ML20141G461

Forwards Final Results of CEOG Task 902 Best Estimated Copper & Nickel Weld Values for DPC C-E Fabricated Vessels, in Response to GL 92-01,Rev 1,Suppl 1

ML20141G461
Person / Time
Site:	Mcguire, Catawba, McGuire
Issue date:	07/03/1997
From:	Tuckman M DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, TAC-M92659, TAC-M92660, TAC-M92694, TAC-M92695, NUDOCS 9707080137
Download: ML20141G461 (9)

Text

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.. ll l "M Af.S Tuarva fa j kni ! Mce he&nt Charicite, NC282011006 NuclearGenemon (704)38722000 nice (701)3824360 Fax

) DUKEPOWER July 3,1997 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk ,

Washington, D.C. 20555 l

Subject:

Catawba Nuclear Station Units 1 & 2  !

Docket Nos. 50 -413, 414 TAC Nos. M92659 & M92660 McGuire Nuclear Station Units 1 & 2 i Docket Nos. 50 -369, 370 l TAC Nos. .M92694 & M92695 l Generic Letter 92-01, Revision 1, Supplement 1 l Request for Additional Information Concerning Data That Resulted From the Owners Groups' ]

Reactor Vessel Integrity Programs In the Closecut Letters for Generic Letter 92-01, Revision 1, Supplement 1, dated July 29, 1996 for Catawba Nuclear Station and July 31, 1996 for McGuire Nuclear Station, the NRC requested that Duke provide the results of the ongoing Owners Groups' RPV integrity programs relative to our plants.

The NRC was specifically referring to Task 902 of the C-E Owners Group (CEOG), Reactor Vessel Working Group (RVWG).

In Task 902, the CEOG went back through the manufacturing logs and all other known test data and developed best estimated copper and nickel values for all C-E fabricated reactor vessel welds. McGuire Unit 1 and Catawba Unit 2 reactor vessels were fabricated by C-E. This work has been completed and reviewed. There are no changes that would significantly impact Duke Power. ,

The final results of the CEOG Task 902 best estimated hkCOI /

copper and nickel weld values for the Duke Power C-E fabricated vessels are attached. The results of CEOG Task 902 confirm that Duke was using appropriate values that are 9707000137 970703 PDR ADOCK 05000369' P PDR lllllllllfllll llll l

. s U.S. NRC July 3,1997 Page 2 within the recommended range of final C-E values and are bounded by the specific recommended CEOG values. Duke has concluded that there is no need to make revisions to the previously submitted evaluations concerning reactor pressure vessel integrity and that the LTOP and P-T limits in the Technical Specifications remain valid. These evaluations were in accordance with the requirements of 10 CFR 50.60, 10 CFR 50.61 and Appendices G and H to 10 CFR Part 50.

Should you have any questions or require any additional information regarding this subject, please call Allison Jones-Young at (704) 382-3154.

Very truly yours,

. . [\ VLYM-M.S. Tuckman Senior Vice President Nuclear Generation Enclosures xc: L.A. Reyes Regional Administrator, Pegion II V. Nerses, ONRR P.S. Tam,'ONRR S.M. Shaeffer Senior Resident Inspector (MNS)

R.J. Freudenberger Senior Resident Inspector (CNS)

A

ENCLOSURE 1 TIIIS ENCLOSURE PROVIDES TIIE INFORMATION REQUESTED IN SUPPLEMENT 1, REVISION 1 OF GENERIC LETTER (GL) 92-01 CLOSE OUT LETTER FOR MCGUIRE UNIT 1.

McGuire Unit ~1'And Sister Plant Weld Information for Lower Shell Long.

Seams,~3-442 A, B & C (Heat No. 21935 and 12008, Linde 1992 Flux) '

Plant Component Data Pt.- Wt% Wi%. Reference

. No. -Cu Ni- l McGuire 1 Lwr. Shell Long Weld I,2 Salem 2 Lwr. Shell Long Weld 3 C-E MML Supplemental Test 1 0.20 8-0,86 4, 5 Analysis C-E MML Supplemental Test 2 0.22 6 Analysis Diablo Canyon 2 Inter. Shell Long. Weld 7 Diablo Canyon 2 Upr. Shell Long. Weld 8 Diablo Canyon 2 Beltline Weld Repair 3 0.23 0.90 9,10 Diablo Canyon 2 Beltline Weld Repair 4 0.21 0.76 9,10 Diablo Canyon 2 Beltline Weld Repair 5 0.22 0.90 9,10 Average Chemistry (Beltline Weld Repair) 0.22 0.85 Diablo Canyon 2 Surveillance Weld 6 0.22 0.83 11 Diablo Canyon 2 Surveillance Weld 7 0.219 0.86 12 Diablo Canyon 2 Surveillance Weld 8 0.212 0 88 12 i Diablo Canyon 2 Surveillance Weld 9 0.213 0.90 12 Diablo Canyon 2 Surveillance Weld 10 0.225 0.875 13 Diablo Canyon 2 Surveillance Weld 1I 0.213 0.856 13 Diablo Canyon 2 Surveillance Weld 12 0.225 0.877 13 Diablo Canyon 2 Surveillance Weld 13 0.196 0.763 14 Diablo Canyon 2 Surveillance Weld 14 0.240 0.958 14 Diablo Canyon 2 Surveillance Weld 15 0.230 0.910 14 Surveillance Weld Average 0.22 0.87 mm SOverall' Average t , -. 4 ,. & t 0.221 70.86; > -

