ML17264A310

Responds to NRC 951211 RAI Re PTS Assessment for Plant Reactor Vessel

ML17264A310
Person / Time
Site:	Ginna
Issue date:	12/21/1995
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, TAC-M93827, NUDOCS 9601020322
Download: ML17264A310 (25)

Text

CATEGORY j.

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDE)

ACCESSION NBR:9601020322 DOC.DATE: 95/12/21 NOTARIZED: NO DOCKET FACIL:60-.24A Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

SUBJECT:

Responds to NRC 951211 RAI re PTS assessment for plant reactor vessel.

DISTRIBUTION CODE: A028D COPIES RECEIVED:LTR 1 ENCL J(Reactor SIZE: II Vessel Struct TITLE: Generic Letter 92-01, Rev 1, Suppl 1 Responses NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL INTERNAL'ECIPIENT PD1-1 PD 1 1 . JOHNSON,A 1 1 CENTE 1 1 NRR/DE/EMCB 2 2 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS3 1 0 RES/DET/EMMEB 1 1 EXTERNAL: NOAC 1 1 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D"5(EXT 415-2083) TO ELIMINATE YOUR NAME

~ FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR,. 'l ENCL, "'.'10

0 '

I

\

AHD ROCHESIER GAS ANDEIECTRIC CORPORATION ~ 89 EASTAVENUE, ROCHESTER, N. Y IrI6d94001 AREA CODE 7I6 546-2700 ROBERT C. MECREDY Vice President Nvcleor Operotions December 21, 1995 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-1 Washington, D.C. 20555

Subject:

Response to Request for Additional Information on Pressurized Thermal Shock (PTS) Assessment for Ginna Reactor Vessel R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref. (a): Letter from A.R. Johnson (NRC), to R.C. Mecredy (RGE),

Subject:

R.E. Ginna Nuclear Power Station Request for Additional Information Pressurized Thermal Shock- (PTS)

Assessment for Ginna Reactor Vessel (TAC No. M93827),

dated December 11, 1995.

Dear Mr. Johnson:

Rochester Gas and Electric Corporation has reviewed the referenced Request for Additional Information and provides the following responses:

Question l: i Since the ni tial reference temperature data for heat 62782 shows large variability (two values at 1'F and -38 F), provide the technical basis for not li uti zi ng the generi c mean val ue and generic standard deviation for the initial reference temperature for B&W fabricated Li nde 80 welds.

Note: The square of the standard deviation for these values should have been determined by dividing the sum of the squares of the differences between the value and the mean value by n-2 to give an approximate unbiased estimate.

Response: RG&E proposes to revise the PTS submittal to use an initial reference temperature of -4.8'F and a oz value of 19.7'F. These values are supported by the RG&E Generic Letter 92-01 Revision 1 submittal dated July 2, 1992 as provided in BAW 1803, Revision 1 Table 3-3 which measured 34 data points.

The use of these values combined with the use of surveillance capsule data yields a margin term of (19.7) + (14) = 48.3 F (R.G. 1.99, Rev. 2) 03000' 7601020322 951221 PDR ADOCK 05000244 P PDR

guesti'on 2: Provide the unirradiated drop weight test data and charpy test data for welds material fabricated from heat number 62.782 weld wire.

Response: With the use of the initial reference temperature and standard deviation as discussed in 1. above, the heat number 61782 unirradiated drop weight and charpy test data are no longer required.

Question 3: Provide the actual chemi stry data utilized in determining the best-estimate chemistry for heat number 61782 wel ds and the chemi stry for the l

survei lance welds. Identify the source of the data and the reference document. Hov vas the best-esti mate and the chemistry for the survei ance veld determined from this data?

ll Response: Attachment A provides a discussion of the heat number 61782 and surveillance capsule weld SA 1036 chemistry.

Question 4: Identify whether the survei llance data meets the li credi bi ty criteria in Regulatory Guide 2. 99, Revision 2. Demonstrate the cri teri a 3 (scatter about the best-fi t line should normally be less than 28'F for welds) has been met by determining the scatter of the >RTNDT from surveillance data about the best-fi t line described in Regulatory Position 2.l. Does the correlation monitor material in the capsules fall within the scatter band of the data base for the material?

Response: Attachment B provides a discussion of the surveillance capsule credibility criteria.

Ver trul yo s, Robert C. Me redy REJ4412 xc: Mr. Allen R. Johnson (Mail Stop 14B2)

Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

~ r Attachment A Heat number 61782 chemistry (1) Data used in heat number 61782 chemistry estimate:

The values of Cu and Ni used come from BAW 1500, pg. B-42 for welds SA 1036 and SA 1135 which are archive reactor vessel weldments for this material heat number. A copy of the data table is provided as page (A-2).

