ML20196H160

Qualified Life Calculation for Nutherm FRVS Recirc Control Panel Components

ML20196H160
Person / Time
Site:	Hope Creek
Issue date:	02/02/1993
From:	Public Service Enterprise Group
To:
Shared Package
ML20196H149	List: ML20196H144 ML20196H160 ML20196H166
References
EQH-042, EQH-42, NUTHERM-ARRH, NUTHERM-ARRH-00, NUTHERM-ARRH-001, NUTHERM-ARRH-1, NUDOCS 9812080225
Download: ML20196H160 (15)

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yygg Qualified life calculation for NUTHERM FRVS E

R, eire controi canei coneonents Nuclear Department ID NUEEER REFERENCE CALCULATION Cov1R SEERT NUTHERM-ARRH-001 E0H-042 l OF 15 CALCULATION REVISION O

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CP NUMBER N/A N/A N/A j

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REVISION HISTORY Et#.ET) CAGES Dt)E TD rnA*JCR l

(INTERIM or FINAL) z,G,si; AnAc4 REVIoION of THe INTERIM = Proposed Plant sg (4 S r;' Cat.c.ut.muCN,

Change tEhAlt. Paces REVIsmu 2*As FINAL = Supports Instal-A"katu1 P3 49ARe ntT USEb led condition ALD feiero % c s FUTGRE CONFIRMATION REQUIRED:

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AM 6/W91 g I 2l93 REVIEWER

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(Initial & Date)

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,i29/o gg6 Public Service SUPERVISOR APPROVAL (Initial & Date) 7.b.9y gff/p/

MM(3 COVER SHEET (Number Pages)

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CALCULATIONS (Number Pages) gg

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(Excluding ggf Attachments)

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ATTACHMENTS to (Number / Total Pages) e4 54 AN*"TS 77 e) VOIDED PA6Et in g -

@8 TOTAL PAGES co 7 i2 8e

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YES If yes, design verifigation required per DE-AP.ZZ-0010(Q) (Design Verification, Ref. 3.3)

ATTACHMENT 5 s

TITLE GOAL 2FsEb LIFE.

IO No. NOTHEAM. AR

.QI SHEET CA4 FC8L NOTMIAm FM.S i

C RE43RC. c.ewT1 ten PAwet.

REFERENCE c.centem.

EQH-04f 2

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ORIGINATOR I

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CALCULATION DATE Elll9 4 CONTINUATION SHEET PEER REVIEW 19 DATE 2> do s TABLE OF CONTENTS I

Pace No TABLE OF CONTENTS 2

OBJECTIVE 2

SCOPE 2

DESIGN INFUT 3

ASSUMPTIONS 4

CALCULATION 5

CONCLUSION 13

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REFERENCES 14 ATTACHMENTS 1) DCP 4EX-3133 test temperatures

2) DCP 4EC-3254 test temperatures

3) Letter from D. Fisher to W. O'Malley, 7/11/91

4) To date Surveillance and Aging time

5) Component test level summary 1.O OBJECTIVE i

The objective of this calculation is to determine the level of Qualification for the existing Hope Creek FRVS Recirculation panel with no door along with shielding modification implemented under DCP 4EC-3254 pkg.

2, demonstrated by NUTHERM report N-160-00R, Rev.4 (Reference 2), Bussmann report 470-8 (Reference 5), AMP report 110-11004, Rev 0 (Reference 8), and Supplemental j

NUTHERM testing provided in NUTHERM report N-160-00RA1 Rev. 0 (Reference 11).

4 2.0 SCOPE This calculation applies to the following Hope Creek control panels.

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ATTACHMENT 2 m

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MLE GOAL 1F3Eb LIFE, IO No. NOTHEAM-ARM-MI SHEET ET cAu::, Rxt woTata,m fus g"C (.3-rec 3RC, ceuTitch. Pment.

REFERENCE conwe any.

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ORIGINATOR N

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CALCULATION DATE EliM3

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CONTINUATION SHEET PEER REVIEW

_ATt DATE

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l Room No FRVS Recirculation 1A-C-043 4410 Control Panels 18-C-043 4617 l

1C-C-043 4411 1D-C-043 4615 L

1A-C-044 4614 1B-C-044 4616 i

3.0 DESIGN INPUT 1.0 Component temperatures measured during test DCP 4EX-3133, and Design Change DCP 4EC-3254 will be used to determine the heat rise values of the control panel components.

See Attachment 1 and 2 for test data.

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The measured heat rise values are used to calculate the postulated control panel component temperatures during accident condition in a closed door with two muffin fans for cooling configuration by adding the heat rise value to the base-line accident ambient.

