ML17353A835
| ML17353A835 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point |
| Issue date: | 08/05/1996 |
| From: | Croteau R NRC (Affiliation Not Assigned) |
| To: | Plunkett T FLORIDA POWER & LIGHT CO. |
| References | |
| RTR-REGGD-01.099, RTR-REGGD-1.099 TAC-M92742, TAC-M92743, NUDOCS 9608080046 | |
| Download: ML17353A835 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 August 5, 1996 gy -250 Hr. T. F. Plunkett President - Nuclear Division Florida Power and Light Company P.O.
Box 14000 Juno
- Beach, Florida 33408-0420
SUBJECT:
CLOSEOUT FOR THE FLORIDA POWER AND LIGHT RESPONSE TO GENERIC LETTER 92-01, REVISION 1, SUPPLEHENT 1
FOR TURKEY POINT UNITS 3 AND 4 (TAC NO. H92742 AND H92743)
Dear Hr. Plunkett:
On Hay 19,
- 1995, the NRC issued Generic Letter 92-01, Revision 1, Supplement 1
(GL 92-01, Rev.
1, Supp.
1), "Reactor Vessel Structural Integrity."
In GL 92-01, Rev.
1, Supp.
1, the NRC requested that nuclear licensees perform a
review of their reactor pressure vessel structural integrity assessments in order "to identify, collect, and report any new data pertinent to [the]
analysis of [the] structural integrity of their reactor pressure vessels (RPVs) and to assess the impact of that data on their RPV integrity analyses relative to the requirements of Section 50.60 of Title 10 of the Code of Federal Regulations (10 CFR 50.60),
10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which emcompass pressurized thermal shock (PTS) and upper shelf energy (USE) evaluations),
and any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits."
Hore specifically, in GL 92-01, Rev.
1, Supp.
1, the NRC requested that addressees provide the following information in their responses:
(1) a description of those actions taken or planned to locate all data relevant to the determination of RPV integrity, or an explanation of why the existing data base is considered complete as previously submitted; (2) an assessment of any change in best-estimate chemistry based on consideration of all relevant data; (3) a determination of the need for the use of the ratio procedure in accordance with the established Position 2. 1 of Regulatory Guide 1.99, Revision 2, for those, licensees that use surveillance data to provide a
basis for the RPV integrity evaluation; and (4) a written report providing any newly acquired data as specified above and (1) the results of any necessary revisions to the evaluations of RPV integrity in accordance with the requirements of 10 CFR 50.60, 10 CFR 50.61, Appendices G and H to 10 CFR Part 50, and any potential impact of the LTOP and R-T limits in the technical specifications, or (2) a certification that previously submitted evaluations remain valid.
s 9608080046. 960805 PDR ADOCK,'05000250 P
Hr. T. F. Plunkett 2
Revised evaluations and certifications were to include consideration of Position 2. 1 of Regulatory Guide 1.99, Revision 2, as applicable, and any new data.
The information in Reporting Item (1) was to be submitted within 90 days of the issuance of the GL.
The information in Reporting Items (2) (4) was to be submitted within 6 months of the issuance of the GL.
The staff has noted that the Florida Power and Light submitted the information requested in Reporting Item (1) on August 9,
- 1995, and requested in Reporting Items (2) (4) on November 16, 1995.
Since Florida Power and Light has submitted the requested information and has indicated that the previously submitted evaluations remain valid, the staff considers the RPV integrity data for the Turkey Point Units 3 and 4 to be complete at this time and have closed TAC numbers M92742 and H92743, The staff has noted that the most recent reactor vessel integrity assessment for the Turkey Point Units 3 and 4 is covered by the scope of Babcock and Wilcox (BLW) Topical Evaluation BAW-2257, Revision 1.
This topical report was the subject of an April 30, 1996 meeting between the staff and representatives of the Babcock and Wilcox Owners Group (BWOG).
