ML20083A422

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Rev 2 to Procedure 1040-001-022, Safety Features Actuation Sys
ML20083A422
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 11/02/1983
From:
TOLEDO EDISON CO.
To:
Shared Package
ML17150A231 List:
References
1040-001-022, 1040-1-22, IEB-79-01B, IEB-79-1B, NUDOCS 8312200283
Download: ML20083A422 (44)
v • d • e


Text

_ _ _ _ _ _ _ _ _ _ _ _

l CALCULATION / PROBLEM COVER SHEET Calculation / Problem No: 1040-001-022 Title. Safety Features Actuation System 2.19 Client: Toledo Edison Company Project: Davis-Besse Unit 1 JobNo: 1040-001-671 I & E Bulletin 79-01B Equipment Qualification De:Ign input /

References:

Design Inputs are outlined inthe Cover Report.

Accumptions:

Assumptions are outlined in the Cover Report.

Msthod:

I I Methods are' outlined in the Cover Report.

R; marks:

EDS Nuclear Report No. 02-1040-1076. ,,

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50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Prepm "2 by: W Checka Date: #8 Index No.: 219H-004 by: ) Rev. 2 l

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ll l EQUIPMENT DESCRIPTION ll_

l l ENVIRONMENT _ l l l l Illl Parameter l Specification l Qualification lSp DOCUMENTATION REF.

l System: i l l Safety Features ll Operating l I I

ecificationl Qualification ll Qualification l Outstanding l Actuation 1 Year l I__ , Method l Itees l ll Time l l 1.19 Ye*ars l Note 2 J-10 I

_l l Plant ID No.

ll l l l l Note 1 l Simultaneous l l PT2001 ll l l V-16A l None l l l l l

Test l ll Temperature l l l l l Component 267.0 l l Pressure }l l _

l (*F) l 314.0 l 1 l l C-501 l l l Transmitter ll l l l J-10 l Simultaneous l

~l ll l l V-16A None l lMInufccturer: Foxboro l l l l Test l ll Pressure l l l l l 15.61 l l l ll(PSIA) l 13.0 l l l Modal Number: l l C-501 l l i

EllAH ll l l J-10 l l

S/N 319-2422ll__

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Test l ll Relative l l l l l 100.0 l l Pressure Signals ll Humidity l 100.0 l l l

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, I Accursey: Specs 1.0% ll l l l

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tl ll l l l l I

l l l j lSarvico ll Chemical l N/A l l l

1 Containment l N/A l l l l Pressure Input to SFAS llllSpray l l

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1 I l Sequential Testi None l l l l ll 40 Years l l l

!Nasdad fors l 1.19 Years l I l l

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  • acility : D M C-Berse Unit 1 SYSTDI COMPONENT ATION WORKSHEET Index No.--[ 219H-004A k>ckst : 50-346 Re v. : 2

./ NOTES

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  • M Dates
heck d by: A.+/w

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.. According to Profile C-501, room conditions will return to ambient within 19 minutes and remain there for the duration of tha accident and ensuing cooldown. At the completion of the 30-day LOCA simulation test, test conditions had returned to 150'F, 5 psig. This test exposed the transmitter to an overall more severe environment than that which would result f rom tha postulated high energy line break. Since the transmitter remained operable throughout the test, it can be concluded that the transmitter will maintain functional operability during the short-term accident environment and the long-term

  • j cooldown at ambient conditions.

1

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

l. Materials evaluation conducted. Materials sensitive to radiation and/or thermal aging summarized on attached evaluation.
l. Materials and/or components sensitive to thermal aging will be replaced as per maintenance and replacement schedules to c2;ure that associated component will maintain functional operability in harsh environments.

Th2 limiting material is the transmitter amplifier which has an aging life of 1.19/0.54 years at 104*F/120'F, respectively (Reference CAL-74). However, there is operating experience at Davis-Besse Unit I and in other nuclear plants to support a longer qualified life.

Although the 1.19/0.54 year qualified life is the best analytically supported life estimate, operating experience shows that e longer life is justified. The surveillance and maintenance program will detect age-related degradation and proper curveillance frequencies will be adjusted to ensure that no common mode aging failures predominate.

l l

l

O FIcility: Avic-Berse Unit 1 O COMPONENT MATERa h EVALUATION SHEET Rev.:

n Index U 219H-0048 2

Dockit 50-346 Prepared by: N. Date: ## )

Checked by: hs/h Dater ///.A//)

I j l Plant I.D. No.: PT2001 Component: Pressure Transmitter l l

Manufacturer Foxboro Model No.t EllAM* l l

l  !

l l THERMAL AGING l RADIATION l l

l Parts Lfst l Materials List l Qualification l Reference l Qualification Reference l l l l l l l

l Cover l Aluminum 214 l 40 Years l AA l N/A l N/A l 40 Years l AA l N/A l N/A l l Screws and Nuts l Steel l l Washers l Steel l 40 Years l AA l N/A l N/A l i l Esse Assembly l Cast Iron l 40 Years l AA l N/A l N/A l l l Zero Shaft l Steel l 40 Years l AA l N/A l N/A l Sleeve l Steel l 40 Years l AA l N/A l N/A l l

l Zaro Coupling Assembly l Steel l 40 Years l AA l N/A l N/A l l l RItaining Rings l Steel l 40 Years l AA l N/A l N/A l l Force Bar and Base l Steel l 40 Years l AA l N/A l N/A l Assembly l l l l N/A l N/A l j l

l Junction Box l Cast Iron l 40 Years l AA l N/A l N/A l l

l Coupling l Stainless Steel l 40 Years l AA l N/A l N/A l l Brackets l Steel l 40 Years l AA l N/A l N/A l l Flsxure Assemblies l Steel l 40 Years l AA l N/A l N/A l l Columns l Steel l 40 Years l AA l N/A l N/A l l l Este l Cast Iron l 40 Years l AA l N/A l N/A l j l Cover Plate Molding l Steel l 40 Years l AA l N/A l N/A l l Tarminal Block Assembly l Steel l 40 Years l AA l N/A l N/A l l Detector Assembly l Steel l 40 Years l AA l N/A l N/A l l Plates l Steel l 40 Years l AA l N/A l N/A l l Level Assembly l Steel l 40 Years l AA l N/A l N/A l l l l I i l l l

i Fccilitys" Davis-Besse Unit 1 Docket: 50-346 d

COMPONENT MATERIALS EVALUATION SHEET Prepared by: _ Index No.: ~219H-004C

^, Rev.:

l Checked by: .MofA - y Date: _ W /

Dates p/>/O

) 2 i

1 l

Plant I.D. No.: _

PT2001 l Components Manufacturers Foxboro _

Pressure Transmitter

! Model No.: l EllAH*

l_ l l

l l Parts List l THERMAL AGING l l_ __

Materials List l l

RADIATION

{ l Blocks I Qualification l Reference l l

l Lever l Steel I l I I Qualification l Reference l l Steel 40 Years l AA I l Clamp Spring l l l l Eushings l Steel 40 Years l AA l N/A l N/A l j

l Coil Assembly l Steel l l 40 Years l AA l N/A l N/A l l Zaro screw Assembly l Steel 40 Years l AA l N/A N/A l N/A l l Spring Assemblies l Steel l l 40 Years l AA l l N/A l l Tubing l Steel 40 Years l AA l N/A l N/A l l Steel l 40 Years N/A l l Clamps l l AA l N/A l t l Lubricant l Steel l 40 Years l AA l N/A l N/A l l Silicone Oil 40 Years N/A l N/A i l Transmitter Anplifier l Not Affected l AA l N/A l

[l Assembly l

l Solid State Electronics l l AA l N/A l N/A l 1l O-Rings 1.19 Years 0 104*F l CAL-74 l l N/A l I

l Nylon Washer l Viton l l l l N/A l N/A l l Nylon (Polyamide) 40 Years 9 265'F N/A l

[l Cable l  % Years' S 120*F l CAL-74 l N/A N/A l jl Insulator l Nylon (Polyamide) l CAL-74 l l N/A l l Nylon (Polyamide) l  % Years 9120*F N/A N/A

}l Scalant l l CAL-74 l N/A l l 96 Years 9 120*F l CAL-74 l N/A i l Force Motor Assembly l Silicone RTV (Silastic) l 40 Years 8 302*F l N/A l N/A l

3 l Armature Assembly l Formvar Insulation l l CAL-74 l N/A l l Formvar Insulation 40 Years 0 122*F l CAL-74 l N/A l il Tar..inal Block l Phenolic l 40 Years 8 122*F l CAL-74 l N/A l N/A 1l Column l l N/A l 1l l Phenolic l 40 Years 8 230*F l CAL-74 l N/A l N/A l i 1 40 Years @ 230*F l CAL-74 l l N/A l l N/A l l l N/A l Materials & Parts List Reference : AA 1 i

j

  • The EllGH junction materials box, list is applicable to the EllAH and EllG and electronics.

i

{Notela M transmitters because these transmitters have cal topworks,identi Conservative aging (see Reference value AA,based CAL-38).on the fact that the transmitt er amplifier assembly is the most limiting component for the rmal 1,

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Facility: L do-Be co Unit 1 SYSTDi COMPONENT ATION WORKSHEET Index L..-/ 219H-005 Dockrt: 50-346 Rev.: 2 Prepar6d bys s Date: // [3 Check;d by: Ah Date // / 4 / t3 l ll l l l l l EQUIPMENT DESCRIPTION ll ENVIRONMENT l DOCU:tENTATION REF. l Qualification l Outstanding l l ll Parameter l Specification l Qualification l Specification l Qualification l Method Items l l ll l l l l J-10 l l lSystcm: Safety Features ll Operating l 1. Year l 1.19 Years l Note 2 l Note 1 l Simultaneous l None l l Actuation ll Time l l l l V-16A l Test l l l ll l l l l l l lPltnt ID No. Pr2002 ll l l l l l l l l ll Temperature l 249.0 l 314.0 l C-500 l J-10 l Simultaneous l None l l Component: Pressure ll (*F) l l l l V-16A l Test l l l Transmitter l l l l l l l l l l ll l l 1 l l l l lManufteturers Foxboro ll Pressure l 15.61 l 78.0 l C-500 l J-10 l Simultaneous l None l l ll(PSIA) l l l l V-16A l Test l l l Modal Number: EllAH ll l l l l l l l l S/N 319-2423l l l l l l l l l l Function: Transmits ll Relative l 100.0 l 100.0 l A l J-10 l Siraultaneous l Hone l l Pressure Signals ll Humidity l l l l V-16A 'l Test l l l ll (o l l l l l l l l Accuracy: Spect 1.0% ll l l l l l l l l Demon: 0.94% 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 lStrvice: Containment ll Spray l l l l l l l l Pronure Input to SFAS ll l l l l l l l l Channel 3 and Indication ll l l l l l l l lLocItion: Auxiliary Bldg.ll l l l l l l l l nm, 500 llRadiaticn l 2. 0 x 10 RADS 2 l 7.6 x 10 7RADS l 'I l v,hbh l Sequential Testl None l l ll l l 1 I l l l l Flood Level Elev N/A ll l l l l l l l lAbova Flood Level N/A ll Aging l 40 Years l 1.19 Years l I l CAL-74 l Analysis l None l l ll l l Note 4 l l Note 3 l l l lN xded 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 N/A l N/A l N/A l N/A 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

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Fzcility: L 5-Be2ca Unit 1 SYSTEM COMPONENT ATION WORKSHEET Index L,/ 219H-005A Dock;t: 50-343 Rev.: 2 Prepar;d by: . Date // )

Ch;ck;d by: hh Date: a /s//)

1. According to Profile C-500, room conditions will return to ambient within 19 minutes and remain there for the duration of th:3 accident and ensuing cooldown. At the completion of the 30-day LOCA simulation test, test conditions had returned to 150*F, 5 psig. This test exposed the transmitter to an overall more severe environment than that which would result f rom tha postulated high energy line break. Since the transmitter remained operable throughout the test, it can be concluded th t the transmitter will maintain functional operability during the short-term accident environment and the long-tern cooldown at ambient conditions.

