Letter Sequence Request |
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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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1 Wisconsin Electnc eowea couranr 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 October 12, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention: Mr. William Gammill Acting ?.ssistant Director for Operating Reactors Projects Gentlemen:
DOCKET NOS. 50-266 AND 50-301 ADEQUACY OF STATION DISTRIBUTION SYSTEM V0LTAGES POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Your letter dated August 8,1979, requested that we perform additional analyses and tests to demonstrate that the onsite electrical distribution system has sufficient capability to automatically start, as well as operate, all required safety loads. We have addressed the subject of onsite electrical distribution system voltages in three previous letters.
Our letter to Mr. Benard C. Rusche, dated September 17, 1976, provided a description of our onsite distribution system, transmission system operating range and resulting distribution system bus voltages.
That letter also listed our expected worst case fault, worst case overload and results of that overload, and described our undervoltage protection system.
Our response to the NRC generic letter of June 2,1977, was in the form of a Technical Specification change request dated July 28, 1977.
In that response, we agreed to make a change in the tettings of our undervoltage relays which are used to detect degraded voltage co.'ditions, and to modify our periodic diesel generator test procedure.
Included in our response was a detailed description of the multi-layered undervcitage protection system at Point Beach Nuclear Plant.
Our third previous submittal, addressed to Mr. Harold R. Denton and dated August 24, 1979, provided additional time delay and tolerance information to be included in our Technical Specifications, and described the effects of relay failures at the various protection levels.
/9 1l95 g07 hY 7910220S
Mr. Harold R. Denton, Director October 12, 1979 The additional analyses requested in your August 8,1979 letter are provided in Enclosure 1.
Results of the verification testing described in will be submitted separately after the tests have been completed.
Very truly yours,
/l
(/dd C. W. Fay, Di rector Nuclear Power Department Attachments 1195 008
ENCLO5URE 1
- a MINIMUM EXPECTED VOLTAGE ANALYSIS Since the Point Beach area is characterized by excess generation and high trans-mission system voltages, it is necessary to assume heavy loading conditions and a circuit breaker failure in order to arrive at the lowest expected grid voltage.
A system load flow was run with the foll,<ing initial conditions:
1979 Sunrner He avy Loading Both Point Beach Units at 100% power To establish the low voltage conditions, the following assumptions were made:
Point Beach Unit 2 tri;.s while at 100% power; A stuck breaker causes the Point Beach 345kv bus to split, leaving the weakest line tn provide auxiliary power;
' :ad transfers to the system The entire Unit 2 auxilia; auxiliary transformers; All automatically applied accident loads are placed on the safety related buses.
Unit 2 was chosen as the accident unit because it would se.e a lower voltage than Unit 1 for similac circumstances.
The combination of heavy auxiliary system loading and minimum expected grid voltage resulted in these bus voltages:
i Bus Nominal Volts Volts Before Trio Volts After Trio
(% of Nom.)
B.S. 5 345kv 358.46kv 345.69kv (100.2%)
H06 13.8kv 13.94kv 12.82kv (92.9%)
2A01 4.16kv 4.310kv 3.906kv (93.9%)
2A02 4.16kv 4.314kv 3.O xv (94%)
2A05 4.16kv 4.306kv 3.906Lv (93.9%)
2A06 4.16kv 4.306k-3.91kv (94%)
Since most of the Point Beacn safety-related loads are supplied by 480v buses 1(2)B03 and 1(2)B04, the bus voltages for 2B03 and 2B04 were calculated.
For bus 2B03:
Maximum automatic loading < 1500 kVA; a conservative power factor of 80% was assumed; transfomer regulation at 1500 kVA and 80% P.F. is 4.29%*.
2B03 voltage = 2A05 voltage - regulation = 430V (90% of Nom.)
turns ratio A similar calculation for 2B04 results in a bus 2B04 voltage of 431V (90% of Nom.)
- From certified test reports g
The safety-related motors supplied by the 480V buses are rated at 460V, +10%,
-20% and would have no difficulty operating at 430V. The only remaining question is whether or not the motor starting contactors will pull in at 108V. An informal test was conducted at Point Beach in 1976 as a result of the Millstone event whicn showed that our contactors would pull in below 100V and would not drop out until the voltage was reduced to 60-70V. The actual pull-in and drop-cut voltages will be verified by test for each size motor starter used on the safety-related 480V buses.
The transformer tap settings used co achieve the auxiliary bus voltages listed above for low voltage conditions will result in high voltage, no load values of 4370V on the 4160V buses and 504V on the 480V buses. These bus voltages are both less than the maximum voltage allowed by the equipment ratings.
1195 010 4
9 ENCLOSURE 2 AUXILIARY BUS VOLTAGE ANALYSIS - VERIFICATION TESTS In order to provide confidence in the auxiliary distribution system voltage drop calculations, voltage, current, and watt readings will be taken on the auxiliary system. The readings will be taken when the auxiliary system is heavily loaded and is being supplied by offsite power. The major items of interest are the transformer regulation values and the power factor of the loads. The actual results of the test will then be compared to the calculated results for verification.
A second test which will be performed is intended to demonstrate that the motor starters at Point Beach are capable of pulling in and holding at a voltage lower than the calculated, sustained low voltage of 108V. The minimum pull-in and maximum drop-out voltages for each size motor starter used on the safety-related matcc control center will be determined.
O 1195 01I 4