Text

Rev 2 to Procedure 1040-001-022, Safety Features Actuation Sys
	ML20083A422
Person / Time
Site:	Davis Besse
Issue date:	11/02/1983
From:	; TOLEDO EDISON CO.
To:	;
Shared Package
ML17150A231	List: ML17150A230; ML20083A206; ML20083A216; ML20083A222; ML20083A234; ML20083A237; ML20083A244; ML20083A252; ML20083A264; ML20083A269; ML20083A278; ML20083A283; ML20083A294; ML20083A298; ML20083A315; ML20083A322; ML20083A336; ML20083A365; ML20083A376; ML20083A396; ML20083A415; ML20083A422; ML20083A439; ML20083A454; ML20083A473; ML20083A486; ML20083A500;
References
	1040-001-022, 1040-1-22, IEB-79-01B, IEB-79-1B, NUDOCS 8312200283
	Download: ML20083A422 (44)
	v • d • e

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

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 1040-001-671 I & E Bulletin 79-01B JobNo:

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.

R EV. -N O.

REVISION APPROVED DATE Orhf(d

@h, EO chu t o-? -9 O

cmmu %wn A///ockdan0 //k/s.

1 2

aw:mac

~

/ /

I I-l 8312200283 831129 I

[

PDR ADOCK 05000346 l

[

P PDR ces oaos $7 j

Sheet i

of I

)

FccilitNJavis-M223 Unit 1 MASTER u t Index No \\

J-001 Dockat:

50-346 HARSH ENVIRONMENT Rev.:

2 SAFETY FFATURES ACTUATION SYSTEM 3

Prs: pared by:

Date 82 Checked by:

c'/jjl f6 s fl Dates

,V _ 'c.' 4 s

I l

l l

l LOCATION I

I i

l l

l I

Inside l

Outside i

I I worksheet l l

Plant i

I Primary l

Primary I

l l

Index No.

I Rev. IID Number I Generic Name I Containment I Containment i REMARTE I

I l

l l

l 219H-004 l

2 IPT2001 1 Pressure Transmitter i

l Rm. 501 i

l 1 21911-005 1

2 IPT2002 I Pressure Transmitter I

l Pa. 500 l

I i 219H-006 1

2 ipr 2003 i Pressure Transmitter I

l Rm. 426 I

I I 219H-007 1

2 lPTRC2A3

'l Pressure Transmitter l

Rm. 410 I

I I

I 219H-008 1

2 IPTRC2A4 i Pressure Transmitter i

Rm. 410 l

I I

l 219H-009 l

2 iPTRC2B3 i Pressure Transmitter i

Rm. 407 I

I I

I 219H-010 1

2 l PTRC2B4 i Pressure Transmitter I

Rm. 407 I

I I

I 219H-011 1

0 IRE 2004 I Radiation Detector I

I Annulus l

I I 219H-012 1

0 IRE 2005 i Radiation Detector I

I Annulus l

I I 219H-013 1

0 IRE 2006 i Radiation Detector I

l Annulus i

I I 219H-014 1 0 IRE 2007 i Radiation Detector i

I Annulus l

I I

l l

1 I

i l

i I

I I

I l

i I

I I

l I

i i

l l

I I

l I

I I

l I

I I

l l

1 1

I I

l l

I I

i l

I 4

I I

i l

l I

I I

I l

l I

I I

l l

I I

I l

l l

I I

l I

I I

l l

l 1

I l

I I

i l

I I

l 1

~

FacilijDavis-Besse Unit 1 MASTi. - sT Index No

-002 Docket:

50-346 NON-HARSH ENVIRONMENT Rev.:

2 SAFETY FEATURES ACTUATION SYSTEM Prepared by:

% E,.

Date: f8 2

l Checked by:

, _ A s' Date:

J.

l 1

1 I

I LOCATION l

l l

Inside l

Outside _l I

I Worksheet l l

Plant l

l Primary l

Primary l

l l

Index No.