• note: During the CEOG review it was discovered that the 0.86% Ni value referenced in the Salem report is actually an averaged value, not a data point from D7525 as stated. The weighted average above still remains the same once this value is dropped.

CEOG Task 902 Values (Referer.ce 36):

Heat No. 21935 and 12008, Linde 1092 Flux Sample weighted mean: 0.213% Cu and 0.867% Ni i 1

j

l McGuire Unit 1 And Sister Plant Weld Information for Intermediate Shell

~ Lo'ng. Seams,2-442 A, B & C (Heat No. 20291 and 12008, Linde 1992 Flux) l l Plant Component . Data Wt% Wt% Reference Pt.# .Cu Ni McGuire ! Int. Shell Long Weld 15,16,1 Calvert Cliffs 1 Int. Shell Long Weld 7 McGuire i Supplemen'.al Test 1 0.19 0.89 17 McGuire 1 Surveillance Weld 2 0.21 0 88 18 McGuire 1 Surveillance Weld 3 0.20 0.91 19 McGuire i Surveillance Weld 4 0.20 0.87 20,21 McGuire i Surveillance Weld 5 0.19 0.85 20,21 McGuire 1 Surveillance Weld 6 0.19 0.86 20,21 McGuire 1 Average 0.20 0.88 Pilgrim 1 CVN Specimen Y4A 7 0.14 0.81 22,23 Pilgrim 1 CVN Specimen Y45 8 0.16 0.81 22,23 Pilgrim i CVN Specimen Y5M 9 0.17 0.78 22,23 Pilgrim i CVN Specimen Y6U 10 0.17 0.81 22,23 Pilgrim i CVN Specimen Y6Y l1 0.16 0.77 22,23 Pilgrim i CVN Specimen Y61 12 0.16 0.79 22,23 Pilgrim 1 CVN Specimen Y65 13 0.17 0.80 22,23 Pilgrim 1 CVN Specimen Y66 14 0.16 0.77 22,23 Pilgrim i CVN Specimen Y4A 15 0.16 0.79 22,23 Pilgrim 1 CVN Specimen Y4A 16 0.16 0.81 22,23 Pilgrim i ID, Surveillance Weld 17 0.17 0.98 23,24 Pilgrim I ID, Surveillance Weld 18 0.16 0.94 23,24 Pilgrim i T/4, Surveillance Weld 0.16 0.96 23,24 19 ..~

Pilgrim 1 T/4, Surveillance Weld 20 ul3 0.72 23,24 Pilgrim 1 T/4, Surveillance Weld 21 a19 0.86 23,24 Pilgrim 1 T/2, Surveillance Weld 22 0.17 0.76 23,24 Pilgrim 1 T/2, Surveillance Weld 23 0.16 0.79 23,24 Pilgrim 1 3T/4, Surveillance Weld 24 0.18 0.93 23,24 Pilgrim 1 3T/4, Surveillance Weld 25 0.17 0.95 23,24 Pilgrim 1 3T/4, Surveillance Weld 26 0.19 0.83 23,24 Pilgrim 1 OD, Surveillance Weld 27 0.17 0.97 23,24 Pilgrim i OD, Surveillance Weld 28 0.13 0.74 23,24 Pilgrim 1 Average 0.16 0.84 Overall Average 0.18 l 0.86 CEOG Task 902 Values (Reference 36):

Heat No. 20291 and 12008, Linde 1092 Flux j Sample weighted mean: 0.199% Cu and 0.846% Ni

l McGuire Unit 1 And Sister Plant Weld Information for Intermediate To Lower Shell Circumferential Weld,9-442 (IIcat No. 83640, Linde 0091 Flux)

Plant Component - Data Pt. Wt% Wi% Reference No. Cu Ni j Almarez 1 Surveillance Weld 1 .05 .120 25 l D-12745 2 .05 ---

26 D-23725 3 .06 .04 7 D-14090 4 .05 --

27 McGuire 1 Int / Lwr. Shell Cire. Weld 28 Farley 2 Lwr. Shell Long. Weld 29 Overall Average 0.05 0.08 i

_CEOG Task 902 Values (Reference 36_);

Heat No. 83640, Linde 0091 Flux Simple mean: 0.051% Cu and 0.096% Ni

4 ENCLOSURE 2 Tills ENCLOSURE PROVIDES TIIE INFORMATION REQUESTED IN SUPPLEMENT 1, REVISION 1 OF GENERIC LETTER (GL) 92-01 CLOSE OUT LETTER FOR CATAWBA UNIT 2.

