Letter Sequence Meeting |
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Results
Other: ML19290F175, ML19309E293, ML19309F675, ML19309G820, ML19312D649, ML19320C939, ML19322E558, ML19322E568, ML19323B469, ML19345B402, ML19347D269, ML19347E607, ML20008F619, ML20054F303, ML20126D163
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MONTHYEARML19241C2491979-07-0202 July 1979 Safety Evaluation Rept Re Licensee Compliance W/Nrc 790516 Order.Requirements of Order Were Fulfilled.Plant May Resume operations.Long-term Mod Must Be Completed Project stage: Approval ML19241C2481979-07-0606 July 1979 Draft Ltr Re NRC 790516 Order Requiring Increase in Capability & Reliability of Plant to Respond to Various Transient Events.Plant May Resume Operations.Schedule for long-term Mod Will Be Forwarded within 30 Days Project stage: Draft Other ML19290E4671980-02-27027 February 1980 Transcript of 800227 Morning Briefing in Washington,Dc Re Event at Crystal River.Pp 1-74 Project stage: Request ML19312D0651980-02-29029 February 1980 Notification of 800304 Meeting W/B&W Licensees & Util in Bethesda,Md to Hear Presentation by Util Re 800226 Incident Project stage: Meeting ML19312D6491980-02-29029 February 1980 Responds to IE Bulletin 79-27, Loss of Non-Class IE Instrumentation & Control Power Sys Bus During Operation. Addl Time Is Required to Complete Review & Evaluation of non-class IE Instrumentation & Control Power Sys Project stage: Other ML19322E5681980-03-0606 March 1980 Ltr to All B&W Reactor Licensees Requesting Responses to IE Bulletin 79-27,Items 1-7.Responses to Items 1-5 Should Be Submitted by 800312.Responses to Items 6 & 7 Should Be Submitted by 800317 Project stage: Other ML19322E5581980-03-0606 March 1980 Forwards NRC Sent to B&W-designed Reactor Licensees,Requesting Info Re 800226 Transient Project stage: Other ML19290E8971980-03-12012 March 1980 Forwards Responses to NRC 800306 Request for Info Re Recent Transient.Util Will Perform Tests to Verify Remaining Info Following Nni/Ics Power Upsets.Will Verify That Operator Has Available Major Plant Parameters Identified in Response 4 Project stage: Request ML20126C6521980-03-13013 March 1980 Summary of 800304 Meeting W/Util,B&W Licensees Re Facility 800226 Nonnuclear Instrumentation Power Supply Failure Resulting in 43,000 Gallons of Coolant Escaping Primary Coolant Sys Into Reactor Bldg.Supporting Documentation Encl Project stage: Meeting ML19290F1751980-03-17017 March 1980 Forwards Response to Items 6 & 7 of Re Crystal River Unit 3 Incident.Corrective Action Plan Submitted 800312.Restart Projected for May 1980 Project stage: Other ML19312D4261980-03-24024 March 1980 Forwards Commitments Re Loss of Instrumentation Discussed During 800318 Meeting W/Nrc.Commits to Take Action to Allow Operator to Control Various Combinations of Loss of Instrumentation & Control Functions Prior to Restart Project stage: Meeting ML19309D4391980-03-24024 March 1980 Forwards Proposed Changes to Tech Specs,App a Project stage: Request ML19309E2931980-03-26026 March 1980 Updates 800229 Response to IE Bulletin 79-27.Util Will Complete Review & Evaluation of Non-Class IE Instrumentation & Control Sys as Required by Bulletin.Rept Will Be Submitted by 800426 Project stage: Other ML20126D1631980-04-0101 April 1980 Forwards Annotated Sequence of 800226 Events & Simplified Electrical Circuitry Schematics Per 800227 Request Project stage: Other ML19309G8201980-04-14014 April 1980 Confirmatory Order Re Util 800324 & 26 Commitments to Implement Actions Prior to Restart & to Respond to IE Bulletin 79-27 by 800426 Project stage: Other ML19309F6751980-04-25025 April 1980 Forwards Response to IE Bulletin 79-27, Loss of Non-Class IE Instrumentation & Control Power Sys Bus During Operation. Equipment Necessary for Cold Shutdown Available Project stage: Other ML19323C1221980-05-0202 May 1980 Forwards Request for Addl Info for Safety Evaluation Re 800226 Incident at Facility.Includes Info Re Mods Which Validate Info Provided by Indicators During Power Loss Situation Project stage: Approval ML19312D8521980-05-0202 May 1980 Forwards Response to Part I of NRC 800502 Request for Addl Info Re Restart After 800226 Accident.Util Is Installing Redundant Indicators Above Intercommunication Sys Section of Control Board.Part II Responses Will Follow Project stage: Request ML19323B4691980-05-0606 May 1980 Summarizes Background,Status & Future Plans Re Changes in Main Steam Line Rupture Matrix Sys,Safety Task Force Priority Item 51.Includes Description & Justification of short-term Change & Conclusions Project stage: Other ML19320A8541980-06-25025 June 1980 Responds to NRC 800502 Request for Info Re Pressurizer Safety Valves.Includes Data Taken During 800226 Incident to Assist in Determining Flow