2 On2-year operating time is used as a conservative maximum specification.

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

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

Tha limiting material is the transmitter amplifier which has an aging life of 1.19/0.54 years at 104*F/120*F, respectively (R;ference CAL-74). However, there is operating experience at Davis-Besse Unit 1 and in other nuclear plants to support a longar qualified life.

Although the 1.19/0.54 year qualified life is the best analytically supported life estimate, operating experience shows that c longer life is justified. The surveillance and maintenance program will detect age-related degradation and proper surveillance frequencies will be adjusted to ensure that no common mode aging failures predominate.

o Facilitys~ c vio-Becco Unit 1 Docket 50-346 O

COMPONENT MATERIALS EVALUATION SHEET CJ N

Index No.: 219H-005B Rev.: 2 Prepared by:

  • Dater //

Checked by: g#j 4 Dater ///>[4 l Plant I.D. No.: PT2002 Component: Pressure Transmitter l l Manufacturer: Foxboro Model No.: EllAH*

l l l l l l THERMAL AGING l RADIATION l Parts List l l l Materials List l l

Qualification l Reference l Qualification l l l Reference l i l Cover l Aluminum 214 40 Years l l t I l l AA l Screws and Nuts l Steel l N/A l N/A l l Washers l 40 Years l AA l N/A i

l Steel l 40 Years l N/A l l Bate Assembly l Cast Iron l AA l N/A l N/A l l Zaro Shaft l 40 Years l AA l N/A l Steel l N/A l l Siseve l 40 Years l AA l N/A l Steel l 40 Years l N/A l l Zaro Coupling Assembly l Steel l 40 Years l AA l N/A l N/A l l Ritaining Rings l AA l N/A l Steel l 40 Years l N/A l l Force Bar and Base l AA l N/A l Steel l 40 Years l N/A l l Assembly l AA l N/A l l l N/A' l l Junction Box l Cast Iron l 40 Years l l N/A l N/A l l Coupling l Stainless Steel l 40 Years l AA l N/A l N/A l l Brackets l Steel l 40 Years l AA l N/A l N/A l l AA l Flcxure Assemblies l Steel l 40 Years l N/A l N/A l l Columns l AA l N/A l Steel l 40 Years l N/A l l Bare l AA l N/A l Cast Iron l 40 Years l N/A l l AA l Cover Plate Molding l Steel l 40 Years l N/A l N/A l l Terminal Block Assembly l Steel l AA l N/A l 40 Years l N/A l I Detector Assembly l Steel l AA l N/A l N/A l l Plates l 40 Years l AA l N/A l Steel l 40 Years l N/A l l Level Assembly l AA l N/A l Steel l 40 Years l N/A l l l AA l l l l l l l l 1

Facilityr \oavic-Bessa Unit 1 O

COEPONENT MATER 1. J EVALUATION SHEET Index sg Rev.:

>219 2

H-005C Dock 2t 50-346 Prepared by: Date #[/

Checked by: 2?_L 12-_ H Date MV.Qth Plant I.D. No.: PT2002 Component : Pressure Transmitter l l

Foxboro Mode 1 No. EllAH* l l Manuf acturer I

l l l THERMAL AGING l RADIATIGI l l

l Parts List l Materials List l Qualification l Ref erence I Qualification l Reference l 1 I I l l l 1 40 Years AA l N/A l N/A l l ' Blocks l Steel l l AA N/A l N/A l 40 Years l l l Leve r l Steel l 40 Years l AA l N/A l N/A l l Clup Spring l Steel l l Bushings l Steel l 40 Years l AA l N/A l N/A l l Coil Assembly l Steel l 40 Years l AA l N/A l N/A l l Zaro Screw Assembly l Steel l- 40 Years l AA l N/A l N/A l Spring Assemblies Steel l 40 Years l AA l N/A l N/A l

.l l l Tubing l Steel l 40 Years l AA l N/A l N/A. l l Clups l Steel l 40 Years l AA l N/A l N/A l Not Affected AA l N/A l N/A l l Lubricant- l Silicone Oil l l N/A N/A l Transmitter Anplifier l Solid State Electronics l 1.19 Years e 104*F l CAL-74 l l l Assembly l l l l N/A l N/A l l

O-Rings l Viton l 40 Years 9 265'F l CAL-74 l N/A l N/A l l

l Nylon Washer l Nylon (Polyamide) l 96 Years 0 120*F l CAL-74 l N/A l N/A l

% Years 9 120*F CAL-74 l N/A l N/A l l Cable l Nylon (Polyamide) l 96 Years 9 120*F l

CAL-74 l N/A l N/A l Insulator l Nylon (Polyamide) l l l

Saalant l Silicone Rrv (Silastic) l 40 Years e 302*F l CAL-74 l N/A l N/A l l

l Force Motor Assembly l Formvar Insulation l 40 Years 0 122*F l CAL-74 l N/A l N/A l l Armature Assembly l Formvar Insulation l 40 Years 6 122*F l CAL-74 l N/A l N/A l l Phenolic 40 Years 9 230*F CAL-74 l N/A l N/A l l Tarminal Block l l l Column l Phenolic l 40 Years @ 230*F l CAL-74 l l l l l I I I l ,

l Materials & Parts List

Reference:

AA

  • The EllGH materials list is applicable to the EllAH and EllGM transmitters because these transmitters have identical topworks, junction box, and electronics.

Note la Conservative value based on the f act that the transmitter anplifier assembly is the most limiting c' nonent f or thermal aging (see Reference AA, CAL-38).

,m j'^N ln  ;

\ l Pccility:\ ivis-D;;ta Unit 1 Dock;t:

, N) w-50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Prepared by:

Ch;cked by:

Date: Af Index No.: 219H-006 I Rev.:

M ;% % f d [ Date: g//N5 2

ll l EQUIPMENT DESCRIPTION l l_

l_ l ENVIRONMENT l

llll Parameterl l Specification [

l l l

lSystsm: DOCUMENTATION REF. l l Safety Features llOperating l Qualification lSpecificationl0ualificationil l

Qualification Method l Outstanding l Actuation llTime l 1 Year i 1.19 Years ! Note 1 l J-6 i Items l l 1 l

l I CAL-30 l 1 l__ l l l Analysis l lPIsnt ID No. PT2003 i l V-16A l None l ll l I i l l I 1 l Component: llTemperaturel N/A l I I

l l

Pressure ll (*F) i N/A l l l l l Note 2 l I Transmitter l l_. 1 l

l l N/A I N/A _l I l l None l ll I l l Manufacturer: Foxboro 1 I l l l llPressure i N/A l l I

l l

ll(PSIA) l N/A l _l l Modal Number: EllAH l l

l Note 2 l N/A l l l l_ 1 l I N/A t l l l None IFunction: S/N 319-242411 l 1 l l Transmits l 1 l l ll Relative l N/A 1 I I

1 Pressure Signals ll Humidity l N/A l l _l l l l

l Note 2 l N/A l lAccurney: Spec: 11. (%) I l l N/A l 1.0% l l l None l t ll 1 l l Demon: 0.94% ll l I l

1 l

l l l l 1 1 ll Chemical i 1 l l' lSarvica: Containment l flSpray N/A l N/A l I

I l

l Pressure Input to SFAS I N/A I ll i I N/A l I l l l N/A l None Chtnnel 4 and Indicationll_ l l l l ILocation: Auxiliary Bldg.ll 1 I

l l l l

l 1 I l Rm. 426 l I l 1 llRadiation l4.17 x 105 RADSl7.6 x 107 l l

I I

l

] Flood Level Elev:

l l_ l RADS l T J-6 l l

_I N/A ll l l V-16A l IAbova Flood Level: l l

I ISequential Testl None I N/A IIAging l 40 Years l l

1 l

l l l

' NM.dEd f or:

ll l 1.19 Years l I l

l l

l l CAL-74 Hot Shutdown

_ l l_ l Note 4 l l Analysis i l

11l ll l -l Note 3 )

None i l 1 l l llSubmergencel l l l N/A l l Cold Shutdown 111 lI l

l N/A I N/A l l _l l l N/A l

_l l_ l l l N/A -l I l l None l l l l l l l

l

_l

. . . .-. - _ ~ . . - - - -

/

l

Fccility d vis-Besca Unit 1 Docksta 50-346 SYSTDI COMPONENT EVALUATION WORKSHEET Index No.
219H-0064 Prtpared by:

4 Chzcked bys An12 -J Date: _// ![j Re v. : 2 Dates W/p/f]

1.

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

, 2.

t The only harsh environment seen is increased radiation due to recirculat e du fl s.

id j 3 i

Materials evaluation conducted.

4 Materials sensitive to radiation and/or thermal aging susunarized on att

ached evaluation.

