & Emergency Power Sys Project stage: Other ML19350D3341981-03-31031 March 1981 Safety Evaluation Supporting Amends 47 & 52 to Licenses DPR-24 & DPR-27,respectively Project stage: Approval ML19350D3361981-03-31031 March 1981 Notice of Issuance & Availability of Amends 47 & 52 to Licenses DPR-24 & DPR-27,respectively Project stage: Other ML19347D9111981-04-0909 April 1981 Responds to Preliminary Results of NRC Review of Environ Qualification of safety-related Equipment.Deficiencies Cited Result from Inadequate Review of Documentation.No High Energy Lines in Normal Operation Which Could Cause Hazard Project stage: Request ML19352A9991981-05-30030 May 1981 Informs That Mod of Protective Relaying Unavoidably Delayed, Due to Longer than Anticipated Delivery Times for Required Replacement Relays for safety-related Electrical Distribution Buses.Anticipates Mod Completion by 810831 Project stage: Other ML20004C8371981-06-0101 June 1981 Submits Clarification of Previous Submittals & Results of Addl Analyses Performed Re Adequacy of Electrical Distribution Sys Per 810326 Request Project stage: Other ML20004D1471981-06-0202 June 1981 Memo to Operating Reactor & Licensing Project Managers Re NRC Review of Emergency Procedures & Training for Station Blackout.Licensee 90-day Responses to Generic Ltr 81-04 Should Be Provided Project stage: Approval ML20004E5321981-06-0909 June 1981 Informs That Time Is Needed to Study Generic Info Being Developed by Westinghouse Owners Group Before Accurately Predicting Completion Date of Tasks Outlined in Generic Ltr 81-04 Project stage: Other ML18086B7271981-07-0909 July 1981 Informs of Unacceptability of Proposed Schedule for Development & Implementation of Emergency Procedures & Training for Station Blackout.Optimal Recovery Guidelines for Station Blackout Should Be Completed Soon as Possible Project stage: Other ML20009F1411981-07-20020 July 1981 Requests Info Re Station Blackout,Addressing Unresolved Safety Issue A-44.Questionnaire & LER Documentation Encl Project stage: Other ML20030C8451981-08-20020 August 1981 Advises That Addl Info Requested in NRC Re Adequacy of Station Distribution Sys Voltages Will Be Provided by Dec 1981 Project stage: Other ML20030C8311981-08-21021 August 1981 Forwards Completed Data Tables Re Reliability of Onsite Standby Diesel Generators,Per NRC 810720 Request Concerning Station Blackout Project stage: Other ML20010E5851981-08-21021 August 1981 Requests That Licensee Expedite Implementation of Emergency Procedures & Training for Station Blackout Event to Be in Effect by Sept 1981.Revised Schedule for Implementation Must Be Submitted within 20 Days Project stage: Other ML20005B9171981-09-11011 September 1981 Notifies That Special Order Implementing Requirements of Generic Ltr 81-04 Re Emergency Procedures & Training for Station Blackout or Loss of All Ac Power Events Will Be in Effect by 810930 Project stage: Other ML20031G0951981-09-29029 September 1981 Approves 810911 Commitments & Schedule Re Procedures & Training for Station Blackout Events.Intention to Implement Permanent Procedures & Conduct Operator Training Per 810609 Schedule (in Response to Generic Ltr 81-04) Ack Project stage: Other ML20039D6141981-12-30030 December 1981 Application for Amend to Licenses DPR-24 & DPR-27,responding to NRC 811218 Telecopied Request for Addl Info on 811203 Tech Spec Change Request 74 Re Emergency Power Undervoltage Relay Protection Project stage: Request ML20049H8411982-02-26026 February 1982 Informs That Requested Analyses of Effects of Transient Voltages Present During Switching & Motor Starting Operations Will Be Completed by 820501 Project stage: Other ML20052G3531982-05-14014 May 1982 Advises That Addl Info Requested 820226 Re Adequacy of Station Distribution Sys Voltages Will Be Submitted by 820601 Project stage: Other ML20053D8781982-06-0101 June 1982 Forwards Clarification & Updated Info Re Adequacy of Station Electrical Distribution Sys Voltages Referenced in NRC .Info Combined w/810601 & 1230 Ltrs Completes Response Project stage: Other ML20063M5941982-09-10010 September 1982 Responds to 820813 Request for Addl Info Re Adequacy of Electrical Distribution Sys Voltages.Theoretical & Actual Voltages for safety-related Buses Listed Project stage: Request ML20065T5841982-10-29029 October 1982 Responds to NRC Re Adequacy of Station Electrical Distribution.Failure of Both Low Voltage Station Auxiliary Transformers Is Condition Described in Fsar,Chapter 7, Electrical Sys Project stage: Other ML20077K6701983-02-0909 February 1983 Adequacy of Electric Distribution Sys Voltages for Point Beach Nuclear Plant,Units 1 & 2, Technical Evaluation Rept Project stage: Other ML20069E6501983-03-14014 March 1983 Suppls 791012 & 810601 Responses to Requests for Addl Info Re Offsite Power Distribution Sys.Nrc Safety Analysis Concluded That Ac Auxiliary Power Sys Adequate & Physical & Electrical Separation of Power Sys Acceptable Project stage: Other ML20072J6891983-03-23023 March 1983 Application for Amend to Licenses DPR-24 & DPR-27,modifying 820427 Tech Spec Change Request 77 Re Loss of Voltage Protective Relays Project stage: Request ML20204F5251983-04-25025 April 1983 Forwards Safety Evaluation of Util Preferred Ac Power Sys Conformance to GDC 17.Power Sys Do Not Fully Meet Intent of GDC 17 Since Sys Could Be Automatically Disconnected from 4,160-volt Safeguards Buses in Worst Case Accident Loads Project stage: Approval ML20204F5381983-04-25025 April 1983 Safety Evaluation of Util Preferred Ac Power Sys Conformance GDC 17.Proximity of Low Voltage Transformers Does Not Fully Meet GDC 17 Requirements for Physical Separation,But Deluge Sprinkler Sys Adequate Project stage: Approval ML20085A7491983-06-30030 June 1983 Informs of No Significant Changes to Electrical Distribution Sys Described in FSAR Which Would Affect Degree of Conformance w/GDC-17.Available Info Adequate to Determine Intent of GDC-17 Re Offsite Power Distribution Sys Project stage: Other 1981-06-01
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I Nsconsin Electnc ecata couesur 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 September 11, 1981
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Mr. Harold R.