Rates & Conditioners in RCV-8 Relief Train.Test Results Will Be Sent When Available Project stage: Request ML19320C9391980-07-16016 July 1980 Advises That Restart W/O Completion of Item 51 Is Justified,As Original FSAR Is Still Valid for Present Design.All Items Will Be Completed Prior to Mode 2 Operation.Affidavit Encl Project stage: Other ML19330A9791980-07-18018 July 1980 Forwards Safety Evaluation Re 800226 Incident.Corrective Actions Taken Are Sufficient to Permit Restart & to Ensure Safe Operation Project stage: Approval ML19330A9821980-07-18018 July 1980 Safety Evaluation of Corrective Action Following 800226 Incident.Actions Taken Are Sufficient to Permit Restart Project stage: Approval ML19345B4021980-11-26026 November 1980 Forwards Nonproprietary Version of Nuclear Safety Review Task Force, Final Rept.Nuclear Safety Task Force Was Established to Identify Areas That Indicate Potential for Improvement in Safety of Facility Project stage: Other ML19347D2691981-03-0606 March 1981 Submits Nuclear Safety Task Force Recommendations Which Will Be Resolved in 1981.Schedule & Resources Estimate 1981 for Resolution of Recommendations in Category 7 Will Be Submitted by 810417 Project stage: Other ML20008F6191981-04-16016 April 1981 Forwards Schedule & Resources Estimate for Nuclear Safety Task Force Recommendations.Detailed Schedule Provided Re Completion of Engineering Studies Identified in Util Project stage: Other ML19347E6071981-04-30030 April 1981 Evaluation of Crystal River Nuclear Power Station Project stage: Other ML20054F3031982-06-11011 June 1982 Submits Status of Engineering Studies Resulting from Nuclear Safety Task Force Recommendations Re 800226 Transient Project stage: Other 1980-04-01
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g Power C O R PO n A Y *0 pt March 24, 1980 File: 3-0-3-a-3 Mr. Robert W. Reid Chief Operating Reactors Branch #4 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Commitments - During March 18, 1980 Meeting
Dear Mr. Reid:
During Florida Power Corporation's meeting with you, Tuesday, March 18, 1980, you requested a ~ letter committing to compliance with three (3) specific items.
The purpose.of.this letter is to formally transmit to you our comitment to those three (3) items, stated in Attachement 1, discussed during the meeting.
Details as to how Florida Power Corporation will satisfy the attached commitments were provided by letter to Mr. Harold R.
Denton, dated March 12,1980, from Mr. J. A. Hancock.
Should you have any questions concerning this matter, please contact this office.
'Very truly yours,
. FLORIDA r 'ER CORPORATION R. M. Bright Acting Manager Nuclear. Support Services Attachmenc RMBhewR01(D1)1
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8003240 3 9I LGeneral Office 3201 Tnitty-fourin street soutn. P O. Box 14o42, st. Petersburg. Florida 33733 813-866 5151
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M.~. Bright ~' states LthatG he Jis.theJ Acting? Manager, - Nuclear Support m-
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IS'ervices,yof YFlorida~ PowerfCorporation; that' he Eis1 authorized.on the -
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3.y-Subscribed and sworn to before me, a Notary Public in and for.the State
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--ATTCHMENT'1'
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TActions'which will allow the operator to cope'with various combina-tions -of: loss L of instrumentation and control functions. - This in-
+ J' clude's< changes' in -(A):equipmentjand :c'ontrol systems. to give clear indications of functions which are: lost or: unreliable; and (B) pro-
, icedures and. training;to assure positive and safe manual response by
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the-operator. sin ~ the event: :that. competent' ' instruments are' t
unavailable.;
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- Response:
t Florida Power : Corporation ' commits to -accomplish thisiitem prior to 2
the restart of Crystal River Unit 3.
'2.
Verification -of the. effects' of various combinations. of loss of' in-strumentation: and ^ control functions by design review analysis and by test.
1 Response:
' Florida. Power ' orporation comits to accomplish this -item prior to.
C the restart of Crystal River Unit 3.-
13.
Correctionofelectri$aldeficiencieswhich-mayallowthepowerop-Lerated trelief valve and pressurizer spray valve' to open on non-
-nuclear. instrumentation power failures, such as, the-event which s
. occurred at Crystal River Unit 3.on February 26, 1980.
Response:-
- Florida Power ' Corporation l commits to' accomplish this ' item. prior to the~ start.of' Crystal. River Unit 3.
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