Catawba Unit 2 The Catawba Unit 2 reactor pressure vessel was manufactured by C-E in Chattanooga, Tennessee.

The vessel was ordered by Westinghouse Electric Corporation under C-E Contract 8871. The weld wire (not Cu coated) used to fabricate the beltline welds was low in Cu and Ni content. As a result of the low Cu/Ni weld in the Catawba Unit 2 vessel, it is plate limited for 10 CFR 50.61 RTPTS at EOL and is plate controlled for the current P-T limit curves and LTOP analysis. The most limiting weld material calculated EOL RTPTS using surveillance capsule data is 4.5 F which is over 200 F below the 10CFR50.61 screening criteria. With these low EOL RTPTS values and plate limited critical material, this additional information is oflittle value for detennining the structural integrity of the reactor vessel since it is controlled by the plate properties.

] Catawba Unit 2 Beltline Weld Material (IIcat No. 83648, Linde 0091 Flux)

Plant _ Component - Data Pt.' Wt % - Wt % Reference No. Cu Ni Catawba 2 Surveillance Program i 0040 o. I 40 37,39 Catawba 2 Surveillance Program 2 0.036 0.140 37,39 Catawba 2 Surveillance Program 3 0 051 0.180 37,40 CE Original Weld Cert. Job Number D32255 0.040 37,41 Overall Combined Average l 0.042 l 0.153 l l 4

CEOG Task 902 Values (Reference 36h Heat No. 83648, Linde 0091 Flux Simple mean: 0.042% Cu and 0.136% Ni

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l l

i REFERENCES

1. Weld Inspection Record, Combustion Engineering Contract & Unit No. 2167, Seam No. 3-442 A, February 24,1970.

2. Weld inspection Record, Combustion Engineering Contract & Unit No. 2167 Seam No. 3-442 B, February 24,1970.

l l 3. Response to Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity, 10CFR50.54(f), Salem Generating Station Unit Nos. I and 2, Public Service Electric & Gas Company, June 30,1992.

4. Salem Units 1 & 2, Reactor Vessel Weld Data, Combustion Engineering Report Prepared for Public Service Electric & Gas Co, November 1985.

5. Welding Materials Qualifications to Requirements of ASME, Section 111, Wire Heat No.

21935 & 12008, Sample No. D-7525, Combustion Engineering Metallurgical Research and Development Department, October 27,1969.

6. Welding Materials Qualifications to Requirements of ASME, Section Ill, Wire Heat Nos.

21935 & 12008, Sample No. D-7278, Combustion Engineering Metallurgical Research and Development Department, August 12,1969.

7. RPVDATA Reactor Vessel Materials Database, developed by ATI Consulting, Version 1.2, August 28,1995.

8. Evaluation of Diablo Canyon Pmver Plant Reactor Vessel Materials by the NRC Pressurized Thermal Shock Screening Criteria, Pacific Gas and Electric Department of Engineering Research, Report 420-85.687, Revision 1, January 13,1986.

9. Evaluation of Diablo Canyon Units I and 2 Reactor Vessel Beltline Weld Chemistry, Westinghouse Electric Corp., WCAP-10472, Septembcr 1983.

10.WCAP-10755,"Diablo Canyon Unit 2 Flux Reduction Program for Reactor Vessel Integrity Phase 1," R.L. Turner, et al., Westinghouse Electric Corp., July 1995.

I 1. Pacific Gas and Electric Company Diablo Canyon Unit No. 2 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-8783, December 1976.

12. Analysis of Capsule U from the Pacific Gas and Electric Company Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-11851, May 1988.

13. Analysis of Capsule X from the Pacific Gas & Electric Company Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-12811, December 1990.

14.WCAP-14363," Analysis of Capsule Y from the Pacific Gas and Electric Company Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program," E. Terek, et al., May 1995.

a

15. Weld Inspection Record, Combustion Engineering Contract & Unit No. 2167, Seam No. 2-442'B, April 22,1969.

. 16. Weld Inspection Record, Combustion Engineering Contract & Unit No. 2167, Seam No. 2-442 C, April 22,1969.

