ML20135G010

Forwards RAI Re CP&L Request for Amending Pressure - Temperature Curves in TS for BSEP

ML20135G010
Person / Time
Site:	Brunswick
Issue date:	06/20/1997
From:	Trimble D NRC (Affiliation Not Assigned)
To:	Hinnant C CAROLINA POWER & LIGHT CO.
References
TAC-M97938, TAC-M97939, NUDOCS 9706240184
Download: ML20135G010 (5)

Text

. . . . -- . _ - . . - .-- - - - - - . - - . - . - . -- . .-._ -- -

] June 20, 1997  !

Mr. C. S. Hinnant, Vice President I Carolina Power & Light Company j Brunswick Steam Electric Plant Post Office Box 10429 Southport, North Carolina 28461 i

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING CAROLINA POWER &  !

LIGHT COMPANY'S REQUEST FOR AMENDING THE PRESSURE - TEMPERATURE CURVES IN THE TECHNICAL SPECIFICATIONS FOR THE BRUNSWICK STEAM a

ELECTRIC PLANT (TAC NO. M97938 AND M97939)

Dear Mr. Hinnant:

By Test pressure-temp Limit Curves to Add New Ones|letter dated January 7, 1997]], Carolina Power & Light Company (CP&L)

submitted requested revisions to the pressure - temperature (P-T) limits

, curves contained in the Technical Specifications for Brunswick Steam Electric l Plant (BSEP), Units 1 and 2.

I As a result of examining this submittal, the NRC staff has identified a need

, for additional information. The information is described in the enclosed request for additional information (RAI).

~

Please provide your response within 30 days of the receipt of this letter. l 4

l It should be noted that, pursuant to 10 CFR 50.60, CP&L must request an exemption to the requirements of 10 CFR Part 50, Appendix G, in order to be allowed to use Appendix A methodology of the ASME Boiler and Pressure Vessel l Code,Section XI, for calculating the BSEP P-T limits. )

4 Sincerely,

! f(Original Wigned'By) a

David C. Trimble, Project Manager i

. Project Directorate II-l Division of Reactor Projects - I/II l Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324

Enclosure:

RAI ,

/

cc w/ enclosure: See next page FILENAME - G:\BRUNSWIC\BR97938.RAI OFFICE PM:POII-1 LA:PDl! 1 D:PDI!- b 9 k _ j /

NAME DTrimble b EDunningtonhY e P (h i o o DATE 06/8/97 06/697 [ 06/Z/97 COPY /No /Yes)No he/No 0FFICIALRECORD COPY NBC fitE CENTEB COPY 9706240184 970620 PDR ADOCK 05000324 p PDR

l

. Mr. W. R. Campbell Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:

Mr. William D. Johnson Ms. Karen E. Long Vice President and Senior Counsel Assistant Attorney General Carolina Power & Light Company State of North Carolina l Post Office Box 1551 Post Office Box 629 '

Raleigh, North Carolina 27602 Raleigii, North Carolina 27602 Mr. Jerry W. Jones, Chairman Mr. Robert P. Gruber l Brunswick County Board of Commissioners Executive Director Post Office Box 249 Public Staff - NCUC

Bolivia, North Carolina 28422 Post Office Box 29520 l Raleigh, North Carolina 27626-0520 Resident Inspector U.S. Nuclear Regulatory Commission Mr. W. Levis 8470 River Road Director

.Southport, North Carolina 28461 Site Operations Brunswick Steam Electric Plant Regional Administrator, Region II Post Office Box 10429 U.S. Nuclear Regulatory Commission Southport, North Carolina 28461 Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303 Mr. William H. Crowe, Mayor City of Southport Mr. Mel Fry, Acting Director 201 East Moore Street Division of Radiation Protection Southport, North Carolina 28461 N.C. Department of Environment, Health and Natural Resources Mr. Dan E. Summers

! 3825 Barrett Dr. Emergency Management Coordinator Raleigh, North Carolina 27609-7721 New Hanover County Department of Emergency Management Mr. R. P. Lopriore Post Office Box 1525 Plant Manager Wilmington, North Carolina 28402 Carolina Power & Light Company Brunswick Steam Electric Plant Ms. D. B. Alexander Post Office Box 10429 Manager ,

Southport, North Carolina 28461 Performance Evaluation and Regulatory Affairs Public Service Commission Carolina Power & Light Company State of South Carolina 412 S. Wilmington Street Post Office Drawer 11649 Raleigh, North Carolina 27601 Columbia, South Carolina 29211 Mr. K. R. Jury Mr. Milton Shymlock Manager - Regulatory Affairs ,

