ML20083A415

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Rev 2 to Procedure 1040-001-021, Reactor Protection Sys
ML20083A415
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 11/02/1983
From:
TOLEDO EDISON CO.
To:
Shared Package
ML17150A231 List:
References
1040-001-021, 1040-1-21, IEB-79-01B, IEB-79-1B, NUDOCS 8312200281
Download: ML20083A415 (69)
v • d • e


Text

CALCULATION / PROBLEM COVER SHEET Calculation / Problem No:

1040-001-021

Title:

Reactor Protection System 2.18 ClientToledo Edison Company Project: Davis-Besse Unit 1 Job No: inkn_nn,_Av1 I&E Bulletin 79-01B Equipment Qualification Dmign input /Reforences:

Design Inputs are outlined in the Cover Report.

Assumptions:

Assumptions are outlined in the Cover Report.

M thod:

I I

Methods are outlined in the Cover Report.

R; marks:

EDS Nuclear Report No. 02-1040-1076.

REV. NO.

REVISION APPROVED DATE orQhoa

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MAS fLIST IndExN)i218M-001 Docket:

50-346 HARSH ENVIRONMENT Rev.:

2 REACTOR PROTECTION SYSTEM Date: //

@I Prepared by:

Checked by: _W2d Date: ///.A/ d l

l l

l l

LOCATION l

l l

l l

l l

Inside l

Outside l

l

'l Worksheet l l Plant l

l Primary l

Primary l

l l

Index No.

I Rev. IID Number l Generic Name l Containment l Containment l REMARKS l

I I

I i

1 l

l t

l 218H-004 1 0 lFTRCIAl i Flow Transmitter l

El. 4 l

l l

l 218H-004 l

2 lFTRCIAl l Flow Transmitter i

El. 4 l

l l

l 218H-005 l 0 lFTRCIA2 l Flow Transmitter l

El. 4 l

l l

l 218H-005 l 2 lFTRCIA2 l Flow Transmitter l

El. 4 l

l l

l 218H-006 1 0 IFTRCIA3 l Flow Transmitter i

El. 4 l

l l

l 218H-006 l

2 lFTRCIA3 i Flow Transmitter l

El. 4 l

l l

l 218H-007 l 0 lFTRCIA4 i Flow Transmitter l

El. 4 l

l l

l 218H-007 l

2 lFTRCIA4 l Flow Transmitter i

El. 4 l

l l

l 218H-008 l 0 lFTRCIBl i Flow Transmitter l

El. 4 l

l l

l 218H-008 l

2 lFTRCIBl i Flow Transmitter l

El. 4 l

l l

l 218H-009 l

0 lFTRCIB2 l Flow Transmitter l

El. 4 l

l l

l 218H-009 l

2 l FTRCIB 2 l Flow Transmitter l

El. 4 I

l l

l 218H-010 1

0 l FTRClB 3 l Flow Transmitter i

El. 4 l

l l

l 218H-010 l 2 lFTRCIB3 l Flow Transmitter l

El. 4 l

l l

l 218H-011 1 0 lFTRCIB4 l Flow Transmitter l

El. 4 l

l 1

l 218H-Oll l

2 lFTRCIB4 l Flow Transmitter l

El. 4.

l l

l l 218H-012 l

2 lPSNI-15-1 l Pressure Switch l

l Rm. 501 l

l l 218H-013 l

2 lPSNI-15-3 l Pressure Switch l

l Rm. 426 l

l l 218H-014 l

2 lPSNI-15-4 i Pressure Switch l

l Rm. 500 l

l l 218H-015 l 2 lPTRC2Al 1 Pressure Transmitter l

Rm. 410 l

I 1

l 218H-016 l

2 lPTRC2A2 l Pressure Transmitter l

Rm. 410 l

l l

l 218H-017 l

2 lPTRC2B1 l Pressure Transmitter l

Rm. 407 l

l l

l 218H-018 l

2 IPTRC2B2 l Pressure Transmitter i

Rm. 407 l

l l

l 218H-019 l 2 lTERC3A2 i Resistance Temperature Detector l

El. 4 l

l l

l 218H-020 1

2 lTERC3A4 l Resistance Temperature Detector l

El. 4 l

l l

l 218H-021 l

2 lTERC3B2 l Resistance Temperature Detector l

El. 5 l

l l

l 218H-022 l

2 lTERC3B4 l Resistance Temperature Detector l

El. 5 l

l l

l 1

I i

l l

1 l

l l

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1 l

1 I

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(] Davis-BessaUnit1 fLIST d

Faci 1 Q s MASTE Index No: 218M-002 Docket:

50-346 NON-HARSH ENVIROMENT Rev.:

z REACTOR PROTECTION SYSTEM Prepared by:

Date:

2 Checked by: p e-. %

,1,,y Date:

/ ' -

2.

1 I

l l

l LOCATION I

l l

l l

l l

Inside l

Outside l

l l Worksheet l l Plant l

l Primary l

Primary l

l l

Index No.

I Rev. IID Number I Generic Name I Containment I Containment REMARKS I

I i

i l

I I

i i

l 1 0 lC3630 l Auxiliary Shutdown Panel l

l Rm. 324 I

I I

l 0 IC5755E l RPS Panel Ch. 2 l

l Rm. 505 l

l l

l 0 IC5755F I RPS Panel Ch. 2 1

1 Rm. 505 l

l l

l 0 IC5756E I RPS Panel Ch. 4 l

l Rm. 505 l

I l

l 0 IC5756F I RPS Panel Ch. 4 l

l Rm. 505 l

l l

l 0 IC5762E I RPS Panel Ch. 1 i

l Rm. 505 I

1 i

1 0 lC5762F l RPS Panel Ch. 1 l

l Rm. 505 I

I l 0 lC5763E I RPS Panel Ch. 3 l

l Rm. 505 I

I i

1 0 IC5763F l RPS Panel Ch. 3 l

l Rm. 505 l

l l

l 0 lPSNI-15-2 I Pressure Switch l

l Rm. 400

)

l i

l l 0 l RC3601 1 Relay Cabinet l

l Rm. 325 i

i 1 0 lRC3602 l Relay Cabinet l

l Rm. 323 l

l l

1 0 lRC3603 l Relay Cabinet i

I Rm. 324 l

l l

l 0 IRC3604 l Relay Cabinet 1

i Rm. 322 l

l I

I I

I I

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I 4

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Facilii sDavis-Bess 2 Unit 1 MASTLaST Index'No 8M-003 s

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2 REACTOR PROTECTION SYSTEM Prepared by:

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Outside l

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Primary i

I Index No.

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I l

i I

I I

I I

I I

I I

I I

I I

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Index No.: 218H-004 N N b Date: O&f*Of Rev.:

O Cncked by:

1 A [d Ge*fe. Date : 9/28/Al l~

ll l EQUIPMENT DESCRIPTION ll_

ENVIRONMENT l

l l__

ll Parameter l Specification l

DOCUMENTATION REF.

l l

1 l System:

ll 1

Qualification (Specification l Qualification ll Qualification l Outstanding l Reactor l l Operating l

1 Year l

1 1 Years l

Note 2 l

J-l l

Analysis l

None l

l I

Method l

Items l

Protection System ll Time l

l l

l l

1 l

lPlcnt ID No.

ll l

l FTRCIAl ll l

l Note 3 l

l l

l l

l Component l lWaperature l l

l l

l l

l l

l Flow 283.0 l

300.0 l

H, X l

J-l l

ll

(*F) l l

l

~j l

l Simultaneous l

None l

Transmitter ll_

l l

l l

Test l

l l

l lI l

l l

l lManufactu rer : Bailey Mete r l l Pressure l

l l

1 l

l 52.0 l

74.7 l

G, X l

J-l l

l l

l l Modal Nu:abert ll(PSIA) l l

BY3X41X-A ll l

l Function:

11_

l l

l Simultaneous l None l

l l

l l

l hat l

l Transmits Flow ll Relative l

l l

l l

l l

l 100.0 l

100.0 l

A l

J-l l

l Signals ll Humidity l

l l

~l ll l

l Simultaneous l Hone l

lAccurecy: Spec: +.5s ll_ (u l

l l

l Test l

l l

l l

l l

Specs [.234 ll l Boric Acid l Boric Acid l

l l

l l

l l

l l

l l

lServica:

ll Chemical l

1800 ppm l

1800 ppm l

A l

CAL-42 l

Analysis l

None l

l Reactor Coolant ll Spray l

pH 5.0 l

pH 5.0 l

l l

l I40P 2 Hot l

l Leg Flow ll l

l for RPS Channel 1 ll l

l l

l 1

l cnd Indication l

l l

l lIncation:

ll l

l l

l l

l l

Containment ll Radiation l1.7 x 107 l

l l

l l

El. 4 ll_

l RADS l4.0 x 107 l

l Flood Imvel Elev:

RADS l CAL-44 l

AG l

l 572'-2"ll l

l l

l l Sequential h atl l Abova Flood Imvel:

l Hone l

l Yes ll Aging l

40 Years l 10.83 Years l

I l

CAL-38 l

l l

l l

l l

lNeedId fors ll l

l l_

l Notu 1 l

ll l

Hot Shutdown lxl ll l

l Analysis l

None l

l l

l l

l l

l l

~

ll Submergence l 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

l Cold Shutdown l1l ll l

l l

l l

l l

l lL l

l l

l l

l l

l l

l I

I

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O V

O O

- Scility: Davio-Begoa Unit 1 SYSTEM COMPONENT EVALUA7 ION WORKSHEET Index No.: 218H-004A i

bckat:

50-346 R3v.:

0 NOTES

' Nepsred by: M/E#tud Dates

&l *S A 2ncksd byshJ/ edf.M Date

/0/2 // /

r i

I

!.. Thio component is scheduled for replacement during the first refueling outage subsequent to component on-site availability.

Interim operation will not be affected due to the time margin provided.

Ons year operating time is used as a conservative maximum specification.

1.

According to profiles G and H, containment conditions will nearly return to ambient (2.5 psig, 104'F) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with e complete return to ambient within seven days.

Asabient conditions will remain for the daration of the accident and ensuing cooldown.

'Ihe 24-hour IDCA simulation test exposed the transmitter to a more severe environment than that which would result from the postulated loss of coolant accident. Since the transmitter remained operable throughout the test, it can be concluded that it will also maintain functional operability during the short term accident envirorunent and the long-term i

cooldown at ambient conditions.

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F cility:

Aic-D2Esa Unit 1 Dockst 50-346 SYSTDI COMPONENT EVAIAIATION WORKSHEET Index No.: 218H-004 Rev. :

2 Prepared by: _

"b Date:

e J Ch ck:d by:

gpt/> A_

V Dates __f/Jo/4 I

II lECUIPMENT DESCRIPTION ll l

l ENVIRONMENT l

ll Parameter I

l l

Specification l Qualification DOCUMENTATION REF.

l

-l ll 1

l

!SpecificationIQualification!l Qualification l Outstanding l lSyctem:

Reactor ll Operating l 1 Year l

1.1 Years l Notes 1 and 2l l

l 1

Method l

Items l

. l l

t Protection System ll Time l

l l

l l

Test l

l l

J-36 l Simultaneous l None l

ll l

l l

l l

l l

lPlcnt ID No. FTRCIAl ll l

l l

l l

l l

r l

ll Temperature l 283.0 l

350.0 l

H, X l

J-36 l Simultaneous l None l

l Component:

Flow ll

(*F) l l

l l

l Test l

l l

Transmitter ll l

l l

l l

l l

ll l

l l

1 l

l l

l Manufacturer Rosemount ll Pressure l

52.0 l

85.0 l

G, X l

J-36 l Simultaneous l None l

l l

ll(PSIA) l l

l l

l Test l

l ll l

l l

l l

1 l

l Modal Number: 1153 ll l

l l

l l

l l

l ll Relative l

100.0 l

100.0 l

A l

J-36 l Simultaneous l None l

l Function:

Transmits ll Humidity l

l l

l l

Test l

l l

Flow Signals ll

(%)

l l

l l

l l

l l

ll l

l l

l l

l l

l Accuracy: Spect 5.0%

ll l Boric Acid l Boric Acid l

l CAL-40 l Simultaneous l l

l Demon:

.42%'

ll Chemical l

1800 ppm l

1800 ppm l

A l

J-36 l

Test l

None l

l ll Spray l

pH 5.0 l

pH 5.0.

l l

Note 3 l

l l

lSarvics: Reactor Coolant ll l

l l

l l

l l

1 l Loop 2 Hot Leg Flow for ll_

l l

l l RPS Ch. 1 and Indication ll l

l l

l l

l Location: Containment ll Radiation l1.7 x 107 l

l l

l l

El. 4 ll RADS l5.0 x 107 l

l RADS l CAL-44 l

J-36 l

l Flood Level Elev: 572'-2"ll l

l l

l j

l

_l l Sequential Testl l

l l

l l

l None l

l Above Flood Ievel Yes ll Aging l

40 Years l

10 Years l

I l

CAL-66 l Sequential l

None l

.)

ll l

l Note 4 l

l J-36 l

Test l

l

,Nerdad for ll l

I Hot Shutdown lX l ll l

l l

l l

l l

l l

1 l

l l Submergence l 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

Cold Shutdown lX l ll l

l l

l l

l l

ll l

l l

l l

l l

" Ficility: E s -Oss32 Unit 1 SYSTEM COMPONENT EV7haiON WORKSHEET Indax NLs.21TH-004A Dockst:

50-346 Rev.:

2 Prsparcd by:

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  1. 8.I Checkzd by: MefL - 17' Date f/]c//}

1.

Tha Rosemount replaces the Bailey Meter in accordance with FCR 78-525.

1

)2 Ons year operating time is used as a conservative maximum specif teation.

l 3.

CAL-40 qualifies components tested in a high pH Boric Acid Spray to a pH value of 5.0.

4 M::terials and/or components sensitive to thermal aging will be replaced as per maintenance and replacement schedules to l

assure that associate component will maintain functional operability in harsh environments.

i 1

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Facility: L418-Besse Unit 1 Dockst:

50-346 SYSTD4 CDMPONENT EVALUATION WORKSHEET Index No.: 218H-005 Rev.

O Prspared by:

. /.

Date 8788/.

Checksd by:

. W JdZn4y[ Date: 9/JA/Af l

ll l

l l

l l EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOCUMENTATION REF.

l ll Parameter Specification Qualification l

ll l Specification Qualification ll Qualification l Outstanding l Method l

Items l

l System Reactor ll Operating l

1 Year l

1 1 Years l

Note 2 l

J-l l

Analysis l

None l

l l

l l

i l Protection System ll Time l

l l

l Note 3 l

l l

l ll l

l l

l l

l lPlcnt ID No.

FIRCIA2 ll l

l l

l l

L l

l l lWaperature l 283.0 l

300.0 l

H, X l

J-l l Simultaneous l

None l

l Component:

Flow ll

(*F) l l

l l

l Test l

l l

Transmitter ll l

l l

l l

l l

l ll l

l l

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I l Manufacturer: Bailey Meter ll Pressure l

52.0 l

74.7 l

G, X l

J-l l Simultaneous l None l

l ll(PSIA) l l

l l

l Test l

l lModel Number BY3X41X-A ll l

l l

I l

l l

' l ll l

l l

l l

l l

l Manction : Transmits Flow ll Relative l

100.0 l

100.0 l

A l

J-l l Simultaneous l None l

l Signals l lIfumidity l

l l

l l

Test l

l l

ll to l

l 1

I l

l l

l Accuracy: Spect +.5%

ll l

l l

l l

l l

l Demons I.23% ll l Boric Acid l Boric Acid l

l l

l l

l

~

ll Chemical l

1800 ppm l

1800 ppm l

A l

CAL-42 l

Analysis l

None l

lServican Reactor Coolant ll Spray l

pH 5.0 l

pH 5.0 l

l l

l l

1 InoP 2 Hot leg Flow ll l

l l

l l

l l

l for RPS Channel 2 ll l

l l

l l

l l

'l end Indication ll l

l l

l l

l l

'lIncations containment l l Radiation l1-7 x 107 RADS l4.0 x 107

l El. 4 ll l

l l

l l

l l

RADS l CAL-44 l

AG l Sequential Wstl None l

l Flood Imvel Elev: 572'-2"ll l

l l

l l

l l

l Abova Flood Invel Yes ll Aging l

40 Years l 10 83 Years l

I l

CAL-38 l

Analysis l

None l

s

!l ll l

l Note 1 l

l l

l l

'lNerdad fors ll l

l l

l l

l

'l

}l Hot Shutdown lxl ll l

l l

l l

l l

l ll Submergence l 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

l Cold Shutdown lX l ll l

l l

l l

l l

-l ll l

I l

I I

l l

1 f

___--._ _ ~ __- -_ _ _ __ _. _ _ _ _ _ _ _ _

i k

tcility: Davio-Becco Unit 1 SYSTIBt COMPONENT EVALUATION WO'RKSHEET

. ockst 50-346 Index No.: 218H-005A' Rev.:

0 w parad by: M / N ##'-3:

Date:

861$/

l h2cked by: M g7. M Dater

/0///9) r 1

j his component is scheduled for replacement during the first refueling outage subsequent to component on-site availability.

