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
,
8 005079QQ UNITED STATES OF AMERICA h
NUCLEAR REGULATORY COMMISSION In the Matter of Florida Power Corporation
)
Docket No. 50-302 (Crystal River Unit No. 3 Nuclear Generating Plant)
)
CONFIRMATORY ORDER I
The Florida Power Corporation (the Licensee) is the holder of Facility Operating License No. DPR-72 which authorizes the Licensee to operate the Crystal River Unit No. 3 Nuclear Generating Plant (the facility) at power levels not in excess of 2,452 megawatts thermal.
The facility is a pressurized water reactor located at the Licensee's site in Citrus County, Florida.
II Following the incident of February 26, 1980, at the Crystal River facility, the NRC staff held meetings with the Licensee, other operating licensees with Babcock and Wilcox (B&W) reactor systems, and B&W. The meetings ware held in Bethesda, Maryland on March 4,17 and 18,1980. These meetings resulted in the development of three licensee comitments.
j 1.
Actions which will allow the operator to cope with various combinations of loss of instrumentation and control functions.
This includes changes in (A) equipment and control systems to give clear indications of functions which are lost or unreliable; (B) procedures and training to assure posi-tive and safe manual response by the operator in the event that competent instruments are unavailable.
~2" Q:
2.
Determination of the effects of various combinations of loss of instru-mentation and control functions by design review analysis and verification by test.
3.
Correction of electrical deficiencies which may allow the power operated relief valve and pressurizer spray valve to open on non-nuclear instru-mentation power failures, such as, the event which occurred at Crystal River, Unit 3 on February 26, 1980.
The Licensee confirmed by letter dated March 24, 1980, that it would implement all three actions at its facility prior to the restart of Crystal River Unit No. 3 which is currently shutdown for maintenance and refueling.
The March 24 letter included by refer-ence the licensee's submittal of March 12, 1980; the March 12 letter provided the detailed listing of various combinations of loss of instrumentation which constitutes the comit -
ment in Item 1 and the letter also provided the specific list of tests which constitutes the comitment in Item 2.
I have concluded that timely implementation of these three short term actions, at operating B&W system nuclear power plants is necessary to provide continued assurance of public health and safety.
III The Office of Inspection and Enforcement (IE) issued Bulletin 79-27 following an event at the Ocunee Nuclear Station, Unit No. 3, on November 10, 1979 which was similar to the Crystal River incident.
This event was described in Information Notice 79-29, dated November 16, 1979, which was sent to this Licensee.
This Licensee was requested by IE Bulletin 79-27, dated November 30, 1979, Loss of Non Class I-E Instru-mentation and Control Power Bus During Operation, to review, among other things, busses supplying power to certain instrument and control systems, emergency procedures related to loss of power to such busses and failure to certain power supplies.
In accordance taith Bulletin 79-27 the Licensee was requested to submit to the Comission the results of its review by February 28, 1980.
This Licensee has not met this date.
, The responses to IE Bulletin 79-27 must be submitted in order that NRC can determine whether this license should be modified to protect the health and safety of the public.
The Licensee's letter of March 26, 1980 committed to respond to the Bulletin by April 26, 1980.
IV In view of the importance of this matter I have determined that these commit-ments be formalized by order and that the public health, safety and interest require that this Order be made immediately effective.
Accordingly, pursuant to the Atomic Energy Act of 1954, as amended, and the Comnission's regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED, EFFECTIVE IMMEDIATELY, THAT:
(1)
The Licensee prior to restart after the current outage will implement all three actions provided in Part II of this Order.
(2) The Licensee shall submit by April 26, 1980 the written responses to IE Bulletin 79-27 to the NRC.
V l
Any person who has an interest af fected by this Order nay request a hearing within twenty-five days of the date of the Order. Any request for a hearing will not stay the effectiveness of this Order. Any request for a hearing shall be sub-mitted to the Director, Office of Nuclear Reactor Regulation, U. S. Nuclear Regula-tory Commission, Washington, D. C.
20555, with a copy to the Executive Legal Director at the above address.
If a hearing is requested by a person who has an interest affected by this Order, the Commission will issue an Order oesignating the time and place of any such hearing.
.- In the event any person who has an inter t affected by this Order requests a hearing as provided above and a hearing is held, the issues to be considered at such a hearing shall be:
(1) Whether the facts set forth in, si. II and III of this Order provide an adequate basis for the actions ordered, and (2) Whether the Licensee should perform the actions required by Part IV of this Order in accordance with the schedule stated therein.
Operation of the facility on terms consistent with this Order is not stayed by the pendency of any proceedings on the Order.
FOR THE NUCLEAR REGULATORY COMMISSION i-/e M sk 1
t Harold R. Denton, Director Office of fluclear Reactor Dated at Bethesda, Maryland this 14th ay of April 1980.
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