Letter Sequence Draft 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
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Text
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pmVc UNITED STATES 3 m( [%j NUCLEAR REGULATORY COMMISSION
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WASHING TO N, D. C. 20555 s...../
Docket No.: 50-302 July 6,1979 Mr. W. P. Stewart Manager, Nuclear Operations Florida Power Corporation P. O. Box 14042 Mail Stop C 4 St. Petersburg, Florida 33733
Dear Mr. Stewart:
By Orfer of May 16,1979, the Commissic onfirmed your undertaking a series of actions, both immed' nd long tert, to increase the capa-bility and reliability of t e Crystal Ri -
, Unit No. 3 to respond to various transient events.
In
, the Order confirmed that you would maintain the plant in a shutdown condition until the following actions had been satisfactorily completed:
"(a) Upgrade the timeliness and reliability of delivery from the Emergency Feedwater System by carrying out actions as identified in Enclosure 1 of the licensee's letter of May 1, 1979."
"(b)
Develop and implement operating procedures.for initiating and controlling emergency feedwater independent of Inte-grated Control System control."
"(c)
Implement a hard-wired control-grade reactor trip that would be actuated on loss of main feedwater and/or turbine trip."
"(d)
Complete analyses for potential small breaks and develop and implement operating instructions to define operator action."
"(e) All licensed reactor operators and senior reactor operators will have completed the TMI-2 simulator training at B&W."
By your letter dated May 1,1979 and supplemented by five letters, dated May 16, June 12,15, 22, and 29,1979, you have documented the action' taken in response to the May 16 Order. We have reviewed this submittal, and are satisfied that, with re;pect to Crystal River, Unit 3, you have satisfactorily completed the actions prescribed in items (a) through (e) of paragraph (1) of Section IV of the Order, the specified analyses are acceptable, and the specified implementing procedures are appropriate. The bases for these conclusions are set forth in the enclosed Safety Evaluation.
53GCC7
. so no0 Wo iA
Mr. W. P. Stewart As noted ~on page 12 of the Safety Evaluation, you are required to conduct a test during power ascension (<l57. rated power) to demonstrate the capability to provide and control emergency feedwater flow to both steam generators independent of the integrated control system.
Appropriate Technical Specifications for Limiting Conditions for Operation and for surveillance requirements should be developed as soon as practicable and provided to the staff within seven days with regard to the design and procedural changes which have been completed in compliance with the provisions of the May 16,1979 Commission Order. The revised Technical Specifications should cover:
(1) Addition of flow rate indication for the emergency feedwater system; (2) Addition of the auto start circuitry for the emergency feedwater pumps; (3) Addition of the anticipatory reactor trips; and (4) Changes in set points for high pressure reactor trip and PORV actuation.
Within 30 days of receipt of this letter, you should provide us with your schedule for completion of the long-term modifications described ir Section II of the May 16 Order.
My finding of satisfactory compiiance with the requirements of items (a) through (e) of paragraph (1) of Section IV of the Order will permit resumption of operation in accordance with the terms of the Commission's Order; it in no way affects your duty to continue in effect all of the above provisions of the Order pending your submission and approval by the Commission of the Tech-nical Specification changes necessary for each of the required modifications.
Sincerel v,
W P3rold R. Denton, Director Office of Nuclear Reactor Regulation
Enclosures:
1 Sa fety Evaluation 2.
Notice cc w/encis:
See next page
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