1 Interim operation will not be affected due to the time margin provided.

Ons year operating time is used as a conservative maximum specification.

i According to profiles G and H, containment conditions will nearly return to ambient 4

(2.5 psig, 104'F) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with a complete return to ambient within seven days. Ambient conditions will remain for the duration of the accident and ensuing cooldown.

he 24-hour IDCA simulation test exposed the transmitter to a more severe environment than that which would

)

rceult from the postulated loss of coolant accident. Since the transmitter remained operable throughout the test, it can be concluded that it will also maintain functional operability during the short term accident environment and the long-tera cooldown at ambient conditions.

j l

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i f

I 1

9 I

a 1

J l

1 1

4

q F;cility: L40-Be:202 Unit 1 Dock.t 50-346 SYSTDI COMPONENT EVALUATION WORKSHEET Index No.: 218H-005 Rev. :

2 Prsparsd by:

i

==

Dates Checked by:

M_14cf Date: _ ' M/JJ f

l ll l

l 1

l l EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOQJMENTATION REF.

l Qualification l Outstanding l l

ll Parameter l Specification

! Qualification l Specification lQualificationl l

ll i

Method l

Items l

i i

i l System:

Reactor l l Opera' ting l 1 Year l

1.1 Years l Notes 1 and 2l J-36 l Simultaneous l None l

l l

1 l

Protection System ll Time l

l l

l l

Test l

l l

ll l

l l

l l Plant ID No. FTRCIA2 ll l

l l

l l

l l

ll Temperature l 283.0 l

350.0 l

H, X

l J-36 l Simultaneous l None l

l Component Flow ll

("F) l l

l l

l Test l

l l

Transmitter ll l

l l

.l ll l

l 1

i l

I l

l l

I l

lM2nufccturers Rosemount ll Pressure l

52.0 l

85.0 l

G, X l

J-36 l Simultaneous l None l

l ll(PSIA) l l

l l

l Test l

l

'l ll l

l l

l l

l l

l Modal Numbers 1153 ll l

l l

l l

l l

l ll Relative l

100.0 l

100.0 l

A l

J-36 l Simultaneous l None l

'l Function:

Transmits ll Humidity l

l l

l l

'Ns t l

l l

Flow Signals ll

(%)

l l

l l

l l

l l

))

l l

I I

l l

l lAccursey Spec:

5.0%

ll l Boric Acid l Boric Acid l

l CAL-40 l Simultaneous l l

l Demon:

.42%

ll Chemical l

1800 ppm l

1800 ppm l

A l

J-36 l

Test l

None l

l ll Spray l

pH 5.0 l

pH 5.0 l

l Note 3 l

l l

lStrvice s Reactor Coolant ' l l l

l l

l l

l l

l Loop 2 Hot Leg Flow for ll l

l l

l l

l l

- l RPS Ch. 2 and Indication ll l

l l

l l

l l

il Location: Containment ll Radiation l1.7 x 107 RADS l5.0 x 107 RADS l CAL-44 l

J-36 l Sequential Test l None l

l El. 4 ll l

l l

l l

l

!l Flood Level Elev: 572'-2"ll l

l l

l l

l

] Abova Flood IAtvel Yes ll Aging l

40 Years l

10 Years l

I l

CAL-66 l Sequential l

None l

l ll l

l Note 4 l

l J-36 l

Test l

l lNezdsd for:

ll l

l l

l l

l l

l Hot Shutdown lX l ll l

l l

l l

l l

l l l Submergence l 572' - 2" l

603' - 0" j

B l

J-28 l

N/A l

None l

l Cold shutdown lX l ll l

l l

l l

l l

l ll l

l l

l l

l l

4 i

O O

O racility: Divss-Bacce Unit 1 SYSTEM COMPONENT EVAhdION WORKSHEET Ind:x Nol d l8H-005A Mcksts 50-346 Rev.:

2 9.r.Jr2

$ _A_'"O

_ Date Pr: pared by:

hicksd by: h w/)_ 3/ Date 7/jlo//3 1.

The Rosemount replaces the Bailey Meter in accordance with FCR 78-525.

! 2.

One year operating time is used as a conservative maximum specification.

i 3

CAL-40 qualifies components tested in a high pH Boric Acid Spray to a pH value of 5.0.

4 Materials and/or components sensitive to thermal aging will be replaced as per maintenance and replacement schedules to acaure that associate component will maintain functional operability in harsh environments.

?

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Fzcilitys(

ic-Bers Unit 1.

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j Dock ;t s b -346 SYSTDI COMPONENT WALUATION WORKSHEET Index No. : _218H-006 Prepared by: g/Me Date 8 88 f/

ney.:

0

~

Checkad by

WAIIhh, Date:

9/2Bfg/

l~

il l EQUIPMENT DESCRIPTION ll_

ENVIRONMENT l

l ll_

l l

l ll Parameter l Specification l Qualification DOCIEENTATION REF.

l Qualification l Outstanding l l

l 1

l Specification Qualification l l

lSy; tem Pe sctor ll Operating l 1 Year l

1.1 Years l

Note 2 l

J-l l

Analysis l

None l

i Method l

Items l

l Protection System ll Time l

l l

l l

ll l

l Note 3 l

l lPlcnt ID No.

FTRCLA3 ll.

I I

l l

l l

l l

l l l Temperature l l

l l

l

~l l

l l Component:

Flow ll

(*F) l l

l l

l Test l

283.0 l

300.0 l

H, X l

J-l l Simultaneous l

None l

l Transmitter ll l

l l

ll 1

l l Manufacturer: Bailey Meter ll Pressure l

l l

l l

l l

l l

l 52.0 l

74.7 l

G, X l

J-l l Simultaneous l None l

l l Mod 31 Number ll(PSIA) l l

l l

l Test l

l l

BY3X41X-A ll lhancticn ll_

l l

l l

l l

l l

l l

l 1

l l

Transmits Flow ll Relative l

100.0 l

100.0 l

A l

J-l l Simultaneous l None l

l l

l Signals ll Humidity l

l l

l l

Test l

l ll (s )

l l

l Accurccy: Spect +.5%

ll l

l l

1 l

l Demons I.23% ll l Boric Acid l Boric Acid l

l l

l l

l l

l l

l l

l

~

lServica ll Chemical l

1800 ppm l

1800 ppm l

A l

CAL-42 l

Analysis l

None l

l

~l l

Reactor coolant ll Spray l

pH 5.0 I

pH 5.0 l

l Icop 2 Hot Iag Flow ll l

l for RPS Channel 3 ll l

l l

l l

l cnd Indication ll_

l l

l l

l l

l l

l l

l

]Incation: Containment ll Radiation l1.7 x 107 l

l l.

l

._l l

l l

RADS l4.0 x 107 El. 4 ll__

l l

RADS l CAL-44 l

AG l Flood Ievel Elev l

l Sequential Test l 572'-2"ll l

l l

l l Abova Flood Invel None l

Yes ll Aging l

40 Years l 10.83 Years l

I l

CAL-38 l

Analysis l

None l

l l

l l

l l

l l

ll l

l Note 1 l

Heidad fors ll l

l l

l l

l Hot Shutdown lTl ll l

l l

l l

l l

l]X llSubmergencel 572'

-2" l

603' - 0" l

B l

J-28 l

N/A l

None l

l l

l l

~ l Cold Shutdown

-l ll l

l l

l l

l l

ll l

l l

l l

l l

\\

n O

[ Facility:

EL..J-Besse Unit 1 SYSTEM CDMPONENT LALUATION WORKSHEET Dockst 50-346 Index No.: _21CH-006A Rev.:

0 HOTES Prapared by:

N'V.@/F b Date

/#'d '8/

l Checked bys W AD.M Dates

/g/w/p i

/

4 L.

Ric component is scheduled for replacement during the first refueling outage subsequent to component en-site availability.

I Intsrim operation will not be affected due to the time margin provided.

i 2.

Ons year operating time is used as a conservative maximum specification.

1.

According to profiles G and H, containment conditions will nearly return to ambient (2.5 psig, 104*F) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with a complete return to ambient within seven days. Ambient conditions will remain for the duration of the accident and ensuing cooldown.

he 24-hour IDCA simulation test exposed the transmitter to a more severe environment than that which would result from the postulated loss of coolant, accident. Since the transmitter remained operable throughout the test, it can be concluded that it will also maintain functional operability during the short term accident environment and the long-term cooldown at ambient conditions.

i l

1 i

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a I

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O O

Facility 0-Bessa Unit 1 Dockst:

50-346 SYSTEM ODNPONENT EVALUATION WORKSHEET Index No.: _218H-006 Rev.:

2 Prepared by: _

Date:

Checksd by:

.n/deum (A - # Dates,

3 m

f/.Re//3 I

il l EQUIPMENT DESCRIPTION ll l

l ENVIRONMENT l

I l

l DOCUMENTATION REF.

ll Parameter l Specification ll l

i Qualification l Specification l Qualification!l Qualification l Outstanding l l

l Systems Reactor l l Operating l 1 Year l

1.1 Years l Notes 1 and 2l J-36 l Simultaneous l None l

Method I

Items l

1 l

l l

l Protection System ll Time l

l l

l l

Test l

l l

~l 1

ll l

l l

l l

l l

l Plant ID No. FTRCIA3 ll l

l l

l l

l l

l ll Temperature l 283.0 l

350.0 l

H, X l

J-36 l Simultaneous l None l

l Component:

Flow ll

(*F) l l

l l

l Test l

l l

Transmitter ll l

l l

l l

l l

I ll 1

l l

l 1

l l

l Manufacturer: Rosemount ll Pressure l

52.0 l

85.0 l

H, X l

J-36 l Simultaneous l None l

l l

ll(PSIA) l l

l l

l Test l

l.

ll l

l l

l l

l l

l Modal Number: 1153 ll l

l l

l l

l l

l ll Relative l

100.0 l

100.0 l

A l

J-36 l Simultaneous l None l

l Function:

Transmits ll Humidity l

l l

l l

Test l

l l

Flow Signals ll (t) l l

l l

l l

l l

ll l

1 l

l l

l

~l l Accuracy: Specs 5.0%

ll l Boric Acid l Boric Acid l

l CAL-40 l Simultaneous l l

l

. Demon:

.42%

ll Chemical l

1800 ppm l

1800 ppm l

A l

J-36 l'

Test l

None l

l ll Spray l

pH 5.0 l

pH 5.0 l

l Note 3 l

l l

lStrvices Reactor Coolant ll l

l l

l l

l l

l Loop 2 Hot Leg Flow for l l l

l l

l l

l l

l RPS Ch. 3 and Indication ll l

l l

l l

l

'l l Location: Containment l l Radiation l1.7 x 107 l

El. 4 ll l

l l

l l

l l

RADS l 5.0 x 107 RADS l CAL-44 l

J-36 l Sequential Test l None l

.l Flood Level Elev: 572'-2"ll l

l l

l l

l l

lAbova Flood Level:

Yes ll Aging l

40 Years l

10 Years l

I l

CAL-66 l Sequential l

None l

)

ll l

l Note 4 l

l J-36 l

Test l

l Nesded fors ll l

l I

Hot Shutdown lX l ll l

l l

l l

ll Submergence l 572' - 2" l

603' ~ 0" l

B l

J-28 l

N/A l

None l

l

_l Cold Shutdown lX l ll l

l l

l l

l ll l

l l

l l

l l

J

~

Fccility: Lavie-Becca Unit 1 SYSTEM COMPONENT EVALUATION WORKShEET Docksts 50-346 Index No.: 218H-006A s

Rev.

2 Pr7 pared by:

{^^

Date Y [8 8]

Chicksd by: gjer@/1 Date f/34 /3

/

l.

The Rosemount replaces the Bailey Meter in accordance with FCR 78-525.

2 One year operating time is used as a conservative maximum specification.

i 3.

CAL-40 qualifies components tested in a high pH Boric Acid Spray to a pH value of 5.0 j

4 M.terials and/or components sensitive to thermal aging will be replaced as per maintenance and replacement schedules to 1

assure that associate component will maintain f unctional operability in harsh environments.

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CNv)io-BerseUnit1 N,

Facility

's Dock;ts 50-346 SYSTEM COMPONENT EVALUATION WORXSHEW Index No. : 218H-007 Prcpared by: AM&M ' # '

Rev.:

O Date: 8 39.54 Checkad by:

JB_W " f4 Dater

/2m/A g l

ll lBQUIPMENT DESCRIPTION ll l

l ENVIROletENT l

l l

l ll Parameter l Specification l

DOCUMENTATION REF.

' Specification l Qualification )l Qualification l Outstanding l ll_

l Qualification 1

l lSyctem:

Reactor lloperating l 1 Year l

1.1 Years l

Note 2 l

J-l l

Analysis l

Hone l

Method l

Items l

l l

l l

l l

Protection System ll Time l

l l

l Note 3 l

l l

1 ll l

l l

l l

l l

lPlent ID No.

FTRCIA4 ll l

l J

l l

j l

l llMaperature l 283.0 l

300.0 l

H, X l

J-l l Sirultaneous l None l

l Component:

Flow ll

('F) l l

l l

l Test l

l l

Transmitter ll l

l l

l l

l l

1 ll 1

lManufccturer: Bailey Meter ll Pressure l

l l

1 I

I l

52.0 l

74.7 l

G, X

l J-1 l Simultaneous l None l

l ll(PSIA) l l

l l

l hst l

l lModel Number BY3X41X-A ll l

l l

l l

l l

l Il l

l l

l l

l l

l Function: Transmits Flow ll Relative l

100.0 l

100.0 l

A l

J-l l Simultaneous l None l

l Signals ll Humidity l

l l

l l

Wat l

l l

ll n) l l

l l

l l

l l Accuracy: Spect +.5%

ll l

l l

l l

l l

l Demon: +.23t ll l Boric Acid l Boric Acid l

l l

l l

l

~

ll Chemical l

1800 ppm l

1800 ppm l

A l

CAL-42 l

Analysis l

None l

.lServica:

neactor coolant ll Spray l

pH 5.0 l

pH 5.0 l

l l

l l

l IcoP 2 Hot Img Flow ll l

l l

l l

l l

l for RPS Channel 4 ll l

l l

l l

l

,.)

and Indication ll l

l l

l l

l

_l

'lIncation: Containment l l Radiation ll.7 x 107 l

El. 4 ll l

l l

l l

l l

RADS l4.0 x 107 RADS l CM.- C l l

AG l Sequential Mstl None l

l ll Flood Imvel Elev: 572'-2"ll l

l l

l l

l l

Il Abov3 Flood Ievel Yes ll Aging l

40 Years l 10.83 Years l

I l

CAL-38 l

Analysis l

None l

l ll l

l Note 1 l

l l

l l

lNerded for ll l

l l

l l

-l l

[l Hot Shutdown lX l ll l

l l

l l

l l

l ll Submergence l 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

0 told Shutdown lX l ll l

l l

l l

l l

0 ll l

l l

l l

l l

J tellity: Davis-Besse 14 tit 1 4:x:kat:

50-346 SYSTitt COMPONENT EVALUATION WORKSHEET I

Index No. : 218H-007A nov.:

o

! Ycparsd by: F*AESI4f?

NOTES Date M* 2'8/.

1 hecksd by:M 4/. M Deter

/4/2.-/f/

c/

his component is scheduled for replacement during the first refueling outage subsequent to component on Interin operation will not be affected due to the time margin provided.

-site. availability.

l 1

Ons year operating time is used as a conservative maximum specification.

