ML20217K780
| ML20217K780 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 04/24/1998 |
| From: | Wigginton D NRC (Affiliation Not Assigned) |
| To: | Mcgaha J ENTERGY OPERATIONS, INC. |
| References | |
| GL-92-01, GL-92-1, TAC-MA1209, NUDOCS 9805040116 | |
| Download: ML20217K780 (7) | |
Text
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'i UNITED STATES s
j NUCLEAR REGULATORY COMMISSION
's WASHINGTON, D.C. *naas aaat
- ,o April 24, 1998 Mr. John R. McGaha, Jr.
Vice President - Operations Entergy Operations, Inc.
River Bend Station P. O. Box 220 St. Francisville, LA 70775
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY AT RIVER BEND STATION, UNIT 1 - (TAC NO. MA1209)
Dear Mr. McGaha:
Generic Letter (GL) 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural integrity" was issued in May 1995. This GL requested licensees to perform a review of their reactor pressure vessel (RPV) structural integrity assessments in order to identify, collect, and report any new data pertinent to the analysis of the structural integrity of their RPVs and to assess the impact of those data on their RPV integrity analyses relative to the requirements of Section 50.60 of Title 10 of the Code of Federal Reaulations (10 CFR Part 50.60).10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which encompass pressurized thermal hock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low s
temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits.
After reviewing your response, the NRC issued you a letter dated July 30,1996, in this letter we acknowledged receipt of your response, noted that additional RPV information may become available as a result of Owners Group efforts and requested that you provide us with the results of the Owners Groups' programs relative to your plant. We further indicated that a plant specific TAC Number may be opened to review this material. Following issuance of these letters, the BWR Vessel and intemals Project (BWRVIP) submitted the report " Update of Bounding Assessment of BWR/2 6 Reactor Pressure Vessel Integrity lasues (BWRVIP-46)." This report included bounding assessments of new data from 1) the Combustion Engineering Owners Group (CEOG) database released in July 1997, which contains all known data for CE fabricated welds in PWR and BWR vessels; 2) Framatome Technologies incorporated (FTI) analyses of Linde 80 welds which are documented in NRC inspection Report 99901300/97-01 dated January 28,1998;
- 3) FTI's analysis of electro-slag welds which was referenced in a Dresden and Quad Cities P-T limits submittal dated September 20,1996; and 4) Chicago Bridge and Iron quality assurance records. New data for one vessel fabricated by Hitachi was also included in the BWRVIP report.
The staff is requesting that you re-evaluate the RPV weld chemistry values that you have previously submitted as part of your licensing basis in light of the information presented in the CEOG, FTl and BWRVIP reports. The staff expects that you will assess this new information to determine whether any values of RPV weld chemistry need to be revised for your facility.
Therefore, in order to provide a complete response to items 2,3 and 4 of the GL, the NRC requests that you provide a response to the enclosed request for additional information (RAI) j within 90 days of receipt of this letter. If a question does not apply to your situation, please indicate this in your RAI response along with your technical basis and, per GL 92-01, Rev.1, i
Supp.1, provide a certification that previously submitted evaluations remain valid.
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9805040116 980424 PDR ADOCK 05000458 P
l John R. McGaha, Jr. The information provided will be used in updating the Reactor Vessel integrity Database (RVID).
Also, please note that RPV integrity analyses utilizing newly identified data could result in the need for license amendments in order to maintain compliance with 10 CFR Part 50.60, and
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Appendices G and H to 10 CFR Part 50, and to address any potential impact on P-T limits. If additionallicense amendments or assessments are necessary, the attached requests that you provide a schedule for such submittais.
If you should have any questions regarding this request, please contact David Wigginton at (301)-415-1301.
Sincerely, David L igginton, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects lil/lV 1
Office of Nuclear Reactor Regulation I
Docket No. 50-458
Enclosure:
As stated cc: See next page
John R. McGaha, Jr. The information provided will be used in updating the Reactor Vessel integrity Database (RVID).
Also, please note that RPV integrity analyses utilizing newly identifed data could result in the need for license amendments in order to maintain compliance with 10 CFR Part 50.80, and Appendices G and H to 10 CFR Part 50, and to address any potential impact on P-T limits. If additional license amendments or assessments are necessary, the attached requests that you provide a schedule for such submittals.
If you should have any questions regarding this request, please contact David Wigginton at (301)-415-1301.