Materials and/or components sensitive to thermal aging will be replaced as assure that associated component will maintain functional operability in harsh environmentper s. maintenance and re}

The limiting (Reference material la the transmitter amplifier which has an aging life of 1.19/0.54 CAL-74).

longer qualified life.However, there is operating experience at Davis-Besse Unit 1 and inyehrs at 104*F/120*F, respectively other nuclear plants to support a l Although the 1.19/0.54 ,

a longer life is justified. year qualified life is the best analytically su surveillance frequencies will be adjusted to ensure that no escommon mode predominate.

aging on and proper failurThe 1

'l i

j -

}

i i

I 4

/

y-(,)T (

\J

)

F cilitys vic-Be:Ya Unit 1 Docket: 50-346 COMPONENT MATERIALS EVALUATION SHEET Index No.: 219H-006B

' Rev. 2 Prepared by: a Dates // O Ch;cked by: A&/JLs/ Dates e/////3 l Plant I.D. No.: PT2003 Component:

l Manufacturer: Pressure Transmitter l Foxboro Model No.:

l EllAH' l

l l l l THERMAL AGING l l RADIATION Parts List l Materials List l l Qualification l l l Reference l Qualification l Reference l l Cover l Aluminum 214 l l l l Screws and Nuts l 40 Years l AA l l l l Steel N/A l N/A l W:shers l 40 Years l AA l l

l Steel N/A l N/A l Base Assembly l 40 Years l l Cast Iron l 40 Years l AA l N/A l N/A l l Zaro Shaft l Steel l AA l N/A 40 Years l N/A l l Sleeve l Steel l l AA l N/A l N/A l Zaro Coupling Assembly l Steel l 40 Years l AA l l

l 40 Years N/A l N/A l l Rstaining Rings l Steel l AA l N/A l N/A l Force Bar and Base l 40 Years l AA l l

l Steel N/A l N/A l l Acsembly l 40 Years l AA l l l N/A l N/A l l Junction Box l Cast Iron l l N/A l N/A l Coupling l 40 Years l AA l

l Breckets l Stainless Steel l 40 Years l AA l N/A l N/A l l Steel l 40 Years l N/A l N/A l l Flcxure Assemblies l Steel l AA l N/A l N/A l l Columns l 40 ears l AA l l Steel N/A l N/A l Eaae l 40 Years AA l l Cast Iron l 40 Years l l N/A l N/A l l Cover Plate Molding l Steel l AA l N/A l N/A l Terminal Block Assembly l Steel l 40 Years l AA l l

40 Years N/A l N/A l l Detector Assembly l Steel l

l AA l N/A l N/A l Plates l 40 Years l AA l l Steel l 40 Years l N/A l N/A l l Level Assembly l Steel l AA l N/A l N/A l l 40 Years l AA l l

l l l l l l l l

m Facilitys ke.vis-Be na Unit 1 Dockst: 50-346 CCMPONENT MATERIALS EVALUATION SHEET Index No.: 219H-00GC Re v. : 2 Prepared by: Dater (/ /

Checked by: 9 : & _ V Date: st/A'//1 I

l Plant I.D. No. : PT2003 Component Pressure Transmitter l l Manufacturers Foxboro Model No. EllAH* - l j l

l. l l l THERMAL AGING l RADIATICH l l Parts List I Materials List l Qualification l Reference l l l Qualification l Reference l l I i l Blocks l Steel l t l l 40 Years l l Leve r l Steel l 40 Years l AA l N/A l N/A l l l Clcmp Spring

' l Steel l 40 Years l AA l N/A l N/A l l Bushings l AA l N/A l Steel l 40 Years l N/A l l Coil Assembly l Steel l 40 Years l AA l N/A l N/A l l Zaro Screw Assembly l AA l N/A l Steel l 40 Years l N/A l l Spring Assemblies l Steel l AA l N/A l N/A l l 40 Years l AA l Tubing l Steel l N/A l N/A l l Clapps l 40 Years l AA l N/A l Steel l 40 Years l N/A l l Lubricant l Silicone Oil l Not Affected l AA l N/A l N/A l l Transmitter Applifier l Solid State Electronics l AA l N/A l N/A l l Assembly l l 1.19 Years 0 104*F l CAL-74 l N/A l N/A l l l l O-Rings l Viton l N/A l N/A l l Nylon Washer l 40 Years e 265'F l CAL-74 l N/A l Nylon (Polyamide) l 96 Years 0 120*F l N/A l l Cable l Nylon (Polyamide) l CAL-74 l N/A l N/A l l 96 Years 0 120*F l CAL-74 l N/A l Insulator l Nylon (Polyamide) l 96 Years 0 120*F l N/A l l Saaltnt l CAL-74 l N/A l N/A l Silicone RTV (Silastic) l 40 Years 0 302*F l CAL-74 l l

l Force Motor Assembly l Formvar Insulation N/A l N/A l l Armature Assembly l 40 Years 0 122*F l CAL-74 l N/A l Formvar Insulation l 40 Years 0 122*F l CAL-74 l l N/A l l Torminal Block l Phenolic l 40 Ye'ars 0 230*F N/A l N/A l l Column l Phenolic l CAL-74 l N/A l N/A l l

l 40 Years @ 230*F l CAL-74 l l l l 1 I l l l Materials & Parts List

Reference:

AA

  • Tha EllGH materials list junction box, and electronics. is applicable to the EllAH and EllGM transmitters because these transmitters have identical topworks, Note 1:

Conservative value based aging (see Reference AA, CAL-38).on the f act that the transmitter amplifier assembly is the most limiting component for thermal

cility: Dav b BeDOS Unit 1 SYSTEM COMPONENT EV; h TION WORKSHEET Index No.:N i9H-007 ckst 50-346 Rev.: 2 eparad by:

  • Date M 3 cckId by: M _/.2..// Dater u /.8//)

11 I I I l QUIPMENT DESCRIPTION ll ENVIRONMENT DOCUMENTATION REF. l Qualification l Outstanding l ll Parameter l Specification ! Qualification Specification Qualification l Method l Items l ll l l 1 J-10 l l l yttem Safety Features ll Operating l 1 Year l 1.1 Years l Note 2 l Note 1 l Simultaneous l None l Actuation ll Time l l l l V-16A l Test l l ll l l l l l l l lant ID No. PTRC2A3 ll l l l l l l l ll Temperature l 283.0 l 314.0 l H, X l J-10 l Simultaneous l None l ompontnts Pressure ll (*F) l l l l V-16A l Test l l Transmitter ll l l l l l l l ll l l I l l l l anufacturers Foxboro ll Pressure l 52.0 l 78.0 l G, X l J-10 l Simultaneous l None l ll(PSIA) l l l l V-16A l Test l l odal Number: EllGH ll l l l l l l

, S/N 266-0831ll l l l l l l l

' unction: Transmits ll Relative l 100.0 l 100.0 l A l J-10 l Simultaneous l None i i Pressure Signals ll Humidity l l l l V-16A l Test l l ll (%) l l l l l l i ccuracy: Spect 1.0% ll l l l l l l l Demon: 0.94% ll l Boric Acid l Boric Acid l l J-10 l l l ll Chemical l 1800 ppm l 1800 ppm l A l V-16A l Simultaneous l None l ervica RC Loop 2 HLG ll Spray l pH 5.0 l pH 5.0 l l CAL-40 l Test, l l ida Range Pressure for ll l l l l Note 3 l Analysis l l FAS Ch. 4 and Indication ll l l l l l l l ocation: Containment ll l l l l J-5 l l l Rm. 410 ll Radiation l 4.69 x 106 RADS l1.0 x 107 RADS l AF l V-16A l Sequential Test l None l ll l l l l l l l

' lood Level Elev: 572 '-2" l l l l l l l l l bova Flood Level Yes ll Aging l 40 Years l 0.54 Years l I l CAL-74 l Analysis l None l j ll l l Note 5 l l Note 4 l l l I esdad fors ll l l. l l l l l i Hot Shutdown lX l ll l l l l l l l llSubmergencel 572' - 2" l 606' - 0" l B l J-ll l N/A l None l

) Cold Shutdown lX l ll l l l l l l l

ll l l 1 1 I I I

Facility: ( -2;c;Q Unit 1 SYSTEM COMPONENT ATION WORKSHEET Index 19H-07A

)ockst 5.-i43 R;v.: 2 Prepar:d by: h Date I .I heckId by: Ahf21W Date: ///J//)

L. According to Profiles G and H, containment conditions will return to emblent within seven days and remain there for the duration of the accident and ensuing cooldown. At the completion of the 30-day LOCA simulation test, test conditions had rcturned to 150*F, 5 psig. This test exposed the transmitter to an overall more severe environment than that which would rzcult f rom the postulated loss of coolant accident. Since the transmitter remained operable throughout the test, it can be i c:ncluded that the transmitter will maintain functional operability during the short-term accident environment and the )

l long-term cooldown at ambient conditions. l l

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.

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

5 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.

Tha limiting material is the transmitter amplifier which has an aging life of 1.19/0.54 years at 104*F/120'F, respectively ,

(Rzference CAL-74). However, there is operating experience at Davis-Besse Unit 1 and in other nuclear plants to support a '

longer qualified life.

Although the 1.19/0.54 year qualified life is the best analytically supported life estimate, operating experience shows that a longer life is justified. The surveillance and maintenance program will detect age-related degradation and proper surveillance f requencies will be adjusted to ensure that no common mode aging failures predominate.

