ML14184B104
| ML14184B104 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 09/29/1993 |
| From: | Mozafari B Office of Nuclear Reactor Regulation |
| To: | Dietz C Carolina Power & Light Co |
| References | |
| GL-92-001, TAC-M83504 NUDOCS 9310060050 | |
| Download: ML14184B104 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 29, 1993 Docket No. 50-261 Mr. C. R. Dietz, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 Post Office Box 790 Hartsville, South Carolina 29550-0790
SUBJECT:
RESPONSE TO GENERIC LETTER 92-01, REVISION 1, "REACTOR VESSEL STRUCTURAL INTEGRITY," H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 (TAC NO. M83504)
The subject generic letter (GL) was issued on March 6, 1992, to gather information necessary to confirm that licensees and permit holders satisfy the requirements for ensuring reactor vessel integrity. In the GL, the NRC requested responses to three questions to provide information regarding: 1)
Appendix H to CFR Part 50, 2) Appendix G to 10 CFR Part 50, and 3) Commitments made in responses to GL 88-11.
By letter dated July 6, 1992, Carolina Power & Light Company ( licensee) responded to GL 92-01, Revision 1, by providing the information requested in the Required Information portion of the GL. The NRC staff has completed its initial review of your response and has determined that additional information is needed. Enclosed is a request for additional information (RAI). We request that the response to the RAI be provided within 45 days from receipt 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 addressee's response. This estimate pertains only to the identified response-related matters and does not include 9310060050 930929 PDR ADOCK 05000261 P
-2 the time required to implement actions required by the regulations. This action is covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.
Sincerely, Original Signed By:
Brenda L. Mozafari, Project Manager Project Directorate II-1 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/enclosure:
See next page DISTRIBUTION:
GDo cket=F1iz1:e!
NRC/Local PDRs PD II-1 R/F SVarga GLainas SBajwa BMozafari PAnderson D. McDonald 14-B-2 J. Strosnider 7-D-3 OGC ACRS (10)
EMerschoff, RH cc:
Plant Service list OFFICE L
PE 1:lDRPE AD:PD21:DRPE NAME PAnderson ozafari/rst SBajwa DATE
/,_ /_A 93
/;1/93
/
/93 OFFICIAL RECORD COPY DOCUMENT NAME:
G:\\ROBINSON\\ROB83504.RAI
Mr. C. R. Dietz H. B. Robinson Steam Electric Carolina Power & Light Company Plant, Unit No. 2 cc:
Mr. H. Ray Starling Mr. Dayne H. Brown, Director Manager -
Legal Department Department of Environmental, Carolina Power & Light Company Health and Natural Resources Post Office Box 1551 Division of Radiation Protection Raleigh, North Carolina 27602 Post Office Box 27681 Raleigh, North Carolina 27611-7687 Karen E. Long Assistant Attorney General Mr. Robert P. Gruber State of North Carolina Executive Director Post Office Box 629 Public Staff -
NCUC Raleigh, North Carolina 27602 Post Office Box 29520 Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Resident Inspector's Office Mr. Heyward G. Shealy, Chief H. B. Robinson Steam Electric Plant Bureau of Radiological Health Route 5, Box 413 South Carolina Department of Health Hartsville, South Carolina 29550 and Environmental Control 2600 Bull Street Regional Administrator, Region II Columbia, South Carolina 29201 U.S. Nuclear Regulatory Commission 101 Marietta St., N.W., Ste. 2900 Mr. H. W. Habermeyer, Jr.
Atlanta, Georgia 30323 Vice President Nuclear Services Department Mr. Ray H. Chambers, Jr.
Carolina Power & Light Company Plant Manager Post Office Box 1551 Carolina Power & Light Company Raleigh, North Carolina 27602 H. B. Robinson Steam Electric Plant Post Office Box 790 Hartsville, South Carolina 29550 Public Service Commission State of South Carolina Post Office Drawer 11649 Columbia, South Carolina 29211
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 Question 2a in GL 92-01 The response to GL 92-01 does not specify the unirradiated Charpy upper shelf energy (USE) values for the beltline welds 1-273A, B, C, 2-273A, B, C, 3-273A, B, C, and 11-273. Either provide the unirradiated Charpy USE for these beltline welds or provide the unirradiated Charpy USE and analysis from welds that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification as the H. B. Robinson, Unit No. 2 (HBR2) beltline welds to demonstrate that the HBR2 beltline welds will meet the requirements of Appendix G of 10 CFR Part 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.
Using the methodology in paragraph c.1 of Regulatory Guide 1.99, Revision 2, upper shell plates W10201-1 and W10201-3 have calculated upper-shelf energy values less than 50 ft-lb. In accordance with 10 CFR Part 50, Appendix G, provide an analysis to demonstrate that all beltline plates with upper-shelf energies less than 50 ft-lb will provide margins of safety against fracture that are equivalent to those required by Appendix G of the ASME Code.
Question 2b in GL 92-01 The response to GL 92-01 reports the amounts of phosphorus and sulfur for all beltline welds except for the lower circumferential weld. The source of the amounts of copper and nickel in the lower circumferential weld is identified as the Millstone-1 surveillance weld and the Robinson-2 head weld. Provide the chemical analyses from these welds and the basis for the conclusion that the lower circumferential weld has 0.17% copper and 0.92% nickel.
Provide the amounts of phosphorus and sulfur for the lower circumferential weld.
The end-of-license (EOL) fluence has been provided for the beltline plates and, by extension, the axial welds. However, there are no fluence data for the upper and lower circumferential weld seams.
Provide EOL fluences for the upper and lower circumferential welds.