ML20084K510

Forwards Addl Info Re DPC 940518 Submittal,Proposing Integration of McGuire Nuclear Station Unit 1 Reactor Vessel Matl Surveillance Program W/Diablo Canyon Unit 2,as Agreed During 950118 Telcon

ML20084K510
Person / Time
Site:	McGuire
Issue date:	05/30/1995
From:	Mcmeekin T DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TAC-M89625, NUDOCS 9506060506
Download: ML20084K510 (13)

Text

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. Duke herCompany T.C AlcVam

. . f kkGuke Nudeur Generation Department Mce Presiderd 12700Wqers ferryRoad(WAIW) (TM)S754800 Hunteno'!!e, NC280788% (TM)8754809Far l DUKEPOWER May 30, 1995 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 22055

Subject:

McGuire Nuclear Station, Unit 1 Docket No. 50-369 Request for Additional Information TAC No. M89625/6

Dear Sir:

By submittal dated May 18, 1994, Duke Power Company proposed the integration of the McGuire Nuclear Station Unit 1 Reactor Vessel Material Surveillance Program with that of the Diablo Canyon Unit 2.

During the submittal review, the need for additional information concerning specific aspects of the submittal were identified by Mr. John Tsao of your staff. The information requested by Mr. Tsao was discussed during a teleconference on January 18, 1995 with Mr. Victor Nerses and J.C. Tsao, representing ONRR and J.D. Gilreath, A.M. McClenny, and J.M.

Washam representing Duke Power Company. At the conclusion of the conversation, agreement was reached that the formal response would be delayed until May 30, 1995, in order to obtain additional data from the third surveillance capsule report from Diablo Canyon. The report is presently in draft form; however, sufficient data is available to address the subject areas of interest.

9506060506 950530 PDR ADOCK 05000369 f P PDR g

.4 U.S. Nuclear Regulatory Commission May 30, 1995 page 2 To this end, find enclosed the Duke Power Company response to the request for additional information as received by FAX on January 6, 1995.

Please contact John Washam at (704) 875-4181 if questions arise concerning this response.

Very truly yours, u .

(s.

.C. McMeekin l

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U.S. Nuclear Regulatory Commission May 30, 1995-page 3 xc. Mr. S.D. Ebneter Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Mariette Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Victor Nerses, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 9H3 Washington, DC 20555 Mr. George F. Maxwell ,

Senior NRC Resident Inspector, McGuire I McGuire Nuclear Station l l

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J.E. Snyder

i. A.M. McClenny J.D. Gilreath l File:RAI ELL (EC050) 9 a

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l h ' #12008 mai 21935 in MdG61st Unit 1 Ins a"similar eslirittlem '

himateElil' response %Irrailladoniak the embElitlement ltrbhd in"ths Diable f '

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d2 Canyon sErseillaWceY w <. u n hint n numhAE12008nad

. mm; c up 21935N W~ w , Wh , .g y' ygQ: M Jad- .sM7 W ~ , W . %n lf Duke Power does not- debe irradiatsd weld data; 1) can' Duke PoWerM

'ssenths;shichnsnsdtlieMinlhesdom i in a $uiseillance[ capsule [iNjpMh T

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Mktuise Uniti14sssel for the"fstuirel tests so suppsrt the' assumption'thst)

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Cah;d. weld, of 2) Can Duke Power find irradiated data from the'sames 1 keki thanother.resEter to compare them 'to'ths em'brittlement tr$Ad hf t'heiO

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Duke Power addr;essed this issue in

'but.ths staff isllook.idg}sr)pe'cificinlAttachinent 1," page 2, in g Duke has performed a search for irradiated weld material data of heat number 12008/21935 and could find no additional test data other than that of Diablo Canyon Unit 2. No spare weld material of this heat was discovered for the insertion into McGuire Unit 1. PG&E is maintaining a small piece of this weld material. However,it is reserved for potential future issues, and is not available for additional capsules at McGuire.

We do not feel it is necessary to perform additional testing with 12008/21935 material frem the McGuire Unit i vessel since the environments are so similar. The only sign;ficane difference is the Twy operating temperature between the two plants with a differential of approximately 13 degrees (McGuire Twu is 13 hotter). This is a significant conservatism which should more than envelop any other minor differences between the two plants.