1

Docket:

o Ficility: MIvic-Be 03 Unit 1 50-346 O

COMPONENT MATERIALS EVALUATION SHEET O

Index N3. 219H-0078 Rev.: 2 Prepared by: . Dater // /

Checked by: Mk A A Date: ///.a//3 ,

l Plant I.D. No.: PTRC2A3 Component Pressure Transmitter l l Manufacturers Foxboro Model No.: EllGH* l l

l l l l THERMAL AGING l RADIATION l l Parts List l Materials List l Qualification l Reference l Qualification l Reference l l l l l 1 I l Cover l Aluminum 214 l 40 Years l AA N/A l Screws and Nuts l l N/A l l Steel l 40 Years l AA l N/A l N/A l Washers l Steel l 40 Years l AA N/A l l l Bare Assembly l Cast Iron l l N/A l )

l 40 Years l AA l N/A N/A l Zero Shaft l Steel l 40 Years l AA l N/A l l l l Sleeve l N/A l l Steel l 40 Years l AA l N/A N/A l Zaro Coupling Ascembly l Steel l 40 Years l AA N/A l l l Rstaining Rings l l N/A l l Steel l 40 Years l AA l N/A N/A l l l l Force Bar and Base l Steel l 40 Years l AA l Assembly l N/A l N/A l l l l l N/A l N/A l Junction Box l Cast Iron l 40 Years l AA N/A l

l l N/A l l Coupling l Stainless Steel l 40 Years l AA l N/A l N/A l Erackets l Steel l 40 Years l AA N/A l

l Flexure Assemblies l l N/A l l Steel l 40 Years l AA N/A l Columns l l N/A l l Steel l 40 Years l AA l N/A N/A l Base l Cast Iron l 40 Years l AA N/A l l l Cover Plate Molding l l N/A l l Steel l 40 Years l AA l N/A l Tarminal Block Assembly l Steel l N/A l l 40 Years l AA l N/A l N/A l Detector Assembly l Steel l 40 ' rears AA l

Plates l l N/A l N/A l l l Steel l 40 Years AA l l N/A l N/A l l Level Assembly l Steel l 40 Years AA l

l l N/A l N/A l l 1 l l l l

Fccility %Ivis-Mrs3 Unit 1 COMPONENT MATE d. d EVALUATION SHEET Index d 4 f 219H-007C Dockst 50-346 Rev.: 2 Prepared by: . Dater // N Checked by: M M s/ Dater ///.4//3 l Plant I.D. No.: PTRC2A3 Component Pressure Transmitter l l Manufacturers Foxboro Model No.: EllGH*

4 l I

l l l l THERMAL AGING l RADIATION

, l l Parts List l Materials List l Qualification ' Reference l Qualification l Reference l l i I I i l l Blocks l Steel l 40 Years AA j

l l N/A l N/A l l Lever l Steel l 40 Years l AA l N/A l N/A l

) l Clamp Spring l Steel l 40 Years l AA l N/A l N/A l l Bushings l Steel j 40 Years l AA l N/A l N/A l l Coil Assembly l Steel l 40 Years l AA l N/A l N/A l l Z:sro Screw Assembly l Steel l 40 Years l AA l N/A l N/A l l Spring Assemblies l Steel l 40 Years AA l N/A l l N/A l l Tubing l Steel l 40 Years l AA l N/A l N/a l l Citmps l Steel l 40 Years l AA l N/A Y /A l l l Lubricant l Silicone Oil l Not Sensitive l AA l N/A l N/A l l Transmitter Anplifier l Solid State Electronics l 0.54 Years @ 120*F l CAL-74 l N/A l N/A l l Assembly l l l l N/A l N/A l l O-Rings l Viton l 40 Years 0 265'F l CAL-74 l N/A l N/A l

, l Nylon Washer l Nylon (Polyamide) l 96 Years 9 120*F l CAL-74 l N/A l N/A l l Cable l Nylon (Polyamide) l 96 Years 0 120*F l CAL-74 l N/A l N/A l l Insulator l Nylon (Polyamide) l 96 Years 9 120*F l CAL-74 l N.'A l N/A l l Saalant l Silicone RTV (Silastic) l 40 Years 0 302'F l CAL-74 l N/A l N/A l 5

l Force Motor Assembly l Formvar Insulation l 40 Years 0 122*F l CAL-74 l N/A l N/A l l Armature Assembly l Formvar Insulation l 40 Years @ 122'F l CAL-74 l N/A l N/A l

, l Tarminal Block l Phenolic l 40 Years @ 230*F l CAL-74 l N/A l N/A l 4

l Column l Phenolic l 40 Years 9 230*F l CAL-74 l N/A l N/A l

l l l l l l l 1

l Materials & Parts List

Reference:

AA

]

  • Tha EllGH materials list is applicable to the EllAH and EllGM transmitters because these transmitters have identical topw<r*4s, t

junction box, and electronics.

a

, Note 1: Conservative value based on the f act that the transmitter amplifier assembly is the most limiting component for thermal l aging (see Reference AA, CAL-38).

Fccility: Davio-B:sse Unit 1 L)

Dockst 50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Prepared by: _ . Index No.: _219H-008 Chseksd by: g h flM9 Dater [ d Rev.: _ 2 Dater /////A I

ll l EQUIPMENT DESCRIPTION ll_

l ENVIRONMENT 1

l l l l ISystem: ll Parameterl l Specification l Qualification lSpecifiDOCUMENTATION cationlQualificationll Qualification l Outstanding l REF. ~l Safety Features ll Operating l l Method l 1 Year l l l Items l

Actuation ll Time l 1.1 Years l Note 2" J-10 l l l l Note 1 l ~l l Plant ID No.

ll l l

l l l Simultaneous l None 1

PTRC2A4 ll l V-16A l Test l i l 1 I l l l l ll Temperature l l l  !

l Component: 283.0 l l l Pressure ll (*F) l 314.0 l H, X l l l l l l J-10 l l Transmitter ll l l

l l l Simultaneous l None ll l l

V-164 l Test l l Manufacturers l l l l Foxboro ll Pressure l l l l l 52.0 l l l 78.0 l l ll(PSIA) l l G, X l lModel Number: E11GH ll l l

l l J-10 l Simultaneous l

~l l l l V-16A None l S/N 266-0832ll l l Test l Function: Transmits l l l l l l l ll Relative l 100.0 l l I Pressure Signals ll Humidity l 100.0 l l l l l A l J-10 l (s) l ~l lAccursey: Specs 1.0% ll l l l l V-16A l Simultaneous l None l l ll l l l l Test l Demon: 0.94% ll l l l l

ll Chemical l Boric Acid l Boric Acid l l

l l l

~l l 1800 ppm l l llSarvicer RC Loop 2 HLG ll Spray l l 1800 ppm l A J-10 l l l

llWida Range Pressure for ll pH 5.0 l pH 5.0 l V-16A l l l l CAL-40 l Simultaneous l None l llSFAS Ch. 2 and Indication ll l l l l Test, l LOLocation: Containment ll l l l Note 3 l Analysis l O

Rm 410 l l l l l l l 9 ll Radiation l4.60 x 106 RADS l1.0 x 107 RADS l l J-5 l l

~l ll_ l AP l

)Plood Level Elev 572'-2"ll l l V-16A l Sequential Test l l l l None

}Abova Flood Level Yes ll Aging l l l l

} l 40 Years l l l Nasdad fors ll l l 0.54 Years l I l CAL-74 l

l 1

ll l Note 5 l l Analysis l Hot Shutdown l l Note 4 l None l lYl ll l l l

~ l l l l l l l l Submergence l 572' - 2" l l l Cold Shutdown~ lYl ll l l 606' - 0" l B l l

l l J-ll ll l l

l l l N/A l None

~l l l l l l l l l l l

' -x

/ h Pccilityr ( j,-BeccaUnit1 SYSTEM COMPONENT ATION WORKSHEET

)ockst: 5,-346 Index NU.i 219H-09A Rev.: 2 3r; par;d by:

hecksd bys h Date: Nl .7 M&&f Date ///aff)

L. According to Profiles G and H, duration of the accident and ensuingcontainment cooldown. conditions will return to ambient within seven days and remain there for the l rsturned to 150'F, 5 psig. At the completion of the 30-day LOCA simulation test, test conditions had This test exposed razult from the postulated loss of coolant accident. the transmitter to an overall more severe environment than that which would Since the transmitter remained operable throughout the test, it can be concluded that the transmitter will long-term cooldown at ambient conditions.maintain functional operability during the short-term accident environment and the l

l 2.

On2-year operating time is used as a conservative maximum specification. l l

3.

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

1 M:terials evaluation conducted.

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

5.

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

The limiting (Reference material However, CAL-74). is the transmitter amplifier which has an aging life of 1.19/0.54 years at 104*F/120*F, respectively longer qualified life. there is operating experience at Davis-Besse Unit 1 and in other nuclear plants to support a Although the 1.19/0.54 a longer life is justified.

year qualified life is the best analytically supported life estimate, operating experience shows that The surveillance and maintenance program will detect age-related degradation and proper surveillance f requencies will be adjusted to ensure that no common mode aging failures predominate.

% N/ \

Facility: Davio-Berso Unit 1 Docket 50-346 COMPONENT MATERIALS EVALUATION SHEET Prspared by:

  • i Date: # Index No.: _219H-008B Ch:cked byr M e O f Date: _<//s//5 ) Rev. _ 2 l

Plant I.D. No.: _

PTRC2A4 l

Manufacturer Components l

Foxboro _

Pressure Transmitter i Model No.: l l

EllGH*

l _

l l

Parts List l

_l THERMAL AGING l l_ Materials List l l

l Cover l Qualification RADIATION l Aluminum 214 t l Reference l Qualification

_l l Screws and Nuts l Steel l 40 Years l l l Reference l l Wachers l AA l Base Assembly l Steel l 40 Years l AA l N/A 1

l N/A

^l l Zero Shaft l Cast Iron l 40 Years l AA l N/A l l

l Sleeve l Steel l 40 Years l AA l N/A l N/A l I l l Steel l 40 Years l N/A N/A l Zaro Coupling Assembly l Steel l 40 Years l AA l l N/A l l Rstaining Rings l AA N/A l l Force Bar and Base l Steel l 40 Years l AA l N/A l N/A l l Anzembly l Steel l 40 Years l AA l N/A l N/A N/A l

l l 40 Years l N/A l l Junction Box l l AA l N/A l Coupling l Cast Iron l l N/A l N/A l

l 40 Years l l ll Stainless Steel 2 rackets l N/A AA

$ ll Flexure Assemblies Steel l 40 Years l l N/A l N/A l Columns l Steel l 40 Years l AA AA l N/A l l N/A l

} ll Easo l Steel l 40 Years l AA l N/A l N/A l

,l l Cast Iron l 40 Years l N/A N/A l Cover Plate Molding l Steel j 40 Years l AA l l N/A l l N/A Tarminal Block Assembly l Steel l D0tector l 40 Years l AA l N/A l N/A l Assembly Plates l Steel l 40 Years l l AA AA l N/A l N/A l k ll Leval Assembly l Steel l 40 Years l AA l N/A l N/A l k l_ l Steel l 40 Years l AA l N/A l l N/A l I l 40 Years l N/A l l AA N/A l l l N/A l l N/A l l N/A l l l 1

3

! Docket:

o Fccilitys ^Cavis-BeOS2 Unit 1 50-346 O

COMPONENT MATERIALS EVALUATION SHEET Prepared by: Index No.: 219H-008C I Date: _N Rev.: 2

~

Checked by: ,Mo/A # Dates p/2/6

! l Plant I.D. No.: PTRC2A4 l Components Manufacturer:

Foxboro Pressure Transmitter 1

Model No.: l 1

EllGH*

l l l

} l_ Parts List l l

l THERMAL AGING l 3 l Materials List l RADIATION i l Blocks I Qualification l Reference l l

l Lever l Steel l l- Qualification l Reference l l l l Clamp Spring l Steel 40 Years l AA l l l l Bushings l Steel l 40 Years l AA N/A l N/A l '

l Coil Assembly I Steel l l

40 Years l AA l l N/A l N/A

  • l 1 l Z3ro Screw Assembly l Steel 40 Years l AA l N/A l N/A l i l Spring Assemblies l Steel l 40 Years l AA N/A l N/A l i l Tubing l Steel l l