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2.0 Normal Design Room Ambient =

95'F (Ref 1)

Postulated Accident Room Ambient = 148'F Post Accident Operability Period = 110 Days 3.0 Estimated' amount of Surveillance time of original panel components to date in the closed door condition is 620 Hours. (See Attachment 4, calculation uses 682

^

hours to account for decay heat.)

Estimated amount of Surveillance time of replaced components (ie., fuses and contactors) is 20 Hours.

(See Attachment 4.)

Estimated amount of Surveillance time in no-door l

configuration is 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. (See A0ttachment 4) 4.0 Estimated amount of Normal Aging time of original panel components to date is 54,750 Hours. (See.)

DE-AP.ZZ-0002(Q)

ATTACHMENT 2

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SHEET RE43RC cewt1tcs. PAtett.,

REFERENCE

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5.0 Activation energy values i

NUTHERM ACTIVATION REFERZNCE PART No ENERGY,eV 1

FUSE KTS-R60 1.3 Reference 5 FUSE HOLDER 20 1.2 Reference 2 CONTACTOR 68 1.29 Reference 10 TRANSFORMER 51 1.03 Reference M WIRE TERMINAL 559 1.27 Reference 8 WIRE (14GA)

L114-1 1.1 Reference 10 TERMINAL BLOCK 111 1.2 Reference 2 3

TERMINAL BLOCK 217 1.2 Reference 2 T/C WIRE 581 1.3 Reference 2 TERMINAL BLOCK 65 1.2 Reference 2 FUSE BLOCK 41513-1 1.2 Reference 2

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6.0 The additional test data provided by NUTHERM in Reference 11 is used in determining the level of qualification of certain control panel components (as indicated on page 6). This additional test data was obtained by NUTHERM and was determined to be applicable to Hope Creek design.

7.0 No margin in temperature is required to calculate component PAOP times because the components are not subjected to accident transient (LOCA) or steam environment in accordance with IEEE 323 - 1974.

4.0 ASSUMPTIONS

1) The temperature rise data measured is representative of the FRVS Recirculation heater control panel components.

2) Aging mechanism of components is controlled by one chemical reaction over a given temperature range.

3) In order to account for decay heat of the components during the surveillance tests, a margin of lot in operating time will be used.

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ATTACHMENT 2

TITLE Q)AL3F3Eb LgFr.

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4) A heat rise of 5'F is assumed for all non stand-by components in the closed door surveillance evaluation.

5.O CALCULATION i

The safety related, age sensitive FRVS Recirculation heater control panel components (reference 3) are listed below.

This table also includes component test data based on the vendor qualification reports. These numbers l

were calculated using the Arrhenius methodology (outlined below) that reconciled component test (s) to the appropriate service conditions (from references 2,5,8,9

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and 11) in order to establish an equivalent test level.

t1 = t2

• exp((Ae/B)*(1/T1 - 1/T2))

where: t1 = Service time t2 = Accelerated aging time Ae = Activation Energy, eV B = 0.8617e-04 eV/*K T1 = Service temperature,

'K l

T2 = Aging temperature,

• K As an example, Reference 5 indicates that the Bussman fuse was tested to the following levels.

1) 169'C (442*K) for 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />

2) 100*C (373*K) for 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> total equivalent test time at 373*K, is therefore j

calculated for an activation energy of 1.3 as....

104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> + 15 hr

• exp ( (1. 3 /B) * (1/ 373 -1/ 4 4 2 ) )

= 8387.82 Hours DE AP.ZZ-0002(Q)

ATTACHMENT 2 m

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CALCULATION DATE ElllT3

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CONTINUATION SHEET PEER REVIEW _M OATE

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.l COMPONENT NUTHERM TEST TEMPERATURES EQUIVALENT

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Part No QUAL TEST W/O DOOR WITE DOOR DATA

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Fuse KTS-R601 135'F to 180*F to 8387 Hr 9 f

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155'F 212*F 373*K (Ref 5)

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Tdiis TIolder~

20

'13 4

• F - ~ 184'F 1,139.15 Hr 9 384.827*K (Ref 10) 4 Contactor 68 133*F to 170*F to 5,037.71Hr 9 144*F 195'F 385.938'K (Ref 10)

Transformer 51 134*F 184*F 3,790.29Hr 9 385.938'K (Ref 10)

Wire 559 144*F 195'F 504 Hr 9 i

Terminal 438*K (Ref 8)

Wire (14G)

SRGS600 144*F 195'F 188.99 Hr 9 472.049*K (Ref 10)

Terminal 111 131*F2 ito'F2 1,082 Hr 9 Block 385'K (Ref 2) 2 Terminal 217 131*F 190'F2 983.5 Hr 9 Block 385'K (Ref 2) 2 T/C Wire 581 131*F 190*F2 305.5 Hr 9 385'K (Ref 2) 2 Terminal 65 131'F 190*F2 1,929.16 Hr 9 Block 385.938*K (Ref 10)

Fuse Block L1513-1 148'F 184*F 1,917.30 Hr 9 385.938'K (Ref 10)

1) Replacement Bussmann fuse

2) A 10*F margin was added to corresponding temp levels.

