ML20035H719

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Rev 1 to, Evaluation of Upper Shelf Energy (Use) of Big Rock Point Reactor Vessel (Rv) Base Metal & Weld Metals
ML20035H719
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 04/22/1993
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20035H718 List:
References
GL-92-01-01, GL-92-01-01-R01, GL-92-1-1, GL-92-1-1-R1, NUDOCS 9305060311
Download: ML20035H719 (6)
v • d • e


Text

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Comunes BIG ROCK POINT NUCLEAR PLANT u. GD-92-01-01

.-yM ENGINEERING ANALYSIS WORK SHEET sheet._.1_of 6 Evaluation of the Upper Shelf Ener9y-(USE) of the Big Rock Point Title Reactor Vessel (RV) Base Metal & Weld Metals INITIATION AND REVIEW Initiated Rev Method Check (,/)

Technically Rev'd By Date Description By Date C Ic R

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I.

OBJECTIVE:

To determine the end of life (E0L) upper shelf energy (USE) of the reactor vessel base and weld metal.

II.

REFERENCES:

1) 10CFR50 App.G.

2)

Reg. Guide 1.99 Rev. 2, May 1988 3)

G.L. 92-01 Rev. 1, March 6, 1992 4)

WCAP-9794, Analysis of Capsule 125 from the CPCo BRP Nuclear Plant RV Radiation Surveillance Program, Sept.,1980 5)

NRL Memorandum Report 2027, August 1969 6)

GECR-4442, December 1963 7)

Letter to R.E. Kettner, CPCo from F.A. Hollenbach, Gen Electric Co., dated Feb 26, 1962 8)

NRL Memorandum Report 1638, Aug. 15, 1965 9)

NRL Report 6349, Jan. 31, 1966 i

10)

Nuclear Engineering and Design, Vol.11, No. 3, April 1970, C.Z. Serpan and H.E. Watson, pp. 393-415 11)

ASTM E185-82 111 ANALYSIS INPUTS:

All inputs for this analysis are extracted from references 2, 4, 5, and 7 above.

IV ASSUMPTIONS:

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9305060311 930427

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PDR ADOCK 05000155 P

PDR BKP 090 U2/U1/58

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cansamer Pnrer BIG ROCK POINT NUCLEAR PLANT EA. GL-92-01-01 ENGINEERING ANALYSIS CONTINUATION SHEET sheet __2_of 6 renaam Rev #

0 maarm=say5 PamE**Et V ANALYSIS:

A.

Method The USE is derived from Figure 2 of Reg. Guide 1.99 Rev 2 (Attachment 1) for both base metal and weld metal as described in paragraph C.2.2 of the same document. This is done by establishing a line parallel to the existing upper bound lines based on % decrease in USE as measured by surveillance specimens for each material (base & weld) of interest. To determine the USE at any fluence of interest, simply identify the % decrease in USE on the ordinate which corresponds to the fluence value taken off the material specific parallel line as drawn above. This percentage decrease in USE can'be compared to the unirradiated base line USE to identify the USE for that fluence.

B.

Surveillan'ce Data Five (5) Surveillance Capsules have been evaluated from the BRP RV to date. Two (2) capsules (capsules 119 wall and 122 accelerated) were evaluated in 1964 and two (2) more (capsules 127 wall and 124 accelerated) in 1967 by the Naval Research Laboratory (NRL). Wall capsule 125 was evaluated in 1980 (Ref.

4) by Westinghouse Corp. in conjunction with EPRI. Table 9.2 of Ref. 5 (Attachment 2) identifies values for full shear absorption energy (USE) of capsules 119, 122, 127 and 124.

Identification of these values is in accordance with the definitions presented in paragraphs 4.17 and 4.18 of ASTM E185-82 (Attachment 3). The USE for capsule 125 is indicated via Table 5-5 of Ref. 4 (Attachment 4). USE for all five(5) capsules is presented below.

TABLE 1 survelliance capsule USE Data Capsule TYPE F X 10

BASE

  • 1 Decrease nELD **

1 Decrease USE (ft*lb)

Base USE USE (ft*1b)

Weld USE 119 WALL

.15 82 0

80 15.8 127 WALL

.71 73 11.0 70 26.3 125 WALL 2.27 68 17.1 74 22.1 122 ACCEL 2.3 62 24.4 57 40 124 ACCEL 10.7 70 14.6 65 31.6

  • Unitradiated base metal USE = B2 ft*1bs
    • Unirradiated weld metal USE = 95 ft*Lbs BRP 091 02/01/88

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C.

