ML20249C781

Forwards RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, Issued in May 1995

ML20249C781
Person / Time
Site:	Perry
Issue date:	05/04/1998
From:	Pickett D NRC (Affiliation Not Assigned)
To:	Myers L CLEVELAND ELECTRIC ILLUMINATING CO.
References
GL-92-01, GL-92-1, TAC-MA1205, NUDOCS 9807010191
Download: ML20249C781 (9)

Text

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-g j NUCLEAR REGULATORY COMMISSION WASHINGTON D.C. 30806 0001 o% ...../ May 4, 1998 Mr. Lew W. Myers Vice President - Nuclear, Perry i Centerior Service Company P.O. Box 97, A200 Perry, OH 44081 l

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY AT PERRY NUCLEAR POWER PLANT, l UNIT NO.1 - (TAC NO. MA1205)

Dear Mr. Myers:

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 structurai 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 Regulations (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 response, the NRC issued you a letter dated August 19,1996, for the Perry Nuclear Power Plant, Unit No.1. 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 Internals Project l (BWRVIP) submitted the raport " 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)

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 4 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 k 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

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L ,; s Mr. Myers requests that you provide'a response to the enclosed request for additional information 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.

, 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 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 enclosed requests that you

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provide a schedule for such submittals. .

- if you should have any questions regarding this request, please contact me at (301) 415-1364.'

Sincerely,

' Orig'inal signed by:

Douglas V. Pickett l Senior Project Manager Project Directorate 111-3 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation

Enclosure:

As stated -

Docket No.' 50-440 DISTRIBUTION.

PUBLIC - PDill-3 R/F ,

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GGrant, R3, ADLee, EMCB BBoger .-

LI DOCUMENT NAME: G:\ PERRY \MA1205.RAI ~

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.' TA receive e copy of this document, Indicate in the box: "C" = Copy without enclosures *E" = Copy with enclosures "N* = No copy

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, Mr. Myers l 1

requests that you provide a response to the enclosed request for additional information within 90 days of receipt of this letter. If a question does not apply to your situation, please indicate j this in your RAI response along with your technical basis and, per GL 92-01, Rev.1, Supp.1, 1 provide a certification that previously submitted evaluations remain valid.

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 50.60, and i

! 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 enclosed requests that you provide a schedule for such submittals.

If you should have any questions regarding this request, please contact me at (301) 415-1364.

Sincerely, Original signed by:

Douglas V. Pickett, Senior Project Manager  ;

Project Directorate 111-3 Division of Reactor Projects - lil/IV i Office of Nuclear Reactor Regulation j l

Enclosure:

As stated l Docket No. 50-440 DISTRIBUTION. l PUBLIC PDlli-3 R/F EGA1 RBellamy -

GGr;nt, R3 ADLee, EMCB BBoger DOCUMENT NAME: G:\PERRYWIA1205.RAI Ta receive e copy of thie docurment, indcate in the box: "C" - Copy without enclosures *E" = Copy with enclosures "N" = No copy

0FFICE PM:PDIIL-3o E t'- LA:PDIII-3 (L NAME DPicket r ' EBarnhill F/v-DATE 05/ 4 /98 05/H/98  !

0FFICIAL RECORD COPY l

1 ..

Mr. Myers requests that you provide a response to the enclosed request for additional information within' 90 days of receipt of this letter. If a question does not apply to your situation, please indicate l 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.

l- 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 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 enclosed requests that you provide a schedule for such submittals.

! If you should have any questions regarding this request, please contact me at (301) 415-1364.

l Sincerely, T, V l Douglas V. Pickett, Senior Project Manager l i

Project Directorate lil-3

, Division of Reactor Projects - lil/IV l Office of Nuclear Reactor Regulation

Enclosure:

As stated l

Docket No. 50-440 l

L. Myers Perry Nuclear Power Plant, Units 1 and 2 Centerior Service Company cc:

Jay E. Silberg, Esq. James R. Williams l

Shaw, Pittman, Potts & Trowbridge Chief of Staff 2300 N Street, NW. Ohio Emergency Management Agency Washington, DC 20037 2855 West Dublin Granville Road Columbus, OH 43235-2206 Mary E. O'Reilly Centerior Energy Corporation Mayor, Village of Perry 300 Madison Avenue 4203 Harper Street Toledo, OH 43652 Perry, OH 44081 Resident inspector's Office Roy P. Lessy, Jr.

U.S. Nuclear Regulatory Commission Akin, Gump, Strauss, Hauer P.O. Box 331 and Feld, L.L.P.

Perry, OH 44081-0331 1333 New Hampshire Ave., NW.

Suite 400 Regional Administrator, Region 111 Washington, DC 20036 U.S. Nuclear Regulatory Commission 801 Warrenville Road Radiological Health Program Lisle, IL 60532-4531 Ohio Department of Health P.O. Box 118 Lake County Prosecutor Columbus, OH 43266-0118 Lake County Administration Bldg.

105 Main Street Ohio Environmental Protection Painesville, OH 44077 Agency DERR-Compliance Unit Sue Hiatt ATTN: Mr. Zack A. Clayton OCRE Interim Representative P.O. Box 1049 8275 Munson Columbus, OH 43266-0149 Mentor, OH 44060 Chairman Terry J. Lodge, Esq. Perry Township Board of Trustees 618 N. Michigan Street, Suite 105 3750 Center Road, Box 65 Toledo, OH 43624 Perry, OH 44081 Ashtabula County Prosecutor State of Ohio 25 West Jefferson Street Public Utilities Commission Jefferson, OH 44047 East Broad Street Columbus, OH 43266-0573 Henry L. Hegrat Regulatory Affairs Manager William R. Kanda, Jr., Plant Manager Cleveland Electric Illumiilating Co. Cleveland Electric illuminating Co.

Perry Nuclear Power Plant Perry Nuclear Power Plant P.O. Box 97, A210 P.O. Box 97, SB306 Perry, OH 44081 Perry, OH 44081

cc: (continued)

Donna Owens, Director Ohio Department of Commerce Division of industrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road P.O. Box 4009 Reynoldsburg, OH 43068-9009 Mayor, Village of North Perry North Perry Village Hall 4778 Lockwood Road North Perry Village, OH 44081 Attomey General Department of Attorney General 30 East Broad Street Columbus, OH 43216

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REQUEST FOR ADDITIONAL INFORMATION l l

• REACTOR PRESSURE VESSEL INTEGRITY l- PERRY NUCLEAR POWER PLANT. UNIT NO.1 DOCKET NO. 50-440 l SaGlicq.1(L Assessment of Best-Estimate Chemistry The staff recently received the BWRVIP report " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel integrity lasues (BWRVIP-46)." l 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 applic. ability to .

the determination of the best-estimate chemistry for all of your RPV beltline welds. I

- 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 lesponse to this question, the staff notes that some issues regarding the j 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 Refarence 1 may be useful in helping you to prepare your response.

i 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 I 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- l 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- l estimate chemistry should be evaluated both by assuming the data came from "one weld" and j by assuming that the data came from an appropriate number of" multiple welds." A justification  !

should then be provided for the assumption chosen when the best-estimate chemistry was ,

determined.

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Section 2.0: P-T Limit Evaluation I l

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 RTuoy value for the limiting material. In addition, if the adjusted RTuoy 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.'

Reference

1. Memorandum dat3d November 19,1997, from Keith R. Wichman 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."

Attachment:

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