! l.

According to profiles G and H, containment conditions will nearly return to ambie t j

o complete return to ambient within seven days.

(2 5 psig, 104*F) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with n

He 24-hour IOCA simulation test exposed the transmitter to a more severe environment than cooldown.

4 recult from the postulated loss of coolant accident.

which would concluded that it will also maintain functional operability during the short term accident environme tSince t i

cooldown at ambient conditions.

n and the long-tera i

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FJcilityt Lic-Be223 Unit 1 SYSTEM COMPONENT EVALUATION WORKSHEET v

Dock;t:

50-346 Index No.: 218H-107 Rev.

2 Check;d by:

h, Date:

.2 Prepar;d by:

Date:

9/Ja/d l

ll l

l 1

l l EQUIPMENT DESCRIPTION ll ENVIRONMENT DOCUMENTATION REF.

l Qualification l Outstanding l l

ll Parameter l Specification Qualification Specification Qualification' Method Items l

l ll i

l lSyr.tsc Reactor ll Operating l 1 Year l

1.1 Years l Notes 1 and 2l J-36 l Simultaneous l None l

l Protection System ll Time l

l l

l l

Test l

l l

ll 1

l l

l l

l lPirnt ID No. FTRCIA4 ll l

l l

l l

l s

l ll Temperature l 283.0 l

350.0 l

H, X

l J-36 l Simultaneous l None l

l Component:

Flow ll

(*F) l l

l l

l Test l

l l

Transmitter ll l

l l

l l

l l

l ll l

l l

l l

l l

l Manufacturer: Rosemount ll Pressure l

52.0 l

85.0 l

G, X

l J-36 l Simultaneous l None l

l lj(PSIA) l l

l l

l Test l

l l

ll l

l l

l l

l l

lModel Number: 1153 ll l

l l

l l

l l

l ll Relative l

100.0 l

100.0 l

A l

J-36 l Simultaneous l None l

l Function:

Transmits ll Humidity l

l l

l l

Test l

l l

Flow Signals ll

(%)

l l

l l

l l

1 ll l

l 1

l l

1 l

lAccurccy: Spect 5.0%

ll l Boric Acid l Boric Acid l

l CAL-40 l Simultaneous l l

l Demon:

.42%

ll Chemical l

1800 ppm l

1800 ppm l

A l

J-36 l

Test l

None l

l ll Spray l

pH 5.0 l

pH 5.0 l

l Note 3 l

l l

lSi;rvice s Reactor Coolant ll l

l l

l l

l l

l Loop 2 Hot Leg Flow for l l l

l l

l l

l l

l RPS Ch. 4 and Indication ll l

l l

l l

l l

lLocEtion: Containment l l Radimtion l1.7 x 107 RADS 15.0 x 107 RADS l CAL-44 l

J-36 l Sequential Testl None l

l El. 4 ll l

l l

l l

l l Flood Level Elev: 572'-2"ll l

l l

l l

l l

lAbova Flood Level Yes ll Aging l

40 Years l

10 Years l

I l

CAL-66 l Sequential i

None l

l ll l

l Note 4 l

l J-36 l

Test l

l lNeeded fors ll l

l l

I l

l l Hot Shutdown lX l ll l

l l

l l

l l

ll Submergence l 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

l Cold Shutdown lX l ll l

l l

l l

l l

l ll l

l l

l l

l l

N

\\

/

Fccilitys L Jie-Berse Unit 1 SYSTEM COMPONENT EVAUJATION WORKSHEET l Dockat:

50-346 Index No.: 218H-007A Rev.:

2 Prsparsd by:

ge-d Date _

[d

! Checksd by: h /7m _ #

Date f/Fh//3 4

1.

The Rosemount replaces the Bailey Meter in accordance with FCR 78-525.

t 4

j 2 Ons year operating time is used as a conservative maximum specification.

3 CAL-40 qualifies components tested in a high pH Boric Acid Spray to a pH value of 5.0 4.

Materials and/or components sensitive to thermal aging will be replaced as per maintenance and replacement schedules to '

assure that associate component will maintain functional operability in harsh environments.

I l

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'LJc-Berse Urtit 1 d

Dck t:

50-346 SYSTDt COMPONDIT EVALUATION WORKSHEET Index No. : 218H-008

?rspar;d by
N/NA ;^ h Re v. :

0 Date:

9' 38' 0$

2 necked by:

11JLWPMAs, Date:

4,.}2AlbI l

ll lIQUIPMENT DFSCRIPTION ll l

ENVIROtetENT l

l ll Parameter l Specification l

DOCUMENTATION REF.

l l

ll l

l Specification l Qualification ll Qualification l Outstanding l

' Qualification I

l System:

Reactor l l Operating l 1 Yea r l

1.1 Years l

Note 2 l

J-l l

Analysis l

None l

Method l

Items l

l l

l

~l l

Protection System ll Time l

l l

l Note 3 l

l l

ll l

l l

l l

l l

lPlcnt ID No.

F7RC181 ll l

l l

l l

l l

ll'Itaperature l 283.0 l

300.0 l

H, X l

J-l l Simultaneous l None l

Component:

Flow ll

('F) l l

l l

Test l

l Transmitter ll l

l l

l l

l l

1 ll l

Manufccturer : Bailey Mete r l l Pressure l

l l

l l

l l

52.0 l

74.7 l

G, X

l J-l l Simultaneous l

None l

ll(PSIA) l l

l l

l Test l

l Model Number: BY3X41X-A ll l

l l

l l

l l

ll l

1 1

Function: Transmits Flow ll Relative l

100.0 l

100.0 l

A l

J-l l Simultaneous l

None l

l l

l l

l Signals ll Humidity l

l l

l l

Test l

l ll

(* )

l l

l l

l l

l Accur:cy: Spec: +.5%

ll l

l l

l l

l l

Demons I.23% ll l Boric Acid l Boric Acid l

l l

l l

~

ll Chemical l

1900 ppm l

1800 ppm l

A l

CAL-42 l

Analysis l

None l

Servica Reactor Coolant ll Spray l

pH 5.0 l

pH 5 0 l

l l

l l

Ioop 1 Hot Img Flow ll l

l l

l l

l l

for RPS Channel 1 ll l

l l

l l

l l

end Indication ll l

l Incation: (bntainment l l Radiation l1.7 x 107 l

l l

l l

RADS l4.0 x' 107 El. 4 ll l

l l

l l

l l

RADS l CAL-44 l

AG Flood Ievel Elev 572 '-2 " l l l

l l

l l

l l

l Sequential Twat l None l

Abova Flood Invel Yes ll Aging l

40 Years l 10.83 Years l

I l

CAL-38 l

Analysis l

None l

ll l

l Note 1 l

l l

l l

Ne:ded fcr:

ll l

l l

l l

l l

Hot Shutdown lxl ll l

l l

l l

l l

lisubmergencel 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

Cold Shutdown lxl ll l

l l

l l

l l

ll l

l l

l l

l l

lt

~

tcility: Davio-Becco Unit 1 SYSTDi COMPONENT EVALUATION WORKSHEET ockst 50-346 Index No.: 218H-008A Rev.:

o rcparsd by: 48/./

  • Date

/G 2 1/,

hocked by: M XM.M Dates

/d/2/P i f

His component is scheduled for replacement during the first refueling outage subsequent to component on-site availability.

Interim operation will not be affected due to the time margin provided.

1 Ono year operating time is used as a conservative maximum specification.

According to profiles G and H, containment conditions will nearly return to ambient (2.5 psig,104*F) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with a complete return to ambient within seven days.

Ambient conditions will remain for the duration of the accident and ensuing cooldown.

We 24-hour IDCA simulation test exposed the transmitter to a s.tr, severe environment than that which would rssult from the postulated loss of coolant accident.

Since the transmitter remained operable throughout the test, it can be concluded that it will also maintain functional operability during the short term accident environment and the long-term cooldown at ambient conditions.

1 I

i l

l i

7_.s f

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PJcility: b _ d-Be r 2 Unit 1 k

)

SYSTEM COMPON ALUATION WORKSHEET Index No'.i 218H-008

~

Dock t 50-346 Rev.:

2 Pr: pared by:

Dater [

Checksd by:

M _ s>/

Date:

7/.7)//J l

11 I

i 1

-l l EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOCUMENTATION REF.

l Qualification l Outstanding l l

ll Parameter l Specification l Qualification Specification IQualification Method l

Items l

l ll l

1 t

I l

lSyctcs:

Reactor ll Operating l 1 Year l

1.1 Years l Notes 1 and 2l J-36 l Simultaneous l None l

l Protection System ll Time l

l l

l l

Test l

l 1

11 l

l l

l 1

I I

lP14 tnt ID No. FTRClB1 ll l

l l

l l

l l

l ll Temperature l 283.0 l

350.0 l

H, X l

J-36 l Simultaneous l None l

l Component:

Flow ll

(*F) l l

l l

l Test l

l l

Transmitter ll l

l l

l l

l l

l ll 1

l l

l l

l l

lManufteturer: Rosemount ll Pressure l

52.0 l

85.0 l

G, X l

J-36 l Simultaneous l None l

l ll(PSIA) l l

l l

l Test l

l l

il l

l l

l l

l l

l Modal Number: 1153 ll l

l l

l l

l l

l ll Relative l

100.0 l

100.0 l

A l

J-36 l Simultaneous l None l

l Function:

Transmits ll Humidity l

l l

l l

Test l

l l

Flow Signals ll

(%)

l l

l l

l l

l ll 1

I l

i i

I l

lAccurtcy: Spec:

5.0%

ll l Boric Acid l Boric Acid l

l CAL-40 l Simultaneous l l

l Demon:

.42%

ll Chemical l

1800 ppm l

1800 ppm l

A l

J-36 l

Test l

None l

l ll Spray l

pH 5.0 l

pH 5.0 l

l Note 3 l

l l

lSsrvice Reactor Coolant ll l

l l

l l

l l

l Loop 1 Hot Leg Flow for ll l

l l

l l

l l

l RPS Ch. I and Indication ll l

l l

l l

l l

lIocction: Containment l l Radiation l1.7 x 107 RADS l5.0 x 107 RADS l CAL-44 l

J-36 l Sequential Test l None l

l El. 4 ll l

l l

l Flood Level Elev: 572'-2"ll l

l l

lAbova Flood Level: Yes ll Aging l

40 Years l

10 Years l

I l

CAL-66 l Sequential l

None l

l ll l

l Note 4 l

l J-36 l

Test l

l lNerdsd fors ll l

l l

l l

l l

l Hot Shutdown lX l ll

^

l l

l l

l l

l

~

l l l Submergence l 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

l Cold Shutdown lX l ll l

l l

l l

l l

l ll l

l l

l l

l l

f%)

(OJ J

Pccility: ts.vic-Besse Unit 1 SYSTEM COMPONENT EVALUATION WORKSHEET Dockst 50-346 Ind x No.: 218H-008A Rev.:

2 Prcparsd by:

't Date checkcd by: & nEL_-H Date f/Jo//h

[

1.

The Rosemount replaces the Bailey Meter in accordance with FCR 78-525.

e 2

Ona year operating time is used as a conservative maximum specification.

3.

CAL-40 qualifies components tested in a high pH Boric Acid Spray to a pH value of 5.0 4

Materials and/or components sensitive to thermal aging will be replaced as per maintenance and replacement schedules to casure that associate component will maintain functional operability in harsh environments.

i 4

E i

i i

i 1

1

Y C

I Facility:

L_.,,ac-Becco t# tit 1 SYSTEM CDMPONDIT EVALUATION WORKSHEET Dockst:

50-346 Index No. : 218H-009 Rev.:

0 Prcpared by: g/ [fM M Date: 9 J#d/.

Quecked bya

,khPw~TWM. Date: 9,/2A/At l

ll l

l EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOCUMENTATION REF.

, l l

l l

ll Parameter l Specification l Qualification l Qualification l Outetanding l l

l ll

, Specification Qualification l Method l

Iteras l

a i

?

l l

l l Systems hactor l l Operating l 1 Yea r l

1.1 Years l

Note 2 l

J-l l

Analysis l

None l

l Protection System ll Time l

l l

l Note 3 l

l l

l ll l

l l

l l

l l

lPlcnt ID No.

F'I1tClB2 ll l

l l

l l

l l

i l

l lMaperature l 283.0 l

300.0 l

H, X l

J-l l Simultaneous l

None l

l Component:

Flow ll

(*F) l l

l l

l Test l

l

! l Transmitter ll l

l l

l l

l l

l ll l

l l

l l

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lManufccturer: Bailey Meter ll Pressure l

52.0 l

74.7 l

G, X

l J-l l Simultaneous l None l

l ll(PSIA) l l

l l

l Wat l

l lModer Number BY3X41X-A ll l

l l

l l

l l

I ll 1

I l

l l

l l

l Punction : Transmits Flow ll Relative l

100.0 l

100.0 l

A l

J-l l Simultaneous l None l

l Signals ll Humidity l

l l

l l

hst l

l l

ll (t )

i I

l l

l l

I l Accur cy: Spec

+.5%

ll l

l l

l l

l l

l Demons I.23% ll l Boric Acid l Boric Acid l

l l

l l

l ll Chemical l

1800 ppm l

1800 ppm l'

A l

CAL-42 l

Analysis l

None l

~

' l Services Reactor Coolant ll Spray l

pH 5.0 l

pH 5.0 l

l l

l l

ll InoP 1 lbt Img Flow ll l

l l

l l

l l

l l for RPS Channel 2 ll l

l l

l l

l l

l cnd Indication ll l

l l

l l

l l

llIncation Containment l l Radiation l1.7 x 107 RADS l4.0 x 107 RADS l CAL-44 l

AG l Sequential hatl None l

l El. 4 ll l

l l

l l

l l

3 l Flood Imvel Elev 572'-2"ll l

l l

l l

4 l Abova Flood Imvel Yes l l Aging l

40 Years l 10.83 Years l

I l

CAL-38 l

Analysis l

None l

l l

l ll l

l Note 1 l

l l

l l

llNerdid fors ll l

l l

l l

l l

l Hot Shutdown lX~l ll l

l l

l l

l

~l r

4l llSubmergencel 572'

-2" l

603 - 0" l

B l

J-28 l

N/A l

None l

!l Cold Shutdown lX l ll l

l l

l l

l l

.I ll l

l l

l l

l l

R

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/

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a

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\\

l

?acility:

SYSTEM COMPONENT ATION WORKSHEET Index Nok'218H-009A bckst 50-346 Rev.:

0

>repar:d by: /4 Date

/ *

  • 2'//.

f

heck d by: M Ap,M Date

/o/z,/1/

g Wic component is scheduled for replacement during the first refueling outage subsequent to component on-site availability.

Intsrim operation will not be af fected due to the time margin provided.

Ono year operating time is used as a conservative maximum specification.

B.