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ATTACHMENT 2 n.w

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IDNo. NOThEAM-ARRM-CC1 SHEET PSC

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i CALCULATION DA1E Z)f)9.3 CONTINUATION SHEET PEE A REVIEW A?f DATE

__-d tJ 9 3 DCP 4EC-3254 COMPONENT NUTHERM TEST EQUIVALENT Part No TEMPERATURES QUAL TEST DATA 5

Fuse KTS-R60 136.4*F 8387 Hr 9 373*K (Ref 5)

Fuse Holder 20 136.4*F 1139.15 Hr 9 384.827'K (Ref 10)

Contactor 68 149.1'F 5037.71 Hr 9 385.938'K (Ref 10) f Transformer 51 129.6*F 3790.29 Hr 9 385.938'K (Ref 10)

Wire 559 136.4*F 504 Hr 9 Terminal 438'K (Ref 8)

Wire SRGS600 136.4*F 188.99 Hr 9 472.049'K (Ref 10)

Terminal 111 105'F 1082 Hr 9 Block 385'K (Ref 2)

Terminal 217 105'F 983.5 Hr 9 Block 385*K (Ref 2)

T/C Wire 581 90.9'F 305.5 Hr 9 385'K (Ref 2)

Terminal 65 105'F 1929.16 Hr 9 Block 385.938'K (Ref 10)

Fuse Block L1513-1 105'F 1917.30 Hr 9 385.938*K (Ref 10)

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DE. AP.ZZ 0002(O)

ATTACHMENT 2

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1D NO-A4 RM nOTntLm FRY,5 NOMEATQ-ARRM.@)

$HEET PSL REE3RC. cc6mten. PANEL.,

REFERENCE ccmteus.uv

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CALCULATION DATE fill 93

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CONTINUATION SHEET PEER REVIEW W

DATE thi43 Normal Acine To-Date l

The following table summarizes results of the normal aging evaluation of the panel components. It calculates the amount of test time required to envelope the estimated 54,118 hours0.00137 days <br />0.0328 hours <br />1.951058e-4 weeks <br />4.4899e-5 months <br /> of to-date normal aging at the indicated test temperature.

For the fuse & contactor the estimated hours is 9480.

COMPONENT

.NUTHERM POSTULATED AGING EQUIVALENT Part No TEMP DURING

TEMP, TEST TIME NORMAL AGING

(*K)

REQUIRED TO (DOORS ON)

ENVELOPE

'F('K)

NORMAL AGING TO DATE, HRS

'k FUSE KTS-R60 100(310.94) 373 2.9565 i

FUSE HOLDER 20 115(319.27) 384.83 32.0805 CONTACTOR 68 120(322.05) 385.94 4.3125 TRANSFORMER 51 115(319.27) 385.94 84.0653 WIRE 559 100(310.94) 438 0.0578 l

TERMINAL WIRE (14GA)

L114-1 100(310.94) 472.05 0.0445 TERMINAL BLK 111 100(310.94) 385 9.8088 TERMINAL BLK 217 100(310.94) 385 9.8088 T/C WIRE 581 100(310.94) 385 4.7842 TERMINAL BLK 65 100(310.94) 385.94 8.9816 FUSE BLOCK L1513-1 100(310.94) 385.94 8.9816

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CALCULATION DATE

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CONTINUATION SHEET PEER REVIEW Mf

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DATE

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j Surveillance To-Date The following table summarizes results of the surveillance evaluation of the panel components. It calculates the amount of test time required to envelope the to-date surveillance i

tests at the indicated component test temperature.

Surveillance time is 682 hours0.00789 days <br />0.189 hours <br />0.00113 weeks <br />2.59501e-4 months <br /> for all the original i

components and 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> for the contactors and the fuses.

I COMPONENT NUTHERM TO-DATE AGING EQUIVALENT l..