The following data is a comparison of the McGuire and Diablo Canyon irradiated weld surveillance results. The McGuire surveillance weld data is heat number 12008/20291 which is representative of the McGuire Unit 1 intermediate shelllongitudinal weld seams. The Diablo Canyon surveillance weld data is heat number 12008/21935 and is representative of McGuire Unit I and Diablo Canyon Unit 2 limiting weld.

liven though these surveillance weld materials are not the same heat number, they are similar enough to show that the McGuire data is trending below the Diablo Canyon data.

This in conjunction with the similarity of the other parameters, indicate the use of Diablo Canyon data for McGuire would be a reasonable and conservative approach.

COMPARISON OF MCGUIRE UNIT I AND DIABLO CANYON UNIT 2 SURVEILLANCE WELD MATERIAL DATA Station Surveillance IIcat # Cu Ni Reference

( Weld Material Diablo Canyon Unit 2 12008/21935 0.22 0.87 See Answer to Question 4 McGuire Unit i 12008/20291 0.20 0.87 WCAP-13949, McGuire Unit 1. Capsule V, Feb.1994 Station Surveillance llEAT #. Fluence

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ARTsor Initial Reference Weld Material x 10"n/cm2 RTunr Diablo Canyon Unit 2 12(X)S/21935 0.716 173.8 WCAP-14363, Capsule Y Diablo.

Diablo Canyon Unit 2 12008/21935 0.960 204.2 -50 Canyon Unit 2, DRAFT Diablo Canyon Unit 2 12008/21935 1.077 212.5 McGuire Unit i 12008/20291 0.472 160 WCAP-13949, McGuire Unit I, McGuire Unit i 12008/20291 1.409 165 -50 Capsule V, Feb.1994 McGuire Unit 1 12008/20291 2.186 175

'2jf k lSPirhvidii1T5Eidf5Eh5UNEIriiniIillhe[Diibi(UinYohidMEIE9 surveillance weld; heat number 12008 and 21935, is loc'ated and at ' thel b reador vessel wall ahd 2)'the neuthon flux'spdtrum at thelMcGuire reactor]

il ' vessel where the weld is located.t Provide a comparisonFDuke Power : n f ;providid ont neuti$n fluence' comparison tatweeri Diablo danson and I )

LadicGtdre at 32EFPhdu.mana m. cm.zcmams . J See following letter from S. L. Anderson (Westinghouse) dated May 25,1995, addressing this question. Please note statement in second paragraph of attachment,"

the design of the reactor internals and pressure vessel are identical, these relative spectra applv to both of these plants." Therefore, all data contained in Tables I and 2 apply to both McGuire Unit I and Diablo Canyon Unit 2 stations.

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e SE-FSRE-95-186 May 25, 1995 (412) 374-5165 Mr. Jeff Gilreath Duke Power Company 526 South Church Street

'P . O. Box 1006 Charlotte, NC 28201-1006 l

SUBJECT:

Transmittal of Neutron Spectra for McGuire Unit 1 and Diablo Canyon Unit 2.

The attached writeup entitled " Neutron Energy Spectra at -

Surveillance Capsule and Pressure Vessel Inner Radius Locations" provides the additional neutron exposure information requested by the NRC to support the evaluation of the proposed integrated reactor vessel surveillance program for McGuire Unit 1. ,

If you have any questions or require any additional information, please feel free to contact me. .

(

very truly yours, WESTINGHOUSE ELECTRIC CORPORATION S. L. Anderson, Engineer Fluid Systems and Radiation Engineering l

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o ATTACHMENT NEUTRON ENERGY SPECTRA AT SURVEILLANCE CAPSULE AND PRESSURE VESSEL INNER RADIUS LOCATIONS l l

The attached tables provide the energy distributions of neutron flux and fluence at the center of reactor vessel surveillance ,

capsules and at the pressure vessel inner radius for the Diablo j Canyon Unit 2 and the McGuire Unit 1 reactors. In order to i provide a direct comparison from location to location, the  ;

spectral data have been normalized to a neutron flux of 1.0 n/cm2 -sec (E > 1.0 MeV). Also included in the tables are the ,

. ratios of [dpa/sec] / [$(E > 1.0 MeV)] and

($ (E > 0.1 MeV) / [$ (E > 1. 0 MeV) ] . These ratios provide an indication of the relative embrittlement associated with the various spectra.

Since these reactors are sister units; i.e., the design of the reactor internals and pressure vessel are identical, these relative spectra apply to both of these plants. Absolute spectra can be determined by multiplying the data from Tables 1 and 2 by the appropriate flux or fluence (E > 1.0 MeV).