40 Years l AA l

l N/A l N/A l

)l Clamps l Steel 40 Years l AA l N/A l N/A l l l Lubricant l Steel l l

40 Years l AA l

' N/A l N/A l l Silicone Oil 40 Years N/A l Transmitter Amplifier l l Not Sensitive l AA l N/A l N/A l i l Assembly Solid State Electronics l l AA l N/A l N/A l

,l O-Rings l 0.54 Years 9 120'F l CAL-74 l N/A l l N/A l (l Nylon Washer l Viton l l N/A l l N/A l

! l Cable l Nylon (Polyamide) 40 Years 9 265'F l CAL-74 l l N/A l l 96 Years 9 120*F N/A l Insulator l Nylon (Polyamide) l CAL-74 l l N/A l '

l Nylon (Polyamide) l 96 Years 9 120'F N/A l Sealant l 96 Years 9 120'F l CAL-74 l N/A l N/A l l Force Motor Assembly l Silicone RTV (Silastic) l l CAL-74 l N/A l N/A l l Armature Assembly ll Formvar Insulation 40 Years 9 302*F l CAL-74 l N/A l l l N/A l ll Tarminal Block Formvar Insulation 40 Years 9 122*F l CAL-74 l l N/A l l N/A

  • l Column l Phenolic l 40 Years 9 122'r l CAL-74 l l N/A l l Phenolic 40 Years 9 230'F N/A

, l__

l l CAL-74 l N/A l N/A l l 40 Years 9 230'F l CAL-74 l l N/A l l N/A l l N/A l

, Materials & Parts List

Reference:

AA l

l i

l

  • The EllGH junction box,naterials list is applicable to the EllAH and EllG and electronics.

Note l: _

M transmitters because these transmitterscal have identi topworks,

{ Conservative aging (see Reference value based on the fact thatm the trans itt AA, CAL-38).

er amplifier assembly is the most limiting component f or the rma l

Ficility: LJic-Bessa Unit 1 Dockst o 50-346

)

SYSTDI COMPONENT EVALUATION WORKSHEET O

Index No.: 219H-009 Rev.: 2 Prepared by: Date / 2 Checkad by: gg)d/ Date: ar/J//7 l ll l l l EQUIPMENT DESCRIPTION l l ll_ ENVIRONMENT U DOCUMENTATION REF. l Qualification l Outstanding l l ll Parameter l Specification l Qualification SpecificationlQualificationi

. l ll l Method l Items l

' l J-10 lSyctem: Safety Features ll Operating l 1 Year l 1.1 Years 1

Note 2 l l l l l Actuation ll Time l l Note 1 l Simultaneous l None l 3 l l l

' l ll l V-16A l Test l l l l l l l Plant ID No. PTRC2B3 ll l l l l l 1 l

l l l ll Temperature l 283.0 l 314.0 X

) l l H, J-10 l Components Pressure ll (*F) l l l l Simultaneous l None l I l Transmitter ll l l V-16A l Test l l l l l I l 1

l ll l l t l l l Manufacturers Foxboro ll Pressure l 52.0 l 78.0 G, X i l l _i l J-10 l ll(PSIA) l l l l Simultaneous l None l l Modal Number: E11GH l l V-16A l Test l l ll l l l l l l S/N 266-0832ll l l l lFunctic't

~

l l l Transmits ll Relative l 100.0 l 100.0 l A l l l Pressure Signals ll Humidity l l l J-10 l Simultaneous l None l l l V-16A l l ll (s) l l l l Test l l l Accuracy: Spec: 1.0% ll l l l l l l l l l Demon: 0.94% ll l Boric Acid l Boric Acid l l J-10 l l l ll Chemical l l l l 1800 ppm l 1800 ppm l A V-16A lSarvicer RC Loop 1 HLG ll Spray l pH 5.0 l pH 5.0 l l Simultaneous l None l l l CAL-40 l llWida Range Pressure for ll l l l l Note 3 l Test, Analysis l l SFAS Ch. 3 and Indication ll l l l l l l '

I l Location: Containment ll l l l l l l ,

l Rm. 407 ) J-5 l

' l l Radiation l5.44 x 106 RADS l1.0 x 107 RADS l AF l V-16A l Sequential Testl l l l ll l l l l None l

. l Flood Level Elev 572'-2"ll l l l l l l j lAbova Flood Level: Yes ll Aging 40 Years l l l l 0.54 Years l I l CAL-74 l Analysis None ll

lNacded for

ll l l Note 5 l l Note 4 l l l

ll l l l

{l Hot Shutdown lX l ll l l I

l l

l l

l l l

]l l lSubmergencel 572' - 2" l l l 606' - 0" l B l J-ll N/A l Cold Shutdown lX l ll l l l l l l None l l

l ll l l l l l l l l l i

a Facility: L ds-Bezca Unit 1 SYSTEM COMPONENT w ,1UATION WORKSHEET Index L as 219H-009A Dockat: 50-346 Rev.: 2 i Nl fl b

< . NOTES

. Prsparsd by: g8"J Dates j Checksd by: ,M W Dates ///J//7 5

t

1. According to Profiles G and H, containment conditions will return to ambient within seven days and remain there for the duration of the accident and ensuing cooldown. At the completion of the 30-day LOCA simulation test, test conditions had i rsturned to 150*F, 5 psig. This test exposed the transmitter to an overall 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 the transmitter will maintain functional operability during the short-term accident environment and the long-term cooldown at ambient conditions.
2. Ona-year operating time is used as a conservative maximum specification.

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

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

1

] 5. 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.

j Tha limiting material is the transmitter amplifier which has an aging life of 1.19/0.54 years at 104*F/120*F, respectively (Raference CAL-74). However, there is operating experience at Davis-Besse Unit 1 and in other nuclear plants to support a j longer qualified life.

i j Although the 1.19/0.54 year qualified life is the best analyt'ically supported life estimate, operating experience shows that j a longer life is justified. The surveillance and maintenance program will detect age-related degradation and proper j surveillance f requencies will be adjusted to ensure ths.t no comanon mode aging failures predominate.

1 i

a l

1 i

i I

i 4

( ['%

Fccility: Davic-Be r;2 Unit 1 . . _

Docket: 50-346 COMPONENT MATERIALS EVALUATION SHEET Index No.: 219H-009B Rev.: 2 Prepared by: N Date If /!f2 Checked by gh Date ///J//7 l Plant I.D. No.: PTRC2B3 Component:

l Pressure Transmitter l Manufacturers Foxboro Model No.:

l EllGH* l l l l

l THERMAL AGING l RADIATION l Parts List l l

Materials List l Qualification l Referer,ce l l l Qualification l Reference l 1

l Cover l Aluminum 214 1 I i l 40 Years AA l

l Screws and Nuts l l N/A l Steel l 40 Years l N/A l l wxhers l AA l N/A l Steel l 40 Years l N/A l l Bre Assembly l Cast Iron l 40 Years l AA l N/A l N/A l l Zaro Shaf t l AA l N/A l Steel l 40 Years l N/A l l Siceve l Steel l 40 Years l AA l N/A l N/A l l Zaro Coupling Assembly l Steel l 40 Years l AA l N/A l N/A l l R;taining Rings l Steel l 40 Years l AA l N/A l N/A l l Force Bar and Base l AA l N/A l Steel l 40 Years l N/A l l Assembly l AA l N/A l l l N/A l l Junction Box l Cast Iron l 40 Years l l N/A l N/A l l Coupling l Stainless Steel l AA l N/A l N/A l l Crackets l 40 Years l AA l N/A l Steel l 40 Years l N/A  !

l Flcxure Assemblies l AA l N/A l Steel l 40 Years l N/A l l Columns l Steel l AA l N/A l N/A l l Bare l 40 Years l AA l Cast Iron l 40 Years l N/A l N/A l l Cover Plate Molding l Steel l 40 Years l AA l N/A l N/A l l Tanninal Block Assembly l Steel l 40 Years l AA l N/A l N/A l l Detector Assembl;' l Steel l AA l N/A l N/A l Plettes l 40 Years l AA l l l Steel N/A l N/A l l 40 Years l Level Assembly l Steel l AA l N/A l N/A l l 40 Years l AA l l l l N/A l N/A l l l l l

q f Fccilityi- Uavic-Becco Unit 1 1

Docket: 50-346 COMPONENT MATERIALS EVALUATION SHEET Index No.: 2198-009C mev. : 2 Prepared by: _h Checked by: M _s Dates b Dater ///J/r3 i l Plant I.D. No.: PTRC283 Components l l Nanufacturers Pressure Transmitter l Foxboro Model No.: EllGH*

1

! I _

l !

l l l THERMAL AGING

) l_ Parts List l RADIATION l Materials List l l

l l Qualification l Reference l l Qualification l l Blocks l Steel l l l l Reference l

! l Lever l 40 Years l l l Steel l AA -

l N/A l Clamp Spring l 40 Years l N/A l l Steel l AA l N/A '

i l Euzhings l 40 Years l N/A l l Steel l AA l N/A

} l Coil Assembly l 40 Years l AA l N/A l l Steel l N/A l N/A

) l Zaro Screw Assembly l 4D Years l AA l l

l Spring Assemblies l Steel l 49 Years N/A l N/A l j l Steel l AA l N/A

! l Tubing l 40 Years l AA l N/A l i

l Steel 40 Years l N/A l N/A l

} l Clamps l Steel l l AA l , N/A N/A fll Transmitter Amplifier

! l 40 Years l l Lubricant l Silicone Oil l Not Sensitive l

l AA AA l l N/A l N/A l l Solid State Electronics l ' N/A l N/A l l l Assembly l 0.54 Years 9 120*F l CAL-74 l N/A

) ! O-Rings l l l N/A l l Viton l N/A l N/A

{ l Nylon Nasher l 40 Years 9 265*F l CAL-74 l  !

l Nylon (Polyamide) l N/A l N/A

! l Ccble l Nylon (Polyamide) l 96 Years 9 120*F l CAL-74 l N/A l N/A l

l 96 Years 9 120*F l l Insulator l Nylon (Polyamide) l CAL-74 l N/A l N/A i l Saalant l 96 Years 9 120*F l CAL-74 l l Silicone RTV (Silastic) l N/A l N/A l l 40 Years 9 302*F l CAL-74 l

{ ll Force i

Notor Assembly Armature Assembly l Formvar Insulation l 40 Years 9 122*F l CAL-74 N/A l N/A l l Formvar Insulation l N/A l N/A l

!l Tarminal Block l 40 Years 9 122*F l CAL-74 l N/A l Phenolic 40 Years 9 230*F l N/A l i l Column l Phenolic l l CAL-74 l N/A

  • N/A l I 1

l_ l l 40 Years 9 230*F l CAL-74 l N/A 1

1 l N/A l I l l '

3 Materials & Parts List

Reference:

AA

}

)

  • The EllGH junction materials box, list is applicable to the EllAH and EllGM transmitters because these tr and electronics. ansmitters have identical topworks, i
Note 1

j Conservative aging value based (see Reference on the fact that the transmitter amplifier assembly is the most limiting component for thermal AA, CAL-38).