17." Chemical Analysis of Weld Metal Specimens for Baltimore Gas & Electric Company,"

Wylie Laboratories Report No. 40602-04, July 27,1989.

18. Duke Power Company William B. McGuire Unit No.1 Reactor Vessel Surveillance Program, Westinghouse Electric Corp., WCAP-9195, November 1977.

19 Analysis of Capsule U from the Duke Power Company McGuire Unit i Reactor Vessel

! Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-10786, February 1985.

20. Evaluation of Pressurized Thermal Shock for McGuire Unit 1, Westinghouse Electric Corp.,

WCAP-13948, May 1994.

21. Westinghouse Electric Corporation Nuclear Service Division CMT- Analytical Laboratory, i Waltz Mill Site, Analytical Request #15211, Alloy Analysis - Steel, Duke Power Company McGuire Nuclear Plant Unit 1, Lawrence Kardos, November 15,1993.

22.Perrin, J.S., et al.," Evaluation of Mechanical Properties of Unitradiated Specimens from Pilgrim Unit No.1,"Battelle Columbus Laboratories, October 1979.

23." Reactor Vessel Weld Metal Chemical Composition Variability Study for Baltimore Gas &

Electric Company," B&W Nuclear Technologies, BAW-2220, June 1995.

24. " Pilgrim Surveillance Program Weld Documentation", Combustion Engineering, Report No.

B-PENG-ER-002, February 1994.

25. Weld inspection Record, Combustion Engineering Contract & Unit No. 2167, Seam No. 9-442, September 17,1972.

26. Central Nuclear de Almarez, Almarez Unit No.1 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-8819, December 1976.

27. Welding Materials Quali0 cations to Requirements of ASME, Section lit, Wire Heat No.

83640, Sample No. D-12745, Combustion Engineering Metallurgical Resem ;a a nd Development Department, August 17,1972.

28. Welding Materials Quali0 cations to Requirements of ASME,Section III, Wire Heat No. l 83640, Sample No. D-23725, Combustion Engineering Metallurgical Research and Development Department, March 25,1976.

29. Welding Materials Quali0 cations to Requirements of ASME, Section 111, Wire Heat No.

83640, Sample No. D-14090, Combustion Engineering Metallurgical Research and Development Department, January 30,1973.

30. WCAP-13763," Evaluation of Pressurized Thermal Shock For Catawba Unit I", P.A. Peter, dated August 1993. Submitted to the NRC by letter dated August 12,1993.

1

31. An'alysis of Capsule U from the Duke Power Company McGuire Unit 1 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-10786, February 1985.

32. Analysis of Capsule X from the Duke Power Company McGuire Unit 1 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-12354, August 1989.

J J 33. Evaluation of Diablo Canyon Units I and 2 Reactor Vessel Beltline Weld Chemistry.

Westinghouse Electric Corp., WCAP-10472, September 1983.

34. Analysis of Capsule V Specimens and Dosimeters and Analysis of Capsule Z Dosimeters from the Duke Power Company McGuire Unit 1 Reactor Vessel Radiation Surveillance Program, Westinghouse Electric Corp., WCAP-13949, February 1994.

35. WCAP-13518," Evaluation of Pressurized Thermal Shock For McGuire Unit 2", J. M.

Chicots, dated October 1992.

36. CE NPSD - 1039 Rev.1, Final Report,"Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds", CEOG Task 902, Prepared for the C-E Owners Group, April 1997,

37. WCAP-13874," Evaluation of Pressurized Thermal Shock For Catawba Unit 2", P.A. Peter, 2

dated February 1994. Submitted to the NRC by letter dated March 2,1994.

l 38. WCAP-13875," Analysis of Capsule X From the Duke Power Company Catawba Unit 2 Reactor Vessel Radiation Surveillance Program", E. Terek, S. L. Zawalick, A. Madeyski, P.A.

Peter, dated February 1994. Submitted to the NRC by letter dated March 2,1994.

39. WCAP-10868," Duke Power Company Catawba Unit No. 2 Reactor Vessel Radiation Surveillance Program", L. R. Singer, November 1985.

40. WCAP-11941," Analysis of Capsule Z from the Duke Power Company Catawba Unit No. 2 Reactor Vessel Radiation Surveillance Program", S. E. Yanichko, September 1988.

41. Letter from Combustion Engineering, Inc. to Westinghouse," Core Region Weld Materials Contract 161053/8871 & 161054/8971", M. C. Herder, dated April 8,1974 and Combustion Engineering Metallurgical Research and Development Department - Chattanooga, Welding Material Qualification to requirements of ASME Section III, Job Number D3225, project Number 960009, December 12,1972.