ML20217K753
| ML20217K753 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/27/1998 |
| From: | Donohew J NRC (Affiliation Not Assigned) |
| To: | Hagan J ENTERGY OPERATIONS, INC. |
| References | |
| GL-92-01, GL-92-1, TAC-MA1191, NUDOCS 9805040104 | |
| Download: ML20217K753 (7) | |
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NUCLEAR RESULATORY COMMISSION 2
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April 27, 1998 Mr. Joesph J. Hagan Vice President, Operations GGNS Entergy Operations, Inc.
P. O. Box 756 Port Gibson, MS 39150
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY AT GRAND GULF NUCLEAR STATION - (TAC NO. MA1191)
Dear Mr. Hagan:
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 p eactor 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 shock (PTS) and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure (LTOP) limits or pressure-temperature (P-T) limits.
After reviewing your responses, dated August 14,1995, (GNRO-95/00091) and November 20, 1995, (GNRO-95-00125), the NRC issued you a letter dated August 22,1996. In this letter we acknowledged receipt of your responses, 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. The letter closed out the staff's actions 1
related to the GL; however, we 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 issues (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) Frematome
/
Technologies incorporated (FTI) analyses of Linde 80 welds which are documented in NRC inspection Report 99901300/97-01 dated January 28,1998; 3) FTl's analysis of electro-stag
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welds which was referenced in a Dresden and Quad Cities P-T limits submittal dated September
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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 wold 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 (RAl) 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, Supp.1, provide a certification that previously submitted evaluations remain valid.
9905040104 990427 PDR ADOCK 05000416 P
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-4 Joseph J. Hagan The information provided will be used in updating the Reactor Vessel Integrity Database (RVID).
Also, please note that RPV integrity analyses utilizing newly identifM data could result in the need for license amendments in order to maintain compliance with 10 CFR Part 50.60, 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 Jack Donohew at (301)-415-1307.
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Jack N. Dono
, Sen' r Project Manager r
Project Directorate IV-1 Division of Reactor Projects ill/IV f.
Office of Nuclear Reactor Regulation i
a Docket' No. 50-416 l
Enclosure:
As stated cc: See next page i
i DISTRIBUTION:
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J.Donohew T. Gwynn, RIV ACRS OGC (15818)
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DATE f/ l/98 4M3/98 k/N /98 COPY YES/NO YES/NO YES/NO OFFICIAL RECORD COPY -
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Joseph J. Hagan 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 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 submittals.
If you should have any questions regarding this request, please contact Jack Donobew at (301)-415-1307.
Sincerely,
)
1 ack hon ior Project Manager Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
As stated cc: See next page
l Mr. Joseph J. Hagan l
Entergy Operations, Inc.
Grand Gulf Nuclear Station ec:
Executive Vice President General Manager, GGNS
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc.
P. O. Box 756 P. O. Box 31995 Port Gibson, MS 39150 Jackson, MS 39286-1995 Attomey General Wise, Carter, Child & Caraway Department of Justice P. O. Box 651 Stats of Louisiana l
Jackson, MS 39205 P. O. Box 94005 Baton Rouge, LA 70804-9005 Winston & Strawn 1400 L Street, N.W. - 12th Floor State Health Officer Washington, DC 20005-3502 State Board of Health P. O. Box 1700 Director Jackson, MS 39205 Division of Solid Waste Management Mississippi Department of Natural Office of the Govemor Resources State of Mississippi P. O. Box 10385 Jackson, MS 39201 Jackson, MS 39209 Attomey General President, Asst. Attomey General Claibome County Board of Supervisors State of Mississippi P. O. Box 339 P. O. Box 22947 Port Gibson, MS 39150 Jackson, MS 39225 Regional Administrator, Region IV Vice President, Operations Support U.S. Nuclear Regulatory Commission Entergy Operations, Inc.
611 Ryan Plaza Drive, Suite 1000 P.O. Box 31995 Ariington, TX 76011 Jackson, MS 39286 1995 Senior Resident inspector Director, Nuclear Safety U. S. Nuclear Regulatory Commission and Regulatory Affairs Route 2, Box 399 Entergy Operations, Inc.
Port Gibson, MS 39150 P.O. Box 756 Port Gibson, MS 39150
i i
REQUEST FOR ADDITIONAL INFORMATION REACTOR PRESSURE VESSEL INTEGRITY i
Section 1.Q; Assessment of Best-Estimate Chemistry The staff recently received the BWRVIP report " Update of Bounding Assessment of BWR/2 6 Reactor Pressure Vessel integrity issues (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 apphcability to the determination of the best-estimate chemistry for all of your RPV beltime welds. Based i
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 wold, 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 i
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, 1
using similar welding input parameters, and using the same coil (or coils in the case of tandem are 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 suffcient 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 which 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 temperatue 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 RTa value increased, provide a schedule for revising the P-T limits. The schedule should ensure that compliance with 10 CFR 50 Appendix G is maintained.
ENCLOSURE
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Reference 1.
Memorandum dated November 19,1997, from Keith R. Wichman to Edmund J. Sullivan, l
" Meeting Summary for November 12,1997, Meeting with Owners Group Representatives l
and NEl Regarding Review of Responses to Generic Letter 92-01, Revision 1, Supplement 1 Responses."
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