1

t

' Facility: b 12-Becco Unit 1 Dockst: 50-346 SYSTDI COMPONENF EVALUATION NORKSHEET Index No.: 219H-010

Prepared by
Check
d by NM cMJ/

Dates id</P1 Rev. : 2 Date: es/A/PJ ,

I l ll t l l EQUIPMENT DESCRIPTION ll l

{l_ ENVIRONMElff I DOCUMENTATION REF.

l l l ll Parameterl l Specificationl l Qualification l Specification l QualificationMethod ll Qualification l Outstand l'

l Items l lISyctems Safety Features ll Operating l 1 l l l 1 Year l 1.1 Years l J-10 l

' Actuation ll Time Note 2 l Note 1 { l [

I il 1 l l l V-16A l Simultaneous l Mone l l l l Test l 2

l Plant ID No. PTRC254 ll l l l l l

j i l l l l j l Components llTemperaturel 283.0 l l Pressure ll (*F) l 314.0 l H, X l J-10 l l l Il l l l Simultaneous l Transmitter ll l Mone l l l V-16A il 11 l l l l Test l l  ;

I I I l '

i l Manufacturers Foxboro ll Pressure l 52.0 I l 1 l

j l ll(PSIA) l 78.0 l G, X l J-10 l l .

l l l Simultaneous l

{ lNodel Number EllGH ll l l V-164 Mone l

!l l l I Test l S/N 266-0834ll l l l IFunction: Transmits l l l

l ll Relative l l l l 100.0

{l

>l Pressure Signals ll Humidity l l l 100.0 l A l J-10

[

l Simultaneous l l

Mone

_l ll Accuracy: Spec ll (t) l l

\ l V-16A I Test l l l 1.Os ll 1 l l l l t

!l I 1

l Demon
0.94% ll l Boric Acid l Boric Acid I I I I l

llChemical l l J-10 l l l 1800 ppm l 1800 ppm l l jlSarvics: RC Loop 1 HLG ll Spray l pH 5.0 l A l V-16A l 1lNida Range Pressure for ll l pH 5. 0" l l CAL-40 l Simultaneous l None l  !

l l Note 3 l Test, I lSFAS Ch. I and Indication ll l l l Note 3 l l l Analysis l l Location: Containment ll l l l l l

t l Rm. 407 l l l l l l l Radiation l4.89 x 106 RADS l1.0 x 107 RADS l AF l J-5 l l 11 l V-16A l I l l l Sequential Test l None

! l Flood Level Elev: 572'-2"ll l l l 1 l e

)lAboveFloodLevel Yes ll Aging l l l l jl l 40 Years l 0.54 Years l l l1 l I l CAL-74 l l l l Analysis IlNeeded fors ll Note 5 l l Note 4 l Mone l i l l l l l Hot Shutdown lXl ll l l l l l

l l l l l i l lSubmergencel 572' - 2" l l l Cold shutdown lX l l 606' - 0" l B l l ll l l J-11 l N/A l l l None l! l l l l l l l

l 1 l l

1 l l  !

l

t N '

Fccility: L vis-Becco Unit 1 Dockst: 50-346 SYSTDI COMPONENT EVALUATION WORKSHEET Index No. _219H-010h Prcpared by: _b Rev.: 2 Checkzd bya Dates. I hod r Dates ///A//w l

i j 1.

According to Profiles G and H, containment conditions will retur duration of the accident and ensuing cooldown.

rsturned to 150*F, 5 psig. At the completion of the 30-day LOCA simulation test,n to ambie rasult from the postulated lossThisoftest exposed coolant the transmitter to an overall more severe envir accident. test conditions had j concluded that the ler.g-term cooldown transmitter at ambient will maintain functional operability during thSince the transmitter remained conditions. , it can be opera e short-term accident environment and the

2 Ona year operating time is used as a conservative maximum specifi cation.

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

1 4 Materials evaluation conducted. )

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

Materials and/or components sensitive to thermal aging will be repl assure that associated component will maintain functional operability in harsh onments. enviraced as per maintenance and replac i

Th2 limiting (Reference material is the transmitter amplifier which has an aging lif CAL-74). e of 1.19/0.54 longer qualified life.However, there is operating experience at Davis-Besse Unit 1 and inyears at 104*F/120*F, respectively other nuclear plants to support a '

Although the 1.19/0.54 i

a longer life is justified. year qualified life is the best analyticelly I surveillance frequencies will be adjusted to ensure that noures common mode and egradation predominate.

aging properfailThe sur i '

1 i

l i

I t i

i 1

l 4

1 i

4

n Fccilithi Davic-Berta Unit 1 Docket:

(v3 J 4

\

50-346 COMPONENT MATERIALS EVALUATION SHEET Ptspared by b Index No.: _219H-010B Chsched by:

~ Dates j /!82 Rev.: 2

./WCW Dates ///>//)

l

' Plant I.D. No.: PTRC2B4 l Components Manufacturers Foxboro Pressures Transmitter 1 Model No.: __

EllGH*

l l_ l l

l l i Parts List l THERMAL AGING l l_ Materials List l Qualification RADIATION l

1 l Cover l l Referenca l Qualification l Aluminum 214 l l Reference l l Screws and Nuts l Steel l 40 Years l AA 1

I l Washers l l l Steel l 40 Years N/A l N/A l Btse Assembly l AA l l l Cast Iron l 40 Years N/A l N/A l Zaro Shaft l AA l l l 40 Years N/A l Sleeve l Steel l l AA l N/A l N/A l l Steel 40 Years 1 l AA l N/A l I l Zero Coupling Assembly l Steel l 40 Years l AA l N/A l N/A l Rztaining Rings l Steel l 40 Years l l N/A l N/A l

AA l l l Force Bar and Base l Steel l 40 Years l AA N/A l N/A l l Assembly l N/A l l 40 Years l AA l N/A l l Junction Box l Cast Iron l l

l N/A l N/A l Coupling l 40 Years l N/A N/A l

l Brackets l Stainless Steel l AA l l l l e l Steel l 40 Years l AA l N/A l N/A l Fl'xure Assemt! '

l Steel l 40 Years l AA N/A l N/A l Columns l l N/A l  !

l Steel 40 Years l N/A l Base j Cast Iron l 40 Years l AA l N/A l  !

l AA l N/A l l Cavar Plate Molding l Steel l 40 Years l AA l N/A l N/A '

l l l Tarminal Block Assembly l Steel l 40 Years l AA N/A l N/A l l Detector Assembly l l Steel l 40 Years l N/A l N/A l Plates l AA l l l Steel 40 Years l AA N/A l N/A l Level Assembly l l N/A l l l Steel l 40 Years l AA l N/A l N/A l l 40 Years l AA l N/A l l l N/A l 1 l N/A l l l

_ _ _ . _ _ _ - - ~

a

Fccilityt % 2vis-Cosza Unit 1 '

Docket COMPONENT MATERIALS EVALUATION SHEET 50-346 Index No.: _219H-010C Rev.: 2 Prepr. red by: b h Date: ( I Checked bys h Cl__J/ Dates N/M P) l Plant I.D. No.: PTRC2B4 Components Pressure Transmitter l l Manufacturer Foxboro Model No.: EllGH* l l

l l l l THERMAL AGING l RADIATION l

] Parts List l Materials List l Qualification l Reference l Qualification Reference l l

l l l

< l Blocks l Steel l 40 Years.

l I l AA l Lever l Steel l 40 Years l

AA l N/A l N/A l l Clamp Spring l l N/A l N/A l Steel l l 40 Years AA l Bushings l Steel l 40 Years l l N/A l N/A l l AA N/A l Coil Assembly l Steel l 40 Years l l N/A l

] AA l N/A l Zsro Screw Assembly l Steel l 40 Years l N/A l l Spring Assemblies l AA l N/A l N/A l Steel 40 Years l l l AA N/A l Tubing l l N/A j l Steel l 40 Years AA l Clamps l Steel l l N/A l N/A l l 40 Years AA l Lubricant l Silicone Oil l Not Sensitive l

l AA l N/A l N/A l l Transmitter Amplifier l N/A l N/A l l Solid State Electronics l 0.54 Years 9 120*F l CAL-74 l N/A l Assembly l l N/A l l l N/A l O-Rings l Viton l l N/A l

] 40 Years e 265'F l CAL-74 l N/A l Nylon Washer l Nylon (Polyamide) 96 Years @ 120*F l N/A l l Cable l Nylon (Polyamide) l l CAL-74 l N/A l N/A l l 96 Years 0120'F l CAL-74 l H,'A l Insulator l Nylon (Polyamide) l N/A l l 96 Years 0 120*F l CAL-74 N/A l Stalant l Silicone RTV (Silastic) l 40 Years e 302*F l CAL-74 l l N/A l l Force Motor Assembly l Formvar Insulation l N/A l N/A l l Armature Assembly l 40 Years @ 122'F l CAL-74 l N/A N/A l Formvar Insulation l 40 Years @ 122'F l CAL-74 l N/A l ]

l Terminal Block Phenolic l N/A l l l 40 Years 0 230*F l CAL-74 l N/A N/A l l Column l Phenolic l l 40 Years @ 230'F l CAL-74 l N/A l N/A l l l l l 1 l l Msterials & Parts List

Reference:

AA

  • Thejunction E11GH materials box, and electronics. list is applicable to the EllAH and EllGM transmitters because these transmitters have identical topworks, Note 1:

Conservative value based on the fact that the transmitter amplifier assembly is the most limiting component for thermal aging (see Reference AA, CAL-38).