According to profiles G and H, containment conditions will nearly return to ambient (2.5 psig,104*F) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with a complete return to ambient within seven days. Ambient conditions will remain for the duration of the accident and ensuing cooldown. We 24-hour IDCA simulation test exposed the transmitter to a more severe environment than that which would rszult from the postulated loss of coolant accident. Since the transmitter remained operable throughout the test, it can be concluded that it will also maintain functional operability during the short term accident environment and the long-term cooldown at ambient conditions.

m k

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F_cility: k m.j-Be =3 Unit 1 SYSTEM COMPON_ _ iALUATION WORKfHEET Index N 18H-009 Dockit 50-346 Rev.:

2

[

[/

Pr:parad by:

Dater Check 1d by:

M n fl-fL/

Date:

q/3 eft's l

ll l

l l

l l EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOCUMENTATION REF.

l Qualification l Outstanding l l

ll Parameter l Specification Qualification l Specific.ation Qualification Method Items l

l ll l

1

.I l

1 l

lSyttea:

Reactor ll Operating l 1 Year l

1.1 Years l Notes 1 and 2l J-36 l Simultaneous l None l

l Protection System ll Time l

l l

l l

Test l

l l

ll l

l l

l l

?

l lPltnt ID No. FTRClB2 ll l

l l

l l

l l

l ll Temperature l 283.0 l

350.0 l

H, X l

J-36 l Simultaneous l None l

l Component:

Flow ll

(*F) l l

l l

l Test l

l l

Transmitter ll l

l l

l l

l l

l ll l

l l

l l

l l

lM:nufseturer: Rosemount ll Pressure l

52.0 l

85.0 l

G, X

l J-36 l Simultaneous l None l

l ll(PSIA) l l

l l

l Test l

l l

ll l

l l

l 1

lModel Number: 1153 ll l

l l

l l

l l

l ll Relative l

100.0 l

100,0 l

A l

J-36 l Simultaneous l None l

\\

l Function:

Transmits ll Humidity l

l l

l l

Test l

l l

Flow Signals ll

(%)

l l

l l

l l

l l

ll l

l l

l l

l l

lAccurccy: Spect 5.0%

ll l Boric Acid l Boric Acid l

l CAL-40 l Simultaneous l l

l Demon:

.42%

ll Chemical

.l 1800 ppm l

1800 ppm l

A l

J-36 l

Test l

None l

l ll Spray l

pH 5.0 l

pH 5.0 l

l Note 3 l

l l

lSarvices Reactor Coolant ll l

l l

l l

l l

l Loop 1 Hot Leg Flow for l l l

l l

l l

l l RPS Ch. 2 and Indication ll l

l l

l l

l l

7 7 RADS l 5.0 x 10 RADS l CAL-44 l

J-36 lSequer tial Test l None l

l Location: Containment ll Radiation l1.7 x 10 l

El. 4 ll l

l l

l Flood Level Elev: 572 '-2" l l l

l l

l l

lAbova Flood Level Yes ll Aging l

40 Years l

10 Years l

I l

CAL-66 l Sequential l

None l

l ll l

l Note 4 l

l J-36 l

Test l

l lNatdsd for ll l

l l

l l

l l

Hot Shutdown lX l ll l

l l

1 l

l l

l l l Subme rgence l 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

l Cold Shutdown l X l ll l

l l

l l

l l

l ll l

l l

l l

l l

F&cility: L 42-Beaca Unit 1 SYSTEM COMPONENT EV L ulION WORKSHEET Index Lv'218H-009A Dockat:

50-346 Rev.

2 Pr: pared by:

^3 Date 28 j

Check:d by: M Date F/Ja/#J i

1.

The Rosemount replaces the Bailey Meter in accordance with FCR 78-525.

2 One year operating time is used as a conservative maximum specification.

3.

CAL-40 qualifies components tested in a high pH Boric Acid Spray to a pH value of 5.0.

4 Materials and/or components sensitive to thermal aging will be replaced as per maintenance and replacement. schedules to assure that associate component will maintain functional operability in harsh environments.

i j

i t

1 1

l

A

\\

tellity: Ib,~l-Becca thit 1 ockst 50-346 SYSTEM COMPONENT EVALUATION WORKSHEET 4

Index No. : _218H-010 Rev.:

0 Tcpared by:

M Date: 9.J 8 #.

h:cksd by K 6 glL Datea f/Ja/d/

s ll l

EQUIPMENT DESCRIPTION ll ENVIRONMENT l

l l

l DOCUMENTATION REF.

ll Parameter l Specification Qualification l Specification l Qualification ll Qualification l Outstanding l ll l

1 l

l l

l l

Method l

Items l

Sy2tems Reactor ll Operating l 1 Yea r l

1.1 Years l

Note 2 l

J-l l

Analysis l

None l.

Protection System ll Time l

l l

l Note 3 l

l l

ll l

l l

l 1

I l

Plcnt ID No.

FTRClB3 ll l

l l

l l

l l

l l'Itaperature l 283.0 l

300.0 l

H, X l

J-l l Simultaneous l

None l

l Component Flow ll

('F) l l

l l

l

'It st l

l Transmitter ll l

l l

l l

l l

i ll l

l l

l l

l I

Nanufteturer : Bailey Meter l l Pressure l

52.0 l

74.7

\\

G, X l

J-l l Simultaneous l None l

ll(PSIA) l l

l l

l Test l

l Model Number BY3X41X-A ll l

l l

l l

l l

ll l

l l

l l

l l

4 Ebnction: Transmits Flow llnelative l

100.0 l

100.0 l

A l

J-l l Simultaneous l None l

Signals ll Humidity l

l l

l l

Test l

l ll (s) l l

l l

l I

1

Accuracy: Spec

+.5s ll l

l l

l l

l l

Demon: I.23% ll l Boric Acid l Boric Acid l

l l

l l

~

ll Chemical l

1800 ppet l

1800 ppm l

A l

CAL-42 l

Analysis l

None l

} Servican Reactor Coolant ll Spray l

pH 5.0 l

pH 5.0 l

l l

l l

IcoP 1 Hot Img Flow ll l

l l

l l

l l

for RPS diannel 3 ll l

l l

l l

l

\\

ond Indication ll l

l l

l l

l l

'tocation: Containment l l Radiation l1. 7 x 107 RADS l4.0 x 107 RADS l CAL-44 l

AG l Sequential Test)

None l

El. 4 ll l

l l

l l

l l

Flood Imvel Elev
5 72 '-2 " l l l

l l

l l

l l

j @ ova Flood Imvel Yes ll Aging l

40 Years l 10.83 Years l

I l

CAL-38 l

Analysis l-None l

ll l

l Note 1 l

l l

l l

Azdzd for ll l

l l

l l

l l

Hot Shutdown lXl ll l

l l

l l

l l

ll Submergence l 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

Cold Shutdown lX l ll l

l l

l l

l l

lI l

l l

l l

l l

(~s,

['N kCi-)Bemo Lktit 1

(

/

Facility:

SYSTEM COeiPONENT ATION WORKSHEET Index No. M ICH-010A Dock:t:

50-346 Rev.:

0 NOTES Pr^parsd by: M/.

Dater

/d /

  • 8 /,

' 31:ckad by: M #. 77/es,/u Dater fo/f/p/

/

L.

Rio component is scheduled for replacement during the first refueling outage subsequent to component on-site availability.

Int 0ria operation will not be af fected due to the time margin provided.

2.

Ono year operating time is used as a conservative maximum specification.

5.

According to profiles G and H, containment conditions will nearly return to ambient (2.5 psig, 104*F) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with a complete return to ambient within seven days. Ambient conditions will remain for the duration of the accident and ensuing cooldown. We 24-hour IOCA simulation test exposed the transmitter to a more severe environment than that which would risult from the postulated loss of coolant accident. Since the transmitter remained operable throughout the test, it can be cencluded that it will also maintain functional operability during the short term accident environment and the long-term cooldown at ambient conditions.

- - - - - - ~ - - - -

F;cility: L.v.c-Be::;s2 Unit 1 Dockst 50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Index No.: 218H-010 Rev.:

2 Prepared by:

Chicksd by:

N 't'{4 M /,

Dates Date:

$/)laf/3 I

il I

i 1

l l EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOCUMENTATION REF.

l Qualification l Outstanding l l

ll Parameter l Specification l Qualification ISpecification ! Qualification l Method l

Items l

l ll l

1 i

I i

l l

lSyttsm:

Reactor ll Operating l 1 Year l

1.1 Years l Notes 1 and 2l J-36 l Simultaneous l None l

l Protection System ll Time l

l l

l l

Test l

l l

ll l

l l

l l

l l

l Plant ID No. FTRClB3 ll l

l l

l l

l l

l ll Temperature l 283.0 l

350.0 l

H, X

l J-36 l Simultaneous l None l

l Component:

Flow ll

(*F) l l.

l l

l Test l

l l

Transmitter ll l

l l

l l

l 1

.ll l

1 1

I i

l l

l Manufacturer: Rosemount ll Pressure l

52.0 l

85.0 l

G, X l

J-36 l Simultaneous l None l

l ll(PSIA) l l

l l

l Test l

l l

ll l

l 1

l l

l l Modal Number: 1153 ll l

l l

l l

l l

l ll Relative l

100.0 l

100.0 l

A l

J-36 l Simultaneous l None l

1 l Function:

Transmits ll Humidity l

l l

l l

Test l

l l

Flow Signals ll

(%)

l l

l l

l l

l l

ll 1

1 I

I l

l l

' l Accurecy: Spect 5.0%

ll l Boric Acid l Boric Acid l

l CAL-40 l Simultaneous l l

4 l

Demon:

.42%

ll Chemical l

1800 ppm l

1800 ppm l

A l

J-36 l

Test l

None l

l ll Spray l

pH 5.0 l

pH 5.0 l

l Note 3 l

l l

{ l Services Reactor Coolant ll l

l l

l l

l I

i l Loop 1 Hot Leg Flow for ll l

l l

l l

l l

j l RPS Ch. 3 and Indicationll l

l l

l l

l l

l Location: Containment l l Radiation l1.7 x 107 RADS l5.0 x 107 RADS l CAL-44 l

J-36 l Sequential Test l None l

,l El. 4 ll l

l l

l l

l l Flood Level Elev: 572'-2"ll l

l l

l l

l l

1 lAbova Flood Level: Yes ll Aging l

40 Years l

10 Years l

I l

CAL-66 l Sequential l

None l

l ll l

l Note 4 l

l J-36 l

Test l

l lNasdad fors ll l

l l

l l

l l Hot Shutdown lX l ll l

l l

l l

l l

l l Submergence l 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

l Cold Shutdown lX l ll l

l l

l l

l l

l ll l

l l

l l

l l

4

\\o J

d 4

l 1 Mcility: L vde-Bessa Unit 1

) h kst 50-346 SYSTDI COMPONENT EVALUATION WORKSHEET Index No.: _218H-010A Prcparsd by:

Check:d by: _

d't" h

Rev.: _

2 Date _

MO -ff Date_ 7/Je/p>

4 l.

The Rosemount replaces the Bailey Meter in accordance with FCR 78 525 2

Ons year operating time is used as a conservative maximum sp ecification.

'3 CAL-40 qualifies components tested in a high pH Boric Acid Sp i

ray to a pH value of 5.0 4

Msterials and/or components sensitive to thermal aging will b assure that associate component will maintain functional operability in he replaced as per maintenance and replacement arsh environments, l

1 i

i l

l l

l l

q

/O Facility:

,10-Be ra Unit 1 U

Dockct:

50-346 SYSTEM ODMPONENT EVALUATION WORKSHEET Index No. : 218H-Oll Rev.:

O Prcpared by: MMM/ M Date 7 Jf'8/.

f Check 2d by:

M d "3" M l Date: Jf M fgl g

l ll l EQUIPMENT DESCRIPTION ll l

l ENVIRONMENT l

l l

ll Parameter l

DOCUMENTATION REF.

l Qualification l Outstanding l l

Specification l Qualification, Specification Qualification l Method l

Items i

ll l

l System:

Heactor l loperating l 1 Year l

1.1 Years l

Note 2 l

J-l l

Analysis l

None l

l 1

l l

l l

Protection System ll Time l

l l

l Note 3 l

l l

l ll l

l l

l l

I l

lPlcnt ID No.

FTRClB4 ll l

l l

l l

l l

l ll Temperature l 283.0 l

300.0 l

H, X

l J-l l Simultaneous l

None l

l Component:

Flow ll

('P) l l

l l

l Test l

l l

Transmitter ll l

l l

l l

l l

l ll l

l l

l l

l

~l lManufccturer: Bailey Meter ll Pressure l

52.0 l

74.7 l

G, X

l J-l l Simultaneous l

None l

l ll(PSIA) l l

l l

l Test l

l l Modal Number BY3X41X-A ll l

l l

l l

l l

l ll l

l l

l l

l l

lR nction: Transmits Flow ll Relative l

100.0 l

100.0 l

A l

J-1 l Simultaneous l

Hone l

l Signals ll Humidity l

l l

l l

'Itr at l

l l

ll (u

l l

l l

l l

l l Accuracy: Spect +.5%

ll l

l l

l l

l l

l Demon: +.23% ll l Boric Acid l Boric Acid l

l l

l l

~

ll Chemical l

1800 ppm l

1800 ppm l

A l

CAL-42 l

Analysis l

Hone l

4 lServica: Beactor Coolant ll Spray l

pH 5.0 l

pH 5.0 l

l l

l l

l IcoP 1 lbt Ieg Flow ll l

l l

l l

l l

l for RPS Ciannel 4 ll l

l l

l l

l l

l cnd Indication ll l

l l

l l

l l

lIncstiens Containment l l Radiation l1.7 x 107 RADS l4.0 x 107 l

d. 4 ll l

l l

l l

l l

RADS l CAL-44 l

AG l Sequential 'Itratl None l

l Flood Ievel Elev: 572'-2"ll l

l l

l l

l l

lAbova Flood Invel Yes ll Aging l

40 Years l 10 83 Years l

I l

C AL-38 l

Analysis l

Hone l

l ll l

l Note 1 l

l l

l l

. lNeedId fors ll l

l l

l l

l l

' l Not Shutdown lXl ll l

l l

l l

l l

. 1 ll Submergence l 572' - 2" l

603' - 0" l

B l

J-28 l

N/A l

None l

l Cold Shutdown l _Xl ll l

l l

l l

l l

l ll l

l l

l l

l l

A

(

) Be Facility km.m-Oa Unit 1 Dockst 50-343 SYSTDI COMPONENT EVALUATION WORKSHEET Index No.

_218H-Oll A NOTES Rev.

0 Preparsd by: M'%b Date:

N'2 'I(

Q1:cked bys M f "M Dates

/ Oft /f/

Y 1.

'Ihis coisponent is scheduled for replacement during the first refueling outage subsequent to c Interim operation will not be affected due to the time margin provided.

omporzent on-site availability.

2.

Oto year operating time is used as a conservative maximum specification.

3.

According to profiles G and H, containment conditions will nearly return to ambi c complete return to ambient within seven days.

ent (2.5 psig,104'F) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with

'Ihe 24-hour IDCA simulation test exposed the transmitter to a more severe environment than

6. hat which wouldAmbient conditions will remain for the du cooldown.

recult from the postulated loss of coolant accident.

concluded that it will also maintain functional operability during the short term accident environSince the trans cooldown at afabient conditions.

ment and the long-term

c)

O O

s F cility: dio-Becca Unit 1 DockIts 50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Index No.: 218H-Oll Prepared by

'A' Rev. :

Date: _[

4I[

2

~

Checksd by: M D--ff~

I

_ Dates ff.9e/J)

P ll IEQUIPMENT DESCRIPTIONll_

ENVIRONMENT l

l ll_ Parameter i Specification l Qualification l

l l

DOCUMENTATION REF.

1

-l ll l

l Specification l Qualification!l Qualification l Outstanding l l System t

Reactor l

l l Operating l 1 Year l

1.1 Years Method l

Items l

l l

Protection System ll Time l

ll l

l Notes 1 and 2l l

l l

l J-36 lPlnnt ID No. FTRCIB4 l

l l Simultaneous l None l

l l

ll l

l l

Test l

l l Component ll Temperature l l

l l

l l

l 283.0 l

350.0 l

H, K l

J-36 l

l l

Flow ll

('F) l l

1 l

Transmitter ll l

lMznufteturer ll _

l l

l Simultaneous l None l

l l

l l

l l

Test l

l l

l l

l Rosemount ll Pressure l

52.0 l

85.0 l

G, X

l J-36 l Simultaneous l None l

l l

l l

l l

l l (PSIA) l ll l

l l

1153 ll _

l l

l l

Test l

l Modal Number:

l l

l l

l l

l l

ll Relative l

100,0 l

100.0 l

A l

J-36 l Simultaneous l None l

l

[ Function:

Transmits 1

l l

l l

lJHumidity l

l l

l Flow Signals ll (%)

l l

l l

Test l

l l

l ll l

l l

l l Accuracy: Spect 5.0%

ll l Boric Acid l Boric Acid l

l CAL-40 l Simultaneous l l

l 1

l 1

l Demon:

.42%

ll Chemical l

1800 ppa l

1800 ppm l

A l

J-36 l

Test l

None l

I l

l i

l lS2rvices Reactor Coolant ll Spray l

pH 5.0 l

pH 5.0 l

l Note 3 l

ll l Loop 1 Hot Leg Flow for ll l

l l RPS Ch. 4 and Indication ll l

l l

l l

l l

l l

l l

l Location:

Containment ll Radiation l1.7 x 107 l

l l

l l

l RADS l5.0 x 107 l

l l

El. 4 ll l

l RADS l CAL-44 l

J-36 Flood Lovel Elev: 572'-2"ll l

l (Sequential Test l l

Abova Flood Level l

l l

l l

None l

Yes ll Aging l

40 Years l

10 Years l

I l

CAL-66 l Sequential l

None l

l l

l ll l

l l

Nerdsd fort 1

l Note 4 l

l ll l

Hot Shutdown lTl ll l

I I

l J-36 l

Test l

l l

I l

l l Submergence l 572' - 2" l

603' ~ 0" l

B l

J-28 l

N/A l

None l

l l

l

~

1 Cold Shutdown lXl ll l

l l

l l

ll_

l l

l l

l l

l l

1 l

l

__l

O Fccility: b iis-Occce Unit 1 1

Docksts 50-346 SYSTDt COMPONENT EVALUATION WORKSHEET Pr; pared by:

Index No.2 218H-011A Date _

0 Rev.:

2 Chicksd by: gjeV & _~__ z f Date_ f b c,/f]

1 1

The Rosemount replaces the Bailey Meter in accordance with FCR 78-525 2

One year operating time is used as a conservative maxi mum specification.

t 3.