The data in Tables 1 and 2 were calculated using the DORT two-

• dimensional discrete ordinates code and the BUGLE-93 cross-section library. The BUGLE-93 library is derived from the ENDF/B-VI data files and its use for vessel fluence calculations is consistent with the proposed fluence regulatory guide DG-1025.

Relative to the surveillance capsule spectra for Diablo Canyon Unit 2, Capsules U and X were located at the 56.0 degree location and Capsule Y was positioned at the 58.5 degree azimuth. In regard to the Mcguire vessel weld locations, the 0.0 degree spectrum from Table 2 is representative of the 180 degree longitudinal weld; whereas, the 30.0 degree spectrum from. Table 2 is applicable to both the 60 degree and 300 degree longitudinal weld positions. The remaining vessel data are presented for comparison.

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. TABLE 1 RELATIVE NEUTRON SPECTRUM AT SURVEILLANCE CAPSULE LOCATIONS Lower Energy 58.5 Deg. 56.0 Deg.

LMe_V] p_apsuto Capsule 1.42E+01 1.19E 04 1.10E-04 1.22E+01 3.83E-04 3.5GE-04 ~

1.00E+01 1.70E-03 1.59E-03 8.61 E +00 3.35E-03 3.14E-03 7.41 E+00 5.93E-03 5.59E-03 6.07E+00 1.45E-02 1.37E-02 4.97E+00 2.26E-02 2.16E-02 3.68E+00 4.78E-02 4.62E-02 3.01 E+00 4.03E-02 3.94E-02 2.73E+00 3.26E-02 3.19E-02 2.47E+00 3.95E-02 3.88E-02 2.35E+00 2.55E-02 2.51 E-02 2.23E+00 2.88E-02 2.84E-02 1.92E+00 8.41 E-02 8.36E-02 1.65E+00 1.05E-01 1.05E-01 1.35E+00 1.69E-01 1.70E-01 1.00E+00 3.78E-01 3.85E-01 8.21 E-01 2.74E-01 2.80E-01 7.43E-01 1.38E-01 1.39E-01

• 6.08E-01 4.74 E-01 4.90E-01 4.98E-01 3.94E-01 4.05E-01 3.69E-01 4.55E-01 4.68E-01 2.97E-01 4.61 E-01 4.79E-01 1.83E-01 5.55E-01 5.59E-01 1.11 E-01 5.69E-01 5.81 E-01 6.74E-02 4.23E-01 4.27E-01 4.09E-02 3.34E-01 3.33E-01 3.18E-02 1.11 E-01 1.06E-01 2.61 E-02 4.62E-02 4.12E-02 2.42E-02 1.24E-01 1.27E-01 -

2.19E-02 019E-02 8.51 E-02 1.50 E-02 1.13E-01 1.34E-01 1 7.10E 03 2.64E-01 2.66E-01 3.36E-03 E ';2E-01 3.89E-01 1.59E-03 3.67E-01 3.66E-01 4.54E-04 5.67E-01 5.56E-01 2.14 E-04 3.02E-01 2.90E-01 1.01 E-04 3.39E-01 3.31 E-01 .

3.73E-05 4.41 E-01 4.31 E-01 1.07E-05 5.20E-01 5.05E-01 5.04E-06 2.86E 01 2.75E-01 1.86E-06 3.53E-01 3.32E-01 8.76E-07 2.44 E-01 2.25E-01 4.14 E-07 1.79E-01 1.54E.01 0.00E +00 6.88E-01 5.19E ')1 l

Flux (E > 1.0 MeV) 1.00 1.00 dpa/sec 1.92E-21 1.94E-21 4.41 4.49 l Flux (E > 0.1 MeV)

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. TABLE 2 RELATIVE NEUTRON SPECTRUM AT PRESSURE VESSEL IR LOCATIONS Lower ,

Energy 0.0 Deg 15.0 Deg 30.0 Dog 45.0 Deg '

[MeV1 Vessel Vessel Vessel Vessel 1.42E+01 7.23E-04 5.63E-04 4.01 E-04 3.29E-04 1.22E+ 01 2.11 E-03 1.69E-03 1.21 E-03 1.02E-03 l 1.00E+01 7.89E-03 6.53E-03 4.78E-03 4.22E-03 8.61 E+00 1.42E-02 1.20E-02 8.81 E-03 7.85E-03 7.41 E+00 2.26E-02 1.98E-02 1.45E-02 1.33E-02 6.07E+00 5.64E-02 5.04E-02 3.57E-02 3.30E-02 4.97E+00 7.49E-02 6.96E-02 5.15E-02 4.85E-02