O Facilitys Doc ket :

G vic-Becca Unit 1 G O 50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Index No. : ~219H-011 Prapared by: Tj M Rev.: 0 Chec ked by :

Date: 9/28/N D Date: 9,/2T,fff--

y l ll l EQUIPMENT DESCRIPTION l

ll ENVIRONMElfr 1

I i l DOCUMENTATION REF. l l ll ll Parameter i Specification l Qualification ISpecification l Qualification l Qualification l l Outstanding l l l Met hod l Items lSyctem: Safety Features ll Operating l 26 Hours l l l l

l Actuation l N/A l F l l1 l l Time l l l Note 3 l N/A l l None lPlcnt ID No.

ll I I l l l l l I l

l FI2004 ll l l l l l l l

l l Temperature l l l l l Component: 109.0 l Ecempt l l Radiation ll (*F) l l C-Annulus l Note 1 l l

l. Detector l N/A None l

ll _

l l l l l l l l l Manufacturer ll l l l l l l l

Victoreen ll Pressure l l l l

l 15 32 l Exempt l l ll(PSIA) l l C-Annulus l Note 1 l N/A l

l l None l

l Modal Number: 84 5 ll l l l l l l l

ll 1 l l l l l

l Function: Radiation iIRelative l 100.0 l 1 I l l l Detection l Exempt l A l l ll Humidity l l l Note 1 l N/A l

ll l l None l n) l l l l Accuracy: Spec: N/A ll l l l l l l l I l I Demon: N/A ll l l l l l

l l l l l l l Chemical l N/A l l l Service: Input to SFAS l l Spray I N/A l N/A l l l l l l N/A l N/A l ll l l None l l l l l l ll l l l l l l

lIccr.tlon: Annulus ll l l l 1 l l l El. 585' l l l l l l l Radiation l1.7 x 107 RADS l Exempt l l l l Flood Level Eley:

ll l l l CAL-44 l Note 2 l N/A l

~l N/A ll l l None I l l l lAbova Flood Level: N/A ll Aging I 40 Years l l l 1 l

.I l N/A l l lNeedId for ll 1 l

l I l Note 3 i N/A l None ll l l l l l l l

l Hot Shutdown lXl ll l l l l l

0 l l l l l lSubmergenc e l N/A l l-0 Cold Shutdown l l N/A l 0

l ll l l l N/A l N/A l N/A l None l

ll. l l l l l l l l l l l l l

n f

SYSTDt COMPONE LUATION WORKSHEET Index 21CH-011A Fac ility: c-Becco Unit 1 Rev. : O Doc ket : 50-346 Prepared by: ,((  ; Date: 7/28/d/

Check;d by: gf M Date: 9/2f/g /

p -- a j 1. This radiation detector provides an input into the safety features actuation system. The only safety-related furetion performed by this detector is the initiation of the SFAS upon measuring high radiation levels resulting from a fueling accident or a LOCA. The detector is exempt from qualification because it does not perform a safety-related function in the l

harsh steam environment caused by a high energy line break. Failure of the detector in this environment (along with a almilar failure of one of the other three detectors) may initiate the safety features actuation system on a high containment rcdiation initialing signal. This unlikely SFAS initiation would have the following results: l

a. Initiation of the emergency ventilation system (EVS).
b. Closure of ECCS Room Isolation Dampers.
c. Closure of the containment air sample isolation valves. l j
d. Closure of the Containment and Penetration Room purge isolation valves. l
e. Stops Control Room normal HVAC units.

These actions will not degrade other safety-related functions because they do not interfere with the mitigation of a HELB. l Initiation of the EVS will merely result in the control of a negative pressure boundary in the Ar.nulus and Penetration Rooms. Closure of the ECCS Room's isolation dampers is of little corcern because the equipment located in these rooms that is needed to mitigate the high energy line break (HPI pumps), will perform their furction. Closure of the containment air The purge valves are c:mple valves is unimportant because it is unnecessary to sample containment air during a HELB. The Control Room normally closed during plant operation and the purge system is only needed in the mitigation of a LOCA.

smergercy HVAC units may be initiated in the event that the normal units stop.

Upon the unlikely occurrerce of these events, the operator would be aware of the SFAS initiation from the indicating lights on the engineering safety features panel. He may override any of these SFAS actions from the Control Foom-

2. This radiation detector is exempt from qualification because its main furetion is to monitor containment radiation levels during re-fueling. The detectors, which are located in the annulus, are moved inside the containment during re-fueling ope rations. They will initiate the safety features actuation system upon sensing high radiation levels that may result f rom a fueling accident.

7 Fac ility : a-Besse Unit 1 SYSTDI COMPONEIC ATION WORKSHEET Index L,_ j 219H-0119 Doc ket : 50-346 Rev.: 0 NOTES Prepared by: T M I MP, Date: 2/28/8/

Chec ked by g. ~)7 Date: 9/2f/f/

During normal pte.nt operations, these SFAS detectors will also initiate the safety features actuation system upon sensing high radiati n. In the event of a loss of coolant accident, SFAS will be initiated by either a low reactor coolant pressure cignal or a high containment vessel pressure signal. These signals will initiate SFAS before initiation would occur due to high radiation levels. Because of this, failure of the detectors, in the accident environment, will not degrade safety related functions. The operator will not be misled by detector failure because he will determine containment rcdiation levels by post-accident sampling.

3. Since these components are not required to operate during the postulated accidents, operating time and thermal aging qur.lification is not applicable.

l l

~

o Facility: N 4vio-Becse Unit 1 Doc ket : 50-346 O

SYSTEM COMPONENT t. VALUATION NORKSHEET O

Index No.: 219H-012 Fev.: 0 Prspared by: IM Dater k[28[6(

3 _

m Chec k;d by : Af/."2PL, Date: f/2t/P/

l ll l EQUIPMENT DESCRIPTION ll l l

l ENVIRONMENT l l l DOCUMENTATION REF.

l ll Parameter l Specification l Qualification ISpec ific ation l Qualific ation ll Qualification l Outstanding l ll l l Method l Items l System: Safety Features ll Operating l 26 Hours l 1

l l l

l Actuation N/A l F Note 3 l l ll Time l l l l N/A l None l l l ll- l l l l l lPlent ID No. RE2005 ll l l l l l

l l l l l l l Temperature l 109.0 l l l l Component: l Exempt l C-Annulus l l Radiation ll (*F) l l Note 1 l N/A l None l l Detector ll l l l l l l l l l ll l l l l $ l l

l Manufacturer: Victoreen ll Pressure l 15.32 l Exempt l l l l l

ll(PSIA) l l C-Annulus l Note 1 l N/A l l l None l l Modal Number: 84 5 ll l l l l l l l l

ll l l l l l l lFuretion: Radiation ll Relative l 100.0 1 l l l Detection l Exempt l A 1 l ll Humidity l l Note 1 l N/A l None l l l

ll (s) l l l l l l l Accuracy: Spect N/A ll l l l l l l

l l l

' l

!l Demon: N/A ll l l l l l l l l l ll Chemical l N/A l l l

l Service: Input to SFAS ll Spray l N/A l N/A l N/A l l l l l N/A l None l ll l l l l l l l

ll l l l l l l l

lIocction: Annulus ll l l l l l l

l El. 585' l l l l l l ll Radiation 11.7 x 107 RADS l ll Exempt l CAL-44 l Note 2 l l l l l N/A l None l Flood Level Elev N/A ll l l l l l l

l l lAbova Flood Ievel: N/A ll Aging l 40 Years l l l l l l N/A l l ll l l I l Note 3 l N/A l Hone lNerdId 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 l l Submergence l l l N/A l N/A l l l Cold Shutdown l l ll l l l N/A l N/A l N/A l None l l l ll l l l l l l l l l l l

f') {}

N Fac ility: L sic-Besse Unit 1 SYSTD( COMPONENT UATION WORKSHEET Index No.'s 219H-012A Doc k;t : 50-346 Rev. : O Prepa red by : [ Dates NE.O[Sf Chec ked by : 4. Date: 9/2fff/

f l

l

1. This radiation detector provides an input into the safety features actuation system. The only safety-related furction l performed by this detector is the initiation of the SFAS upon measuring high radiation levels resulting from a fueling accident or a LOCA. The detector is exempt from qualification because it does not perform a safety-related function in the l harsh steam environment caused by a high energy line break. Failure of the detector in this environment (along with a cicilar failure of one of the other three detectors) may initiate the safety features actuation system on a high containment r diation initialing signal. This unlikely SFAS initiation would have the following results:
e. Initiation of the emergency ventilation system (EVS).
b. Closure of ECCS Room Isolation Dampers.
c. Closure of the containment air sample isolation valves.
d. Closure of the Containment and Penetration Room purge isolation valves.
e. Stops Control Room normal HVAC units.

Thsse actions will not degrade other safety-related functions because they do not interfere with the mitigation of a HELB.

Initiation of the EVS will cerely result in the control of a negative pressure boundary in the Annulus and Penetration Rooms. Closure of the ECCS Room's isolation dampers is of little concern because the equipment located in these rooms that 10 needed to mitigate the high energy line break (HPI pumps), will perform their furetion. Closure of the containment air ccmple valves is unimportant because it is unnecessary to sample containment air during a HELB. The purge valves are normally closed during plant operation and the purge system is only needed in the mitigation of a LOCA. The Control Room smergercy HVAC units may be initiated in the event that the normal units stop.

Upon the unlikely occurrence of these events, the operator would be aware of the SFAS initiation from the indicating lights on the engineering safety features panel. He may override any of these SFAS actions from the Control Room.

2. This radiation detector is exempt from qualification because its main furetion is to monitor containment radiation levels during re-fueling. The detectors, which are located in the annulus, are moved inside the containment during re-fueling ope rations. They will initiate the safety features actuation system upon sensing high radiation levels that may result from c fueling accident.

G Facility: L.Jc-Becse Unit 1 SYSTDS COMPONEfff UATION WORKSHEET Index L j 219H-0127 Doc ket : 50-346 Rev.: O Prepared by YM[ . Date . k28[8l Checked by: M.M Dates //]////

y -- -

During normal plant operations, these SFAS detectors will also initiate the safety features actuation system upon sensing high radiation. In the event of a loss of coolant accident, SFAS will be initiated by either a low reactor coolant pressure oignal or a high containment vessel pressure sigral. These signals will initiate SFAS before initiation would occur due to high radiation levels. Because of this, failure of the detectors, in the accident environment, will not degrade esfety-related functions. The operator will not be misled by detector failure because he will determine containment rcdiation levels by post-accident sampling.

3. Sirce these components are not required to operate during the postulated accidents, operating time and thermal aging qualification is not applicable.

s T

SYSTEM COMPONENT J ATION NORKSHEET. Indrx NQ,)19H-013 2

  • acility: D,au-Becse Unit 1 0 Rev.:

Nx:ket : 50-346 t

Yepsr:d by: ) Y[ m Date: NM8) .