CAL-40 qualifies components tested in a high pH Boric A id Spray to a pH value of 5.0 c

i 4 Materials and/or components sensitive to thermal aging i

assure that associate component will maintain functional operabilitwill be replaced as per maintenance and y in harsh environments.

o 1

i 4

4 i

1 i

)

1

'l I

4 i

n)

O%

J

\\

Fccility: Davie-Be2O3 Unit 1 Dockst:

50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Index No.: 218H-012 Rev.:

2 Pr:parJd by:

Dater

//

Check 2d by:

A #1 Dates ///f/II l

11 l EQUIPMENT DESCRIPTION ll I

l 1

1 1

ENVIRONMENT I

DOCUMENTATION REF.

l Qualification l Outstanding l ll Parameter l Specification l Qualification l Eb ecif ication. Qualification l Method l

Items l

l ll l

l 1

l Syster.2:

Reactor l l Operating l 1 Hour 1 36.5 Years l

L l

Note 2 l

Analysis l

None l

I I

I l

Protection ll Time l

l l

Note 1 l

l l

l l

11 I

l l

l l Plant ID No.

PSNI-15-1 ll l

l l

l l

l 1

l l Temperature l 267.0 l

Exempt l

C-501 l

Note 3 l

N/A l

None l

t l

l l Compontnt Pressure ll

(*F) l l

l l

l l

l l

Switch ll l

l l

l l

l l

l ll l

l l

l l

1 I

lM:nuf teturer: Mercold ll Pressure l

15.61 l

Exempt l

C-501 l

Note 3 l

N/A l

None l

l ll(PSIA) l l

l l

l l

l l Mod 21 Number APW-7041 ll l

l l

\\

l l

l l

ll l

l 1

l 1

I l

l Function:

Reactor ll Relative l

100.0 l

Exengt l

A l

Note 3 l

N/A l

None l

l Protection ll Humidity l

l l

l l

l l

l l1 (s )

l l

l l

l I

l l Accurtcy : Spec :

N/A ll l

l l

l l

l l

l Demon: N/A ll l

l l

l l

l l

l ll Chemical l

N/A l

N/A l

N/A l

N/A l

N/A l

None l

lSarvice:

Ctmt. Pressure l l Sp ray l

l l

l l

l l

l RPS Ch. 2 ll l

l l

l l

l l

l ll 1

l l

l I

l l

lLocEtion: Auxiliary Bldg. ll l

l l

l CAL-73 l

l l

1 Rm. 501 ll Radiation l 2 x 102 RADS l 3. 7 x 104 0

ll l

l l

l l

l l

RADS l T

l Note 2 l

Analysis l

None l

] Flood Level Elev:

N/A ll l

)Abova Flood Level: N/A ll Aging l

40 Years l

36.5 Years l

I l

CAL-73 l

Analysis l

None l

l l

l l

l

)

ll l

l Note 4 l

l Note 2 l

l l

+

Nacdsd for:

ll l

l l

l I

I I

Hot Shutdown lX l ll l

l l

l l

l l

ll Submergence l N/A l

N/A l

N/A l

N/A l

N/A l

None l

Cold Shutdown l l

ll l

l l

l l

l l

ll_

l l

l l

l l

l

i iiPccility: Da v Becse Unit 1 SYSTBt COMPONENT

'ATION WORKSHEET Index No.s 10H-012A l xx:k:t 50-345 Rev.:

2

.4sparsd by:

1 Dates U

l2heckzdby:

, M.'; s g<.<,..f Date:

5

+

I 1

jL. FSAR RPS Instrument Response Time Table gives N/A for containment pressure. Based on conservative engineering judgement, a i

cpecification operating time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is being used.

j !.

Mttarials evaluation conducted. Materials sensitive to radiation and/or thermal aging summarized on attached evaluation.

(

! 3.

This component is a pressure switch which senses containment vessel pressure and trips Reactor Protection System Channel 2 whsn the pressure exceeds 3.175 psig. This provides a backup to the Low Reactor Coolant System Pressure Trip. The pressure l

I cwitch is located in Room 501, which becomes harsh due to a postulated High Energy Line Break of the Main Steam Line to the l

j Auxiliary Feed Pump Turbine. This component would not be required to operate in order to mitigate this postulated HEIA, i

since this HELB would not cause containment pressure to rise. It is considered that the construction of this component is i

{

such as to preclude inadvertant actuation due to the harsh environment resulting f rom the postulated HEIA.

In the highly unlikely event of this failure, Reactor Protection System Channel 2 would be tripped. This component monitors containment i

pressure but is located outside containment. A sensing line allows containsent atmospheric pressure to be measured by a j

sealed sensing element within the switch. This sensing element actuates the switch mechanism. None of the i.nternals of this device will be exposed to the LOCA environment. The sensing line is normally filled with air and, during a IDCA, the air in the sensing line will be compressed by the inside containsent steam-air-pressure mixture rise, but there will be no j

flow in the sensing line and no steam-air-chemical spray mixture will enter the device.

j

}

Based on the above analysis, it is concluded that failure of this component would not adversely ispect safety-related l

f unctions or mislead the operator. Therefore this component is exempt from qualification f rom the postulated High Energy

]

Lins Break.

1

> 4.

Msterials and/or components sensitive to thermal aging will be replaced as per maintenance and replacement schedules to assure that associated component will maintain functional operability in harsh environments.

[

4 i

1 l

4 i

L i

i l

i

O O

3 Ficility: M vic-BeCO3 Unit 1 COMPONENT MATERIAIE EVALUATION SHEET Ind;x No.* 210H-0125 Dockst:

50-346 Rev.:

2 Date:

N[

Prepared by:

Checked by:

,Mf;, wag Dater ///a//3 I

Plant I.D. No.:

PSNI-15-1 Components Pressure Switch l

l Manufacturer:

Mercold Model No.:

APw-7041 I

I I

I I

I THERMAL AGING I

RADIATION I

I Parts List i

Materials List i

Qualification 1 Reference !

Qualification i Reference 1 I

I I

i i

l i

I tottom Housing i Aluminum (214) l Not Sensitive l

I Not Affected l

I j

1 Top Cover l Steel I

Not Sensitive i

I Not Affected i

I I

Diaphragm I 316 Stainless Steel i

Not Sensitive 1

l Not Affected l

l 1 Diaphragm i Teflon 1

40 Years @ 160*F i CAL-73 1

'3.7 x 104 RADS I CAL-73 i

]

l Coating I

I l

l l

I I Switch Body l

Phenolic general I

40 Years e 230*F l CAL-73 1

3.0 x 106 RADS I CAL-73 I

I I

purpose (phenol-1 I

l l

l l

1 I

formald) i I

l l

l i Spring I Spring Steel I

Not Sensitive i

I Not Affected l

l 1 Adjustment

] Steel l

Not Sensitive l

l Not Affected l

l I Gasket i Neoprene l

36.5 Years @ 104*F I CAL-73 1

7.0 x 106 RADS I CAL-73 1

I I

I I

I I

I I

I I

I I

l l

l l

l l

l l

l I

I I

I l

I i

l I

I I

I l

l l

1 1

I I

I I

I

- 1 I

I I

I i

l l

l l

l l

l l

l l I I

I I

i l

i l

i I

I I

I I

I I

I I

I I

I I

I i

i l

i I

4 I

I 1

I I

I I

! l 1

I I

I I

I I

I I

I I

I I

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1 I

I I

I I

I I

I I

I i

I I

I I

I I

I Material r. Parts List

Reference:

AA i

1

~

O Pccility: Ddvio-Desse Unit 1 Dockat:'

50-346 SYSTEM CONPONENT EVALUATION NORKSHEET Index No.: _218N-013 Prepared by Rev.:

2 e

_ Date:

Checksd by:

M & M

  1. Dater l_

///J//3 ll lEQUIPNENT DESCRIPTION ll l

l ENVIRONNENT l

l

~l l

ll Parameter l Specification l l

DOOJMENTATION REF.

ISpecificationl Qualification!l Qualification l Outstanding l Qualification ll 1

I i

l l

l l

l System:

Reactor Nethod l

Items l

ll Operating l 1 Hour l 36.5 Years l

Note 1 l

Note 2 l

Analysis l

Mone

{

l Protection ll Time l

l l

l l

l l

l 11 I

l l

l l

1 l

l Plant ID No.

PSNI-15-3 ll l

l l

l l

l l

l llhaperaturel N/A l

N/A l

Note 3 l

N/A l

N/A l

None l

l Component: Pressure ll

(*F) l l

l l

l l

l l

Switch ll l

l l

l l

l l

I ll l

l l

l l

1 l

lNanufacturers Nercold ll Pressure l

N/A l

N/A l

Note 3 l

N/A l

N/A l

None l

l ll(PSIA) l l

l l

l l

l l Nodal Number APN-7041 ll l

l l

l l

l l

l lI i

l l

t I

l l

l Function:

Reactor ll Relative l

N/A l

N/A l

Note 3 l

N/A l

N/A l

None l

l Protection ll Humidity l

l l

l l

l l

1 ll M1 l

l l

1 I

i l

l Accuracy: Spect N/A ll l

l l

l l

l l

l Demon N/A ll l

l l

l l

l l

'l ll Chemical l

N/A l

N/A l

N/A l

N/A l

N/A l

None l

lSarvice:

Ctat. Pressure ll Spray l

l l

l l

l l

l RPS Ch. 4 ll l

l l

l l

l l

l ll l

l l

l I

i l

l Location: Auxiliary Bldg.ll l

l' l

l CAL-73 l

l l

l Rm. 426 ll Radiation l3.6 x 104 3

RADS l3.7 x 104 RADS l CAL-73 l

Note 2 l

Analysis l

None l

ll l

l l

Flood Level Elev N/A ll l

l l

l l

l Above Flood Level N/A ll Aging l

40 Years l

36.5 Years l

I l

CAL-73 l

Analysis l

None l

I l

l ll l

l Note 4 l

l Note 2 l

l l

Neaded fors ll l

l l

l l

l l

' Hot Shutdown lX l ll l

l l

l l

l l

l l Submergence l N/A l

N/A l

N/A l

N/A l

N/A l

None l

Cold Shutdown l l

ll l

l l

l l

l l

ll l

l l

l l

1 l

/

A N

recility: Lv10-Becca Unit 1 X)ckst s 50-346 SYSTEM COMPONENT EVALUATION WORKSHEET

?repared by:

Index No.: _218H-013A 2hecked by

>ff Date:

20

./

Rev.:

2 ye<wC,f Date:

.*4 L.

FSAR RPS Instrument Response Time Table gives N/A f specification operating time of I hour is being usedor containment pressure.

Materials evaluation conducted.

Based on conservative engineering judgement 2.

,a Materials sensitive to radiation and/or thermal 3

Tha only harsh environment seen is increased radiati aging summarized on attached evaluation.

pressure but is located outside containment.

on due to recirculated fluids.

i scaled sensing element within the switch. This sensing element actuates the switch mechaniA sensing this device will be exposed to the LOCA environm essure to be measured by a air in the sensing line will be compressed by the inside cont iThe serisinsi line is normally filled with air an ent.

sm.

i flow in the sensing line and no steam-air-chemicalspray mixture will enter the device.a nment steam-air-pressure mixture

!4 Materials and/or components sensitive to thermal e no azzure that associated component will maintain functional oper biliaging will be replaced as per maintenanc t

)

a n schedules to ty in harsh environments, "s

I e

e 1

4 L

4

O Facility: Davic-Besse Unit 1 Docket 50-346 COMPONFNT MATERIALS EVALUATION SHEET Prepared by:

Index No.: 218H-Ol?J checked by:

Date:

_/

/I Rev.:

'2;2i,cedd -[ Date: p/e//3 2

/

i l

Plant I.D. No.:

I PSNI-15-3 Manufacturer:

Components l

Mercold Pressure Switch Model No.:

I APW-7041 l_

l l

l Parts List i

THERMAL AGING 1

I i

Materials List l

Qualification i Reference i Qualification I

RADIATION l

t i Bottom Housing i Aluminum (214) l l

i Reference !

l l

I I Top Cover i Steel I

Not Sensitive i

I Not Affected i

I I Diaphragm l

I I

I I Diaphragm 316 Stainless Steel Not Sensitive l

l Not Affected l

I Not Sensitive l

I Not Affected I

i Teflon l

Coating i

i 40 Years 9 160*F l CAL-73 1

3.7 x 104 l

1

)

l Switch Body I

l l Phenolic general l

l RADS l CAL-73 l

I I

1 Purpose (phenol-40 Years 9 230" F I CAL-73 1

3.0 x 106 I

formald) 1 l

l l Spring RADS I CAL-73 l

1 l

1 i Spring Steel I

l I

I l Adjustment l

Not Sensitive i

I Not Affected l

l i Steel l Gaakst l

l 1

I Neoprene I

Not Sensitive i

I Not Affected l

l I

I

]

36.5 Years 9 104*F I CAL-73 1

7.0 x 106 i

i i

RACS I CAL-73 l

I i

i i

i I

I l

i I

i l

i I

I i

I I

I l

l I

I I

I I

I 1

l I

I I

I 0

I 1

l l

i i

0 l

I I

I l

l 0

I I

I I

I I

)

I I

I I

I I

)

l I

I I

I I

1 1

I I

I I

I 1

I I

I I

I I

I I

I I

I I

I I

I I

i I

I I

I I

I l

I I

I I

I l

I I

I I

Daterial & Parts List Reference?

I I

I I

nn

/

A N

Tccility: Davis-Beaca Unit 1 h kst:

50-346 SYSTEM COMPOKENT EVALUATION WCRKSHEET Prcpared by:

Index No.

2M}H-014 Date: !

Rev.: _

2 Checksd by:,Aw (L A7 Dates f//.///7 l

ll

- l EQUIPMENT DESCRIPTION l

ll_

l ENVIRONMENT t

l ll Parameter l Specification l l

DOCUMENTATION REF.

l l

Il_

Qualification l Specification l Qualification ll Qualification l Outstanding l lS Reactor l

l l ystem:

llOperating l 1 Hour l 365 Years l

L l

Note 2 l

Analysis l

None l

Method l

Items l

l l

l Protection l

ll Time l

1 l

ll l

l Plant ID No.

PSNI-15-4 ll-l l

Note 1 l

l l

l l

l l

ll Temperature l l

1 l

l l

l l

l Component: Pressure ll

('F) l l

l l

249.0 l

Exempt l

C-500 l

Note 3 l

N/A l

None l

l l

~l Switch ll_

l l

l l

l l

ll l

\\

l l

l l

l Manufacturer:

l Mercold ll Pressure l

15.61 l

Exempt l

C-500 l

Note 3 l

N/A l

None l

l 1

l l

l l

l Modal Number ll(PSIA) l l

l APW-7041 ll l

I l

l l

l l

l Function:

11 l

l l

l l

l l

Reactor Il Relative l

100.0 l

Exempt l

A I

Note 3 l

N/A l

None l

1 l

l

__l l

l Protection l

ll Humidity l

l l

l ll N

l l

l l

l l Accuracy: Spec:

N/A ll l

l l

l l

l l

l l

Demon: N/A ll l

l l

l l

l l

lSarvica:

ll Chemical l

N/A l

N/A l

N/A l

N/A l

N/A l

None l

l l

l l

l l

l l

Ctmt. Pressure ll Spray l

l l

l l

l l

RM Ch. 3 ll l

l l

] Location:

ll_

l l

l l

l l

Auxiliary Bldg.ll l

l l

l l

l l

l Rm. 500 l

I l l Radiation l 2 x 102 l

l CAL-73 l

l l

RADS l3.7 x 104 ll l

l RADS l T

l Note 2 l

Analysis l

None l

IFlood Level Elev N/A ll l

l l

l 1Abova Flood Level: N/A ll Aging l

40 Years l

36.5 Years l

I l

CAL-73 l

Analysis l

Hone l

l l

l l

l l

ll l

l Note 4 l

l l

Nesdsd for:

ll l

l l

Note 2 l

Hot Shutdown lYl ll l

l l

l l

l l

l l

l l Submergence l l

l l

Cold Shutdown l l

ll l

l

'~

N/A l

N/A l

N/A l

N/A l

N/A l

None l

l l

lI l

l l

l l

l l

l l

l l

l

t scility: DEvig-Tarse Unit 1 ockst:

50-346 SYSTDI COMPONENT EVALUATION WORKSHEET g

repersd by: _7 hecksd by:

jd.

