ML14184A916
| ML14184A916 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 02/27/1992 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | Eury L Carolina Power & Light Co |
| References | |
| TAC-M77599 NUDOCS 9203050183 | |
| Download: ML14184A916 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 February 27, 1992 Docket No. 50-261 Mr. Lynn W. Eury Executive Vice President Power Supply Carolina Power & Light Company Post Office Box 1551 Raleigh, North Carolina 27602
Dear Mr. Eury:
SUBJECT:
MATERIAL PROPERTIES FOR FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS, 10 CFR 50.61 - H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 (TAC NO. M77599)
In your letter of January 16, 1987, you stated that the H. B. Robinson Steam Electric Plant, Unit No. 2 (HBR2), surveillance weld is representative of the upper circumferential weld in the HBR2 reactor vessel.
Both were fabricated using a single arc, RACO 3, Heat 5214 weld wire with Ni-200 addition. The reported amounts of copper and nickel in the HBR2 surveillance weld are 0.34 percent and 0.66 percent, respectively. By letter dated June 19, 1987, the NRC staff issued a Safety Evaluation (SE) which concluded that you have presented acceptable evidence that the HBR2 surveillance material is representative of the HBR2 reactor vessel upper circumferential weld.
In a letter dated December 16, 1991 (Enclosure 1), the Consumers Power Company reported that for RACO 3, Heat 5214 weld wire, the mean values of copper and nickel are 0.18 percent and 1.10 percent, respectively. This chemical composition is different from the HBR2 surveillance weld.
We would like to further review the issue regarding the applicability of the copper and nickel content of the HBR2 surveillance weld to other vessel welds using the same RACO 3, Heat 5214 weld wire. In a telephone conversation on February 14, 1992, you indicated that you attributed the difference in the amount of copper to coil-to-coil variability and the difference in the amount of nickel to varying weld process parameters.
To help us assess your conclusion further, we would like to review your information supporting your conclusion regarding the differences and the documentation that demonstrates the HBR2 surveillance weld was fabricated using RACO 3, Heat 5214 weld wire. We would propose to do this review at your offices in Raleigh, NC on March 10, 1992.
9203050163 920227 PDR ADOCK 05000261 P
-3 Your cooperation in resolving this issue is appreciated. If you have any questions, please contact Mr. Ronnie Lo at 301-504-1457.
Sincerely, Orignal signed by:
Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects -I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc:
See next page DISTRIBUTION Docket File NRC & Local PDRs PD21 Reading File J. Partlow W. Russell J. Richardson S. Varga G. Lainas E. Adensam P. Anderson R. Lo OGC ACRS (10)
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Mr. L. W. Eury 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 P. 0. Box 1551 Division of Radiation Protection Raleigh, North Carolina 27602 P. 0. Box 27687 Raleigh, Nortr, Carolina 27611-7687 Mr. H. A. Cole Special Deputy Attorney General Mr. Robert P. Gruber State of North Carolina Executive Director P. 0. Box 629 Public Staff -
NCUC Raleigh, North Carolina 27602 P. 0. Box 29520 Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Mr. C. R. Dietz Resident Inspector's Office Vice President H. B. Robinson Steam Electric Plant Robinson Nuclear Department Route 5, Box 413 H. B. Robinson Steam Electric Plant Hartsviile, South Carolina 29550 P. 0. Box 790 Hartsville, South Carolina 29550 Regional Administrator, Region II U.S. Nuclear Regulatory Commission Mr. Heyward G. Shealy, Chief 101 Marietta Street Bureau of Radiological Health Suite 2900 South Carolina Department of Health Atlanta, Georgia 30323 and Environmental Control 2600 Bull Street Mr. Ray H. Chambers, Jr.
Columbia, South Carolina 29201 General Manager H. B. Robinson Steam Electric Plant P. 0. Box 790 Hartsville, South Carolina 29550
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B Slade POWERING General Manage' MICHIGAN'S PROGRESS Paiisaces Nuclear Plant 27780 Blue Star Memorial Hghpway. Covert. Ml 49043 December 16, 1991 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT PROJECTED VALUES OF RT P FOR REACTOR BELTLINE MATERIALS -
10CFR50.61 PRESSURIZED THERMAL SHOK This letter submits information required by 10CFR50.61 and responds to the September 3, 1991 NRC request for additional information concerning calculation of the fluence affecting the Palisades reactor vessel.
10CFR50.61 requires each licensee having a pressurized water reactor to submit, by December 16, 1991, projected values of RTPT$ for reactor vessel beltline materials if the value of RTPTs for any material in the beltline is projected to exceed the PTS screening criterion before the expiration date of the operating license. The Palisades operating license expires in March 2007;
- and, as shown in Enclosure 1 "Projected RTPTS Values for the Palisades Reactor Vessel", the circumferential weld is projected to exceed the screening criterion in March 2007 also and the axial welds are projected to exceed the screening criterion in November 2005. provides the bases for the projected RT values, assumptions regarding core loading patterns, the copper and nickesl contents and the fluence values used in the calculation for each beltline material. The assessment of future RTPTs values is based on chemistry data classified per the requirements of revised 10CFR50.61 as "best estimate" and thus eliminates some data points included in our previous projections which were based on "Generic" data. The enclosed projection is based on "best estimate" data and results in extending the date (compared to previous projections) when the axial welds will exceed the screening criterion and shortening the time before the circumferential welds will exceec the screening criterion. This "best estimate" method of classifying the applicable available data has been discussed with our NSSS (Combustion Ergineering) and a leading independent consultant who concur with our approacn and assumptions.
Cl,'- E:
In accordance with the requirements of 10CFR50.61(b)(4), CPCo will submit, before March 16, 1992, an analysis and schedule for implementation of a flux reduction program such as is reasonably practical to avoid exceeding the 10CFR50.61 PTS screening criterion.
An NRC letter dated September 3, 1991 requested 12 items of additional information regarding Palisades use of the DOT 4.3 transport code in our May 17, 1990 and April 17, 1991 submittals which projected the date when the 10CFR50.61 screening criterion would be exceeded. As stated in our November 11, 1991 submittal, we have withdrawn our May 17, 1990 and April 17, 1991 submittals which relied on in-house DOT 4.3 methodology and are basing our fluence estimates on Westinghouse DOT methodology. Enclosure 2 presents a description of the Westinghouse DOT methodology and addresses items 1-9 of the requested additional information as they pertain to the Westinghouse methodology. The information requested in items 10-12 apply to CPCo's use of the Palisades in-house DOT 4.3 methodology which is no longer used as a basis for our fluence estimates. Therefore, the additional information requested in items 10-12 is no longer relevant and is not addressed.
Gerald B Slade General Manager CC Administrator, Region III, USNRC NRC Resident Inspector -
Palisades Attachment
ENCLOSURE 1 Consumers Power Company Palisades Plant Docket 50-255 PROJECTED RT, VALUES FOR THE PALISADES RACTOR VESSEL DECEMBER 1991 December 1991 18 Paces