ML20056H100

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Requests Addl Info Re Util Response to GL 92-01,rev 1, Reactor Vessel Structural Integrity,10CFR50.54(f). Response Required within 60 Days of Ltr Date
ML20056H100
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 08/19/1993
From: Silver H
Office of Nuclear Reactor Regulation
To: Beard P
FLORIDA PROGRESS CORP.
References
GL-92-01, GL-92-1, TAC-M83731, NUDOCS 9309080228
Download: ML20056H100 (4)


Text

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A i E UNITED STATES  !

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! NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 l

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..... August 19, 1993 l t

Docket No. 50-302 r

f Mr. Percy M. Becrd, Jr.  ;

Senior Vice President, '

Nuclear Operations Florida Power Corporation ATTN: Manager, Nuclear Operations  !

Licensing i P. O. Box 219-NA-21 i Crystal River, Florida 32629  :

Dear Mr. Beard:

SUBJECT:

CRYSTAL RIVER UNIT 3 - REQUEST FOR ADDITIONAL l INFORMATION - GENERIC LETTER 92-01, REVISION 1  ;

(TAC NO. M83731)

We have completed our initial review of your June 25, 1992, $

submittal relating to the above subject at Crystal River i Unit 3, and have determined that we will need additional information identified in the enclosure to continue our - i review. In order for us to maintain our review schedule, your response is~ requested within 60 days of the date of this letter. l The information requested by this letter'is within the scope '$

of tne overall burden estimated in Generic Letter 92-01,  !

Revision 1, " Reactor Vessel Structural Integrity, 10 CFR l

50. 54 (f) . " The estimated average number of burden hours is {

200 person hours for each addressee's response. This  ;

estimate pertains only to the identified response-related  ;'

matters and does not include the time required to implement actions required by the regulations. This action is covered ,

by the Office of Management and Budget clearance Number 3120-0011, which expires June 30, 1994.  ;

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-2 - f Please contact me at (301) 504-1475 if you have any questions concerning this letter.  ;

Sincerely, (Original Signed By) i Harley Silver, Project Manager l Project Directorate II-2 l Division of Reactor Projects - I/II ,

Office of Nuclear Reactor Regulation i l

Enclosure:

As stated .

cc w/ enclosure: l See next page l Distribution Docket-File- l NRC & Local PDRs PDII-2 RF  ;

S. Varga ,

G. Lainas H. Berkow E. Tana l H. Silver OGC ACRS (10)  ;

M. Sinkule, RII e OFC LA:PDII-2 PK:h D:PDII-2 NAME ETanafff [ Hb [ '

DATE 7/ 29/93 [//9/93 $ //4) / 93 i OFFICIAL RECORD COPY'i  ;

FILENAME: G:RAI.CR e

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f Mr. Percy M. Beard Crystal River Unit No.3  !

Florida Power Corporation Generating Plant CC. [

Mr. Gerald A. Williams Mr. Joe Myers, Director Corporate Counsel Div. of Fmergency Preparedness i Florida Power Corporation Department of Community Affairs ,

MAC-A5A 2740 Centerview Drive P. O. Box 14042 Tallahassee, Florida 32399-2100 i St. Petersburg, Florida 33733

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Mr. Bruce J. Hickle, Director Chairman Nuclear Plant Operations Board of County Commissioners Florida Power Corporation Citrus County P. 0. Box 219-NA-2C 110 North Apopka Avenue ,

Crystal River, Florida 34423-0219 Inverness, Florida 32650 Mr. Robert B. Borsum Mr. Rolf C. Widell, Director  !

B&W Nuclear Technologies Nuclear Operations Site Support 1700 Rockville Pike, Suite 525 Florida Power Corporation ,

Rockville, Paryland 20852 P. O. Box 219-NA-21  !

Crystal River, Florida.34423-0219 [

Regional Administrator, Region 11 '

U. S. Nuclear Regulatory Commission Senior Resident Inspector l 101-Marietta Street N.W., Suite 2900 Crystal River Unit 3  :

Atlanta, Georgia 30323 U.S. Nuclear Regulatory j Commission '

Mi . Bill Passett i 6745 N. Tallahassee Road Office of Radiation Control Crystal River, Florida 34428 -

Department of Health and l Rehabilitative Services Mr. Gary Boldt 1317 Winewood Blvd. Vice President - Nuclear l Tallahassee, Florida 32399-0700 Production {

Florida Power Corporation i Administrator P.O. Box 219-SA-2C ,

Department of Environmental Regulation Crystal River, Florida 34423-0219 l Power Plant Siting Section i State of Florida j 2600 Blair Stone Road Tallahaseee, Florida 32301 Attorney General l Department of Legal Affairs The Capitol Tallahassee, Florida 32304 j i

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ENCLOSURE '

Crystal River 3 (TAC Nn, M83731)

Question 2a in GL 92-01 i

The response to GL 92-01 indicates that the end-of-life (E0L) upper-shelf energy (USE) value for the limiting weld WF-70 will fall below the screening criterion of i 50 ft-lb. An owners group report on USE equivalent margin analysis regarding i beltline welds with low USE values for Levels A & B is under preparation by the  :

Babcock & Wilcox Owners Group (BWOG); a similar BWOG report for Levels C & D (BAW-2178P) is under NRC review now. The licensee must confirm that these two topical ,

reports will be used as its licensing bases to demonstrate that all beltline welds  !

will meet the USE requirements of Appendix G,10CFR 50. -

Question 2b in GL 92-01 The response indicates that a generic initial RT 7 of -5 F, which is the mean RT value for 34 Linde 80 welds (BAW-1803, Revision 1), has been used for all wefdsexcepttheweldWF-70. Provide justification for not using the generic mean value for Linde 80 welds of 0 F as required by 10 CFR 50.61.

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