ML20217K709

Requests Addl Info Re Proposed License Amend for LTOP TS Features

ML20217K709
Person / Time
Site:	Crystal River
Issue date:	08/12/1997
From:	Raghaven L NRC (Affiliation Not Assigned)
To:	Richard Anderson FLORIDA POWER CORP.
References
TAC-M99277, NUDOCS 9708180073
Download: ML20217K709 (4)

Text

_ _ _ _ _ _ _ __

August 12, 1997 Mr. Roy A Anderson Senior Vice President, Nuclear Operations florida Power Corporation ATIN: Manager. Nuclear Licensing Crystal River Energy Complex (SA2A) 15760 W Power Line Street Crystal River, Florida 34428 6708

SUBJECT:

CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL-INFORMATION RELATED TO PROPOSED LICENSE AMENDMENT FOR LOW TEMPERATURE OVERPRESSURE PROJECTION TECHNICAL SPECIFICATION (TAC No. M99277)

Dear Mr. Anderson:

The purpose of this letter is to request additional information (RAl) relating to your proposed license amendment for providing low temperature overpressure (LTOP) technical specification (1S) features. The enclosure provides details for the requested information. We also had a telephone conversation with your staf f on August 4.1997, in which we discussed the technical details of this 4 request.

Please note that your requested target date of September 18, 1997 for completing our review is challenging. Accordingly, we request your response as expeditiously as possible. If you have any questions, please write or call me at (301) 415-1471 Sincerely.

Originai signted by L. Raghavan, Project. Manager Project Directorate 11 3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation Docket No. 50-302

Enclosure:

RAI cc: See next page gfd Distribution }

- tDocket file. PUBLIC CR-3 r/f B. Boger I ,\

"J. Zwolinski OGC ACRS J. Lyons C. Liang J. Jaudon, Region II DOCUMENT NAME: G:\ CRYSTAL \n m m u , . . .m . mi. *,. .. w.... in w.: c . em .nnooi .n.cnm.ni,.ncio. . t . co , .,in .ii.ca m.nir.ocio. . u . f4. .. ,

Offitt Polla3/PM [ P0ll 3/LA ,0-[( [ 0011 3/D _) lC. [ 1_ ._i NAME LRagn. van W SCI.yton / F fM.bdon hl _ _

Daft 08/l2,./91 08/17 /97 08/l1/97 , ,

OfflCIAL RECORD COPY ll ,1,l' Ill, I,Il I ll P

R" M m 'a"= PDR mt Rf CHITE11 COPY

Mr. Roy A. And:rs n CRYSTAL RIVER UNIT N0. 3 Florida Power Corporation GENERATING PLANT CCl Mr. R. Alexander Glenn Senior Resident Inspector Corporate Counsel .

Crystal River Unit 3 Florida Power Corporation U.S. Nuclear Regulatory Commission MAC-A5A 6745 N. Tallahassee Road P.O. Box 14042 Crystal River Florida 34428 St. Petersburg, Florida 33733-4042 Mr. John P. Cowan Mr. Bruce J. Hickle, Director Vice President, Nuclear Production Nuclear Plant Operations (NA20) (NA2E)

Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Line Str6)t 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Mr. Robert B. Borsum Mr. James S. Baumstark B&W Nuclear Technologies Director, Quality Programs (SA2C) 1700 Rockville Pike, Suite 525 Florida Power Corporation Rockville, Maryland 20852 Crystal River Energy Complex 15760 W. Power Line Street Mr. Bill Passetti Crystal River, Florida 34428-6708 Office of Radiation Control Department of Health and Regional Administrator, Region 11 Rehabilitative Services U.S. Nuclear Regulatory Commission 1317 Winewood Blvd. 61 Forsyth Street, SW., Suite 23T85 Tallahassee, Florida 32399-0700 Atlanta, GA 30303-3415 Attorney General Mr. Kerry Landis Department of Legal Affairs U.S. Nuclear Regulatory Commission The Capitol 61 Forsyth Street, SW., Suite 23T85 Tallahassee, Florida 32304 Atlanta, GA 30303-3415 Mr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Chairman Board of County Coconissioners Citrus County 110 North Apopka Avenue Iverness, Florida 34450-4245 Mr. Robert E. Grazio. Director Nuclear Regulatory Affairs (SA2A)

Florida Power Corporation Crystal River Energy Complex 15760 W. Power Line Street Crystal River, Florida 34428-6708

CRYSTAL RIVER UNIT 3 REQUEST FOR ADDITIONAL INFORMATION PROPOSED LICENSE AMENDMENT FOR LOW TEMPERATURE OVERPRESSURE PROTECTION

-1) The LTOP limits / values listed in the pro)osed TS are not adjusted for instrument uncertainties. The staff requires that . TOP TS limits / values include instrument uncertainties consistent with other setpoints in plant TS. Please include instrument uncertainties in your proposed TS limits / values.

2) Provide major assumptions used in the LTOP analysis for both heat addition and mass addition transients including reactor coolant system (RCS) temperature and volume, initial RCS pressure, power operated relief valve (PORV) relief capability, opening characteristics and stroke time, pressure signal transmission characteristics. temperature difference between the steam generator (SG) and RCS for heat addition transient, static and dynamic head considerations, etc.

3) For the limiting LTOP transients, describe the amount of transient pressure spike considered above the calculated PORV setpoint (i.e., overshoot) due to the delay of the pressure signal and stroke time of the PORV.

4) Provide quantitative discussion to demonstrate that under the conditions of RCS pressure the pressureis less than 214 asig)

/ temperature ()/T and the limits pressurizer are levelfrom still protected is less thethan 245LTOP limiting inches, transients.

5) Page 6 of the calculational summary sheet states that the PORV will provide a steam flow of 4.1 cu-ft per second at 431 psig which is far in excess of the failed open makeup control valve flow rate of 0.8 cu ft per second. Provide clarification to the above statement considering 0.8 cu-ft of water is far more ,

mass than 4.1 cu ft of steam and considering the fact that LTOP events are analyzed with the pressurizer water solid (i.e., the PORV will be relieving water not steam).

6) Discuss plant procedure available at Crystal River which assure that the operator would terminate the mass addition transient within 10 minutes of event initiation.

7) The temperature difference between the reactor coolant and the vessel metal at a distance one-fourth of the vessel wall thickness from the inside surface (i.e..

-quarter t location) should be factored into the determination of the LTOP enable temperature as is stated in Code Case N 514. Please account for this temperature difference.

8) Action statement B of proposed TS 3.4.11 uses the word " deactivated" to present potential injection from iPI pumps. Confirm that the method used to block this injection flow path is )rotected from a single failure or a single human error (e.g., Pump pull to loct and discharge valve closed). In addition confirm that the actions proposed in Action F.2.1 of Proposed TS 3.4.11 also protect against a single failure or a single human error (e.g, close the valve and remove power).

9) Provide justification for the frequency of surveillance SR 3.4.11.1. SR 3.4.11.2 and SR 3.4.11.3 which deviate from the STS.

Enclosure o

2

10) Provide a list of TS at CR 3 which enforce the limitations of plant operation assumed in the LTOP analysis.

11) You mention that if the PORV is inoperable due to the PORV itself or due to the block valve, additional controls are implemented to limit the capability to overpressurize the RCS. Makeup tank level of no greater than 88 inches will be maintained. Discuss / justify this from a pump protection perspective. l

12) Discuss how boltup temperature is calculated at CR 3. Boltup temperature should have sufficient margin to account for temperature instrument i uncertainty.

1 1

l

--- - . . . - - .. - . _ . .