ML19321A695

Forwards Schedule for Commitments to TMI-2 Related Requirements,Per NRC 800507 Request.Affidavit Encl

ML19321A695
Person / Time
Site:	Crystal River
Issue date:	07/21/1980
From:	Baynard P FLORIDA POWER CORP.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
TAC-45333, NUDOCS 8007240074
Download: ML19321A695 (4)

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Power COR PO R A Y IO N July 21, 1980 File Code:

3-0-1-a Mr. Darrell G. Eisenhut Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Subj ect: Crystal River Unit No. 3 Docket No. 50-302 Operating License DPR-72 Five Additional TMI-2 Related Requiremer.ts to Operating Reactors

Dear Mr. Eisenhut:

The committments to the suggested schedule of your May 7,1980, letter on five additional TMI-2 related requirements to operating reactors is attached.

This response fulfulls Florida Power Corporation's commitment to respond by July 21, 1980, as requested in our June 19, 1980, letter.

Sincerely, FLORIDA POWER CORPORATION ag.' W P. Y. Bayndrd Manager Nuclear Support Services Attachments Klein(NUREG-0660)DN98-2

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.. ~ General Office 3201 inirty fourin street soutn. P O Box 14042, st Petersburg. Florida 33733 813-866-5151 800724089f.

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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 information 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.

rjic A. b ut,a u A g y Y. Bayiiard l

Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 21st day of July,1980.

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Notary Public l

Notary. Public, State of Florida at Large,

-l My Commission-Expires: May 29, 1984 l

PYB/MACNotary(DN-98)'

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FLORIDA POWER CORPORATION'S POSITION ON SELECTED NUREG-0660 ACTION ITEMS AS REQUIRED BY NRC LETTER, DATED MAY 7, 1980 (Only Items Applicable to B&W Reactor's Are Addressed)

Item I.A.1.3 - Shift Manning FPC will review the requirements of I. A.1.3 and respond to the request thirty (30) days after receipt of NRC's requirements referenced in the May 7, 1980, letter.

Item I.A.3.1 - Revised Scope and Criteria for Licensing Examination FPC has used the NRC March 28, 1980, letter referenced in the May 7, 1980, letter to revise the scope and criteria for licensing examina-tion.

The implementation schedule of May 1, 1980 was met.

Item I.C.5 - Procedure for Feedback of Operating Experience to Plant Staff FPC initiated a prog am to improve the feedback of operating experi-ence to plant staff ersonnel after the receipt of NUREG-0578.

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plans to implement the finalized feedback information program by Jan-uary 1, 1981.

The program procedure is covered in AI 500.

The Operation Engiaeer is responsible to provide feedback to the operators through the OTAs.

Item II.K.3 II.K.3.1 - Installation and Testing of Automatic PORV Isolation System FPC plans to monitor the progress of the EPRI report on PORV failures and B&W's report on PORV failure reduction.

The informati ained will be used to analyze and make necessary modifications to th ORV system.

FPC can not commit to installing a particular automatic PORV isolation system until the above information is evaluated and Item II.K.3.2 is performed.

If FPC determines that an automatic PORV Isolation System is needed, a schedule for its installation will be made within 30 days of the decision for the need to install the system.

II.K.3.2 - PWR Vendor Report of PORV Failure Reduction FPC plans to use the B&W report on PORV failure reduction and the EPRI report on PORV failures to respond to this item.

B&W feels that they can meet the January 1,1981, schedule; however, the EPRI report com-pletion schedule is July 1,1981.

The EPRI report should be an inte-gral part of this commitment, and FPC will input the EPRI results in a timely fashion.

Klein(NUREG-0660)DN98-2

FPC will also report future challenges to the relief valve and safety valves in the annual report.

This commitment and schedule date of January 1, 1981 will be met.

II.K.3.5 - Automatic Trip of Reactor Coolant Pumps During LOCA FPC will continue to participate in generic efforts toward development of automatic trip of reactor coolant pumps during a small break loss of coolant accident.

FPC and other Licensees are being requested to analy:e LOFT L3-6 scheduled for December,1980.

This test may provide useful information related to this analysis.

As the schedule for the LOFT effort is not compatible with the date suggested in your letter, FPC cannot commit to the proposed schedule.

FPC will continue to attempt to develop a schedule and will inform you of our progress.

II.K.3.30 - Revise Small Break LOCA Methods to Show Compliance with 10CFR50 Appendix K The scope of work required to resolve this issue cannot be deter-mined.

Additional information is required to show which small break LOCA analysis methods do not satisfy /.ppendix K to 10CFR50.

Cl ari fy-ing information regarding implementation of this action is required from the NRC since Draft 4 of NUREG-0660 did not provide any addition-al information.

II.K.3.31 Plant Specific Calculations to Show Compliance with 10CFR50.46.

The response to II.K.3.30 is applicable to this item.

Item III.D.3.4 - Control Room Habitability FPC will complete a review of control habitability by January 1, 1981.

The review will be done using Regulatory Guides 1.78 and 1.95.

If the review shows that plant modifications are necessary, a schedule vill be provided.

Klein(NUREG-0660)DN98-2 L