Index No.: 218H-014A Date:

NOTES c/ g,, A.. //

Date: _:" 4 ;< (

2 Rev.:

FSAR RPS Instrument Response Time Table specification operating time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is being usedgives N/A for containment pressure.

M&tarials evaluation conducted.

Based on conservative engineering judg ement, a Materials sensitive to radiation and/or th

. This component is a pressure switch which senses contai ermal aging summarized on attached evaluation whIn the pressure exceeds 3.175 psiy This provides a backup to the Low Reactor Cnment vessel pressure and Auxiliary Feed Pump Turbine. switch is located in Room 500, which becomes ha c

This component would not be required to orsh due to a postulated High Energ since this HELB would not cause containment press The pressure such as to preclude inadvertant actuation due to th perate in order to mitigate this postulated HELof ure to rise.

unlikely event of this failure, Reactor Protecti It is considered that the construction of thi e harsh environment resulting f rom the postulat d B,

prescure but is located outside containment on System Channel 3 would be tripped.

s component is this device will be exposed to the LOCAsealed sensing element within the switch.

e HELB.

This sensing element actuates the switchA sensing line allow In the highly eric pressure to be measured by a air in the sensing line will be compressed by the i environment.

The sensing line is normally filled with None of the internals of mechanism.

flow in the sensing line and no steam-air

-chemical spray mixture will enter the devicenside containment s functions or mislead the operator. Based on the above analysis, it is con l d d rise, but there will be no cue Therefore this component is exempt fromthat failure of this component w Lina Ereak.

versely ispect safety-related Mtterials and/or components sensitive t qualification from the postulated High Energy aagure that associated component will maintain fuo thennal aging will be replaced as per mainte nctional operability in harsh environmentsnance and replacement schedules to

o JD

/

N U

Facility: Davic-Sasse Unit 1 Docket:

50-346 COMPONENT MATERIALS EVALUATION SHEET Prepared by:

Index No.: 218H-014B Checked by: _A+4j Dater _

!8)

Rev.:

2 Date:

/////// ~

l Plant I.D. No.:

I PSNI-15-4 Manufacturer:

Components Mercold Pressure Switch I

Model No.:

i l_

APW-7041 l

1 l

l THERMAL AGING I

i_

Parts List i

Materials List i

Qualification l Reference !

Qualification I

RADIATION I

l I Bottom Housing l Aluminum (214)

I I

i Reference i I

I Top Cover l

Not sensitive I

I i Steel 1 Diephragm I

I i

i Not Affected i

I l Diaphragm 316 Stainless Steel Not Sensitive l

l Not Affected l

l I

Not Sensitive l

l Not Affected l

l i Teflon l

Coating I

i 40 Years 9 160*F l CAL-73 1

3.7 x 104 l Switch Body I

I l Pn;enolic general l

40 Years 9 230*F i CAL-73 l

3.0 x 106 RADS I CAL-73 l

i l

I I

Pu gose (phenol-l l

l l

formald) 1 1

RADS I CAL-73 I

1 Spring l

i Spring Steel l

l I

I I Adjustment i

Not Sensitive i

I Not Affected i

I i Steel l

l I Gasket i

Not Sensitive l

l Not Affected 1

I l

i Neoprene I

1 1

36.5 Years @ 104'F I CAL-13 1

7.0 x 106 i

I I

RADS I CAL-73 l

I l

i i

i i

i i

l i

l 1

i i

i l

l i

I i

i i

i I

i l

I i

I I

i I

i l

I I

I I

i i

I I

i l

I I

I I

I l

I I

I I

I I

I i

I I

I I

I I

I I

I I

I I

1 I

I I

I l

1 I

I I

I I

I I

I I

0 1

I

}

l I

I I

l l

l l

I I

L I

l i

1 l

I i

I I

i I

I I

I I

I i

Material & Parts List

Reference:

AA 1

I

[

/

N. -]

Icility: 16 J -Bssc'a Unit 1 P

SYSTEM COMPONENT EVAIDATION WORKSHEET Mckst 50-346 Index No.: 218H-015 Rev.:

2 2reptrsd by:

Date:

N J

heck:d by hw M Dates f/////)

l ll l

l l

l l EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOCUMENTATION REF.

l Qualification l Outstanding l ll Parameter l Specification l Qualification Specification Qualification l Method l

Items l

l ll l

1 I

I l

l l

lSystca Reactor ll Operating l 26 Hours l

50 Hours l

F l

J-8 l Simultaneous l None l

l Protection ll Time l

l l

l l

Test l

l l

ll l

l l

l l

l l Plant ID No.

PTRC2Al ll l

l l

l ll Temperature l 283.0 l

316.0 l

H, X l

J-8 l Simultaneous l None l

i l

l l

lComponznt:

Pressure-ll

(*F) l l

l l

l Test l

l l

Transmitter ll l

l l

l l

l l

l ll l

t I

l l

l l

lMtnufteturer: Rosemount ll Pressure l

52.0 l

84.7 l

G, X l

J-8 l Simultaneous l None l

l l l (PSIA )

l l

l l

l Test l

l lModel Number:

ll l

l l

l l

l l

l ll52GP9A92T0010PB ll l

l

{

l l

l l

-l ll Relative l

100.0 l

100.0 l

A l

J-8 l Simultaneous l None l

.l Function Transmits ll Humidity l

l l

l l

Test l

l

'l Pressure Signals ll (t) l l

l l

l l

l l

ll l

l l

l l

I l

l Accuracy: Spec:

2.0%

ll l Boric Acid l Boric Acid l

l l

l l

l Demon:

.5%

ll Chemical l

1800 ppm l

1800 ppm l

A l

J-7 l Simultaneous l None l

l ll Spray l

pH 5.0 l

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l CAL-40 l

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l lSarvice: RC Loop 2 HLG ll l

l l

l Note 1 l

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l l

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l l

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J-8 l Sequential Test l None l

l Rm. 410 ll l

l l

l l

l 1

l Flood Level Elev: 572'-2"ll l

l l

l l

l l

lAbova Flood Level: Yes ll Aging l

40 Years l 15 3 Years l

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Analysis l

None l

l ll l

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l Note 2 l

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ll l

l l

l l

l l

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l l

l l

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ll l

l l

l l

l l

)

ll l

l l

l l

l l

F cility bs 0-D2esa Unit 1' SYSTI!M COMPONENhiALUATION WORKSHEET Docksta 50-346 Ind x No.: 218H-015A Rev. :

2 Date

[I /

Preptred by:

Checktd by:

As. d. - g Dater

///.4//3 7

1.

CAL-40 qualifies components tested in a high pH boric acid spray to a pH value of 5.

2.

Materials evaluation conducted. Materials sensitive to radiation and/or thermal aging sn==arized on attached evaluation.

i 3.

Materials and/or components sensitive to thermal aging will.be replaced as per maintenance and replacement schedules to assure that associated component will maintain functional operability in harsh environments.

i i

The 15.1 year qualified life does not include the electronic cunponents. We are unable to assign a qualified life to the electronic assembly. The surveillance and maintenance program will assess the changing status of the transmitter and datermine if any aging-related conunon-mode failures exist. The surveillance frequency will be adjusted as necessary to ensure that functional operability is maintained.

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50-346 Index No.: 218H-0155' Rev.:

2 Prepared by:

Date M#

Checked by:

M

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///>//3 i

t l

Plant I.D. No.:

PTRC2Al Components Pressure Transmitter l

l Manufacturer:

Rosemount Model No.:

1152GP9A92700lOPB l

l l

l_

l l

THERMAL AGING l

RADIATION l

I Parts List l

Materials List l

Qualification l Reference l Qualification l Reference l 4

l t

i I

I I

I l Housing and Cover l

316 Stainless Steel l

Not Affected l CAL-64 l

N/A l

N/A l

l Process Flange l

316 Stainless Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Blank Flange l

316 Stainless Steel l

Not Affected l CAL-64 l

N/A l

N/A l

l Valve Stem and Seat l 316 Stainless Steel l

Not Affected l CAL-64 l

N/A l

N/A l

l Adjustment Screw l Steel l

Not Affected l

CAL-64 l

N/A l

N/A I

l Rataining Ring l Steel l

Not Affected l CAL-64 l

N/A l

N/A l

l O-Rings l BUNA N l

15.1 Years @ 120*F l CAL-64 l

N/A l

N/A l

l O-Ring (Process Flange) l Ethylene Propylene l

40 Years 9 172*F l

CAL-64 l

N/A l

N/A l

l Electronics Assembly l Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Hardware l

l l

l N/A l

N/A l

l Bolts l Steel l

Not Affected l CAL-64 l

N/A l

N/A l

1 l Nuts l Steel l

Not Affected l CAL-64 l

N/A l'

N/A l

1 l Mounting Bracket l Steel l

Not Affected l CAL-64 l

N/A l

N/A l

l Circuit Boards l Electronic Assemblies l

Note 3 l CAL-64 l

N/A l

N/A l

I l

Sansor Module l

316 Stainless Steel l

Not Affected l CAL-64 l

N/A l

N/A l

l Sansor Module Oil Fill l Silicone Oil l

40 Years l CAL-64 l

N/A l

N/A l

l l

I i

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l l

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l l

l EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOCUMENTATION REF.

l Qualification l Outstanding l ll Parameter l Specification l Qualification ! Specification l Qualification!

Method l

Items l

ll i

i l

l l

l l

Syrtsa:

Reactor ll Operating l 26 Hours l

50 Hours l

F l

J-8 l Simultaneous l None l

4 Protection ll Time l

l l

l l

Test l

l ll l

l l

l l

t l

Plant ID No.

PTRC2A2 ll l

l l

l

{

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316.0 l

H, X

l J-8 l Simultaneous l None l

Componsnt:

Pressure ll

(*F) l l

l l

l Test l

l q

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l l

l l

l ll l

l 1

l 1

l Manufacturer Rosemount ll Pressure l

52.0 l

84.7 l

G, X l

J-8 l Simultaneous l None l

ll(PSIA) l l

l l

l Test l

l Modal Number:

ll l

l l

l l

l l

1152GP9A92T0010PB ll l

l l

l l

i l

ll Relative l

100.0 l

100.0 l

A l

J-8 l Simultaneous l None l

Function:

Transmits ll Humidity l

l l

l l

Test l

l Pressure Signals ll

(%)

l l

l l

ll I

l i

i l

i

} Accuracy: Spect 2.0%

ll l Boric Acid l Boric Acid l

l l

l l

Denon:

.5%

ll Chemical l

1800 ppm l

1800 ppm l

A l

J-7 l Simultaneous l None l

ll Spray l

pH 5.0 l

pH 5.0 l

l CAL-40 l

Test, I

l t Sarvice: RC Loop 2 HLG ll l

l l

l Note 1 l

Analysis l

l Narrow Range Pressure ll l

l l

l l

l 1

for RPS Ch. 2 ll l

l l

l l

l l

1 Loc tion: Containment ll Radiation l1.08 x 106 RADSl5.0 x 106 RADS l CAL-44 l

J-8 l Sequential Test l None l

Rm. 410 ll l

l l

l l

l

Flood Level Elev
572'-2"ll l

l l

I l

l Abova Flood Level Yes ll Aging l

40 Years l 15.1 Years l

I l

CAL-64 l

Analysis l

None l

ll l

l Note 3 l

l Note 2 l

l l

Nacdad for:

ll l

l l

l l

l l

! Hot Shutdown lX l ll l

l l

l l

l l

i l lSubme rgencel 572'-2" l

606'-0" l

B l

J-ll l

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SYSTDI COMPON VALUATION WORKSHEET DockIts 50-346 Ind;x No.: 21FH-016A Rev.:

2

~$*

Pr: pared by:

Dates

//

Ch2ck3d by: M gg /el d f Date:

//////3 1.

CAL-40 qualifies components tested in a high pH boric acid spray to a pH value of 5.

2 Materials evaluation conducted.

Materials sensitive to radiation and/or thermal aging summarized on attached evaluation.

3.

Materials and/or components sensitive to thennal aging will be replaced as per maintenance and replacement schedules to ccsure that associated component will maintain functional operability in harsh environments.

The 15.1 year qualified life does not include the electronic components. We are unable to assign a qualified life to the electronic assembly. The surveillance and maintenance program will assess the changing status of the transmitter and datermine if any aging-related common-mode failures exist. The surveillance frequency will be adjusted as necessary to ensure that functional operability is maintained.

Fzcility Y.

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50-346 Rev.:

2 Prcpared by:

Dates Checked by: h r Dater j//.4/r'4 l

Plant I.D. No.:

PTRC2A2 Component:

Pressure Transmitter l

l Manufacturer Rosemount Model No.:

ll52GP9A92T0010PB l

l l

l l

l THERMAL AGING l

RADIATION l

l Parts List l

Materials List l

Qualification Reference Qualification Reference l l

l l

1 l

l l

Ilousing and Cover l

316 Stainless Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Process Flange l

316 Stainless Steel l

Not Affected l CAL-64 l

N/A l

N/A l

l B1cnk Flange l

316 Stainless Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Valve Stem and Seat l

316 Stainless Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Adjustment Screw l Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Retaining Ri.ng l Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l O-Rings l BUNA N l

15.1 Years @ 120*F l CAL-64 l

N/A l

N/A l

l O-Ring (Process Flange) l Ethylene Propylene l

40 Years @ 172*F l

CAL-64 l

N/A l

N/A l

l Electronics Assembly l Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Hardware l

l l

l N/A l

N/A l

l Bolts l Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Nuts l Steel l

Not Affected l

CAL-64 l

N/A l

N/A.

l l Mounting Bracket l Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Circuit Boards l Electronic Assemblies l

Note 3 l

CAL-64 l

N/A l

N/A l

l Sensor Module l

316 Stainless Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Sansor Module Oil Fill l Silicone Oil l

40 Years l

CAL-64 l

N/A l

N/A l

l l

l l

l l

l l

l l

l l

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l Materials & Parts Reference List:

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2 3)eck;d by:

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_a/>/#5 I

il l EQUIPMENT DESCRIPTION ll i

l ENVIRONMENT I

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l DOCUMENTATION REF.

l IQualificationll Qualification l Outstanding l l

lSystcm:

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Method l

Items l

l l Operating I 26 Hours l

50 Hours l

F l

J-8 l Simultaneous l Hone l

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ll Time l

l l

l l

Test l

l l

l ll l

lPltnt ID No.

