Letter Sequence Approval |
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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
[Table View] |
Text
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O APR 2 51983 6 asu-ty 9 \\
MEMORANDUM FOR:
D. G. Eisenhut, Director, Division of Licensing, NRR FROM:
C. E. Norelius, Director, Division of Project and Resident Programs, RIII
SUBJECT:
SAFETY EVALUATION OF THE PREFERRED A.C. POWER SYSTEM l
CONFORMANCE TO GENERAL DESIGN CRITERIA 17, POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2, TAC NOS. 46522 AND 46523 (Ltr fm W. G. Guldemond, SRI, to T. Colburn, ORPM dtd 6/11/81, same subject)
Per your request, we have completed the review of the Senior Resident Inspector's concerns that the Point Beach Nuclear Plant's preferred power source does not meet the requirements of General Design Criteria (GDC)-17.
The review concludes that the preferred power systems do not fully meet the intent of GDC-17 because of the proximity of the two low voltage auxiliary transformers, 1-X04 and 2-X04 and because the two preferred l
systems could be automatically disconnected from the 4160 volt safeguards I
buses in the worst case accident loads and the failure of one low voltage f
transformer.
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We were unable to find any guidance in standards, Regulatory Guides, or l
fire codes on what separation distance between the transformers is accept-l abin to prevent or mitigate the likelihood of their simultaneous failure; l
however, the Fire Protection Handbook states that transformers containing I
appreciable quantities of flammable, inhibited mineral oils with flash l
points ranging from 130*C to 135 C are placed at least 25 feet away from l
windows or other openings in the walls of the substation control building l
and from other important structures or placed in a vault of the type speci-l fled in the National Electric Code of the National Fire Protection Associa-tion. The flash point of the PBNP oil is 140"C, a Class III combustible i
oil, and License Amendment Nos. 39 and 44, August 2, 1979, concluded i
G305020128 G30425 PDR ADOCK 05000266 P
PDR
D. G. Eisenhut 2
/LPR 2 51983 that the existing fire protection system for the transformers and the Gas Turbine Building was adequate to protect the equipment required for safe shutdown.
We considered other interactive or simultaneous failures of both trans-formers to be unlikely, but possible. The licensee is considering two ways to mitigate the effects of a simultaneous failure of both transformers.
They are considering the procurement of a spare transformer, which is unique and requires several months to obtain, but only a few days to install, if on hand. They are also working on a procedure to backfeed offsite power through the main transformer, which, if possible, would only require a few hours to accomplish.
The failure of one low voltago transformer with one unit in hot shutdown and the other in an accident situation could drop the voltage to 3714 on the 4160 volt safeguards buses. This is below the degraded grid voltage relay setpoint of 3762 volts and would automatically disconnect the offsite power from the facility for a short period of time. The Power System Branch's (PSP) safety evaluation of the PBNP electrical distribution system voltages, dated March 2, 1983, found this acceptable; however, it should be pointed out that License Amendment Nos. 58 and 62 dated January 6, 1982, increased the degraded grid voltage trip point from 3675 volts, a voltage below that calculated in the above accident case, to 3762 volts, a voltage that would automatically remove all offsite power. The licensee has proposed a further increase in the setpoint to 3875 volts. These actions taken to protect safeguards equipment are contrary to GDC-17 guidance.
The Point Beach Nuclear Plant was designed and built before GDC-17 became effective on May 21, 1971. The facility was designed and constructed under a proposed Criteria 39 which specified that the onsite and offsite power system shall each, independently, provide the capacity to permit the func-tioning required of the engineering safety features assuming a failure of a single active component in each power system.
Since the transformer performance has been very reliable over the twelve years of operational history and Wisconsin Electric Power Company (WEPCo) is considering plans to expeditiously reestablish A.C. power to the facility in the improbable event of failure of both transformers or associated circuit breakers. The evaluation concludes that no backfitting is necessary.
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APR 2 51983 D. G. Eisenhut 3
One hundred fifty-four staff hours were used in this evaluation.
Any questions on this subject should be directed to K. R. Ridgway at 384-2544 (FTS).
dc 16 7
C. E. Norelius, Director Division of Project and Resident Programs
Attachment:
Safety Evaluation cc w/ attachment:
T. G. Colburn, ORPM R. A. Clark, ORB-3 G. C. Lainas, AD/0R V. G. Guldemond, SRI J. O. Thoma, NRR P. A. Barrett, RIII l
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