ML20059A094

Forwards DPC Responses to 931012 NRC RAI Re GL 92-01,rev 1

ML20059A094
Person / Time
Site:	Mcguire, McGuire
Issue date:	12/20/1993
From:	Tuckman M DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, TAC-M83480, TAC-M83481, NUDOCS 9312300010
Download: ML20059A094 (10)

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• DukePbwerCompany M S Tlona PO Box 1006 Senior ViceItesident Diarlotte, NC28201-1006 NuclearGeneration (704)38122000ffice (7003824x0 Fax DUKEPOWER December 20, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk ,

Washington, D.C. 20555

Subject:

McGuire Nuclear Station Units 1 & 2 Docket Nos. 50-369, 370 Response to Request for Additional Information Concerning Generic Letter 92-01, Revision 1 Gentlemen:

By letter dated July 3, 1992, Duke Power Company submitted a response for Oconee, McGuire and Cata*>ba. Nuclear Stations to Generic Letter 92-01, Revision 1. The NRC staff issued a request for additional information (RAI) dated October 12, 1993 ^

for McGuire Nuclear Station. Subsequently, McGuire requested additional response time in order to resolve the discrepancies and provide the additional data. Attached are the responses to the questions contained in the RAI for McGuire Nuclear Station.

I declare under penalty of perjury that these statements are true and correct to the best of my knowledge.

Should you have any questions regarding this submittal, please contact A. Jones-Young at (704) 382-3154.

Very trul yours, b 3. \

M.S. Tuckman Senior Vice President Nuclear Generation adj-y/raio Attachment

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-U.S.'NRC-December 20, 1993

. .Page 2 xc: S. D. Ebneter Regional Administrator, Region II ,

V. Nerses, ONRR

.i G. F. Maxwell Senior Resident Inspector (MNS)  ;

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i ATTACHMENT DUKFs POWER COMPANY'S RFSPONSE TO THE  !

NUCLEAR REGU'LATORY COMMISSION'S RFQUEST '

FOR ADDITIONALINFORMATIOh Ki'GARDING McGUIRE'S RESPONSE TO GENERIC L'ETTER 92-01, .

REVISION 1 (TAC NOs. M83480 AND M83481)  ;

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McGuire Unit 1 (TAC No. M83480)

The staff is requesting additional information on the chemistry contents of beltline materials under question 2.b.5 in Generic Letter (GL) 92-01: l

1) The licensee provided two sets of chemistry data for each of the following beltline materials: plates 115012-1,115012-2, B5012-3,115013-2, B5013-3, and weld M1.22.

Provide a single set 'of chemistry data and its bases.

For the purpose of providing a single set of chemistry data for the requested material, all known chemistry measurements were averaged, provided there was traceability to those measured values.

6 JSingle Chemistry Valusi Derived by A'veraging Kumyn Values CE Code Ni/Ileat No. Cu . Ni - ^P Si  : Referencen

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B5012-1/ C4387-2 0.11 0.59 0.010 0.016 1, 2,3,4,14 & 15 B5Cl2-2 / C4417-3 0.14 0.61 0.012 0.016 2.5, 6,14 & 15 ll5012-3 / C4377-2 0.11 0.66 0.014 0.015 2,4, 7, 14 & 15 B5013-2 / C4374-2 0.10 0.51 0.010 0.015 2,8,9,14 & 15 ll.5013-3 / C4371-2 0.10 0.55 0.011 0.14 2,10, 11,14 & 15 M 1.22 / 20291-12008 0.205 0.895 0.011 0.008 2. I2, 13, 14 & 15 i

Note: There were two errors discovered reported for wt. % of copper in plate heat numbers C4417-3 and C4377-2. The correct values for plate heat numbers C4417-3 and C4377-2 are 0.14% and 0.11% respectively.

2) The licensee did not report sulfur and phosphorus for welds Gl.39, M1.32, M1.33 and Mt.34. Provide the data and its bases.

The following are average values derived from the below references.

Average Sulfur & Phosphorus Values for MNS Unit 1 licilline Welds' )

l CE Code No. Ileat No. - Sulfur - Phosphorus . Reference Gl.39 83640 0.011 0.007 16 & 17  !

M1.32 '21935/12008 0.0086 0.0152 25,26,27,28,29, & 30 -l M1.33 21935 0.0155 0.0105 32 & 33 M1.34 305424 0.008 0.016 18 & 31 I

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3) The copper and nickel contents for weld M1.34 in the GL 92.01 submittal differ with  !

those given in the licensee's pressurized thermal shock submittal on October 21, 1986,

Subject:

Reactor Vessel Fracture Toughness. Resolve the discrepancy and provide a single set of copper and nickel contents wir.: bases.

The Pressurized Thermal Shock analysis submitted on October 21,1986, used an average chemistry value that was taken from the Westinghouse material data bank. This data bank '

incorporated both chemistry values below. In the 92-01 submittal we only submitted those values that where verifiable through Duke specific source documentation without ,

averaging any values.

