BSEP-98-0184, Forwards Response to NRC 980617 RAI Re RPV Integrity for BSEP Units 1 & 2.Based on Review of Rept BWRVIP-46, Update of Bounding Assessment of BWR/2-6 RPV Integrity Issues Util Concluded That Listed Previously Submitted Info Valid

Forwards Response to NRC 980617 RAI Re RPV Integrity for BSEP Units 1 & 2.Based on Review of Rept BWRVIP-46, Update of Bounding Assessment of BWR/2-6 RPV Integrity Issues Util Concluded That Listed Previously Submitted Info Valid

ML20153E085
Person / Time
Site:	Brunswick
Issue date:	09/21/1998
From:	Jury K CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-98-0184, BSEP-98-184, TAC-MA1182, TAC-MA1183, NUDOCS 9809250323
Download: ML20153E085 (6)

Text

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CP&L Carolina Power & Light Company P.o. Box 10429 Southport, NC 28461-0429 SEP 211998 l

SERIAL: BSEP 98-0184 I

l U. S. Nuclear Regulatory Commission ATTN: Document Control Desk j Washington, DC 20555-0001 l

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2

' DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 L RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY (TAC NOS. MA1182 AND MA1183) l Gentlemen:

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By letter dated June 17,1998, the NRC requested additional information regarding reactor I

pressure vessel (RPV) integrity for Carolina Power & Light (CP&L) Company's Brunswick Steam Electric Plant (BSEP), Unit Nos. I and 2. Specifically, the NRC letter requests an impact l l assessment of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) report entitled l l " Update of Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity issues (BWRVIP-46)," on the previously submitted BSEP RPV material chemistry information.

Enclosures 1 and 2 provide CP&L's response to the requested information. Afler reviewing the p data contained within the BWRVIP-46 report, CP&L has concluded that the previously submitted BSEP RPV material chemistry information remains valid.

l This submittal does not contain any regulatory commitments. Please refer any questions regarding this submittal to Mr. Warren J. Dorman, Supervisor - Licensing, at (910) 457-2068.

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Sincerely, //

b .

Keith R. Jury jN'/[

Manager- Regulatory Affairs Brunswick Steam Electric Plant

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9809250323 980921 l

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Document Control Desk .

BSEP 98-0184 / Page 2 l

WRM/wrm

Enclosures:

1. Response To Request For Additional Information

2. Table 1. " Information Requested on RPV Weld and/or Limiting Materials" cc (with enclosures):

U. S. Nuclear Regulatory Commission, Region II l

ATIN: Mr. Luis A. Reyes, Regional Administrator i Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303  !

1 U. S. Nuclear Regulatory Commission

ATTN: Mr. Charles A. Patterson, NRC Senior Resident Inspector l 8470 River Road Southport, NC 28461-8869' D

U. S. Nuclear Regulatory Commission l ATTN: Mr. David C. Trimble, Jr. (Mail Stop OWFN 141122) 11555 Rockville Pike  !

! Rockville, MD 20852-2738 ,

I Ms. Jo A. Sanford l Chair - North Carolina Utilities Co.amission l l P.O. Box 29510 Raleigh, NC 27626-0510 l

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i ENCLOSUREl BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY (TAC NOS. mal 182 AND MAI183)

RESPONSE TO REOUEST FOR ADDITIONAL INFORMATION NRC REOUESTS:

The staff recently received the BWRVIP report " Update of Bounding Assessment of BWR2-6 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 applicability to the determination of the best-estimate chemistry for all of your RPV beltline welds. Based upon this reevaluation, supply the information necessary to completely fill out the data requested in Table I 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.

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 RTun1 value for the limiting material. In addition,if the adjusted RTsor value increased, provide a schedule for revising the P-T limits. This schedule should ensure that compliance with 10 CFR 50 Appendix G is maintained.