Part No SURVEILLANCE

TEMP, TEST TIME i

TEMPERATURE

(*K)

REQUIRED TO j

(DOORS ON, ENVELOPE i (

95'F AMB)

SURVEILLANCE j

'F(*K)

TO DATE, ERS FUSE KTS-R60 212(373.16) 373 20.3499 FUSE HOLDER 20 184(357.60) 384.83 43.3790 i

CONTACTOR 68 195(363.72) 385.94 1.8693 1

TRANSFORMER 51 184(357.60) 385.94 58.6121 i

WIRE TERMINAL 559 195(363.72) 438 0.7065 6

WIRE (14 GA)

L314-1 195(363.72) 472.05 0.2166 TERMINAL BLK 111 190(360.94) 385 61.1688 l

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TERMINAL BLK 217 190(360.94) 385 61.1688 T/C WIRE 581 190(360.94) 385 50.0333

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TERMINAL BLK 65 190(360.94) 385.94 56.0105 FUSE BLOCK L1513-1 184(357.60) 385.94 39.0912

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DE.AP.ZZ-0002(O)

ATTACHMENT 2

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DATE do es J

l' Surveillance with No Door 1

The following table summarizes results of the surveillance evaluation of the panel components. It calculates the amount of test time required to envelope the surveillance test in l-no door configuration at the indicated temperature. The total amount of surveillance hours is estimated to be 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> eventhough heaters will not be energized during the surveillance test.

I 1

COMPONENT NUTHERM SURVEILLANCE AGING EQUIVALENT Part No TEMPERATURE

TEMP, TEST TIME IN NO-DOOR

(*K)

REQUIRED TO 1

CONFIGURATION ENVELOPE l

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SURVEILLANCE

• F(*K)

TO DATE, ERS FUSE KTS-R60 155.0(341.49) 373 0.2874 FUSE HOLDER 20 134.0(329.83) 384.83 0.0287 CONTACTOR 68 144.0(335.38) 385.94 0.0346 TRANSFORMER 51 134.0(329.83) 385.94 0.0618 WIRE TERMINAL 559 144.0(335.38) 438 0.0004 WIRE (14 GA)

L114-1 144.0(335.38) 472.05 0.0002 TERMINAL BLK 111 131(328.16) 385 0.0228 TERMINAL BLK 217 131(328.16) 385 0.0228 T/C WIRE 581 131(328.16) 385 0.0135 TERMINAL BLK 65 131(328.16) 385.94 0.0209 FUSE BLOCK L1513-1 131(328.16) 385.94 0.0209

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DE-AP.ZZ-0002(Q)

ATTACHMENT 2

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CALC PDR 40Tn8Am FMs 'D No NOThE.Af4-ARRM.@

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REFERENCE

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CALCULATION DATE flfl43

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- f tlO Aecident Evaluation The following table summarizes results of the accident j

evaluation of the panel components. It calculates the amount of test time rap ired to envelope the specified 110 day Post Accident Operability Period at the indicated test i

temperature.

COMPONENT NUTHERM POSTULATED AGING EQUIVALENT l

4 Part No TEMP DURING

TEMP, TEST TIME j

ACCIDENT

(*K)

REQUIRED TO i

• F (*K)

ENVELOPE ACCIDENT, ERS l

y i

i FUSE KTS-R60 197.1(364.88) 373 1073.5210 j

1 FUSE HOLDER 20 197.1(364.88) 384.83 365.1132 l

CONTACTOR 68 209.8(371.94) 385.94 612.9231 k

TRANSFORMER 51 190.3(361.10) 385.94 313.6954 WIRE TERMINAL 559 197.1(364.88) 438 3.1133 t-

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j WIRE (14GA)

L114-1 197.1(364.88) 472.05 0.9380 TERMINAL BLK 111 165.7(347.44) 385 52.8774 TERMINAL BLK 217 165.7(347.44) 385 52.8774 T/C WIRE 581 151.6(339.60) 385 14.0205 TERMINAL BLK 65 165.7(347.44) 385.94 48.4183 FUSE BLOCK L1513-1 165.7(347.44) 385.94 48.4183 i

i DE AP.ZZ-0002(O)

ATTACHMENT 2 m

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2, CALCULATION DATE 2MJ93

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Available Life Evaluation i

Since the Surveillance demands of the panels require that the panels are energized for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> every 31 days, the remaining life of the components will be calculated on a i

monthly basis considering the temperature obtained during the surveillance test for the panel in no door along with shielding installed.

i The amount of life that will be used up during the 1.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> surveillance testing and monthly normal aging is summarized below.

