ML17228A255

Requests Addl Info Re GL 92-01,rev 1 within 60 Days of Ltr Date in Order to Maintain Review Schedule

ML17228A255
Person / Time
Site:	Saint Lucie
Issue date:	07/28/1993
From:	Norris J Office of Nuclear Reactor Regulation
To:	Goldberg J FLORIDA POWER & LIGHT CO.
References
GL-92-01, GL-92-1, TAC-M83505, TAC-M83506, NUDOCS 9308170416
Download: ML17228A255 (5)

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%**yW UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 28, 1993 Docket No. 50-335, 50-389 Mr. J.

H. Goldberg Executive Vice President Florida Power and Light Company Post Office Box 14000 Juno

Beach, Florida 33408-0420

SUBJECT:

ST.

LUCIE UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION GENERIC LETTER 92 01'EVISION 1 (TAC NOS.

M83505 AND M83506)

In conducting our review of your July 1, 1992, submittal relating to the above subject at the St. Lucie Units 1 and 2 sites, we have determined that we will need additional information identified in the enclosure to continue our review.

In order for us to maintain our review schedule, your response is requested within 60 days of the date of this letter.

If you cannot provide a full response within the requested time, please provide your full response schedule within 60 days of the date of this letter.

The information requested by this letter is within the scope of the overall burden estimated in Generic Letter 92-01, Revision 1,

"Reactor Vessel Structural Integrity, 10 CFR 50.54(f)."

The estimated average number of burden hours is 200 person hours for each adressee'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.

9308170416 930728 PDRII.ADDCK 05000335 P ," 'DR.';.

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July 1993 Please contact me at (301) 504-1483, if you have any questions concerning this letter.

Sincerely,

Enclosure:

As stated Original Signed By:

Jan A. Norris, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation cc w/enclosure:

See next page Distribution Docket File NRC 6 Local PDRs PDII-2 RF S. Varga G. Lainas H. Berkow E.

Tana J. Norris OGC ACRS (10)

M. Sinkule, RII OFC

,.NAME DATE LA PDII-2 ETana gal+

7/2 /93 PM:PDII-2 D:

I JNorris HBerkow 7 /~/93 7 / t'-$/93 OFFICIAL RECORD COPY FILENAME: G:RAI.SL

Mr. J.

H. Goldberg Florida Power and Light Company CC:

Jack Shreve, Public Counsel Office of the Public Counsel c/o The Florida Legislature 111 West Madison Avenue, Room 812 Tallahassee, Florida 32399-1400 Senior Resident Inspector St.

Lucie Plant U.S. Nuclear Regulatory Commission 7585 S.

Hwy AIA Jensen

Beach, Florida 34957 Mr. Joe Myers, Director Div. of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Harold F. Reis, Esq.

Newman E Holtzinger 1615 L Street, N,W.

Washington, DC 20036 John T. Butler, Esq.

Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 34982 Mr. Thomas R.L. Kindred County Administrator St.

Lucie County 2300 Virginia Avenue Fort Pierce, Florida 34982 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering, Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 St.

Lucie Plant Mr. Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700 Regional Administrator, RII U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Mr.

R.

E. Grazi o Director, Nuclear L>cens>ng Florida Power and Light Company P.O.

Box 14000 Juno

Beach, Florida 33408-0420 D. A. Sager Site Vice President P.O.

Box 128 Ft. Pierce, Florida 34954-0128

ENCLOSURE ST.

LUGIE 1

(TAC No. H83505) uestion 2a in GL 92-01 The response indicates that the initial upper shelf energy (USE) values for welds 2-203A, B,

C are not known.

Either provide the Charpy USE for each beltline weld with no documented initial USE value or provide the Charpy USE and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that all beltline welds with no documented initial USE values will meet the USE requirements of Appendix G,

10CFR 50. If this cannot be provided, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASME Code.

The response indicates that the initial USE value for the limiting

plate, C-8-2, is 103 ft-lb.

The staff believes that this initial USE value of 103 ft-lb is from longitudinal Charpy specimens, mistakenly reported as from transverse Charpy specimens.

Two sources support this conclusion:

pages 57 and 58 of report TR-F-HCH-004 labelled this USE value as "longitudinal," and Table B 3/4.4-1 of the plant's Technical Specifications listed 78 ft-lb as the "transverse" USE value of this plate.

Confirm this and update the EOL USE value for this

plate, If the updated EOL USE is below 50 ft-lb based on NRC criteria, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASHE Code.

ST.

LUCIE 2 (TAC No. H83506) uestion 2a in GL 92-01 The response indicates that the initial USE values for all beltline

welds, except for the surveillance weld, are not known.

Either provide the Charpy USE for each beltline weld with no documented initial USE value or provide the Charpy USE and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that all beltline welds with no documented initial USE values will meet the USE requirements of Appendix G,

10CFR 50. If this cannot be provided, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASHE Code.

The response indicates that the initial USE value for the limiting

plate, H-605-1, is 105 ft-lb.

The staff believes that this initial USE value of 105 ft-lb is from longitudinal Charpy specimens, mistakenly reported as from transverse Charpy specimens.

The plant's

Technical Specifications support this conclusion, where all USE values in Table B 3/4.4-1 were labelled as "longitudinal," and the least USE value recorded there was 91 ft-lb for plate M-4116-1.

The "transverse" USE value for plate M-4116-1, after applying the factor of 0.65, is 59.2 ft-lb.

Confirm this and update the EOL USE value for this new limiting plate.

If the updated EOL USE is below 50 ft-lb based on NRC criteria, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASME Code.