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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
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
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
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
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
ML19320D5021980-07-0808 July 1980
Revised Tech Spec 15.3.4 for Steam & Power Conversion Sys
Project stage: Other
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
ML20009C7371981-07-16016 July 1981
Forwards Response to Generic Ltr 81-14 Re Seismic Qualification of Auxiliary Feedwater Sys.Sys Is Adequately Protected for Seismic Event
Project stage: Other
ML20040G4761982-01-25025 January 1982
Forwards Request for Addl Info Re Response to Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys
Project stage: RAI
ML20041G4231982-03-16016 March 1982
Submits Synopsis of Items Discussed During 820302 Telcon Re Automatic Initiation Features of Auxiliary Feedwater Sys
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
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
ML20052F2161982-05-0404 May 1982
Forwards Addl Response to Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys. Major Mechanical Components Seismically Qualified Except Condensate Storage Tanks
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
ML20054K8491982-06-30030 June 1982
Proposed Tech Spec Changes Re Periodic Testing of Auxiliary Feedwater Sys Automatic Actuation Logic
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
ML20062G6931982-07-27027 July 1982
Notice of Issuance & Availability of Amends 62 & 67 to Licenses DPR-24 & DPR-27,respectively
Project stage: Other
ML20028A7531982-11-12012 November 1982
Requests Encl Contractor Technical Evaluation Rept Re Seismic Qualification of Auxiliary Feedwater Sys Be Reviewed & Comments Provided by 821220
Project stage: Other
ML20067D6311982-12-15015 December 1982
Comments on Technical Evaluation Rept Re Seismic Qualification of Auxiliary Feedwater Sys,Per 821112 Request. Recommendation to Acquire Complete SSE Level of Seismic Capacity Constitutes Unnecessary & Expensive Backfit
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
ML20080B5531984-01-31031 January 1984
Provides Addl Info Re Status of Auxiliary Feedwater Sys Mods Implemented in Response to Generic Ltr 81-14.Last Remaining Mod Involves Replacement of Battery Rack Support Straps & Should Be Completed by Oct 1984
Project stage: Other
ML20091J8581984-05-23023 May 1984
Emergency Operating Procedure Validation Procedure
Project stage: Other
ML20100J0891984-12-0404 December 1984
Provides Final Responses to Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys. Support Straps on Battery Racks Replaced as Scheduled in
Project stage: Other
ML20116D2981985-04-22022 April 1985
Notifies That Installation of Low Suction Pressure Automatic Trips on Auxiliary Feedwater Pumps Expected to Be Completed by 860131,in Response to NRC Request for Commitment Date
Project stage: Request
ML20206S7491986-05-31031 May 1986
Evaluation of Structural Aspects Re Point Beach Plant
Project stage: Other
ML20206S6861986-09-16016 September 1986
Forwards Safety Evaluation & Technical Evaluation Rept on Util 850426 Response to Open Items Re Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys. Addl Info Requested Re Diesel Generator Room Flooding
Project stage: Approval
ML20206S7091986-09-16016 September 1986
Safety Evaluation on Util 850426 Response to Open Items Re Generic Ltr 81-14, Seismic Qualification of Auxiliary Feedwater Sys (Afws). Reasonable Assurance Exists That Afws Will Perform Required Safety Function Following SSE
Project stage: Approval
ML20215N8401986-10-31031 October 1986
Advises of Features & Mods to Diesel Generator Room Air Exhaust Duct Louvers & Diesel Generator Voltage Regulator Cabinets in Response to Concerns Expressed in 860916 Safety Evaluation Re Util Compliance W/Generic Ltr 81-14
Project stage: Other
ML20209H2971987-01-21021 January 1987
Advises That Mods to Protect Diesel Generator Voltage Regulator Cabinets from Fire Protection Sprinkler Operation Adequately Address NRC Concerns Identified in 860916 Safety Evaluation,Per Util
Project stage: Approval
1981-07-16
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Text
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O Wisconsin Electnc ecua ccurnur 231 W. MICHIGAN, P.O. BOX 2046. MILWALKEE, WI 53201 December 17, 1979 Mr. Harold R.
Denton, Director Office of Nuclear Reactor Regulation U.
S. NUCLEAR REGULATORY COMMISSION Washington, D.
C.
20555 Attention:
Mr. A.
Schwencer, Chief Operating Reactors Branch 1 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 POINT BEACH NUCLEAR PLANT LESSONS LEARNED RECOMMENDATIONS 2.1.7.a AND.b The following information and enclosures are provided in response to your December 10, additional information-
~
1979 telecopied request for 2.1.7.a AFW System Automatic Initiation 1.
The Point Beach AFW System design provides for auto-matic initiation from a variety of sources.
A description of conditions which cause automatic AFW initiation can be found on page 10.2-12 of the Point Beach FFDSAR.
The elementary diagrams which show the AFW pump start circuits are enclosed.
2.
Each of the steam generators at Point Beach can be supplied with AFW from either a motor driven or steam turbine driven pump.
In addition, the start initiating circuits for each of the pumps are redundant.
One exception is the automatic start of the motor driven AFW pumps caused by the trip of both main feed pumps.
A failure in this circuit could delay the automatic start of one motor driven AFW pump until the associated steam generator level reaches the low-low setpoint.
3.
The Point Beach design includes provisions for testing Og the AFW initiating signals and circuits from the 3
system monitoring devices through the actuation of the logic relays which make up the start circuits.
DRAwara k RE s i=;IEs 1643 350 Ap on u,m (;fy oy/
.7 912 27 0 y30 p
Mr. Harold R.
Denton December 17, 1979 These tests are performed on a monthly basis.
Once a year, during the refueling shutdown, the AFW pump start circuits associated with safety injection are tested by the Safety Injection / Loss of offsite Power Test.
This Test includes running the pumps after sequencing onto the diesel generators.
4.
All of the initiating signals and circuits are powered from either the emergency buses or the batteries.
5.
All of the AFW pumps and motor operated valves are manually operable from the control room.
The control switches are shown on the enclosed elementary wiring diagrams.
A single failure in the manual portions of the circuits would not result in the loss of system function.
6.
The AC motor driven AFW pumps are automatically loaded onto the emergency buses.
The power supplies to the motor operated valves are not stripped from the emergency buses and, therefore, do not need to be autoraatically loaded on.
7.
The capability to operate the AFW pumps and valves manually from the control room is always retained.
A failure in the automatic start circuit to a pump will not prevent manual actuation of the AFW system.
The AFW motor operated valves are not operated automatically.
The normal valve lineup is shown on FFDSAR Figure 10.2-5 and on TMI Accident Review Task Force Report Figure 3.2-12.
2.1.7.b AFW System Flow Indication to Steam Generators Indication of AFW flow to the steam generators at Point Beach currently consists of locally mounted flow meters on the discharge of each pump.
This is backed up by the steam generator level indication in the control room.
A modification to the flow instrumentation is in progress which will provide AFW pump flow indication in the control room, powered by vital instrument buses.
This modification will be completed ay January 1, 1980.
Further modification, consisting of direct flow indication for each steam generator, will be completed by January 1, 1981.
Very truly yours, 1643 351 C. W.
Fay, Director Nuclear Power Department Enclosures