S!ncerely, ORIGINAL SIGNED BY:
David L. Wigginton, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-458
Enclosure:
As stated cc: See next page,
' DISTRIBUTION:
Docket File PUBLIC-PD4-1 r/f -
J.Hannon C. Howes
. D. Wigginton T. Gwynn, RIV ACRS OGC (15818).
E. Adensam (EGA1)
Document Name: RBA120g.LTR
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e Mr. John R. McGahm Entergy Operations, Inc.
River Bend Station cc:
Winston & Strewn Executive Vice President and 1400 L Street, N.W.
Chief Operating Officer j
Washington, DC 20005-3502 Entergy Operations, Inc.
P. O. Box 31995 Manager-Licensing Jackson, MS 39286 Entergy Operations, Inc.
. River Bend Station General Manager-Plant Operations P. O. Box 220 Entergy Operations, Inc.
St. Francisville, LA 70775 River Bend Station P. O. Box 220 Senior Resident inspector St. Francisville, LA 70775 P. O. Box 1050 St. Francisville, LA 70775 Director-Nuclear Safety Entergy Operations, Inc.
President of West Feliciana River Bsnd Station Police Jury P. O. Box 220 j
P. O. Box 1921 St. Francisville, LA 70775 St. Francisville, LA 70775 Vice President - Operations Support Regional Administrator, Region IV Entergy Operations, Inc.
U.S. Nuclear Regulatory Commission P. O. Box 31995 611 Ryan Plaza Drive, Suite 1000 Jackson, MS 39286-1995-Arlington, TX 76011 Attorney General Ms. H. Anne Plottinger State of Louisiana 3456 Villa Rose Drive P. O. Box 94095 Baton Rouge, LA 70806 Baton Rouga, LA 70804-9095 Administrator Wise, Carter, Child & Caraway Louisiana Radiation Protection Division P. O. Box 651 P. O. Box 82135 Jackson, MS 39205 1
Baton Rouge, LA 70884-2136 f
J REQUEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY Section 10: Assessment of Best-Estimate Chemistry The staff recently received the BWRVIP report " Update of Bounding Assessment of BWR/24 Reactor Pressuns Vessel Integrity lasues (BWRVIP-46)".
Based on this information, in accordance with the provisions of Generic Letter 92-01, Revision 1, supplement 1, the NRC requests the following:
1.
An evaluation of the bounding assessment in the reference above and its applicability to the determination of the best-estimate chemistry for all of your RPV battline welds. Based upon this reevaluation, supply the information necessary to completely fill out the data requested in Table 1 for each RPV beltline weld material. If the limiting material for your vessel's P-T limits evaluation is not a weld, include the information requested in Table 1 for the limiting material also.
With respect to your response to this question, the staff notes that some issues regarding the evaluation of the data were discussed in a public meeting between the staff, NEl, and industry representatives on November 12,1997. A summary of this meeting is documented in a meeting summary dated November 19,1997, " Meeting Summary for November 12,1997, Meeting with Owners Group Representatives and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses" (Reference 1). The information in Reference 1 may be useful in helping you to prepare your response, in addition to the issues discussed in the referenced meeting, you should also consider what method should be used for grouping sets of chemistry data (in particular, those from weld qualification tests) as being from "one weld" or from multiple welds. This is an important consideration when a mean-of-the-means or coil-weighted average approach is determined to be the appropriate method for determining the best-estimate chemistry. If a weld (or welds) were fabricated as' weld qualification specimens by the same manufacturer, within a short time span, using similar welding input parameters, and using the same coil (or coils in the case of tandem arc welds) of weld consumables, it may be appropriate to consider all chemistry samples from that weld (or welds) as samples from "one weld" for the purposes of best-estimate chemistry determination. If information is not available to confirm the aforementioned details, but sufficient evidence exists to reasonably assume the details are the same, the best-estimate chemistry should be evaluated both by assuming the data came from *one weld" and by assuming that the data came from an appropriate number of" multiple welds". A justification should then be provided for eich assumption was chosen when the best-estimate chemistry was determined.
Section 2.0: P-T Limit Evaluation 2.
If the limiting material for your plant changes or if the adjusted reference temperature for the limiting material increases as a result of the above evaluations, provide the revised RT,,, value for the limiting material. In addition, if the adjusted RT,a value increased, provide a schedule for revisino the P-T limits. The schedule should ensure that compliance with 10 CFR 50 Appendix G is maintained.
ENCt.050RE l
. Reference 1.
Memorandum dated November 19,1997, from Keith R. Wu:hman to Edmund J. Sullivan,
" Meeting Summary for November 12,1997, Meeting with Owners Group Representatives and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses."
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