(2) The data values were used to determine a mean value of

.25 Cu and .54 Ni per 10 CFR 50.61 guidance for best estimate of the mean of the values for the heat number of the material. Using the chemistry factor tables of 10 CFR 50.61 yielded a chemistry factor of 167.6'F.

Surveillance capsule chemistry weld SA 1036:

(1) For determining the chemistry factor value used in ratioing (Regulatory Guide 1.99, Rev. 2, position C.2),

available data for Cu and Ni chemistry were summed and mean values established. The data came from WCAP 13902 Table 4-1 for tested capsules; BAW 1500 Exhibit. B-3 for archived weldment dropouts; and BAW 1500 page B-24 weld qualification report. Hard copies of these data are provided as pages (A-3), (A-4), and (A-5).

P (2) The above data values were summed together to yield mean values of .214 Cu and .505 Ni. Using the chemistry factor tables of 10 CFR 50.61, the chemistry factor was determined to be 150.9'F

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ibles 4-1 TABLE 4-1 Chemical Composition (wt%) of the R. E. Ginna Ant cobalt Reactor Vessel Surveillance Materials"

. In Chemical Analysis Lower Shell Forging Intermediate She11 i in the (wt. %) 125P666 Forging 125S255 Surveillance Weld'"

0.19 0.18 0.075 (0.06) 0.67 0.66 1.31 (1.29) were 0.010 0.010 0.012 (0.006) re attained S 0.011 0.007 0.016 (0 020) g points Si 0.20 0.23 O.S9 (0.41)

Ni 0.69, 0.69 o.s6~ (0.50)

Cr 0.37 0.33 O.S9 (0.03)

Co 0.013 0.015 o.ool (--)

Mo 0.57 0.58 0.36 (0 22) ained in 0.02 0.02 o.ool (--)

Cu 0.05 0.07 0.23 (0.22) 0.004 0.003 0.020 (--)

o.ols (--)

Sn 0.01 0.01

[a] The values presented here are from References 2, 13 and 14.

[b) The values in parenthesis are from an analysis performed on an irradiated Capsule T weld metal charpy specimen, W26 (Reference 2).

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Attachment B Evaluation of the R.E. Ginna Reactor Vessel Surveillance Data Credibility INTRODUCTION:

Regulatory Guide 1.99, Revision 2, describes general procedures acceptable to the NRC staff for calculating the effects of neutron radiation embrittlement of the low-alloy steels currently used for light-water-cooled reactor vessels. Position C.2 of Regulatory Guide 1.99, Revision 2, describes the method for calculating the adjusted reference temperature and Charpy upper-shelf energy of reactor vessel beltline materials using surveillance capsule data.

The methods of Position C.2 can only be applied when two or more credible surveillance data sets become available from the reactor in question.

To date there have been four surveillance capsules removed from the R.E.. Ginna reactor vessel. To use these surveillance data sets, they must be shown to be credible. In accordance with the discussion of Regulatory Guide 1.99, Revision 2, there are five requirements that must be met for the surveillance data to be judged credible.

The purpose of this evaluation is to apply the credibility requirements of Regulatory Guide 1.99, Revision 2, to the R.E.

Ginna reactor vessel surveillance data and determine Ginna surveillance data is credible.

if the R.E.

EVALUATION:

Criterion 1: Materials in the capsules should be those judged most likely to be controlling with regard to radiation embrittlement.

The beltline region of the reactor vessel is defined in Appendix G to 10 CFR Part 50, "Fracture Toughness Requirements," May 27, 1983 to be:

"the reactor vessel (shell material including welds, heat affected zones, and plates or forgings) that directly surrounds the effective height of the active core and adjacent regions of the reactor vessel that are predicted to experience sufficient neutron radiation damage to be considered in the selection of the most limiting material with regard to radiation damage."

The R.E. Ginna reactor vessel consists of the following beltline region materials:

a) Intermediate shell forging heat number 125S255,

b) Lower shell forging heat 125P666, and c) Intermediate to lower shell circumferential weld seam SA-847 (fabricated with 1/8 inch Mn-Mo-Ni weld filler wire, heat number 61782 and Linde 80 flux, lot number 8350).

The R.E. Ginna surveillance program utilizes test specimens from both the intermediate and lower shell forgings. The weldment used in the surveillance program was fabricated with 1/8 inch Mn-Mo-Ni weld filler wire, heat number 61782 and Linde 80 flux, lot number 8436. Since, all beltline materials are contained in the surveillance program of the R.E. Ginna reactor vessel, the limiting material is contained in the surveillance program. Hence, the R.E.

Ginna reactor vessel surveillance program meets this criteria.

