ML20153D511

Requests Addl Info Re Emergency Feedwater Sys Overtemp Due to Check Valve Leaks Noted in 880706 Confirmatory Action Ltr,By 880923,in Order to Permit Review Prior to Scheduled Restart Date

ML20153D511
Person / Time
Site:	Crystal River
Issue date:	08/30/1988
From:	Berkow H Office of Nuclear Reactor Regulation
To:	Wilgus W FLORIDA POWER CORP.
References
CAL, TAC-68478, NUDOCS 8809020234
Download: ML20153D511 (4)

Text

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/ 'o,, UMTED STATES

! NUCLEAR REGULATORY COMMISSION

$ WASHINGTON. D. C. 200M August 30, 1988 k *.... / -

Docket No. 50-302 Mr. W. S. Wilgus Vice President, Nuclear Operations Florida Power Corporation ATTN: Manager, Nuclear Licensing P.O. Box 219 Crystal River, Florida 32629

SUBJECT:

CONFIRMATORY ACTION LETTER - CRYSTAL RIVER-3 EFW SYSTEM OVERTEMPERATURE DUE TO CHECK VALVE LEAKS (TAC NO. 68478)

Our Confirmatory Action Letter (CAL) dated July 6,1988 on this subject identi-fled information to be provided by Florida Power Corporation (FPC). Since that time, considerable information was furnished during the meeting of July 8, '

1988, in the submittal of July 14, 1988, and in LER 88-014-00, dated July 21, 1988. Our review of this material indicates that at this time the following matters covered by the information requested by the CAL have not yet been fully resolved. These matters should be resolved prior to restart from your planned October shutdown to repair the leaking valves as discussed in the CAL.

1. The concrete expansion anchors of pipe restraint EFH-126 were found to be pulled partially loose from their structural attachment. Piping analyses performed for piping outside containment were modeled to reflect the as-found condition based on the visual inspections. You have not provided the results of stress analyses that demonstrate the thermal conditions in the piping system that would have led to this failure. In connection with this no information has been provided to determine whether the piping attached to this restraint may have been significantly overstressed prior to the failure of EFH-126.

2. Thermal stratification in piping systems is known to result from low flow conditions. Thermal stratification can cause fatigue damage and large I

bending stresses. You should address the possibility that thermal stratification existed in the piping system as a result of the backleakage and line cooling, and address any damage to the piping that may have re-suited.

3. In response to CAL item nurber 4, you identified a nunber of reasons why you believe that the potential for water hanner was considered unaffected by the backleakage. These reasons have been reviewed, and the staff feels that FPC should provide more substantially supported arguments to resolve the question of whether a water hanner could or did occur.

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Mr. W. S. Wilgus 4. In your July 14, 1988 letter responding to the CAL, you indicated that FPC was evaluating test procedures and acceptance criteria for check valves FWV-43 and 44. FWV-43 has been identified as having a trend of poor per-formance from the standpoint of backleakage. Based on the fact that even a small backleakage through FWV-43 or -44 can result in overheating of the EFW system, you should indicate why these valves are not categorized as ASME Section XI A/C valves and tested accordingly beginning with the post-maintenance testing during the October shutdown.

5. You should discuss your reasuns for increasing the design temperature of the EFW piping and the implications of doing so.

Please provide the requested information by September 23, 1988, or earlier if i possible, in order to permit time for staff review prior to the scheduled restart date. In order to expedite receipt of your subnittal, the substance of the above natters was discussed by telephone with mercers of your staff i on August 26, 1988. '

The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 resper. dents; therefore, OMB clearance is not required under

• P.L.96-511.

Sincerely, i

Herbert N. Berkow, Project Director Project, Directorate !!-2 Division of Reactor Projects-!/II Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION

' Docket File H. Silver NRC & Local PDRs OGC PD22 Reading E. Jordan S. Varga B. Grimes G. Lainas ACRS (10)

H. Berkow Gray File D. Miller L. Marsh L

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August 30, 1988 Mr. W. $. Wilgus 4. In your July 14, 1988 letter responding to the CAL, you indicated that FPC was evaluating test procedures and acceptance criteria for check valves FWV-43 and 44. FWV-43 has been identified as having a trend of poor per-formance from the standpoint of backleakage. Based on the fact that even a small backleakage through FWV-43 or -44 can result in overheating of the EFW system, you should indicate why these valves are not categorized as ASME Section XI A/C valves and tested accordingly beginning with the post-maintenance testing during the October shutdown.

5. You should discuss your reasons for increasing the design temperature of the EFW piping and the implications of doing so.

Please provide the requested information by Septer.ter 23, 1988, or earlier if possible, in order to permit time for staff review prior to the scheduled restart date. In order to expedite receipt of your submittal, the substance of the above natters was discussed by telephone with members of your staff on August 26, 1988.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than 10 respendents; therefore, OMB cicarance is not required under

• P.L.96-511.

Sincerely, Herbert N. Berkow, Project Director Project Division, of Directorate II-2 Reactor Projects-I/II Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION 3.N

• H. Silver NRC & Local PDRs OGC PD22 Reading E. Jordan

s. Yarga D. Grimes G. Lainas ACRS (10)

H. Berkow Gray File D. Miller L. Marsh Li n ' ,

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Mr. W. S. Wilgus .

Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc:

Mr. R. W. Neiser State Planning and Development Senior Vice President Clearinghouse ,

and General Counsel Office of Planning and Budget Florida Power Corporation Executive Office of the Governor i P. O. Box 14042 The Capitol' Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301  !

Mr. P. F. McKee Mr. F. Alex Griffin, Chairman [

Director, Nuclear Plant Operations Board of County Comissioners i Florida Power Corporation Citrus County  ;

P. O. Box 219 110 North Apopka Avenue t Crystal River, Florida 32629 Inverness, Florida 36250  :

Mr. Robert B. Borsum -

Mr. E. C. Simpson  ;

Babcock & Wilcox . Director, Nuclear Site -

Nuclear Power Generation Division Florida Power Corporation Support i 1700 Rockville Pike, Suite 525 P.O. Box 219  !

Rockville, Maryland 20852 Crystal River, Florida 32629 [

t Resident Inspector

• U.S. Nuclear Regulatory Comission ,

15760 West Powerline Street I Crystal River, Florida 32629 Regional Administrator, Region II U.$. Nuclear Regulatory Comission 101 Marietta Street N.W., Suite 3100 Atlanta, Georgia 30323

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Jacob Daniel Nash (

Office of Radiation Control 1 Department of Health and l

Rehabilitative Services  ;

1317 Winewood Blvd.  !

Tallahassee, Florida 32399-0700 J

Administrator i Department of Environmental Regulation  !

Power Plant Siting Section  !

State of Florida  !

2600 Blair Stone Road [

Tallahassee, Florida 32301 L h

Attorney General r Department of Legal Affairs The Capitol Tallahassee, Florida 32304

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