Aveiage Chemistry for %51d ML34,' Heat No. 305424, Flux Type Linde'1092,-Lot No. 3889 Reference ' Cu: Ni- 'P~ >S '

C.E. Metallurgical R & D " Chemical Analysis of Wire-Flux Test 0.300 0.640 0.013 0.010 Coupon", 2-10-70. ,

WCAf-8457, "Duquesne Light Co. Beaver Valley Unit No.1 0.260 0.620 0.018 0.006 .

React x Vessel Radiation Surveillance Program", J. A. Davidson, t Oct. H 3 _

Average 0.280 0.630 0.016 0.008 (This ' average was used in the above referenced PTS calculation) 9

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McGuire Unit 2 (TAC No. M83481)

The stalf is requesting additional information on beltline materials under Questions 2.a and 2.b5 ,

in GL 92-01: '

1) The licensee reported three sets of chemistry data for intermediate to lower shell girth weld, WOS. Provide a single set of chemistry data and its bases.

\ 1 To provide the NRC with a best estimate single set of chemistry values several new chemical analysis data points were used. Three data points were taken from McGuire's most recent capsule analysis and two data points from Catawba Unit l's surveillance capsule program.

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McGuire Unit 2 Intermediate to Lower Shell Girth Weld Control # R747,'(WO5) .

i Reference . Cu Ni P' S' 19 0.05 0.7 0.010 0.01 20 0.031 0.73 0.016 0.015 '

21 0.03 0.66 0.005 0.004 22 0.066 0.71 0.015 0.006  ;

23 0.031 0.74 0.0098 0.009

. 24 0.039 0.765 0.014 0.007 24 0.036 0.747 0.015 0.005 i 24 0.045 0.776 0.014 0.005 Average 0.041 0.729 0.0124 0.008

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2) The reported nickel value for forging 526840 in the GL 92-01 response is different from that in the Capsule X report, WCAP 12556. The GL 92-01 response reported . .

a nickel content of 0.85%, but WCAP-12556 reported a nickel content of 0.79%.

• Resolve the discrepancy and provide the correct nickel value with bases.

The 0.85% Nickel value was the highest reported value in the RDY Material Cenification. l The 0.79% Nickel value was Westinghouse's initial measured value reported in WCAP 12556. The table below incorporates all known measured values to date and their average

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Average Nickel Value for Ring Forging 05 (HT. 526840)

Reference - Nickel .

RDY Material Certification, Lab No. L600 0.85 RDY Material Certification, Lab No. L600 0.78 WCAP-12556, Analysis of Capsule X for McGuire Unit 2 0.79 (Westinghouse Initial analysis)

WCAP-13516. Analysis of Capsule U for McGuire Unit 2, 0.82 Charpy specimen DL-8 >

WCAP-11029, Analysis of Capsule V for McGuire Unit 2, 0.71 Chamy specimen DT-18 '

Average 0.79

3) The unirradiated upper shelf energy (USE) for weld WO5 was not reported in the GL - 92-01 response. Provide the unirradiated USE and its bases.

The unirradiated upper shelf energy is 133 Ft-lbs. This was derived by averaging 5 charpy impact measurements exhibiting 98% shear or greater.

Reference:

WCAP-13516, Table .5-5, Analysis of Capsule U from the Duke [

Power Co., McGuire Unit 2 Reactor Vessel Radiation Surveillance Program a

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In addition, the following clarification's / corrections are made to McGuire Unit 1 GL 92-01 submittal Attachment 2, page 5, McGuire Nucicar Station, Unit 1, CE Vessel 2167 Beltline Weldments Location Scam Weld ' IIcat No. " Flux Flux Lot No.

• Control # l Intermediate Shell Long. Seam 2-442A M1.22 20291/12008 Linde 1092 3854 Intermediate Shell Long. Seam 2-442B M1.22 20291/12008 Linde 1092 3854 Intermediate Shell Long. Seam 2-442C M1.22 20291/12008 Linde 1092 3854  ;

Inter. Shell Long. Seam Double 2-442A,B&C M1.18 20291 Linde 1092 3833 U Root Area Only Intermediate to Lower Shell 9-442 Gl.39 83640 Linde 1091 3490 Girth Lower Shell Long. Seam 3-442A M1.32 21935/12008 Linde 1092 3889  ;

Lower Shell Long. Seam Double 3-442A M1.34 305424 Linde 1092 3889 U Root Area Only Lower Shell Long. Seam 3-442B M1.32 21935/12008 Linde 1092 3889 Lower Shell Long. Seam 3-442C M1.32 21935/12008 Linde 1092 3889

• Lower Shell Long. Seam Double 3-442B&C M1.33 21935 Linde 1092 3889 U Root Area Only i

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REFERENCES:

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1. WCAP-9195, Duke Power Company William B. McGuire Unit No.1 Reactor Vessel Radiation Surveillance Program", J. A. Davidson and S. E. Yanichko, November 1977,

.2. Lukens Steel Company Letter from John A. Soltesz to S. E. Yanichko dated December 6, 1973, Lattel Copper Analysis for Lukens Vessel Materials. .l

3. Combustion Engineering, Inc., Metallurgical Research & Development Depanment, j

" Materials ' Certification Report", Job No. V-70333-001. March 5,1969

4. Lukens Steel Company, Test Certificate", Mill Order No. 20241-2 corrected copy dated 7-23-68.

5. Combustion Engineering, Inc., Metallurgical Research & Development Department,

" Materials Certification Report". Job No. V-70333-0M, corrected copy dated 5/4/70.