Criterion 2: Scatter in the plots Charpy energy versus temperature for the irradiated and unirradiated conditions should be small enough to permit the determination of the 30 ft-lb temperature and upper shelf energy unambiguously.

Plots of Charpy energy versus temperature for the unirradiated condition are presented in WCAP-7254, "Rochester Gas and Electric Robert E. Ginna Unit No.' Reactor Vessel Radiation Surveillance Program," dated May 1969.

Plots of Charpy energy versus temperature for the irradiated condition are presented in:

~ Westinghouse Report FP-RA-1, "Analysis of Capsule V from the Rochester Gas and Electric R.E. Ginna Unit No. 1 Reactor Vessel Radiation Surveillance Program," dated April 1973,

~ WCAP-8421, "Analysis of Capsule R from the Rochester Gas and Electric Corporation R.E. Ginna Unit No. 1 Reactor Vessel Radiation Surveillance Program," dated November 1974/

~ WCAP-10086, "Analysis of Capsule T from the Rochester Gas and Electric Corporation R.E. Ginna Nuclear Plant Reactor Vessel Radiation Surveillance Program," dated April 1982, and

~ WCAP-13902, "Analysis of Capsule S from the Rochester Gas and Electric Corporation R.E. Ginna Unit Reactor Vessel Radiation Surveillance Program," dated April 1993.

The scatter in the data presented in these plots was small enough to permit the determination of the 30 ft-lb temperature and the upper shelf energy of the R.E. Ginna surveillance materials unambiguously. Therefore, the R.E. Ginna

surveillance program meets this criterion.

Criterion 3: When there are two or more sets of surveillance data from one reactor, the scatter of ~RT>>~ values about a best-fit line drawn as described in Regulatory Position 2.1 normally should be less than 28'F for welds and 17'F for base metal. Even if the fluence range is 'large (two or more orders of magnitude), the scatter should not exceed twice those values. Even if the data fail this criterion for use in shift calculations, they may be credible for determining decrease in upper shelf energy if the upper shelf can be clearly determined, following the definition given in ASTM E185-82.

The least squares method as described in Regulatory Guide 1.99, Revision 2 will be utilized to determine a best-fit line for that data and to determine if the scatter of these ~RTNpy values about this line in less than 28'F for welds and less than 17 F for the plate.

Following is the calculation of the best Regulatory Guide 1.99, Revision 2.

fit line as described in (B-3)

TABLE 1 Ginna Surveillance Capsule Data (3)

Material Capsule F(1) FF(2) hRTNDT FFKa,RTNDT FF'x')

(x) (y) (Xy)

Lower Shell 0.556 0.836 25 20.9 0.699 Forging l. 15 1. 039 25 26.0 1.080 125P666 (Tangential) 1.97 1. 185 30 35.6 1 '04 3.87 1. 349 42 56.7 1.820 4.409 122 139.2 5.003 Intermediate 0.556 0.836 0.699 Shell R 1. 15 1. 039 1.080 Forging 125S255 1.97 1.185 1.404 (Tangential) 3.87 1. 349 60 80.9 1.820 i~ 1 4. 409 60 80.9 5.003 Weld Metal 0.556 0.836 140 117.0 0.699 1.15 1. 039 165 171.4 1.080 1.97 1.185 150 177.8 1.404 3.87 1.349 205 276.5 1.820 i~1 4.409 660 742.7 5.003 (1) F = Fluence (10 n/cm, E ) 1.0 MeV)

(2) FF = Fluence Factor = F' (3) ~RTND> values do not include the adjustment ratio procedure of Regulatory Guide 1.99, Revision 2, Position 2.1, since the surveillance capsule materials are equivalent to the actual beltline materials Per the 27th Edition of the CRC Standard Mathematical Tables (page 497), for a straight line fit by the method of least squares, the values b, and bi are obtained by solving the normal equations nbp + bi Exi = Eyi and bpExi + biZxi = EXiyi

These equations can be re-written as follows (b~ = a and b~ = b):

n n Zy< = an + bEx< and i=1 i=1 n n n Ex,y, = aEx, +

i=1 i=1 bEx,'=1 Lower Shell For in 125P666:

Based on the data provided in Table 1 these equations become:

122 = 4a t 4.409b and 139.2 = 4.409a + 5.003b Thus, b = 33.004 and a = -5.879, and the equation of the straight line which provides the best least squares is:

fit in the sense of Y = 33.004 (X) -5.879 The scatter in predicting a value Y corresponding to a given X value is:

e = Y - Y TABLE 2 Lower Shell Forging 125P666 FF hRTNDg Best Fit Scatter of (30 ft-lb) hRTNDg hRTNDg

('F) ('F) ('F) 0.836 25 21.7 3.3

1. 039 25 28.4 -3.4 1.185 30 33.2 3~2 1.349 42 38.6 3.4 The scatter of ~RT>>~ values about a best-fit line drawn as described in Regulatory Position 2.1 (Table 2) is less than 17'F.

