Letter Sequence Other |
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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
[Table View] |
Text
'r Florida Power C C A P '1 % A Y 8 0 N Apri1 16 1981
- 3-041 -2i File:
3-0-3-a-3 Qp(A' Mr. Harold R. Denton s
j Director
(
Office of Nuclear Reactor Regulation
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U. S. Nuclear Regulatory Comission Washington, D.C.
20555 9
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Subject:
Crystal River Unit 3 6
Docket No. 50-302 Operating License No. DPR-72
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Nuclear Safety Task Force Follow Up 4 N _,,: g \\' f
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Dear Mr. Denton:
In our letter of March 6,1981, Florida Power Corporation stated we woulo provide you with a schedule and resources estimate for all Nuclear Safety Task Force recommendations which will result in engineering studies to be completed in 1981.
By this letter, Florida Power Corporation fulfills that comitment. is a detailed schedule for completion of the engineering studies identified in oe ciarch 6,1981, letter. We anticipate that com-pletion of the engineering work identified in Attachment I will involve the expenditure of approximately $70,000.
We will advise you of the re-sults of these studies and our plans for further pursuit of these items early in 1982.
We will also advise you promptly of any significant safety concerns resulting from these studies.
Very truly yours, 4
4 P. Y aynard Manager
/l Nuclear Support Services 00/
Friend (T-07)D1-3 3
/ /
81042103%
f General Office 320s inat -tcurtn street scu:n. P o sex 14c42, st Petersburg. Fcnca 33733 813-566-5151 f
Nuclear Safety Task Force Tollow Up In our March 6, 1981 response, FPC identified 23 Muclear Safety Task Force recreendations which will require addditional evaluation.
Cf these 26 items, 7 have been identified as known problems which will require a formal engi-neering study ta determine the best alternative salution.
These are safety Task Force recomendations 1.21, 3 13, 3 22, 3.23, 5.82, 6.1, and 6.8.
A schedule for the expletion of the studies for these items is shown below. Tne remaining 19 items are in FPC's opinion patential problems that require addi-tianal investigative research before it is determined that a problem exists.
The schedules for this investigative work for each of these items is shown below.
The remaining 19 items are in FFC's opinion patential proble.s that require additional investigative research before it is determined that a pro-blem exists.
The schedules for this investigative work for each of these itets is shown below. Following cocpletion of our additional review of each of these items, we will provide you with our conclusions and justification for these con-clusions as to whether or not a problem exists. In the cases where actual pro-blems are identified, we will provide you with our schedule to resolve each item.
Safety Task Force Recomendtion #
Schedule for Study or Review 1.21 7-3-81 3 13 8-14-81 3 22 8-14-81 3 23 8-28-81 5.82 6-12-81 6.1 10-16-81 6.8 12-31-81 1.19 5-22-81 5.65 5-29-81 5.105 5-29-81 5.106 6-12-81 3 21 6-12-81 5.75 6-26-81 5.76 6-26-81 5.113 7-3-81 5.95 7-13-81 3.6 7-13-81 39 8-7-81 3 10 8-14-81 5 35 8-21-81 3.12 8-28-81 3 11 9-3-81 3 24 9-3-81 5.49 9-25-81 5.54 10-9-81 5 36 10-30-81