Fluence Data i

The most recent fluence (f) data comes from capsule 125 (Attachment 4, Table 5-1) having a measured fluence of 2.27 X 10" nyt, E > 1 MEV. The thermal history at the time capsule 125 was removed indicates 17,858,371.2 MwHrt (Attachment 5, page 1,3,4 and 5). Therefore, Calc. 1 2.27 X 101Snvt, DiMEV=1. 271X10 a nVt, D1N t

17,8 5 8,371. 2MwHr t MwHrt Reference plant operating data for Feb 1979 in Attachment 5.

l l

As of 12-31-92, the BRP RV has 35,494,707 HwHrt (Attachment 5, page 2). The fluence as of this date is then:

Calc. 2 1

12/31/92 f = 3 5,49 4,7 07 MwHr t *

1. 271 X 1012 DVt, D 1M MwHEt I

= 4. 51 X 10" nyt, D1MEV Note that Calc 2 is the fluence at the wall capsule position l

and not at the Vessel ID or the 1/4t position.

As of 12-31-92, BRP has only 89 months left on its license (to the date of May 31,2000) per License No. DPR-6 (Attachment 6).

l l

Typically BRP operates on a twelve (12) month cycle with a l

planned refueling outage of sixty (60) days. Conservatively, forty-five (45) day refueling outages will be used to calculate E0L fluence at the wall capsule location with no outage in the year 2000. Therefore, i

i l

Calc. 3 7 yrs

  • 45 Days Outage 315 Days Outage Time Remaining

=

BRP091 02/01/88

poww BIG ROCK POINT NUCLEAR PLANT EA. Ge92-01-01 conson ENGINEERING ANALYSIS CONTINUATION SHEET Sheet 4 d 6 ae, p 0

rewoesus aur-san men Calc. 4 7 Yrs

  • 365 Days +

151 Days

+

2 Days

= 2708 Days 1 Yr (Year 2000)

(Leap Yrs.)

Calc.5 2393 Operating Days Remaining 27 08 Days - 315 Days

=

Calc. 6 4N#8 2393 Days *

  • 240Mwt = 13,7 83,6 80 MwHrt Remaining 1 Day Calc. 7 49,278,387 MwHr t@EOL 34,49 4,7 07 MwHrt + 13,7 83,6 80 MwNrt

=

Calc. 8 12 nVC 1MW f = 49,27 8,387 MwHrt

  • 1. 271 X 10

=

6. 263 X 10" nvt, gog,*yg*yfapguy, Therefore, the maximum EOL fluence at the wall capsule location for the BRP RV is 6.263 X 10" nyt. E >l MEV.

(Attachment 7 from General Electric Corp calculated a lead factor for i

the wall capsules to be 1.25:1 when compared to the Vessel Wall (I.D.).

Therefore, the E0L fluence at the Vessel ID is:

Calc.9 E> 1 NEV f, 6. 26 3 X 10"nvt, B> 1MEV = 5. 011 X 10"nyt ' EOL f @ Vessel I.D.

1.25 Per paragraph C.1.1 Formula (3) of Attachment 1, the fluence thru the vessel wall is given by the following function:

F, - F,g (e"]

where:

F,s - fluence at Vessel I.D.

F, - fluence at location X x - depth in inches into the vessel wall from the Vessel I.D.

BRP091 02/01/88

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Noting that the BRP RV wall (with cladding) is 5.40625 inches thick, l

the distance x to the 1/4t location is Calc.10

)

(.25)(5.40625 in.) = 1.3515625 inches 1

The EOL fluence at the 1/4t location is j

Calc.ll

]

i nyt, E > l'MEV f = (5.011 X 10) (es2m.ssise2s')

{

f = 5.011 x 10 [e.32ms]

nyt, E > 1 MEV f = 5.011 x 10 (.7229791) nyt, E > 1 MEV f = 3.623 x 10 nyt, E > 1 MEV (E0L 9 1/4 t location) i D. Paraaraoh C.2.2 Analysis Since the measured USE from surveillance specimens must be plotted parallel to the existing lines on figure 2 of i;, it is determined that capsule 122 data is most limiting for both base metal and weld metal. This is because the % decrease in USE is greatest for these capsule specimens.

Accordingly, a line is drawn parallel to the existing upper metal (40% decrease in USE) at a fluence of 2.3 x 10') nyt E >

bound data for both base metal (24.4% decrease in USE and weld I

1 MEV. Refer to figure 1 of this analysis.

1 Per Figure 1 of this analysis (Figure 2 of Attachment 1), EOL USE of the base metal will experience a 7.7.6% reduction and the l

weld metal will experience.a 44.7% reduction. The final EOL USE'S are give below EOL USE 9 f= 3.623 X 10

nyt, E>1MEV 0 1/4t BASE METAL:

(1.0

.267) 82 = 60.1 ft*1bs A

EOL USE 9 f= 3.623 X 10

nyt, E>1MEV 0 1/4t WELD METAL:

(1.0

.447) 95 = 52.5 ft*1bs BRP 091 02/01/88

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M hr FIGURE 2 Predicted Decrease in Shelf Energy as a Function of Copper Content and Fluence

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