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
I Florida Power C O M P O M A i t '] m July 16, 1980 File:
3-0 a Mr. Darrell G. Eisenhut Director Division of Licensing Office of Nuclear Reactor Regulation Washington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Status of 51 Restart Items
Dear Mr. Eisenhut:
Summarizing our July 11, 1980, meeting of the fifty-one (51) restart items, forty-three (43) of the items are complete, and the plant staff is undergoing the final required training.
Six (6) items which required plant modifications are in the final verification testing.
The remaining two items are discussed below:
Item 34 required the provision of redundant indication of main plant parameters as identified in Enclosure B of our May 2, 1980, letter and our March 12, 1980, letter.
Presently, five (5) of these parameters do not have redundant indic6tions per flow loop. These are:
1.
Decay Heat Suction Temperature Adequate infonnation regarding the temperature of the reactor coolant is obtained from the incore thermocouples, Loop A,
TC and T,
and Loop B,
H T.
Therefore, Decay Heat Suction Tem-TC and H
perature should be removed from this list.
2.
Startug Feedwater Flow Enclosure B listed Startup Feedwater Flow as a pa-rameter needed for cold shutdown.
That was an er-ror; the parameter should have been Emergency Feed-water Flow.
General Office 3201 inirty-fourtn street soutn. P O Box 14o42. St Petersburg. Florca 33733 813-866 5151 8007180Q9t/
o Mr. Darrell G. Eisenhut Page Two July 16, 1980 3.
Emergency Feedwater Flow Separate flow indications for Emergency Feedwater Flow are provided to each Once Through Steam Genera-tor (OTSG). Redundant indication is provided by the OTSG level indication. The indications are indepen-dent of the NNI and are consistent with our NUREG-0578 commitments. FPC is pursuing long term modifi-cations to provide redundant safety grade flow indi-cations for each OTSG.
4.
Decay Heat Flow Separate flow indications are provided for each train of Decay Heat, one powered from NNI-(X) and one from NNI-(Y). Each Decay Heat flow path has io-cal flow indication.
Also, temperature indications across the core and heat exchangers provide indica-tion of adequate Decay Heat cooling.
FPC is pursu-ing long term modifications to provide redundant flow indications (one from NNI-(X) and one from NNI-(Y) per path of Decay Heat flow).
]
5.
High Pressure Injection (HPI)' Flow The HP) system has four (4) flow paths to the Reac-tor Coolant System (2 per loop).
Loop A has two (2) injection paths, Al and A2, and Loop B has two (2) injection paths, B1 and B2.
Flow indication for flow paths Al and B2 are provided by NNI-(Y) and A2 and B1 are provided by NNI-(X).
In addition, the operator has redundant Tsat monitors which provide indication of adequate core cooling.
Florida Power Corporation is _ pursuing long term modifications to provide redundant ow indications, one from NNI-(X) and one from NNI
.) per path of HPI flow (8 flow indications).
The present-indications outlined above were determined to be acceptable during our discussions with you and your staff in our meeting on July 11, 1980.
These modifications will be completed at the first outage of sufficent duration following the receipt of equipment.
Item 51 required FPC to evaluate the OTSG Rupture Matrix with the intent ~ to re'nove the signal from FWV-161 and FWV-162 to assure a passive Emergency Feedwater (EFW) flow path to both OTSGs on initiation of EFW.
Mr. Darrell G. Eisenhut Page Three July 16, 1980 As stated at our July lith meeting, Florida Power Corporation has been reevaluating the steam line break analysis, assuming continued emergency feedwater flow addition.
Our evaluation to date indicates that the containment design pressure and temperature limits would be reached in 65 minutes and 36 min-utes, respectively.
These times would allow operator action to terminate EFW and, thereby, end the transient.
- However, the return to criticality analyses portion of our reevaluation of the steam line break analysis has not been completed. Pre-liminary analyses of this event were not sufficient to deter-mine if the reactor would become recritical sooner than 36 minutes.
Florida Power Corporation is presently pursuing additional detailed analysis with B&W to resolve this con-cern. Upon completion of the analysis, Florida Power Corpora-tion will submit them for your review and approval. Following NRC approval, the elimination of FWV-161 and -162 from the rupture matrix will be accomplished as soon as possible.
Restart of CR-3 without the completion of Item 51 is justified as the original FSAR analysis for the steam line break analysis is still valid and bounds the present design at CR-3.
Our completion of the 51 items, as defined in our May 2,1980, letter, and this submittal will be completed prior to our going into Mode 2 operation.
If you have any questions regarding this item, please call us.
Sincerely, FLORIDA POWER CORPORATION Patsy Y. Baynard Manager Nuclear Support Services Klein(NRCSub)DN97-2 i
O STATE OF FLORIDA COUNTY OF PINELLAS P. Y. Baynard states that she is the Manager, Nuclear Support Services Department of Florida Power Corporation; that she is authorized on the part of said company to sign and file with the Nuclear Regulatory Com-mission the infonnation attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of her knowledge, information and belief.
n% k. Yn. J v P4 Y. Beyrfard Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 16th day of July,1980.
bM M
4
(/ Notary Public
/
Notary Public,' State of Florida at Large, My Commission Expires: June 8, 1984 PYB/MAHNotary(DE-2-3)