3mcked by: ~

47 ~)Afossf/ Date:e f/Jf79/ i 7

l l l lI l l Qualification 1 Outstanding l ll ENVIRONMENT l DOCUMENTATION REF.

EQUIPMENT DESCRIPTION Method Items ll Parameter l Specification l Qualification I Specification Qualif icathionl l ll l I I i l N/A l Mone l Safety Features ll Operating l 26 Hours l N/A l P l Note 3 l System l l l l l Actuation ll Time l l l l l l ll l l l l l P1ent ID No. RE2006 ll l l l l l None l C-Annulus l 109.0 Note 1 l N/A 'l l ll Temperature l l Exempt l l  !

Component: Radiation ll (*F) l l l l l l l l l Detector ll l l l l l l l ll l l l l l Hone Manuf acturer: Victoreen ll Pressure l 15.32 l Exempt l C-Annulus l Note 1 l N/A l l l l l l l l ll(PSIA) l l l l l l l

Modal Ntamber: 845 II l l l

)

ll l l l A

l Note 1 l

l N/A 1

l None l i

lIRelative 100.0 Exempt l Function: Radiation I l I l l l Detection lIHumidity l l l l l l l ll (s ) l l l l l l Accuracy: Spec N/A ll l l l l l l l l )

l l Demon: N/A ll l l None ll Chemical l N/A l N/A l N/A l N/A l N/A l l l l l l Servics: Input to SFAS ll Spray l l l l l r ll l l l l l l l l ll l l l l l l Ieccticn: Annulus ll l l l l l None l El. 585' ll Radiation i1.7 x 107 RADS l Exempt l CAL-44 l Note 2 l N/A l l I I l ll l l l ~

l l l N/A ll l l l l Flood Level Elev: None l Abova Flood Level: N/A llAging l 40 Years l N/A I I l Note 3 l N/A l l l ll l l l l l l

Need:d for: ll '

l l l I l l l Hot Shutdown lX l ll l l l l ..

N/A None l l l Suhnergencel N/A I N/A I N/A l N/A l I l l l Cold Shutdown l l ll l l l l l l l 1 ll l l l I I

f Facility: (jc-Berse Unit 1 SYSTDI COMPONE UATION WORKSHEET Index\ 219H-013A Dec ket : 50-30 Rev.: 0 1 Prcpared by: __ M cb Date: _9/16[81 Chec ked by : #(Z 7Pla,./a Date: 9/2////

/

l 1. This radiation detector provides an input into the safety features actuation system. The only safety-related function l performed by this detector is the initiation of the SFAS upon measuring high radiation levele resulting from a fueling accident or a LOCA. The detector is exempt from qualification because it does not perform a safety-related function in the harsh steam environment caused by a high energy line break. Failure of the detector in this environment (along with a cimilar failure of one of the other three detectors) may initiate the safety features actuation system on a high containment rcdiation initialing signal. This unlikely SFAS initiation would have the following results:

a. Initiation of the emergency ventilation system (EVS).
b. Closure of ECCS Room Isolation Dampers.
c. Closure of the containment air sample isolation valves.
d. Closure of the Containment and Penetration Room purge isolation valves.
e. Stops Control Room normal HVAC units.

These actions will not degrade other safety-related functions becausa chey do not interfere with the mitigation of a HELB.

Initiation of the EVS will merely result in the control of a negative pressure boundary in the Annulus and Penetration Rooms. Closure of the ECCS Room's isolation dampers is of little corcern because the equipment located in these rooms that is needed to mitigate the high energy line break (HPI pumps), will perform their function. Closure of the containment air simple valves is unimportant because it is unnecessary to sample containment air during a HELB. The purge valves are normally closed during plant operation and the purge system is only needed in the mitigation of a LOCA. The Control Room cmergercy HVAC units may be initiated in the event that the normal units stop.

Upon the unlikely occurrerce of these events, the operator would be aware of the SFAS initiation from the indicating ligits on the engineering safety features panel. He may override any of these SFAS actions from the Control Room.

2. This radiation detector is exempt from qualification because its main furction is to monitor containment radiation levels during re-fueling. The detectors, which are located in the annulus, are moved inside the containment during re-fueling ope ration s. They will initiate the safety features actuation system upon sensing high radiation levels that may result from a fueling accident.

A Facility se:vic-Bessa Unit 1 Doc ket : 50-346 SYSTEM COMPONENT EVALUATIC1 WORKSHEET Index No.: _219H-013B NOTES Rev.: 0 Prepared by: o7 chec ked by a Date: _ f[26/fl

f. Dete: 9%f/f)

! During high normal radiation. plant operations, these SFAS detectors will also initiate the safety featur j In the event of a loss of coolant ac ident , es actuation system upon sensing signal or a high containment vessel pressure signal. SFAS will be initiated by either a low reactor coolant pressure

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high radiation levels. Because of this, failure of theThese , signals will initiate SFAS before initiation would occur due to detectors, safety related functions. in the accident environment, will not degrade radiation levels by post-accident sampling.The operator will not be misled by detector failure because he will determine n conta 3.

Since these components qualification are not required to operate during the postulated accidents is not applicable.

, operating time and thermal aging i

1 i

5 i

i i

l 1

i i

i

,rh

/

's Facility : i_ac-Becse Unit 1

) EYSTD4 COMPONE ATION WORKSHEET Index\ /219H-014 Dec ket : 50-346 Rev.: O Prcpared by: A. _7 2 Date s f[Eh8I Chec k;d by : #t7. M Date 9./2f./f/

g l ll l l l l lEUJIPMENT DESCRIPTION ll ENVIRONMENT l DOCUMENTATION REF. l Qualification l Outstanding l l ll Parameter i Specification l Qualification l Spec ific at ion Qualific ation l Method l Items l l ll l l l l l 'l lSy stems Safety Features l l Operating l 26 Hours l N/A l F l Note 3 l N/A l None l l Actuation ll Time l l l l l l l l ll l l 1 I l l l lPlcnt ID No. RE2007 ll 1 l l l l l l l l lTempe rature l 109.0 l E*empt l C-Annulus l Note 1 l N/A l None l l Component: Radiation ll ('F) l l l l l l l l Detector ll 1 l l l l l l l ll l l l l l l l l Manufacturer: Victoreen l l Pressure l 15.32 l EKempt l C-Annulus l Note 1 l N/A l None l l ll(PSIA) l l l l l l l l Mod 21 Number: 84 5 ll l l l l l l l ll l l l l l l l Function: Radiation ll Relative l 100.0 l Exempt l A l Note 1 l N/A l Hone l l Detection ll Humidity l l l l l l l l ll (s) l l l , I l l Accuracy: Spec t N/A ll l l l l l l Demon: N/A ll l l l l l l l l l l Chemical l N/A l N/A l N/A l N/A l N/A l None l l Service: Input to SFAS ll Spray l l l l l l l I ll l l l l l l l l ll l l l l l l l

, lIocction: Annulus ll l l l l l l l l El. 585' ll Radiation l1 7 x 107 RADS l Exempt l CAL-44 l Note 2 l N/A l None l l ll l l l l l l l l Flood Level Elev: N/A ll l l l l l l l l Abova Flood Ievel: N/A llAging l 40 Years l N/A l I l Note 3 l N/A l None l l ll l l l l l l l lNe: dad for ll l l l l l l l l Hot Shutdown lX l ll l l l l l l l l l lSubmergerx:e l N/A l N/A l N/A l N/A l N/A l None l l Cold Shutdown l l ll l l l l l l l l ll l l l l l l l

( p

\ -

SYSTEM COMPONE UATION WORKSHEET I

Index/( j'219H-014A Fac ility 'bs ic-Becse Unit 1 Doc ket : 50-346 Rev. O Prepared by: 7 Y M Date: _ 9M9/8 /

Chec ked by : u H W. M Date

y. -,/2f/f/

9 a

1. This radiation detector provides an input into the safety features actuation system. The only safety-related function performed by this detector is the initiation of the SFAS upon measuring high radiation levels resulting from a fueling accident or a LOCA. The detector is exempt from qualification because it does not perform a safety-related function in the i harsh steam environment caused by a high energy line break. Failure of the detector in this environment (along with a ci=ilar failure of one of the other three detectors) may initiate the safety features actuation system on a high containment rcdiation initialing signal. This unlikely SFAS initiation would have the following results:
a. Initiation of the emergency ventilation system (EVS).
b. Closure of ECCS Room Isolation Dampers.
c. Closure of the containment air sample isolation valves.
d. Closure of the Containment and Penetration Room purge isolation valves.
o. Stops Control Room normal HVAC units.

These actions will not degrade other safety-related functions because they do not interfere with the mitigation of a HELB.

Initiation of the EVS will merely result in the control of a negative pressure boundary in the Annulus and Penetration Rooma. Closure of the ECCS Room's isolation dampers is of little concern because the equipment located in these rooms that is needed to mitigate the high energy line break (iRI pumps), will perform their furction. Closure of the containment air ccmple valves is unimportant because it is unnecessary to sample containment air during a HELE. The purge valves are normally closed during plant operation and the purge system is only needed in the mitigation of a LOCA. The Control Room smergercy HVAC units may be initiated in the event that the normal units stop.

Upon the unlikely a:currence of these events, the ' operator would be aware of the SFAS initiation f rom the indicating lights on the engineering safety features panel. He may override any of these SFAS actions from the Control Room.

2. This radiation detector is exempt from qualification because its main furetion is to monitor containment radiation levels during re-fueling. The detectors, which are located in the annulus, are moved inside the containment during re-fueling operations. They will initiate the safety features actuation system upon sensing high radiation levels that may result f rom a fueling accident. .

~~

Facility : ' L Jic-Berse Unit 1 SYSTDI COMPONE UATION WORKSHEET Index 219H-0147 Rev.: 0 Doc ket : 50-346 NUIES Prepa red by : N d Dates f/Ed/I(

Chec ked by : W/. ate: 9/22/rj l l

During normal plant operations, these SFAS detectors will also initiate the safety features actuation system upon sensing high radiation. In the event of a loss of coolant accident, SFAS will be initiated by either a low reactor coolant pressure signal or a high containment vessel pressure signal. These signals will initiate SFAS before initiation would occur due to high radiation levels. Because of this, failure of the detectors, in the accident environment, will not degrade ccfety-related functions. The operator will not be misled by detector failure because he will determine containment rtdiation levels by post-accident sampling.

3. Sirce these components are not required to operate during the postulated accidents, operating time and thermal aging qualification is not applicable. i 1

.

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