6. Lukens Steel Company, " Test Certificate", Mill Order No. 20241-2, dated 7-24-68.'

7. Combustion Engineering,Inc , Metallurgical Research & Development Department.

" Materials Certification Report", Job No. V-70333-007, corrected copy dated 3/31/70.

8. Combustion Engineering, Inc., Metallurgical Research & Development Department,

" Materials Certification Report" Job No. V-70334-001, dated September 4,1969.  ;

9. Lukens Steel Company, " Test Certificate", Mill Order No. 20241-3, dated 5-25-68,

10. Combustion Engineering, Inc., Metallurgical Research & Development Department,

" Materials Certification Report", Job No. V-70334-005, September 4,1979.

I 1. Lukens Steel Company, " Test Certificate", Mill Order No. 20241-3, dated 7-10-68.

12. Combustion Engineering,Inc., Metallurgical Research & Development Department,

" Materials Certification Report", Job No. V-70334-009, dated September 4,1969,

13. Lukens Steel Company, " Test Certificate", Mill Order No. 20241-3, dated 6-24-68.

14. WCAP12354, Table A-1, Analysis of Capsule X From the Duke Power Company McGuire Unit 1 Reactor Vessel Radiation Surveillance Program

15. Lukens Steel Co. Test Certificates (McGuire QA Vault, DAP Data Pkg. 00323 & 00324)

16. Combustion Engineering, Inc., Metallurgical Research & Development, " Chemical Analysis of Wire-Flux Test Coupon", Job Number D32255,8-17-72.

17. WCAP-8819, " Central Nuclear de Almaraz" December 1976

18. Combustion Engineering, Inc., Metallurgical Research & Development, " Chemical Analysis of Wire-Flux Test Coupon",2-10-70. -

19. RDY Weld Test Report, Lab No. R747

20. WCAP-9489, Duke Power Company, McGuire Unit 2 Reactor Vessel Radiation Surveillance Program Table A-2; (Original Analysis)

21. WCAP - 11029, Analysis of Capsule V From the Duke Power Company, McGuire Unit 2 -

Reactor Vessel Radiation Surveillance Program, Table 4-1  ;

22. WCAP-9734, Duke Power Company, Catawba Unit 1 Reactor Vessel Radiation ,

Surveillance Program, Table A-2 (Original Analysis) 23 WCAP-11527, Analysis of Capsule Z From the Duke Power Company, Catawba Unit 1 Reactor Vessel Radiation Surveillance Program, Table 4-1

24. WCAP-13516, Anal, sis of Capsule U From the Duke Power Company, McGuire Unit 2 Reactor Vessel Radiation Surveillance Program, Table 4-3

25. Combustion Engineering, Inc., Welding Material Certification and Release of Section Ill, E-7062, X-32255, " Chemical Analysis of Test Weld Sample", August 12,1969. ,

26. Combustion Engineering, Inc., Metallurgical Research & Development, " Chemical .l Analysis of Wire-Flux Test Coupon", Job Number X-32255,10-14-69 -l

27. WCAP-8783, " Pacific Gas & Electric Company Diablo Canyon Unit No. 2 l Reactor Vessel Radiation Surveillance Program" J.A. Davidson and S. E. Yanichko, j December 1976. I 1

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28. .WCAP-10472," Evaluation of Diablo Canyon Units l and 2 Reactor Vessel Beltline Weld

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Chemistry", S.E. Yanichko and M. K. Kunka, September 1983 (Proprietary)

- 29. .WCAP-11851 " Analysis of Capsule U from the Pacific Gas and Electric Company . ,

Diablo Canyon Unit 2 Reactor vessel Radiation Surveillance Procr Am", S.E. Yanichko, et al., May 1988.

' 30. WCAP-12811, " Analysis Capsule X from the Pacific Gas and f:lectric Company Diablo l Canyon Unit 2 Reactor Vessel Radiation Surveillance Progr.m", E. Terek, et al.,

December 1990.. 1

31. WCAP-8457, "Duquesne Light Company Beaver Valley Unit No.1 Reactor Vessel ';

Radiation Surveillance Program", J.A. Davidson, et al., October 1974.

32. Combustion Engineering, Inc., Welding Material Cenification and Release for Section 111,'-

Chemical Analysis of Test Weld Sample", Sample No. D-7279, August 12,1969.

33. WCAP-10472," Evaluation of Diablo Canyon Units 1 and 2 Reactor Vessel Beltline Weld Chemistry", S.E. Yanichko and M.K. Kunka, September 1983 (Proprietary) --

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