ML19320C939

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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
ML19320C939
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/16/1980
From: Baynard P
FLORIDA POWER CORP.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
TAC-12961, NUDOCS 8007180294
Download: ML19320C939 (4)


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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, H and Loop B, TC and H T. Therefore, Decay Heat Suction Tem-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/

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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-

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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

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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.

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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.

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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 ,

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Nuclear Support Services Klein(NRCSub)DN97-2 i

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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.

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(/ Notary Public Notary Public,' State of Florida at Large, My Commission Expires: June 8, 1984 PYB/MAHNotary(DE-2-3)