U. S. Nuclear Regulatory Commission Carolina Power & Light Company Atlanta Federal Center Post Office Box 10429 61 Forsyth Street, SW, Suite 23T85 Southport, NC 28461-0429 Atlanta, Georgia 30303

4 i

i REQUEST FOR ADDITIONAL INFORMATION REGARDING THE CAROLINA POWER AND LIGHT COMPANY REQUEST TO AMEND THE TECHNICAL SPECIFICATIONS BRUNSWICK NUCLEAR PLANT. UNITS 1 AND 2:

4 PROPOSAL TO UPDATE THE PRESSURE-TEMPERATURE LIMIT CURVES '

i i Questions Reaardina Structural Intearity Associates Desian Structural Intearity Calculation Packaae CPL-420-302 -

1. Pursuant to 10 CFR 50.60, " Acceptance Criteria for Fracture Prevention

Measure for Lightwater Nuclear Power Reactors for Normal Operation,"

1 "all nuclear power reactors must meet the fracture toughness and material surveillance program requirements for the reactor coolant j pressure boundary set forth in Appendices G and H to . . .  ;

[10 CFR Part 50)." " Proposed alternatives to the described requirements i

' in Appendix G and H or portions thereof may be used when an exemption is granted by the Commission under . . [10 CFR 50.12]." ASME first 4 l incorporated Non-mandatory Appendix A into the ASME Code,Section XI in l 1992. The NRC has not yet endorsed the 1992 edition of the ASME Code l i Section XI, nor has the NRC endorsed Non-mandatory Appendix A of Section  ;

XI as an acceptable method of meeting the " Fracture Toughness '

! Requirements" of 10 CFR Part 50, Appendix G. Regarding Reference [5]

l cited on Page 2 of CPL-42Q-302:

i a.

Pursuant to 10 CFR 50.60 and 10 CFR 50.12 submit an exemption request to allow for use of Appendix A methodology of the ASME

Code,Section XI (1992 edition). l

! b. Provide Structural Integrity (SI) Calculation No. CPL-36Q-303, j Rev. O, " Comparison of ASME Code Appendix A vs. Appendix G

Methodology."

2. Regarding Page 3 of CPL-42Q-302

. a. Provide SI Report No. SIR-95-0035, Rev. O, dated April 5, 1995, to

! support the validity of the pressure-stress intensity equation (at

the top of page 3) for materials in the beltline and lower vessel j head,

b. Provide the basis for or the reference material that supports t!.e

validity of the pressure-stress intensity equation for the N16A/B j instrument nozzles.

3. Regarding the data used to calculate the adjusted reference temperatures

! (ARTS) of the Brunswick beltline weld materials fabricated from Linde

124 flux, the staff position is that plant-specific initial RT j (RTenu>) values must be used in the calculations of the ARTS oT7 Enclosure 1

e , -

i beltline weld materials if the RTNOTcu values have been established using credible drop-weight and Charpy)-V testing data in accordance with

, the ASME Code Section III, Paragraph NB-2331. The staff has noted that Structural Integrity Associates is using the generic RT value

(-56*F) fpr the Brunswick Unit 1 and 2 flange weld and $eS3ine weld materials instead of the plant-specific RT value of 10*F that was documented in CP&L's submittal to the staf[I)Y'May 13, 1994 (CP&L response to the NRC request for additional information regarding the

- CP&L response to Generic Letter (GL) 92-01, " Reactor Vessel Structural Integrity"), and in CP&L's response to GL 92-01, Revision 1, I I

Supplement 1, dated November 11, 1995.

1 2

Provide the dropweight and Charpy-V data that were used to establish a i plant-specific RT value of 10*F for the Brunswick beltline weld i materials fabricaYe'$u)from Linde 124 flux. -If the unirradiated

dropweight and Charpy-V test data for the beltline weld materials {

indicate that the largest ART of the weld materials is greater than the i ART of Brunswick N16A/B nozzles (the limiting materials used to i

, establish the P-T curves for the Brunswick RPVs), then revised P-T curves must be submitted to the staff for review.

i l

1 The Unit 1 beltline wetd materials include the circunferential welds fabricated from Heat No.1P4218 l and for the exist welds fabricated from Heat No. 53986; the Unit 2 beltline weld materials include the circunferential welds fabricated from Heat No. 3P4000 and for the axial welds fabricated from

, Heat No $3986. The weld materials for the Brunswick Unit 1 and Unit 2 vessel flanges are also

, fabricated from Heat No. $3986.

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. . jistribution:

• Docket; File-- KWichman PUBLIC ACRS JMedoff OGC PDII-1 RF SVarga l

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