ML20053D265

Forwards Tech Spec Change Request 98,requesting Amend to App a of License DPR-72 to Allow Operation at Power Levels Up to 2,475 MW & 1,400 MW W/Four & Three Reactor Coolant Pumps, Respectively

ML20053D265
Person / Time
Site:	Crystal River
Issue date:	05/28/1982
From:	Mardis D FLORIDA POWER CORP.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20053D266	List: ML20053D265 ML20053D275 ML20053D278
References
3F-0582-28, 3F-582-28, TAC-48471, TAC-48844, NUDOCS 8206040244
Download: ML20053D265 (5)

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M Power C 0 m e o n a f e o se May 28,1982

1. 3F-0582-28 File: 3-0-3-c Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Technical Specification Change Request No. 98 Operation at 2475/1400 MWt without Reactor Coolant Pump Power Monitors

Dear Mr. Denton:

Florida Power Corporation hereby submits three (3) originals and forty (40) copies of Technical Specification Change Request No. 98, requesting amendment to Appendix A of Operating License No. DPR-72. Approval of this Request will allow unit operation at power levels up to 2475 MWt and 1400 MWt for operation with four (4) and three (3) reactor coolant pumps, respectively. Accordingly, revised pages of our November 16, 1981, Cycle 4 Reload Report are submitted as supporting documentation.

Operation of Crystal River Unit 3 (CR-3) without Reactor Coolant Pump Power Monitors (RCPPMs) was initially proposed in Request No. 61 dated April 30, 1980.

Operation of CR-3 for Cycle 4 with RCPPMs was submitted to you for approval on November 16, 1981. Spurious reactor trips resulted from the sensitivity of the RCPPMs, and we requested authorization to allow operation at 2300 MWt with the RCPPMs bypassed. Subsequent to our requests dated April 1,1982, April 6,1982, and April 30,1982, we have performed an analysis similar to that provided in Request No. 61 and have determined the maximum allowable power levels for operation of CR-3 without a Reactor Protection System (RPS) reactor trip based upon RCPPMs. The operation of CR-3 without RCPPMs is a prudent course of action until the resolution of spurious reactor trips can be achieved. Authorization at this time allows operation up to 2300 MWt provided four (4) pumps are operating.

s pD 8206040244 820528 pgg p PDR ADOCK 05000302 P PDR General Office 3201 Trurty-fourin street soutn . P O Box 14042. St Petersburg. Florida 33733 813-866-5151

Mr. Harold R. Denton May 28,1982 Page 2 Your concurrence is requested to discontinue surveillance testing the RCPPMs when they are removed from service (bypassed) and the power level is within Technical Specification limits. Administrative measures will ensure operability of these Monitors prior to their being returned to service.

Pursuant to 10 CFR 170.12, Florida Power Coporation has determined our Request to involve a single safety issue. Accordingly, we hereby remit a check in the amount of

$ts,000.

Also enclosed is a copy of the Certificate of Service for Technical Specification Change Request No. 98 to the Chief Executive of Citrus County, Florida.

Very truly yours, auI M David G. Mardis Acting Manager Nuclear 1.icensing Enclosures DGM:mm cc: Mr. 3. P. O'Reilly, Regional Administrator Of fice of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 3100 Atlanta, GA 30303

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O STATE OF FLORIDA COUNTY OF PINELLAS D. G. Mardis states that he is the Acting Manager, Nuclear Licensing, of Florida Power Corporation; that he is authorized.on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.

~ D. G.~ Mardis

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Subscribed and sworn to before me, a Notary Public in and for the State i and County above named, this 28th day of May,1982, i

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&Wh Notgfy Public Notary Public, State of Florida at Large, My Commission Expires: May 29,1984 l'

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION.

IN THE MATTER OF )

) DOCKET NO. 50-302 FLORIDA POWER CORPORATION )

CERTIFICATE OF SERVICE D. G. Mardis deposes and says that the following has been served on the Chief Executive of Citrus County, Florida, by deposit in the United States mail, addressed as follows:

Chairman, Board of County Commissioners of Citrus County Citrus County Courthouse Inverness, FL 32650 One (1) copy of Technical Specification Change Request No. 98 requesting amendment to Appendix A of Operating License No. DPR-72.

FLORIDA POWER CORPORATION b

7TG. Mardis' Acting Manager Nuclear Licensing SWORN TO AND SUBSCRIBED BEFORE ME THIS 28th DAY OF MAY,1982.

Notar . ublic Notary Public, State of Florida at Large My Commission Expires: May 29,1934 (NOTARIAL SEAL) 1

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TECHNICAL SPECIFICATION CHANGE REQUEST NO. 98 Replace pages 2-3, 2-5, 2-7, B 2-4, B 2-5, B 2-6, 3/4 3-3 and 3/4 4-1 with pages 2-3, 2-5, 2-7, B 2-4, B 2-5, B 2-6,3/4 3-3 and 3/4 4-1 provided.

PROPOSED CHANGES

1. Review NUCLEAR OVERPOWER based on RCS FLOW and AXIAL POWER IMBLANCE upward to allow operation at power levels up to 2475 MWt.

2. Revise the NUCLEAR OVERPOWER trip setpoints for both three and four pump operation to maintain operation within safety analyses.

REASCN FOR PORPOSED CHANGE This change will allow operation of CR-3 at up to 2475 MWt for the four pump configuration and 1400 MWt for the three pump configuration.

SAFETY EVALUATION Attached are revised pages to BAW-1634 wh!ch documents revised analyses of Cycle IV to meet normal acceptance criteria for Reload Reports. Operation with the constraints proposed (both NUCLEAR OVERPOWER and NUCLEAR OVERPOWER BASED on RCS FLOW and AXIAL IMBLANCE) will not exceed FSAR acceptance criteria as long as power operation with three pumps is limited to no more than 1400 MWt. The Integrated Control System will be adjusted to assure reactor runback to this level of loss of fourth pump.

The requirement to adjust the NUCLEAR OVERPOWER setpoints will assure operation within this constraint af ter they are required by ACTION a. for Modes 1 and 2 of Specification 3.4.1.

The nominal allowable power operation with three reactor coolant pumps operating is much less than the allowable Nuclear Overpower Trip Setpoint of 75.67% Rated Thermal Power (RTP). Florida Power Corporation, in recognition of this, has chosen to reduce the Nuclear Overpower Trip Setpoint to 59.7% RTP for this case to more positively limit reactor power to within allowable limits. This is consistent with the allowable 55% RTP analyzed by B&W and is shown graphically in Figure 2.2-1 (page 2-7) by a developed horizontalline at 59.7% RTP.

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