PTRC2B1 ll l

l l

l

)

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l l

l l

l l l Temperature l 283.0 l

316.0 l

H, X l

J-8 l Simulteneous l None l

lComponznt:

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(*F) l l

l l

l Test l

l l

l l

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l l

l l

l ll t

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l ll l

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1152GP9A92T0010PB ll l

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100.0 l

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J-8 l Simultaneous l None l

l Function:

Transmits ll Humidity l

l l

l l

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l l

l l

Pressure Signals ll

(%)

l l

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l lAccurtcy: Spect 2.0%

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l l

l l

1 I

I I

l Demon:

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ll Chemical l

1800 ppm 1800 ppm l

A l

J-7 l Sirruitaneous l None l

I l

l ll Spray l

pH 5.0 l

pH5.0 l

l CAL-40 l

Test, I

l lStrvice: RC Loop 1 HLG ll l

l l

l Note 1 l

Analysis l

l l

N=rrow Range Pressure ll l

l l

l for RPS Ch. 3 ll l

l l

l l

1 Location: Containment ll Radiation 12.21 x 106 l

l l

l 1

RADSl5.0 x 106 Rm. 407 ll l

l l

l l

l l

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J-8 l

l IFlood Level Elev: 572'-2"ll l

l l

l l

l l

l Sequential Test l None l

Abova Flood Level: Yes ll Aging l

40 Years l 15.1 Years l

I l

CAL-64 l

Analysis l

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ll l

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l Note 2 l

l N2edad for:

ll l

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l l

l l

ll Submergence l 572'-2" l

606'-0" l

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ll 1

l l

l l

l l

l l

ll l

l l

l l

l l

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_Jo-Besca Unit 1 SYSTEM COMPONENkN4ALUATION WORKSHEET IndIx No.'s 218H-017A 4

Dock,t:

50-346 Rev.:

2 Preparsd by:

Dates U/

3 Chicked by: fe h A_#,

Date:

_ ///,,af/3 1.

CAL-40 qualifies components tested in a high pH boric acid spray to a pH value of 5.

. 2 Materials evaluation conducted. Materials sensitive to radiation and/or thermal aging summarized on attached evaluation.

3.

Materials and/or components sensitive to thermal aging will be replaced as per maintenance and replacement schedules to assure that associated component will maintain functional operability in harsh environments.

The 15.1 year qualified life does not include the electronic components. We are unable to assign a qualified life to the electronic assembly. The surveillance and maintenance program will assess the changira status of the transmitter and determine if any aging-related common-mode failures exist. The surveillance frequency will be adjusted as necessary to ensure that functional operability is maintained.

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Dockst 50-346 Index No.: _218H-017B' Rev.:

2 Prspared by:

Date:

[

Checked by h _ f l _ F/ Dater v /> //)

t I

Plant I.D. No.:

PTRC2B1 Components Pressure Transmitter l

Manufacturer Rosemount l

Model No.:

1152GP9A92T0010PB

[ l i

l_

l l

THERMAL AGING l

RADIATION l

l

(

l Parts List i

Materials List l

Qualification Reference l Qualification l Reference l l

l I

i Housing and Cover l 316 Stainless Steel l

Not Affected I CAL-64 l

N/A l

N/A l

l i

i l

I Process Flange l

316 Stainless Steel l

Not Affected l CAL-64 l

N/A l

N/A l

l Clank Flange l

316 Stainless Steel l

Not Affected l

CAL-64 l

N/A l

N/A i

l Valve Stem and Seat l

316 Stainless Steel l

Not Affected l CAL-64 l

N/A l

N/A l

i l Adjustment Screw l Steel

'I Not Affected l

CAL-64 l'

N/A l

N/A l

i l Rataining Ring i Steel i

Not Affected l CAL-64 l

N/A l

N/A l

l l O-Rings l BUNA N 1

15.1 Years 9 120*F l CAL-64 l

N/A I

N/A l

] O-Ring (Process Flange) l Ethylene Propylene l

40 Years 9 172*F l CAL-64 i

N/A l

N/A I

1

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Not Affected l CAL-64 l

N/A l

N/A I

l Hardware l

l l

l N/A l

N/A I

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Not Affected l CAL-64 l

N/A l

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1 1 Mounting Bracket i Steel l

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C%-64 l

N/A I

N/A l

j i Circuit Boards l Electronic Assemblies l

Note 3 l CAL-64 l

N/A l

N/A l

1 Sansor Module l 316 Stainless Steel l

Not Affected l CAL-64 l

N/A I

N/A l

{ l Sennor Module Oil Fill l Silicone Oil l

40 Years l CAL-64 l

N/A l

N/A I

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AA, V-34B, J-8 1

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50-346 SYSTDI COMPONENT EVALUATION NORKSHEET Index No.: _218H-018 Rev. :

2 Prepared by:

d Date:

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+

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M s /L / Date: ///.Llf_)

l ll l EQUIPMENT DESCRIPTION ll l

1 l

l l

ENVIRONMENT l

DOCUMENTATION REF.

ll Parameter l Specification l Qualification l Qualification l Outstanding l l

ll I

l i

' Specification Qualification l Method l

Items l

l Syste::::

Reactor ll Operating l 26 Hours l

50 Hours l

F l

J-8 l Simultaneous l None l

l l

l i

l Protection ll Time l

l l

l l

Test l

l 1

ll l

l l Plant ID No.

PTRC2B2 ll l

l I

l l

l l

l l l Temperature l 283.0 l

316.0 l

H, X l

J-8 l Simultaneous l None l

{

l l

l Component:

Pressure ll

(*F) l l

l l

l Test l

l l

Transmitter ll l

l l

l l

ll l

l l

l l

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52.0 l

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G, X

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l l

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l l

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l l

I l

l l

l ll Relative l

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100.0 l

A l

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l l

l l

Test l

l l

Pressure Signals ll l

ll_

(t) l l

l 5

l l

l l

l 1

I l

~l l Accuracy: Spec:

2.0%

ll l Boric Acid l Boric Acid l

l l

l l

l Demon:

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llChemical l

1800 ppm l

1800 ppm l

A l

J-7 l Simultaneous l None l

l ll Spray l

pH 5.0 l

pH 5.0 l

l CAL-40 l

Test, l

l lSarvices RC Loop 1 HLG ll l

l l

l Note 1 l

Analysis l

l l

Narrow Range Pressure ll l

l l

for RPS Ch.1 ll l

l l

l l

I l Location: Containment ll Radiation l2.0 x 106 I

l l

l RADS 15.0 x 106 l

Rm. 407 ll l

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J-8 l Sequential Test l None l

l Flood Level Elev: 572'-2"ll l

l l

l l

l lAbova Flood Level: Yes ll Aging l

40 Years l 15.1 Years l

I l

CAL-64 l

Analysis l

None l

l l

l l

l l

ll l

l Note 3 l

l Note 2 l

l l

QN3eded fort ll l

l l

l l

l l

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l l

l l

l l

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llSubmergencel 572'-2" l

606' 0" l

B l

J-ll l

N/A l

None l

) Cold Shutdown l_

l ll l

l l

l l

l l

1 ll l

l l

l l

l l

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FCcilitys L_.2-Duca Unit 1 SYSTEM COMPONEN ATION WORKSHEET Index L_/21"H-018A Dock;t 50-346 R2v.:

2 Mb Date: //

h Prepar2d by:

Check 2d by:

M.-ft 6h Date:

,//.3//3 r

1.

CAL-40 qualifies components tested in a high pH boric acid spray to a pH value of 5.

2.

Materials evaluation conducted. Materials sensitive to radiation and/or thermal aging summarized on attached evaluation.

3.

M:terials and/or components sensitive to thermal aging will be replaced as per maintenance and replacement schedules to accure that associated component will maintain functional operability in harsh environments.

The 15.1 year qualified life does not include the electronic components. We are unable to assign a qualified life to the electronic assembly. The surveillance and maintenance program will assess the changing status of the transmitter and determine if any aging-related common-mode failures exist. The surveillance frequency will be adjusted as necessary to ensure that functional operability is maintained.

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'L aic-2 c a Unit 1 COMPONENT MATERI ALUATION SHEET Index N C ;18H-018B Dockst 50-346 Rsv.:

2 Date:

//

siJ Prepared by:

Check'.d by:

    1. h(

Dates

///s/h l

Plant I.D. No.:

PTRC2B2 Component:

Pressure Transmitter I

l Manufacturers Rosemount Model No.:

1152GP9A92T0010PB I

I l

l l

l THERMAL AGING l

RADIATION l

l Parts List l

Materials List l

Qualification Reference Qualification Reference l l

l l

l l

Housing and Cover I

316 Stainless Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Process Flange l

316 Stainless Steel l

Not Affected I

CAL-64 l

N/A l

N/A l

l Bitnk Flange l

316 Stainless Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l valve Stem and Seat l

316 Stainless Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Adjustment Screw I

Steel l

Not Affected l

CAL-64 l

N/A I

N/A l

l R2taining Ring l Steel l

Not Affected l

CAL-64 I

N/A l

N/A l

l O-Rings l BUNA N l

15.1 Years 0 120*F l CAL-64 l

N/A l

N/A l

l O-Ring (Process Flange) l Ethylene Propylene l

40 Years U 172*F l

CAL-64 l

N/A l

N/A l

l Electronics Assembly I Steel l

Not Affected l

CAL-64 l

N/A l

N/A I

l H rdware l

l l

l N/A l

N/A l

l Colts l Steel l

Not Affected l

CAL-64 l

N/A l

N/A I

l Nuto l Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Mounting Bracket l Steel I

Not Affected l

CAL-64 l

N/A l

N/A l

l Circuit Boards l Electronic Assemblies l

Note 3 l

CAL-64 l

N/A l

N/A l

l Ssnror Module 1

316 Stainless Steel l

Not Affected l

CAL-64 l

N/A l

N/A l

l Senior Module Oil Fill l Silicone Oil l

40 Years l

CAL-64 l

N/A l

N/A l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l Msterials & Parts Reference List:

AA, V-34B, J-8

n O

O

-019

' rzcility: LO-Basca Unit 1 SYSTEM COMPONENT u.J/JATION NORKSHEET IndIx tha 218H Mckst 50-346 Rev.:

2 Ctb Date M

!h Prepared by:

+

j %ecksd by:

,,r:%7 M L / Dater j//a/r4 i

lll ll l

l l

l i EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOCUMENTATION REF.

l Qualification l Outstanding l il ll Parameter l Specification l Qualification Specification Qualification !

Method Items l

!l ll l

l 1

l llSystta Reactor ll Operating l 1 Hour l

24 Hours l

Note 1 l

ROC-34A l Simultaneous l None l

ll Protection ll Time l

l l

l l

Test l

l 1l ll l

l l

' l Plant ID No.

TERC3A2 ll l

l l

l l

l l

ll Temperature l 283.0 l

325.0 l

H, X l

AG l Simultaneous l None l

, l Component: Resistance ll

(*F) l l

l l

l Test l

l

! l Temperature Detector ll l

l l

l l

l

i. l ll l

l l

l l

l

! l Manufacturer Rosemount ll Pressure l

52.0 l

74.7 l

G, X

l AG l Simultaneous l None l

I

}llModelNumber:

ll(PSIA)

.l l

l l

l Test l

l 177HN-2 ll l

l l

l l

l ll l

l l

l i

l I l Function:

Senses ll Relative l

100.0 l

100.0 l

A l

AG l Simultaneous l None l

I l Temperature ll Humidity l

l l

l l

Test l

l t

l ll

(%)

l 1

l

/

l j l Accuracy: Spect 0.5%

ll l

l i

I l

l

{ l Demon: 0.5%

ll l Boric Acid l

Boric Acid l

l l

l l

l 1l ll Chemical l

1800 ppm l

1800 ppm l

A l

CAL-42 l

Analysis l

None l

j lSarvice: Reactor Coolant ll Spray l

pH 5.0 l

pH 5.0 l

l l

l l

J l Loop 2 Hot Leg Narrow ll l

l l

l l

l l

)l Range Temperature for ll l

I l

l l

l I

lll Location:

l RPS Channel 4 ll l

l l

l l

l 7

8 Containment ll Radiation l3.87 x 10 RADSl3.8 x 10 RADS l CAL-44 l

J-3 l Sequential Test l None l

)l El. 4 ll l

l l

l l

l Flood Level Elev
572'-2"ll l

l l

l l

l l

l lAbova Flood Level Yes ll Aging l

40 Years l

40 Years l

I l

CAL-89 l

Analysis l

None l

l ll l

l l

l Note 2 l

l l

!lNetdedfors ll l

l l

l l

l l

Hot Shutdown lX l ll l

l l

l l

l l

j l l l Submergence l 572' - 2" l

635' - 0" l

B l

J-il l

N/A l

None l

l Cold Shutdown lX l ll l

l l

l l

l l

l ll l

l l

l l

l l

,1, i

1 1

Mcility: L ;-Basse Unit 1 SYSTEM COMPONENTS O ATION WORKSHEET Ind3x N L J18H-019A Jocksts 50-346 Rav.:

2 d^^^

Dater

// /

8d jFrsparsd by:

"hscksd by WAM 1/

Dates

///>/t) 1.

One hour operating time is used as a conservative specification for the initiation of the reactor protection system following a loss of coolant accident.

2.

Materials evaluation conducted. Materials sensitive to thermal aging summarized on attached evaluation.

i i

1 j

i i

t i

i t

9 l

l 1

9 i

i

J Facility: D3vis-Benas Unit 1 CGtPONENT MATERIALS EVALUATION SHEET Index No.: 218H-0198 Dockst:

50-346 Re v.

2 Prepared by:

Dates i

Checked by:

Md_ j Dates (f.L//)

l t

l Plant I.D. No.:

TERC3A2 Component :

Resistance Tesperature Detector l

! l Manuf acturer Rosemount Model No.:

177HW - 2 l

I l

l l

l THERMAL AGING l

RADIATIGE l

l Parts List l

Materials List l

Qualification Ref e rence Qualification Reference l i l 1

I I

l Q-Felt l Felted Micro-Quartz l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l l Varglass Tubing l Fiber-Glass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Flexitallic Gasket l

S.S., Asbestos l

Not Sensitive l

CAL-89 l

N/A l

N/A l

i l Naver Seez l Nickel-Based Lubricant l

Not Sensitive

  • l CAL-89 l

N/A l

N/A l

l Terminal Block l Porcelain l

Not Sensitive l

CAL-89 l

N/A l

N/A l

j l Epoxy l Epoxy l

40 Years 0 147'F l CAL-89 l

N/A l

N/A l

l O-Ring Lubricant l Silicon Grease l

Not Sensitive

  • l CAL-89 l

N/A l

N/A l

! l Harde r l

S.S., Glass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

I l PBX Solvent & Cement l

Inorganic Ceramic Cement l Not. Sensitive l

CAL-89 l

N/A l

N/A l

l l Housing l Aluminum l

Not Sensitive l CAL-89 l

N/A l

N/A l

1 l Connection Head l Aluminum l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Screws l Brass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l l Washer l Brass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l l Connector Plate l Metallic l

Not Sensitive l

CAL-89 l

N/A l

N/A l

! l Sansor Assembly l

Platinum l

Not Sensitive l

CAL-89 l

N/A l

N/A l

} l The rmowell l Stainless Steel l

Not Sensitive l CAL-89 l

N/A l

N/A l

l l Mounting Nut l

Stainless Steel l

Not Sensitive l

CAL-89 l

N/A l

N/A l

1, l Lead Extension l Stainless Steel l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Wire l Nickel-Clad Copper l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Insulation l

Inorganic Fiber, Mica l

Not Sensitive l CAL-89 l

N/A l

N/A l

, l Head-O-Ring l Ethylene Propylene l

40 Years 0 172*F l

CAL-89 l

N/A l

N/A l

1 l l

l l

l l

l

'1 l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l i

1 I

l l

l l

j Msterial & Parts List Ref erence: AA, V-34A, ROC-34E 1

  • Lubricant will be renewed at normal maintenance intervals.

1

t

(

Pccility: L 0-2assa Unit 1 kx:kst :

50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Index No.: 218H-020 Rev.:

2 3reparad by:

Date

.mecksd by: Mo/Lf Date:

afs/A i

II l

l 1

l

)

EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOCUMENTATION REF.

l Qualification l Outstanding l l

ll Parameter l Specification l Qualification lSpecificationlgualification1 ll l

1 I

I i

l l

Method l

Items l

j iSystems Reactor ll Operating l 1 Hour l

24 Hours l

Note 1 l

ROC-34A l Simultaneous l None l

l Protection ll Time l

l l

l l

Test l

l I

ll l

l l

l

} l Plant ID No.