The topical report indicates that all licensees addressed in the report have determined the best estimate copper and nickel contents of their plant's beltline and surveillance welds.
The report also indicates that the ratio procedure described in Position 2. 1 (pages 1.99-3 and 1.99-4) of Regulatory Guide (RG) 1.99, Rev.
2, need not be applied to the pressurized thermal shock assessments and upper shelf energy assessments of RPV beltline welds made from Linde 80 fluxes.
At a meeting on April 30, 1996, representatives of the BWOG provided the bases for the conclusions in the topical report.
The staff informed the BWOG personnel that the information presented was insufficient to support the owners group's proposal.
The BWOG representatives indicated that the owners group would consider performing additional work to address the staff's
- concerns, and would consider submitting another topical report for NRC review.
The staff does not consider the BWOG proposal to be acceptable at this time.
The topical report also included analyses to demonstrate that application of the ratio procedure would not cause the RT values for the limiting materials in BKW fabricated RPVs to exceed the PTS screening criteria specified in 10 CFR 50.61.
However, the report did not address potential impact of applying the ratio procedure to the development of pressure-temperature limit curves and LTOP limits.
Therefore, you are requested to provide an assessment of the application of the ratio procedure, as described in Position 2. 1 of RG 1.99, Revision 2 (Hay 1988), to your pressur e-temperature limit curves and LTOP limits.
This assessment should include an
Mr. T. F. Plunkett evaluation relative to the margins specified in applicable codes and standards (i.e., Appendix G to Section III of the ASME Code).
You, are requested to provide this assessment by December 31," 1996;,, ',
Docket',Nos.
50-250 and 50-251 a
cc:
See next page Distribution Sincerely, I
i 1
Original signed by't Richard P. Croteau, Project Manager
,,Project Directorate II;3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket File; SVarga PUBLIC JZwolinski Turkey Reading ACRS Document Name:
G:TURKEY TP92742.LTR OFFICE NAME DATE LA:PDI I-3 BCla t PM:PDII-3 RCroteau t
'6 / 5 /96 OGC ee D: PDI I-3 FHebdon 96 COPY Yes No Ye No OFFICIAL RECORD COPY Yes No i.Yes No
I
Mr,. T. F. Plunkett Florida Power and Light Company Turkey Point Plant CC:
J.
R.
- Newman, Esquire
- Morgan, Lewis & Bockius 1800 M Street, N.W.
Washington, DC 20036 Jack Shreve, Public Counsel, Office of the Public Counsel c/o The Florida Legislature ill West Madison Avenue, Room 812 Tallahassee, Florida 32399-1400 John T. Butler, Esquire
- Steel, Hector and Davis 4000 Southeast Financial Center Miami, Florida 33131-2398 Mr. Robert J.
Hovey, Site Vice President Turkey Point Nuclear Plant Florida Power and Light Company P.O.
Box 029100 Miami, Florida 33102 Armando Vidal County Manager Metropolitan Dade County 111 NW 1 Street, 29th Floor Miami, Florida 33128 Senior Resident Inspector Turkey Point Nuclear Generating Station U.S. Nuclear, Regulatory Commission
,P.O.
Box 1448 Homestead, Florida 33090 Mr. Bill Passetti Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.
Tallahassee, Florida 32399-0700 Hr. Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive Tallahassee, Florida 32399-2100 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W. Suite 2900 Atlanta, Georgia 30323 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Plant Manager Turkey Point Nuclear Plant Florida Power and Light Company P. 0.
Box 029100 Miami, Florida 33102 Hr. H.N. Paduano, Manager Licensing
& Special Programs Florida Power and Light Company P.O.
Box 14000 Juno
- Beach, Florida 33408-0420 Mr. Gary E. Hollinger Licensing Manager Turkey Point Nuclear Plant P.O.
Box 4332 Princeton, Florida 33023-4332 Hr. Kerry Landis U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W. Suite 2900 Atlanta, Georgia 30323-0199
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