. 3.68E+00 1.19E-01 1.16E-01 9.36E-02 9.18E-02 3.01 E+00 7.56E-02 7.56E-02 6.60E-02 6.66E-02 2.73E+00 5.15E-02 5.25E-02 4.79E-02 4.95E-02 2.47E+00 5.63E-02 5.76E-02 5.46E-02 5.69E-02 2.35E+00 3.38 E-02 3.52E-02 3.43E-02 3.63E-02 2.23E+00 3.33E-02 3.47E-02 3.52E-02 3.70E-02 1.92E+00 8.42E-02 8.71 E-02 9.14E-02 9.52E-02 1.65E+00 8.48E-02 8.79 E-02 9.85E-02 1.01 E-01 1.35E+00 1.14E-01 1.19E-01 1.40E-01 1.42E-01 1.00E+00 1.69E-01 1.75E-01 2.22E-01 2.15E-01 8.21 E-01 1.07E-01 1.11 E-01 1.46E-01 1.38E-01 7.43E-01 5.48E-02 5.68E-02 7.87E-02 7.43E-02 -

6.08E-01 1.46E-01 1.50E-01 2.19E-01 1.98E-01 4.98E-01 1.19E-01 1.22E-01 1.85E-01 1.65E-01 3.69E-01 1.30E-01 1.34 E-01 2.05E-01 1.82E-01 2.97E-01 1.35E-01 1.36E-01 2.11 E-01 1.82E-01 1.83E-01 1.70E-01 1.74E-01 2.83E-01 2.44E-01 1.11 E-01 1.62E-01 1.65E-01 2.75E-01 2.32E-01 6.74E-02 1.15E-01 1.17E-01 2.03E 01 1.70E-01 4.00 E-02 9.21 E-02 9.39E-02 1.67E-01 1.41 E-01 3.18E-02 3.44E-02 3.50E-02 6.49E-02 5.44E-02 2.61 E-02 2.22E-02 2.28E-02 4.27E-02 3.63E-02 2.42E-02 3.88 E-02 3.88E-02 6.82E-02 5.51 E-02 2.19E-02 2.45E-02 2.43 E-02 4.29E-02 3.46E-02 1.50E-02 4.95E-02 4.95E-02 9.30E-02 7.64E-02 7.10E-03 9.15E-02 9.31 E-02 1.79E-01 1.49E-01 3.36E-03 1.02E-0' 1.06E-01 2.03E-01 1.68E-01 1.59E-03 9.41 E-02 9.65E-02 1.92E-01 1.58E-01 4.54E-04 1.51 E01 1.55E-01 3.18E-01 2.61 E-01 2.14E-04 8.68E 32 8.96E-02 1.88E-01 1.54E-01 1.01E 04 9.02E 02 9.39E-02 1.99E-01 1.63E-01 3.73 E-05 1.19E01 1.24E-01 2.71 E-01 2.20E-01 1.07E 05 1.46E-01 1.52E-01 3.43E-01 2.78E-01 5.04E-06 8.48E-02 8.88E-02 2.04E-01 1.65E-01 1.86E-06 1.13E-01 1.19 E-01 2,81 E-01 2.27E-01 8.76E-07 8.62E-02 9.09E-02 2.18E-01 1.77E-01 4.14 E-07 8.09E-02 8.49E-02 2.09E-01 1.70E-01 0.00E+00 9.48E-01 1.23E+00 3.24E+00 3.00E+00 Flux (E > 1.0 MeV) 1.00 1.00 1.00 1.00 dpa/sec 1.55 E-21 1.53E-21 1.64E-21 1.58E-21 Flux (E > 0.1 MeV) 2.05 2.07 2.65 2.45

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WTWesideTtie"v~eselinididnpdaTiUdidsh fdI" cycle 5istEGUire'Unifi91 EI i and Dlabid Canyon Unit' 2 beesusithe staff does not know how and'where' i

[Rthoseitwo.Tempeintures on Page D-f sere obiainedb:www a h d2 I

Refueling : . McGuire U1i McGuire U1 , Diablo Canyon U21 Diablo Canyon U2 .