EQUIV EQUIV

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COMPONENT NUTHERM SURV NORMAL TEST TIME TEST TIME 4

Part No TEMP AGING FOR 1.1 ERS FOR 31

(*F)

TEMP SURVEILL-DAYS OF

(*F)

ANCE AND NORMAL COOLDOWN,ERS AGING,BR8 l

FUSE KTS-R60 136.4 105 0.0066 0.3561 FUSE HOLDER 20 136.4 105 0.0031 0.2034 l

CONTACTOR 68 149.1 120 0.0046 0.3380 TRANSFORMER 51 129.6 110 0.0043 0.8309 1

WIRE TERMINAL 559 105 100 0.00001 0.0008 1

WIRE (14GA)

L114-1 105 100 0.00001 0.0006 TERMINAL BLK 111 105 9fi 0.0003 0.0899 TERMINAL BLK 217 105 95 0.0003 0.0899 T/C WIRE 581 90.9 95 0.0001 0.0424 TERMINAL BLK 65 105 95 0.0003 0.0824 FUSE BLOCK L1513-1 105 95 0.0003 0.0824 The surveillance procedure is revised in July 1991 and the panel will not be energized, However in the calculation it is assumed that panel will be energized for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for conservatism.

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DE AP.ZZ-0002(O)

ATTACHMENT 2

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CALCULATION DATE

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CONTINUATION SHEET PEER REVIEW WM DATE U 2J 43 The following table summarizes these calculations to determine the remaining available life.

COMPONENT NUTHERM REMAINING MONTELY LIFE Part No TEST TIME TEST TIME REMAIN-AFTER AGING USED FROM ING BURVEILLANCE AGING AND

& ACCIDENT SURVEILLANCE YEAR 8 ER8 ERS FUSE KTS-R60 7289.8852 0.3627

>>40 FUSE HOLDER 20 698.5486 0.2065

>>40 CONTACTOR 68 4418.5705 0.3426

>>40 TRANSFORMER 51 3333.8554 0.8352

>>40 WIRE TERMINAL 559 500.1220 0.0008

>>40 WIRE (14GA)

L114-1 187.7907 0.0006

>>40 TERMINAL BLK 111 958.1222 0.0902

>>40 TERMINAL BLK 217 859.6222 0.0902

>>40 T/C WIRE 581 192.0687 0.0425

>>40 TERMINAL BLK 65 1815.7287 0.0827

>>40 FUSE BLOCK L1513-1 1820.7830 0.0827

>>40

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DE AP.ZZ-0002(O)

ATTACHMENT 2 mn,r:,

1 TITLE GDALW3Eb LIFE.

10 NO-Ew.

csw ng uarnegm gas NOTHEAM-ARRn 001 SHEET 73 G' str3RC, coortsten,, PAugL, REFERENCE c.e e e.a n n pg

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ORIGINATOR 7fl' 2,,

CALCULATION DATE

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CONTINUATION SHEET PEER REVIEW JVT DATE 4 tin

6.0 CONCLUSION

The existing FRVS recirculation heater control panels with no-door along with shielding installed under DCP 4EC-3254 is qualified for 40 years and 110 days of Post Accident Operability Time.

7.0 REFERENCE 8 1.0 10855-D7.5, " Environmental Desi Hope Creek Generating Station. gn Criteria for the 2.0 NUTHERM International Qualification Report N-160-00R, Rev. 4 dated 5/23/85, " Equipment Environmental

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Qualification Report for Remote Control Panels &

Thermocouples for Hope Creek Nuclear Plant Unit 1 and 2" 3.0 Test and Experiment DCP 4EX-3133

4. 0 IEEE 323-1974, "IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations" t

5.0 Bussmann Report No 470-8, dated June, 1983. " Nuclear Environmental Qualification Test for Class 1E Equipment" 6.0 WORK ORDERS for replacement of Fuses 1A-C-045; 910718156 IB-C-045; 910718158 7.0 WORK ORDERS for replacement of Contactors 1A-C-045; 910717087 1B-C-045; 910717091 8.0 AMP Qualification Test Report 110-11004 Rev 0, dated 2/2/82, " AMP Insulated terminal and spl1ces for Class i

1E inside Containment service in Nuclear Power Generating Station"

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DE.AP.ZZ 0002(Q)

ATTACHMENT 2

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ilTLE Q)At.1F3Eb t.gfE ID NO.

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CALCULATION DATE gg

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DATE 2Ju e 3 9.0 DCP 4EC-3254 l

10.0 NUTHERM Qualification Report No. N-160-00RA1 Rev.0 6

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ATTACHMENT 2 c~- r rm