TERC3A4 ll l

l 1

l

)

l l

t l l l Temperature l 283.0 l

325.0 l

H, X

l AG l Simultaneous l None l

l l

) i omponent: Resistance ll

(*F) l l

l l

l Test l

l C

i l Tamparature Detectcr ll l

l l

l l

l l

ll l

l l

l l

l l

! lMinufacturers Rosemount ll Pressure l

52.0 l

74.7 l

G, X

l AG l Simultaneous l None l

ll(PSIA) l l

l l

l Test l

l l Modal Number: 177HW-2 ll l

l l

l

)

l ll l

t I

l l Function:

Senses ll Relative l

-100.0 l

100.0 l

A l

AG l Simultaneous l None l

l l

l Temperature ll Humidity l

l l

l l

Test l

l l

ll (t)

I l

l l

l l

lAccursey: Specs 0.5%

ll l

l l

l l

l l

l Demon: 0.5%

ll l Boric Acid l Boric Acid l

l l

l l

l ll Chemical l

1800 ppm l

1800 ppm l

A l

CAL-42 l

Analysis l

None l

lSarvice Reactor Coolant ll Spray l

pH 5.0 l

pH 5.0 l

l l

l l

l Loop 2 Hot Leg Narrow ll l

l l

l l

l l

l Ranga Temperature for ll l

l l

l l

l l

l RPS Channel 2 ll l

l l

l l

l l

l Location: Containment ll Radiation l3.87 x 107 RADS l 3.8 x 108 RADS l CAL-44 l

J-3 l Sequential Test l None l

'l El. 4 ll l

l l

l l

l l

l Flood Level Elev: 572'-2"ll l

1 l

l l

l l

IAbova Flood Level: Yes ll Aging

)

40 Years l

40 Years l

I l

CAL-89 l

Analysis l

None l

l ll l

l l

l Note 2 l

l l

lNasded fors ll l

l l

l l

l l

l Hot Shutdown lX l ll l

l l

l l

l l

l l l Submergence l 572'-2" l

635'-0" l

B l

J-ll l

N/A l

Hone l

l Cold Shutdown lX l ll l

l l

l l

l l

l ll l

l l

l l

l l

/

(%)

(m)

Facility: L Ja-Coses Unit 1 SYSTDI COMPONEN ATION WORKSHEET Index IL,/218H-020A Docksts 50-346 Rev.:

2 Y/

Pr:parsd by:

Dat2:

Chicked by: g&gh Date: _p/J//3 1.

Ona hour operating time is used as a conservative specification for the initiation of the reactor protection system following a loss of coolant accident.

2 Materials evaluation conducted. Materials sensitive to thermal aging summarized on attached evaluation.

k i

()

Tccility: Davis-Be233 Unit 1 Docket:

50-346 CCMPCHENT MATERIALS EVALUATION SHEET Index No.: _218H-020B Rev. :

2 Prepared by:

Date: _//M Checked by:

M- - O_ J Date: g'g/#3 l

Plant I.D. No.:

TERC3A4 Component :

Resistance Terrperature Detector l

Manufacturer Rosemount l

l Model No.:

177HW - 2 l

l l

l l

THERMAL AGING l

RADIATICN l

l Parts List l

Materials List l

Qualification

' Ref e rence l Qualificatio.:

l Reference l l

l l

l Q-Felt l Felted Micro-Quartz l

Not Sensitive l CAL-89 l

N/A l

N/A l

1 l

l 1

l Varglass Tubing l Fiber-Glass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Flexitallic Gasket l

S.S., Asbestos l

Not Sensitive l CAL-89 l

N/A l

N/A l

l Naver Seez l Nickel-Based Lubricant l

Not Sensitive

  • l CAL-89 l

N/A l

N/A I

l Terminal Block l Po rcelain l

Not Sensitive l CAL-89 l

N/A l

N/A l

l Epoxy l Epoxy l

40 Years @ 147'F l CAL-89 l

N/A l

N/A l

l O-Ring Lubricant l Silicon Grease l

Not Sensitive

  • l CAL-89 l

N/A l

N/A l

l Hacder l

S.S., Glass l

Not Sensitive I CAL-89 l

N/A l

N/A l

l PBX Solvent & Cement l

Inorganic Ceramic Cement l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Housing l Aluminum l

Not Sensitive l CAL-89 l

N/A l

N/A l

l Connection Head l Aluminum l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Sc rews l Brass l

Not Sensitive l CAL-89 l

N/A l

N/A l

l Washer l Brass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Connector Plate l MetallJc l

Not Sensitive l CAL-89 l

N/A l

N/A l

l Sanzor Assembly l Platinum l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Thermowell l Stainless Steel l

Not Sensitive l CAL-89 l

N/A l

N/A l

l Mounting Nut l Stainless Steel l

Not Sensitiva l

CAL-89 l

N/A l

N/A l

l Lead Extension l Stainless Steel l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Wira l Nickel-Clad Copper l

Not Sensitive l CAL-89 l

N/A l

N/A l

l Insulation l

Inorganic Fiber, Mica l

Not Sensitive l CAL-89 l

N/A l

N/A l

l Head-O-Ring l Ethylene Propylene l

40 Years @ 172*F l

CAL-89 l

N/A l

N/A l

t l

l l

l l

l 1

l l

l l

l l

l l

l l

l l

l l

1 l

l l

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l l

l l

l l

l l

Material & Parts List

Reference:

AA, V-34A, ROC-34E

  • Lubricant will be renewed at normal maintenance intervals.

FIcility: M vis-3ecte Unit 1 Dockst 50-346 SYSTEM COMPONENT EVALUATION WORKSHEET n

L.

N///p 2

Index No.: _218H-021 Preptred by: TE.

Rev.

w-~

Dates Chicked by:

Wo A -

Date:

_j/,/2/d4 l

ll l EQUIPMENT DESCRIPTION ll_

ENVIRONMENT l

1 l

l l_

I Specification l Qualification l Specification l Qualification ll Qualification l Outst l

ll Parameter ll_

l DOCUMENTATION REF.

1 l

l l

1 l System:

Reactor ll Operating l 1 Hour l

24 Hours l

Note 1 l

ROC-344 l Simultaneous -l None l

Method l

Items l

l Protection l

ll Time l

l l

l l

Test l

l I

l ll l

lPltnt ID No.

TERC3B2 ll l

l l

l l

l ll Temperature l 283.0 l

325.0 l

H, X l

AG l Simultaneous l None l

l l

l t

l Component: Resistance ll

('F) l l

l l

l Test l

l t

l Ttmperature Detector i

l ll l

l l

l l

l ll 1

l l

l l

l l Manufacturers Rosemount ll Pressure l

52.0 l

74.7 l

G.

X l

AG l Simultaneous l None l

l l

l l (PSIA )

l l

l 1

~l l Modal Number 177HN-2 ll l

l l

l Test l

l l

l Function:

ll l

t I

Senses l

l l

l ll Relative l

100.0 l

100.0 l

A l

AG l Simultaneous l None l

l t

i l

Temperature ll Humidity l

l l

l l

Test l

l I

l l

ll (s) l l

l l

l l

l Accuracy: Spect 0.5%

ll l

l l

l l

l l

Demon: 0.5%

ll l Boric Acid l Boric Acid l

l l

l l

l l Service:

ll Chemical l

1800 ppm l

1800 ppm l

A l

CAL-42 l

Analysis l

Hone l

l l

Reactor Coolant ll Spray l

pH 5.0 l

pH 5.0 l

l l Loop 1 Hot Leg Narrow ll l

l l

l l

l Range Temperature for ll l

l l

l l

.l RPS Channel 1 ll l

l l

l l

l l

l

! l Location: Containment l l Radiation l3.87 x 107 l

l l

l

. l RADSl3.8 x 108 El. 5 ll l

l l

l l

l l

RADS l CAL-44 l

J-3 l

l

'IFlood Level Elev:

l Sequential Test l 572'-2"ll l

l None l

,l Abova Flood Level:

Yes ll Aging l

40 Years l

40 Years l

I l

CAL-89 l

Analysis l

None l

l l

l l

l l

ll l

l lNesdsd fort ll l

l l

Note 2 l

l l

l Hot Shutdown lTI ll l

l l

l l

l l

~,

l l

l l

l l

l ll Submergence l 572' - 2" l

635' - 0" l

B l

J-il l

N/A l

None l

l Cold Shutdown lXl ll l

l l

l l

l l

~

ll l

l l

l l

l l

j

(

)

Facility: km ;-Daggo Unit 1 SYSTD1 COMPONEN LUATION WORKSHEET Ind;xd, 218H-021A~

Dock;t 50-346 Rev.:

2 Prrpsred by:

Dater

// / h Checksd by: # #h /1_ /

Date:

a /.'t//3 1.

Ona hour operating time is used as a conservative specification for the initiation of the reactor protection system following a loss of coolant accident.

2.

Materials evaluation conducted. Materials sensitive to themal aging summarized on attached evaluation.

/%

Facility: D:vic-DaO2e Unit 1 CCMPONENT MATERI,43 EVALUATION SHEET IndIx ks.: 218H-0219 Dockst:

50-346 Re v.

2 Prepcred by:

Dater

/

Checked by:

, dip;M G __1/

Dates

//'/A//1 l

Plant I.D. No.:

TERC3B2 Conponent:

Resistance Tenperature Detector l

l Manuf acturer Rosemount Model No. :

177HW - 2 l

l 1

l l

l THERMAL AGING l

RADIATICH l

l Parts List l

Materials List l

Qualification l Ref e rence Qualification l Reference l I

l l

l I

I l

Q-Felt l Felted Micro-Quartz l

Not Sensitive l

LAL-89 l

N/A l

N/A l

l Varglass Tubing l Fibe r-Glass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

j l Flexitallic Gasket l

S.S.,

Asbestos l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Naver Seez l Nickel-Based Lubricant l

Not Sensitive

  • l CAL-89 l

N/A l

N/A l

l Terminal Block l Porcelain l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Epoxy l Epoxy l

40 Years @ 147'F l

CAL-89 l

N/A l

N/A l

l O-Ring Lubricant l Silicon Grease l

Not Sensitive

  • l CAL-89 l

N/A l

N/A l

l Harder l

S.S.,

Glass l

Not Sensitive l CAL-89 l

N/A l

N/A l

l PBX Solvent & Cement l

Inorganic Ceramic Cement l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Housing l Aluminum l

Not Sensitive l CAL-89 l

N/A l

N/A l

j l Connection Head l Aluminum l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Sc rews l Brass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Washer l Brass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Connector Plate l Metallic l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Sansor Assembly l Platinum l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l The rmowell l Stainless Steel l

Not Sensitive l

CAL-39 l

N/A l

N/A l

l Mounting Nut l

Stainless Steel l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Lead Extension l Stainless Steel l

Not Sensitive l

CAL-89 l

N/A l

N/A l

j l Wire l Nickel-Clad Copper l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l l

Insulation l

Inorganic Fiber, Mica l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l l

Head-O-Ring l Ethylene Propylene l

40 Years @ 172*F l

CAL-89 l

N/A l

N/A l

l l

l l

l l

l i

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

Material & Parts List Ref erence : AA, V-34A, ROC-34E

  • Lubricant will be renewed at normal maintenance intervals.

i t

o 0

FJcilitys%isvic-Sas33 Unit 1 Dockst:

50-346 SYSTDI COMPONENT EVALUATION WORKSHEET Prepared by:

h,

ll Rev.:

2 Ch cked by:

g >! % r,J L _

_ Date: _ ///.3/f3 l

ll i

l EQUIPMENT D*;SCRIPTION ll_

ENVIRONMENT l

t l

l ll Parameter l Specification l l

DOCUMENTATION REF.

l

~l 1

(Specification l Qualification ll Qualification l Outstanding l ll Qualification l5ystem:

Reactor l

llOperating l 1 Hour l

24 Hours l

Note 1 l

ROC-34A l Simultaneous l None l

Method l

Itees l

I l

l l

Protection l

ll Time l

l l

l ll l

l l

l Test l

lPlcnt ID No.

l TERC3B4' ll l

l l

l l

l l

ll Temperature l l

l l

l l

l Component: Resistance ll

(*F) l l

283.0 l

325.0 l

H, X l

AG l Simultaneous l None l

l

~l l T2mperature Detector ll lManufteturer:

ll_

l l

l l

Test l

l l

l l

1 l

l l

l Rosemount ll Pressure l

52.0 l

74.7 l

G, X

l AG l Simultaneous l None l

l 1

l l

l ll(PSIA) l l

l l

lModel Number: 177HW-2 ll l

l l

l Test l

l l

l Function:

ll l

l l

l l

4 Senses l

l ll Relative l

100.0 l

100.0 l

A l

AG l

l Temperature 1

l l

l ll Humidity l

l l

l l Simultaneous l None l

ll ts) l l

l l

Test l

l Accuracy: Spect 0.5%

ll l

l l

l l

l l

Demon: 0.5%

ll l Boric Acid l Boric Acid l

l l

l l

l l

l l

l l

l ll Chemical l

1800 ppm l

1800 ppm l

A l

CAL-42 l

Analysis l

Hone l

l l

lSarvico:

Reactor Coolant l l Spray l

pH 5.0 l

pH 5.0 l

l Ioop 2 Hot Leg Narrow ll l

l Ranga Temperature for ll l

l l

l RPS Channel 3 ll_

l l

l l

l l

l l

l l

l l

l ll Location: Containment l l Radiation l3.87 x 107 l

l l

l l

l

-l RADS l3.8 x 108 El. 5 ll l

l RADS l CAL-44 l

J-3 l

l

l Flood Level Elev
572'-2"ll l

l Sequential Test l

!!Above Flood Level l

l l

l None l

Yes ll Aging l

40 Years l

40 Years l

I l

CAL-89 l

Analysis l

None l

l l

l l

l

l ll l

l l

lNeedsd fort ll l

l l Hot Shutdown l _X l ll_

l l

l Note 2 l

l l

l l

l l

l l

~

l lSubmergencel 572' - 2" l

635' - 0" l

B l

J-ll l

N/A l

None l

l l

l l

l 0

"old Shutdown lTl ll l

l l

l l

8

~

1 ll l

l l

l l

l l

l l

l l

i

l D

h i

Fccility: La'3-Iccso Unit 1 SYSTEM COMPONEN ATION WORKSHEET Ind;x L 218H-022A Dockst 50-346 R3v.:

2

////[I Pr par:d by:

Dates Chzcksd bya f fy/rjs Datet n /J//3 1.

Ons hour operating time is used as a conservative specification for the initiation of the reactor protection system following a loss of coolant accident.

2 Materials evaluation conducted. Materials sensitive to thermal aging summarized on attached evaluation.

9 4

9'ivic-Berna Unit 1

-s

/

CCMPCEENT MATERA.d EVALUATION SHEET Ind;x 218H-0227 F.rcility:

Dock %t:

50-346 Re v. :

2 Prepcred by:

Date

/

M Checked by:

Mm @_ _

Date

///A//1 l

Plant I.D. No.:

TERC3B4 Component :

Resistance Tenperature Detector l

l Manuf acturer Rosemount Model No. :

177HW - 2 l

l l

l l

l THERMAL AGING l

RADIATICN l

l Parts List l

Materials List l

Qualification l Reference !

Qualification l Reference l l

l l

l 1

l l

l Q-Felt l Felted Micro-Quartz l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Verglass Tubing l Fibe r-Glass l

Not Sensitive l CAL-89 l

N/A l

N/A l

l Flexitallic Gasket l

S.S.,

Asbestos I

Not sensitive l

CAL-89 l

N/A l

N/A l

l N3ver Seez l Nickel-Based Lubricant l

Not Sensitive

  • l CAL-89 l

N/A l

N/A I

l Terminal Block l

Porcelain l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Epoxy l Epoxy l

40 Years @ 147' F l

CAL-89 l

N/A l

N/A l

l O-Ring Lubricant l Silicon Grease l

Not Sensitive

  • l CAL-89 l

N/A l

N/A l

l Haide r l

S.S.,

Glass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l PBX Solvent & Cement l

Inorganic Ceramic Cement l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Housing l Aluminum l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Connection Head l Aluminum l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Sc rews l B rass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Washer l Brass l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Connector Plate l Metallic l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Sansor Assembly l Platinum l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l The rmowell l Stainless Steel l

Nob Sensitive l

CAL-89 l

N/A l

N/A l

l Mounting Nut l

Stainless Steel l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l L2sd Extension l Stainless Steel l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l W ire l Nickel-Clad Copper l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Inaulation l

Inorganic Fiber, Mica l

Not Sensitive l

CAL-89 l

N/A l

N/A l

l Haad-O-Ring l Ethylene Propylene l

40 Years 0 172*F l

CAL-89 l

N/A l

N/A l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l l

l Miterial & Parts List Ref erence: AA, V-34A, ROC-34E

  • Lubricant will be renewed at normal maintenance intervals,
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