Therefore, this criteria is met for the surveillance data of lower shell forging 125P666.

Intermediate Shell For in 125S255:

Based on the data provided in Table 1 the equations become:

60 = 4a + 4.409b and 80.9 = 4.409a + 5.003b Thus, b = 103.122 and a. = -98.666, and the equation of'he straight line which provides the best least squares is:

fit in the sense of Y = 103.122 (X) -98.666 The scatter in predicting a value Y corresponding to a given X value is:

e = Y - Y TABLE 3 Intermediate Shell Forging 125S255 FF >RTNDx Best Fit Scatter of (30 ft-lb) hRTNgg hRTNpy

( F) ( F) ('F) 0.836 -12.5 12. 5 1.039 8.5 -8. 5 1.185 23.5 -23.5 1.349 60 40.4 19.6 The scatter of ~RTND~ values about a best-fit line drawn as described in Regulatory Position 2.1 (Table 3) is less than 34'F (2 x 17'F). Therefore, this criteria is met for the surveillance data of intermediate shell forging 125S255.

Weld Metal:

Based on the data provided in Table 1 the equations become:

660 = 4a + 4.409b and 742.7 = 4.409a + 5.003b

Thus, b = 106.265 and a = 47.869, and the equation of the straight line which provides the best least squares is:

fit in the sense of Y = 106.265 (X) + 47.869 The scatter in predicting a value Y corresponding to a given X value is:

e = Y - Y TABLE 4 Surveillance Weld Metal FF hRTNDg Best Fit Scatter of (30 ft-lb) hRTNpg dRTNDg

('F) ('F) ('F)

0. 140 136. 7 3.3 836'.039 165 158.3 6.7 1.185 150 '173. 8 -23.8 1.349 205 191. 2 13 '

The scatter of ~RT>>> values about a best-fit line drawn as described in Regulatory Position 2.1 (Table 4) is less than 28'F. Therefore, this criteria is met for the surveillance data of the circumferential weld material.

Criterion 4: The irradiation temperature of the Charpy specimens in the capsule should match the vessel wall temperature at the cladding/base metal interface within +25'F.

The capsule specimens are located in the reactor between the core barrel and the vessel wall and are positioned opposite the center of the core. The test capsules are in baskets attached to the thermal shield. The location of the specimens with respect to the reactor vessel beltline provides assurance that'he reactor vessel wall and the specimens experience equivalent operating conditions such that the temperatures will not differ by more than 25DF.

Criterion 5: The surveillance data for the correlation monitor material in the capsule should fall within the scatter band of the data base for that material.

The correlation monitor material SA302 Grade B utilized in the R.E. Ginna surveillance program was furnished by the U.S.

Steel Corporation through'ubcommittee II of ASTM Committee E10 on Radioisotopes and Radiation Effects. A plot of the Measured Shift minus the Regulatory Guide 1.99, Revision 2, shift was obtained from the Oak Ridge National Laboratory and is described on page B-9 and B-10 of this attachment. The plot shows the Ginna data as solid points. The data has been shifted such that the Mean Value is at zero and the two-sigma bound at 25'F. All the Ginna surveillance correlation monitor material data fall within the two-sigma bounds (scatter band) of the SA302 Grade B data per the criterion as described by the CPED transmittal of page 'B-9.

CONCLUSION:

Based on the preceding positive responses to all five criteria of Regulatory Guide 1.99, Revision 2, Section B, the R.E.

Ginna surveillance data is credible.

(B-8)

0 DEC 15 '95 12:KA'I I'NAt YSIS SEC, 6155749619 P.1/2 OAK RIDGE NATIONALLABORATORY Computational Physics & Engmeering (CPED)

NucIear Analysis 4, Shielding Section Facsimile Transmittal TO: Hd Tele PAX NO. (412) SV+6SSV VEBZFY NO.

OPHCB NO.

PROM: Joe Pace FAX NO. (423) S74-9619 VIHGFYNO. (423) 576-1610 OPPICE NO.

COMMENTS: An additional plot has been gcncrated and shows the Ginna data as a solid symbol. Moreover, the data has been sMScd such that the Mean Value is at zero and thc tw~igma bound at 2S degrees F. Allthe Ginna surveillance CMM data foal within the R.G.

1.99 two-sigma bounds.

THIS TRANSMITTALCONSIST OP~PAGES (EXCLUDING COVER SHEET)

DATE: December 15, 1995 TQdE: 11;30

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