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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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p"%j, o, UNITED STATES f.
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i NUCLEAR REGULATORY COMMISSION
- j WASHINGTON, D. C. 20555
'+A.....,.o' May 16,1980 Dockets Nos.
266 and 50-301 Mr. Sol Burstein Executive Vice President Wisconsin Electric Power Ccmpany 231 West Michigan Street Milwaukee, Wisconsin 53201
Dear Mr. Burstein:
In conducting our review of your responses to our letter of September 21, 1979 relating to NRC requirements for the auxiliary feedwater system at Point Beach Nuclear Plant, Units Nos.1 and 2, we have determined that we will need the additional information and your response to the positions resulting from our review identified in the enclosure to complete the review.
In order for us to maintain our review schedule, your response is req'uested within 45 days of your receipt of this letter. The open items identified in the enclosure.:ust be resolved.in a manner acceptable to the NRC staff before the Safety Evaluation Report related to this matter can be issued.
Please contact us if you have any questions concerning this request.
Sincerely, R. A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Enclosure:
Request for Additional Information and NRC Staff Positions cc w/ enclosure:
See next page 8005270 $1}
Mr. Sol Burstein Wisconsin Electric Power Cogany ec:
Mr. Brace Churchill, Esquire Shaw, Pitt:r.an, Potts and Trewbridge 1800 M Street, N.W.
Washington, D. C.
20036 Docurnent Depart:nent University of Wisconsin Stevens Point Library Stevens Point, Wisconsin 54481 Mr. Glenn A. Reed, Manager Nuclear Operations Wisconsin Electric Power Conpany Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wisconsin 54241 Ms. Kathleen M. Falk General Counsel.
Wisconsin's Environmental Decade 302 E. Washington Avenue ludison, Wisconsin 53703 1
4*
Enclosure POINT BEACH NUCLEAR PLANT, UNITS 1&2 AUXILIARY FEEDWATER SYSTEM REQUIREMENTS DOCKET NOS. 50-266 & 50-301 A.
Short Term Recommendations 1.
Recommendation GS-1 The licensee's response to this recommendation is unacceptable and indicates that the licensee may have misinterpreted our requirement.
We require that all four AFW pumps be operable prior to taking the reactor critical for two unit operation and three of the four AP4 pumps (including two motor driven.and the associated turbine driven pump) be operable for single unit operation.
Under two unit opera-tion, with one motor driven AP4 pump inoperable, both units should be shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the pump cannot be restored. The licensee should revise the appropriate Technical Specifications and submit them to us for review.
2.
Recommendation GS-2 The licensee's response to this recomendation is acceptable.
3.
Recommendation GS-4 The licensee's response to this reconnendation is acceptable.
4.
Recommendation GS-5 The licensee's response to this recommendation is insufficient for us to complete our review.
For the short tenn the licensee should verify that emergency procedures for a complete loss of AC power are available or propose emergency procedures that includes necessary steps to assure cooling water to the turbine driven pump bearings or that require an operator to be stationed at the pump (to monitor bearing temperature) l
vk
. in communication with the control room to allow for on-off control of the turbine driven pump if necessary.
The licensee should also verify i
adequate lighting and communications are available for all operator actions outside the control rocm.
(See Recommendation GL-3 for long term.)
5.
Recommendation GS-6 1
The licensees response to the first part of this recommendation is un-acceptable.
We require that plant procedures be revised to include a second operator independent verification that AFW system valves have been properly aligned to their normal position following performance of periodic testing or maintenance.
The licensees response to the second part of this recommendation is acceptable.
However, the licensee should verify that the periodically perforr.ed full flow inservice inspection test provides AFW flow to the steam generators.
6.
Recommendation GS-7 The licensee's response to this recommendation is currently under re-view.
We will provide the results of our review at a later date.
B.
Additional Short Term Recommendations 1.
The licensees response to this recommendation is acceptable.
2.
The licensee indicates that 72-hour endurance tests were completed on all AFW pumps by December 30, 1979.
In order that we may review the test results, provide us with a copy of the test procedure and resulting test data. The type of information we require is described in the NRC
1, '
memorandum dated December 3,1979 which reduced the test from 72 to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and which you indicate you have in your possession. The licensee should provide as much of the infomation identified in the December 3,1979 memorandum as possible.
3.
The licensee's response to this recomendation is currently being evaluated by the Lessons Learned Implementation Task Force.
4.
The licensee's response to this recommendation is acceptable.
5.
We have the following additional concern based on Preliminary Notifica-tion of Event or Unusual Occurrence - PN0 III-80-25, dated February 5, 1980. The notice describes an incident where the pressure transmitters on the discharge of the two motor driven AP4 pumps were valved out.
The transmitters sense pump pressure and open the motor driven pump discharge valves.
Describe the measures taken such as independent operator verification or other procedural changes to prevent occurrence of similar errors in the future.
C.
Long Tem Recommendations 1.
Recomendation GL-3 The licensee response to this recomendation indicates that the pro-posed modificatier_ to the turbine driven APA pump bearing cooling system described for Recomendation GS-5 is intended as a long term solution for assuring APA pump operation independent of all AC power. We do not consider the design for providing bearing cooling water from the diesel driven fire pump adequate as a final solution since manual operator action
~ sks 1 is required. An acceptable solution is to provide bearing cooling water from a recirculation line directly off the AFW pump discharge.
It is our position that the licensee provide a long term design which will automatically initiate and assure AFW flow and be capable of being operated independently of any AC power for at least two hours.
No credit will be given for any operator actions outside the control room for two hours.
2.
Re ommendation GL-4 The licensees response to this recommendation is unacceptable. The licensee has failed to demonstrate that AFW pump protection can be adequately provided by manual action in the event of a failure in the condensate storage tanks due to a seismic event or torando.
It is our position that the licensee provide automatic switchover to the service water system on low suction pressure to the AFW pumps, or upgrade the pri-mary water supply to meet seismic Category I requirements and tornado protection.
4 3.
Recommendation GL-5 See Recommencation GS-7 above.
D.
Basis for AFW System Flow Recuirements The licensee has indicated that he feels a response to Enclosure 2 of our September 21, 1979 letter concerntng a request for information on AFM system flow requirements is unnecessary in view of the already performed AFW system review. We disagree and it is our position that the licensee respand to expeditiously.