CP&l RESPONSE:

Backcround On May 19,1995, the NRC issued Supplement I to Generic Letter 92-01, Revision 1, " Reactor Vessel Structural Integrity." This supplement requested identification, collection, and reporting of any new data pertinent to the analysis of structural integrity and the assessment of the impact of that data on reactor pressure vessel (RPV) integrity analyses relative to the requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable.

Carolina Power & Light (CP&L) Company provided information applicable the to Brunswick Steam Electric Plants (BSEP), Units 1 and 2, in letters dated August 17,1995 (Serial:

El-1

BSEP 95-0381), and November 16,1995 (Serial: BSEP 95-0572). Subsequently, by letter dated December 23,1996, the NRC found acceptable CP&L's response for BSEP, Units 1 and 2, to '

Generic Letter 92-01, Revision 1, Supplement 1.

By letter dated June 17,1998, the NRC requested additional information regarding RPV integrity for BSEP, Units 1 and 2. Specifically, the NRC letter requests an impact assessment of the Boiling Water Reactor Vessel and Intemals Project (BWRVIP) report entitled " Update of j Bounding Assessment of BWR/2-6 Reactor Pressure Vessel Integrity Issues (BWRVIP-46)," on the previously submitted BSEP RPV material chemistry information.

Response

Within the November 16,1995, CP&L response to Generic Letter 92-01, Revision 1, Supplement 1 (i.e., Enclosures 2 and 3 of the November 16,1995, letter), CP&L provided the results of an comprehensive data gathering effort defining the best estimate chemistries for BSEP, Units 1 and 2, RPV weld materials. The November 16,1995, response demonstrated that chemistry variability was not an issue for the identified weld heats. The BWRVIP-46 report contains no new data having an impact on the previously submitted chemistry values for BSEP, Unit 3 I and 2. Therefore, this response does not revise the RPV weld chemistry information for BSEP, Units land 2.

Enclosure 2 of this letter provides the information requested in Table 1 of the NRC's June 17, 1998, request. The informatien provided in Table I contains data on the limiting base and weld materials for BSEP, Units 1 and 2, RPVs; however, the limiting RPV material for BSEP, Units 1 and 2, relative to RT, are the N16A/B forged nozzles.

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ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR PRESSURE VESSEL INTEGRITY (TAC NOS. mal 182 AND mal 183)

TABLE 1.

"INFORMATION REOUESTED ON RPV WELD AND/OR I.lMITING MATERIALS"

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TABLE 1 Facility: Brunswick Steam Electric Plants (BSEPL Units I and 2 l Vessel Manufacturer: Chicano Bridge & Iron  !

Information Requested on RPV Weld and/or Limiting Materials -

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BSEP, Unit No.1 -

Component RPV "Best "Best End Of Life Assigned Method of Initial o, o3 Margin ' ART or Weld Estimate" Estimate" (EOL)Inside Material Determining RTsor RTsorat ,

Wire Copper Nickel Dimension Chemistry CF2' (RTuorm3) EOL lleat") (ID) Fluence Factor (CF) .

(x 10")  ;

i N16A/B Q2QlVW 0.16 0.82 0.052 123.2 Table 48 0 17 34.00 119 i Nozzles

, Weld IP4218 0.06 0.87 0.106 82.0 Table 10 0 17.6 35.15 80 BSEP, Unit No. 2 l Component RPV "Best "Best End Of Life Assigned Method of Initial a, Margin ART or i o3 Weld Estimate" Estimate" (EOL)Inside Material Determining RTsor RTsorat ,

Wire Copper Nickel Dimension Chemistry CF23 (RTworx3) EOL

[

lleat") (ID) Fluence Factor (CF)  ;

(x 10) {

N16A/B Q2QlVW 0.16 0.82 0.050 123.2 Table 40 0 17 34.00 110 Nozzles l Weld S3986 0.05 0.96 0.089 68.0 Table 10 0 13.4 26.79 64 .

o Table Notes:

(1) Or the material identification of the limiting material as requested in Section 1.0 (1.)

(2) Determined from tables or from surveillance data. [

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