Denton, Director 49 i, b py 4
Office of Nuclear Reactor Regulation O bb d U U.
S.
NUCLEAR REGULATORY COMMISSION
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. -, 1 6 $ 3 M $
Washington, D.
C.
20555 Attention: Mr.
R. A. Clark, Chief Operating Reactors Branch 3 v'
Gentlertan:
f DOCKET NOS. 50-266 AND 50-301 INTERIM LOSS OF ALL AC POWER PROCEDURE POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Iour letter dated August 21, 1981 discussed aspects of our June 9, 1981 response to Generic Letter 81-04 regarding emer-gency procedures and training for station blackout or loss of all AC power events.
Specifically, you stated that our schedule for unplementation of these procedures and training did not satisfy the urgency you have assigned to this matter.
You, therefore, requested that we expedite implementation of emergency procedures and operator training for loss of all AC power events such that they will be in effect by about September 1981.
In a letter 20 Mr. Eisenhut dated August 7, 1981, the Westinghouse Owners Group provided an explanation of its NUREG-0737, Item I.C.1, schedule modification to give a high priority to the loss of all AC power guidelines.
The Owners Group reiterated that presentation of procedure and training guidelires at the September seminar should permit each utility to augment the guidelines with plant-specific considerations and implement plant-specific procedures and training no later than the first refueling in 1982.
We believe this schedule reflects the earliest reasonably practical date for implementation of procedures and training for loss of all AC power events while still allowing accommodation of the many other NRC imposed activities, chapges, and modifications currently in progress at the Point Beach Nuclear Plant.
As discussed in the July 1, 1981 NRC document, " Survey of Licensee Viewpoints on Regulatory Activities", NRC SECY-81-437, the imposition of NRC requirements in the form of generic letters, fD 8109160117 810911 O
s; 0 PDR ADOCK 05000266
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F PDR
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' e Mr. Harold R. Denton September 11, 1981 i
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bulletins, circulars, notices, Regulatory Guides, NUREG's, rule changes, and orders has become nearly overwhelming.
SECY-81-437 also discussed tsie negative safety impacts that repeated procedural changes may have on plant ope *ations.
Development or a procedure is obviously only the first " cap in implementatior..
More important is the operator trainino necessary to insure the procedure is under-etood by the present operators and integrated into the qualification, requalification, and NRC operator testing program.
En this example, you are requesting licensees to include in the plant operator training and cualification program an izterim procedure subject to almost certain change within a relatively short time.
We believe your present requirement for an immediate loss of all AC power procedure, at a time when owners group organizations have been diligently working on the development of emergency procedures in response to the TMI Action Plan, is an inappropriate and unnecessary imposition of new requirements by the NRC staff.
As mentioned in our initial response to your reauest, the availability of four transmission lines to the Point Beach' site,
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emergency diesel generators, and an on-site 20 MW gas turbine-powered generator make the possibility of a complete loss of all AC i
power extremely remote.
Nonetheless, in order to satisfy the urgent requirement you have placed on implementation or these procedures and training, we are developing a special order for response to loss of all AC power events at the Point Beach Nuclear Plant.
This special order will be in effect and sufficient operator training conducted to insure familiarization with the special order to meet your requirement for expedited implementation by September 30, 1981.
Refinement of this special order, based on our review and appraisal of the Westinghouse owners Group guidelines and implementation of the permanent loss of all AC power procedures and training, will be conducted in accordance with the schedule discussed in the August 7, 1981 Owners Group letter.
Very truly yours, A
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2 I
Exe utive Vice President Sol Burstein 4
Copy to NRC Resident Inspector
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