3F0284-09, Application for Amend to License DPR-72,revising Tech Specs to Include Addl DHR Requirements.Amend Fee Encl

Application for Amend to License DPR-72,revising Tech Specs to Include Addl DHR Requirements.Amend Fee Encl

ML20080M905
Person / Time
Site:	Crystal River
Issue date:	02/16/1984
From:	Westafer FLORIDA POWER CORP.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20080M907	List: 3F0284-09, Application for Amend to License DPR-72,revising Tech Specs to Include Addl DHR Requirements.Amend Fee Encl ML20080M908
References
RTR-NUREG-0103, RTR-NUREG-103 3F0284-09, 3F284-9, NUDOCS 8402220004
Download: ML20080M905 (4)

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Florida Power C O A

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• O es February 16,1984 3F0234-09 Mr. H. 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. 65 Decay Heat Technical Specifications

Dear Mr. Denton:

Enclosed are three (3) originals and forty (40) copies of Request No. 65 requesting amendment to Appendix A of Operating License No. DPR-72. As part of this request, the proposed pages are enclosed.

This proposed change includes additional decay heat requirements in the Technical Specifications in response to a letter from Mr. D. G. Eisenhut, dated June 11, 1980.

The revised Technical Specifications are consistent with the Standard Technical Specifications, NUREG-0103, Rev. 4, with a few minor site specific related changes.

Because this change is being made at the request of the Commission and is consistent with NRC recommended changes, an Amendment Fee of twelve hundred

($1,200) dollars is enclosed.

Sincerely, a

G. R. Westafer f '5 df' Manager, Nuclear Operations (M E6 Licensing and Fuel Management PGH/feb 8402220004 840216 f N[ fy PDR P

ADOCK 05000302 PDR f 0\

h,/[ 6 Enclosures t i

! f(0$ k0 xc: Mr. 3. P. O'Reilly Regional Administrator, Region II Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 101 Marietta St., N.W., Suite 2900 Atlanta, GA 30303 GEN ERAL OFFICE 3201 Thirty-fourth Street South e P.O. Box 14042, St. Petersburg, Florida 33733 e 813-866-5151

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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 G.R. Westafer deposes and says that the following has been served on the Designated State Representative and the Chief Executive of Citrus County, Florida, by deposit in the United States mail, addressed as follows:

Chairman, Administrator Board of County Commissioners Radiological Health Services of Citrus County Department of Health and Citrus County Courthouse Rehabilitative Services Inverness, FL 32650 1323 Winewood Blvd.

Tallahassee, FL 32301 One (1) copy of Technical Specification Change Request No. 65 requesting amendment to Appendix A of Operating License No. DPR-72.

FLORIDA POWER CORPORATION 1 W

'G.R. Westafer

- Manager

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Nuc! ear Operations Licensing and Fuel Management SWORN TO AND SUBSCRIBED BEFORE ME THIS 16th DAY of February 1984.

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olary Public fs mAA- -

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Notary Public, State of Florida at Large My Commission Expires:

NOTARY PUBUC STATE OF FLORIDA (NOTARIAL SEAL) Mr COMMISSION ExNES NOV 19 1986 BCNDED THRU GENERAL INSURANCE ONQ {

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STATE OF FLORIDA COUNTY OF PINELLAS G.R. Westafer states that he is the Manager, Nuclear Operations Licensing and Fuel Management for 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 leiowledge, information, and belief.

1 W' G.R. Wesfafer /

Manager, Nuclear Operations Licensing and Fuel Management Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 16th day of February,1984.

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Notary Public, State of Ficrida at Large, My Commission Expires:

NOTARY PUBUC STATE OF FLORIDA MY COMMISSION EXPIRIS NOV 19 1986 BONDED THitU CINERAL INSUllANG Ur D

FLORIDA POWER CORPORATION Crystal River Unit 3 Docket No. 50-302/ License No. DPR-72 Request No. 65, Revision 0 Decay Heat Removal Reliability LICENSE DOCUMENT INVOLVED:

Technical Specifications (Appendix A)

PORTIONS:

Index 3/4.4.1 Coolant Loops and Coolant Circulation Startup and Power Operation Hot Standby Hot Shutdown Cold Shutdown 3/4.9.8 Decay Heat Removal and Coolant Recirculation All Water Levels Low Water Levels Bases DESCRIPTION OF REQUEST:

The changes proposed herein are in resporise to a letter from Mr. D. G. Eisenhut dated June 11,1980 and are intended to assure redundant heat removal paths are available during all modes of operation.

The proposed Specification 3/4.1.2 assures availability of both reactor coolant loops during HOT STANDBY conditions. All reactor coolant pumps can be de-energized for up to one hour provided; (1) no reactivity increases are allowed and (2) a 100F sub-cooling margin is maintained.

The proposed Specification 3/4.1.3 and 3/4.1.4 assures availability of any two cooling loops (reactor coolant or decay heat)'during SHUTDOWN conditions. All reactor coolant and decay heat pumps may be de-energized under the same restrictions as in HOT STANDBY.

The proposed Section 3/4.9.8 -assures that adequate cooling is available to maintain the temperature of the water in the vessel withiri acceptable limits during the Refueling mode.

Only one decay heat removal loop is required when the water level is in excess of 23 feet above the fuel since the volume of water acts as a large heat sink thereby providing sufficient time to take compensatory actions if the decay heat train becomes inoperable.

REASON FOR REQUEST:

As noted in Mr. Eisenhut's letter, the NRC has determined that increased administrative controls to provide greater assorance of sufficient decay heat removal capacity are required. These changes are intended to respond to the Staff's concerns in this area.

SAFETY ANALYSIS OF PROPOSED CHANGE Tho current requirements of Technical Specifications 3/4.4.1 and 3/4.9.8 assume that in MODES 3, 4, 5, and 6 adequate time exists to place back-up equipment into service when cooling from the operating reactor coolant loop is lost. Operating experience at other plants indicates that taking credit for such actions in a timely fashion may be somewhat inadequate. The proposed specifications provide greater availability of necessary heat sinks in MODES 3, 4, 5 and 6. This change in plant operations enhances the reliability plant systems without creating any unanalyzed conditions and without increasing the probability or consequences of analyzed transients. Thus, no unreviewed safety question results from this change.