Outage ; ~- 0% Power ' ' 100% Power 0% Power ? .100% Power I

EOC-#  ? Tcous T 4Tcom *F- Tcom T 'Teow 'F i 557 558.1 547 545 2 557 558.1 547 545 3 557 558.1 547 545 4 557 558.1 547 545 5 557 558.1 547 545 '

I 6 557 558.1 547 545 7 557 558.1 8 557 558.1 9 557 558.1 These temperatures have minimal deviations during each cycle. The McGuire Solid State Protection System monitors these temperatures within a tolerance of 2 F.

As show n in figure 5-19 of the McGuire FSAR, Tn,u remains fairly constant at approximately 558F. A Licensee Event Report search indicated the Technical Specification was violated once. The minimum NC system temperature of 536.7F was reached during a 79 minute event. This event is documented in the Duke Power Company, McGuire Nuclear Station Reportable Occurrence Report No. 370/83-62, dated December 1,1983.

Diablo Canyon Unit 2 reported no significant operating temperature deviations (operating below 525F) in GL92-01 submittal. Their OP L-1 requires Tave = 547F prmr to entering Nhxle 2. Ol' L-5 requires Tave > 541F until reactor is subcritical.

Attached are the McGuire and Diablo Canyon Reactor system temperature versus power curves found in chapter 5 of the FSAR.

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"c-r<xo m 3 E ,, pa,g 5.n-1 l i I  ! j t 1 I O to 20 30 40 50 60 70 to 90 too A pow (R FSAR UPDATE UNITS 1 AND 2 OIABLO C ANYON BITE FIGURE 5 3-1 H0i LEG, C0to t EG, AND AVERAGE RE ACTOR COOLANI LOOP TEMER ATURE AS FUNCTION OF Pt RCf NT FULL POWER

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't frein Duke Power's re, spo,nse^to Generic letter 92-01), the copp er 6a h , fcontent 8and hickel' contint fo/the weld, heat numbsf 12008 a nd 21935, are ,

k i 0.22% and 0 86% respectikely.jIn' Attachrnent 2, pagel DWthe.copperi -

EddontestMas reported 0.20gandlns nickieliontenCwas ripoEtediCla'rlfyb The .20% copper and no nickel reported, was a chemical analysis taken for the McGuire Vessel during fabrication and documented in Combustion Engineering, Inc.,

Metallurgical Research & Development," Chemical Analysis of Wire-Flux Test Coupon", Job Number X-32255,10-14-69, and later referenced in toughness tables for MNSI reactor vessel in WCAP-10786 (see reference below).

The 0.22% copper and 0.86(7c nickel is the average of all known measured values (as of 7/92) for the tantum weld 21935/12008. Most of these data points come from Diablo Canyon Surveillance Capsule Reports (see table below).

REFERENCE WT.% WT. %

CU NI WCAP-10786," Analysis of Capsule U from the Duke Power Company McGuire Unit 0.200 -

I Reactor Vessel Radiation Surveillance Program". S. E. Yanichko, T. V. Congedo and W. T. Kaiser. February 1985. Table A-l MNSI Rx Vessel Toughness Table WCAP-8783," Pacific Gas and Electric Company Diablo Canyon Unit No. 2 Reactor 0.220 0.830 Vessel Radiation Surveillance Program", J.A. Davidson and S.E. Yanichko, December 1976.

WCAP-lG472," Evaluation of Diablo Canyon Units I and 2 Reactor Vessel Belthne 0.230 0.900 Weld Chemistry". S.E. Yanichko and M.K. Kunka, September 1983 (Proprietary). 0.210 0.760 0.220 0.900 WCAP-l1851," Analysis of Capsule U from the Pacific Gas and Electric Company 0.219 0.86 Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program", S. E. 0.212 0.88 Yanichko, et al., May 1988. 0,213 0,90 WCAP-12811," Analysis of Capsule X from the Pacific Gas and Electric Company 0.225 0.875 Diablo Canyon Unit 2 Reactor Vessel Radiation Sun eillance Program", E. Terek, et ().213 0.856 al., December 1990.

0.225 0.877 GL92-01 Ascrage 0.217 0.864 WCAP.14363," Analysis of Capsule Y from the Pacific Gas and Electric Company 0.196 0.763 Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program". E. Terek, et 0.24 0.968 al., DR AIT-0.23 0.910 New Aserage 0.218 0.868 1

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