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

l 1

l l

1 l

l l

l 0 IC3630 l Auxiliary Shutdown Panel l

l Rm. 324 l

l l

I O lC5705 l Control Console l

l Rm. 505 l

l l

l 0 IC5716 l Engineering Safety Feature Panel l

l Rm. 505 l

l l

l 0 1C5717 l Engiccering Safety Feature Panel I

l Rm. 505 l

l l

l 0 IC5755C l Safety Features Actuation Panel l

l Rm. 505 l

l l

l 0 lC5755D l Safety Features Actuation Panel I

l Rm. 505 l

l l

l 0 IC5756C I Safety Features Actuation Panel l

I Rm. 505 l

I l

l 0 IC57560 l Safety Features Actuation Panel l

l Rm. 505 l

l l

l l 0 IC5762C l Safety Features Actuation Panel l

l Rm. 505 l

l l

j l 0 lC5762D l Safety Features Actuation Panel l

l Rm. 505 l

l l

l 0 IC5763C l Safety Features Actuation Panel l

l Rm. 505 l

I l

l 0 lC5763D l Safety Features Actuation Panel l

l Rm. 505 l

l l

l 0 l LT1525A I Level Transmitter l

l BWST. Yard l l

l l 0 ILT1525B l Level Transmitter i

i BWST. Yard l I

I I 0 ILT1525C l Level Transmitter l

l BWST. Yard l l

l l 0 l LT15250 l Level Transmitter l

l BWST. Yard I l

l l 0 IPT2000 l Pressure Transmitter l

l Rm. 404 l

l l

l 1

I I

l l

l 1

l l

1 I

I l

l l

l I

l i

I I

l l

l 1

1 I

I I

l i

I I

l i

i l

i I

I I

w

O C) m Facili-.

Davis-Bess 2 Unit 1 MASTE w tST IndexNohi9M-003 Dockst:

50-346 Rev.:

2 SAFETY FEATURES ACTUATION SYSTEM Prepared by:

9 Date:

O Checked by:

-..., e c %... //

Date:

r './ e

+

l l

l LOCAIION I

i 1

l l

Inside i

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 I Containment i REMARKS l

1 1

I I

I l

l l

l 1

I I

l l

I I

I i

i l

l I

I I

i l

i I

I I

i i

l I

i l

l I

I I

l 1

1 I

I I

i l

1 1

I I

I i

l I

i l

l I

I I

l I

I I

i l

i I

i i

l i

I i

i i

l I

i i

l l

I I

I l

I I

I l

l l

l 1

i i

l i

l I

I i

I l

i l

I I

i l

I i

i l

i i

l i

l I

I I

I i

i l

i I

I I

I l

l I

I I

l l

l I

1 1

r

(~h O

O O

Fccility: Davis-Oesso Unit 1 Dockst 50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Prepm "2 by:

W Index No.: 219H-004 Date:

8 Checka by: N O R - f [ Dater _

)

Rev.

2

///]/&

l ll l EQUIPMENT DESCRIPTION l

ll_

ENVIRONMENT _

l ll Parameter l Specification l Qualification lSp DOCUMENTATION REF.

l l

l

_ Il I

ecificationl Qualification ll Qualification l Outstanding l System:

i l

Safety Features ll Operating l 1 Year l 1.19 Ye*ars l

Note 2 l

Note 1 l Simultaneous l None l

l I

I__, Method l

Itees Actuation ll Time l

l J-10 l

I

_ l l

ll l

l l

l Plant ID No.

l l

V-16A l

Test l

l PT2001 ll l

l l

l Component ll Temperature l l

l l

267.0 l

314.0 l

C-501 l

J-10 l

l Pressure

}l

(*F) l 1

l l

~l Transmitter ll l

l l

l Simultaneous l None l

l l

l V-16A l

Test l

l lMInufccturer:

ll l

l l

l Foxboro ll Pressure l

15.61 l

13.0 l

C-501 l

J-10 l

l l

i l Modal Number:

ll(PSIA) l EllAH ll l

t l Function:

S/N 319-2422ll__

l l

l Simultaneous l None l

l l

(

V-16A l

Test l

l l

Transmits ll Relative l

100.0 l

A l

J-10 l

l l

l Pressure Signals ll Humidity l

l l

l ll l

l l

, I Accursey: Specs 1.0%

ll__ (4) l l

l Simultaneous l None l

l l

V-16A l

Test l

l

'l l

l l

l Demon: 0.944 ll l

l l

tl I

l l

l 1

j lSarvico ll Chemical l

N/A l

None l

l Containment l

l l Pressure Input to SFAS ll Spray l

l l

ll l

l l

'l Channel 2 and Indicationl{

l l

l

.0 Location:

l l

l 0

Auxiliary Bldg.ll l

l l

Rm. 501 l l Radiation l 2. 0 x 102 l

l l

0 l

aADS 17.6 x 107 l

V-lGA l

l

) Flood Level Elev ll.

l aADS l T

l J-6 l

N/A ll l

Above Flood Level:

l 1

I l Sequential Testi l

l l

l None l

N/A ll Aging l

40 Years l

1.19 Years l

I l

CAL-74 l

Analysis l

None l

l l

!Nasdad fors ll l

l ll l

Note 4 l

~~l Hot Shutdown l _X l ll _

l l

l Note 3 l

l l

ll Submergence l l

l l

l

~

l l

Cold Shutdown l

l N/A l

N/A l

None l

l l

lK-l ll l

l

_l l

l

_ l_

l l

,m f

(

)

(

I i

/

s

/

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

50-346 Re v. :

2

./

f NOTES e

M Dates

// r

'r: par d by:

A.+/w d Dates g/.'/o

/

heck d by:

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 O

n COMPONENT MATERa h EVALUATION SHEET Index U 219H-0048 FIcility: Avic-Berse Unit 1 Dockit 50-346 Rev.:

2 Prepared by:

N.

Date:

)

Checked by:

hs/h Dater ///.A//)

I j

l Plant I.D. No.:

PT2001 Component:

Pressure Transmitter l

l l

Manufacturer Foxboro Model No.t EllAM*

l l

l THERMAL AGING l

RADIATION l

l Parts Lfst l

Materials List l

Qualification l Reference l Qualification Reference l l

l l

l l Cover l Aluminum 214 l

40 Years l

AA l

N/A l

l Screws and Nuts l Steel l

40 Years l

AA l

N/A l

l Washers l Steel l

40 Years l

AA l

N/A l

l Esse Assembly l Cast Iron l

40 Years l

AA l

N/A l

i l

l Zero Shaft l Steel l

40 Years l

AA l

N/A l

l Sleeve l Steel l

40 Years l

AA l

N/A l

l Zaro Coupling Assembly l Steel l

40 Years l

AA l

N/A l

l l RItaining Rings l Steel l

40 Years l

AA l

N/A l

l Force Bar and Base l Steel l

40 Years l

AA l

N/A l

l Assembly l

l l

l N/A l

N/A l

j l Junction Box l Cast Iron l

40 Years l

AA l

N/A l

l l Coupling l Stainless Steel l

40 Years l

AA l

N/A l

l Brackets l Steel l

40 Years l

AA l

N/A l

l Flsxure Assemblies l Steel l

40 Years l

AA l

N/A l

l Columns l Steel l

40 Years l

AA l

N/A l

l l Este l Cast Iron l

40 Years l

AA l

N/A l

j l Cover Plate Molding l Steel l

40 Years l

AA l

N/A l

l Tarminal Block Assembly l Steel l

40 Years l

AA l

N/A l

l Detector Assembly l Steel l

40 Years l

AA l

N/A l

l Plates l Steel l

40 Years l

AA l

N/A l

l Level Assembly l Steel l

40 Years l

AA l

N/A l

l l

I i

l l

d i

Fccilitys" Davis-Besse Unit 1 Docket:

50-346 COMPONENT MATERIALS EVALUATION SHEET Index No.:

~219H-004C Prepared by: _

^,

Date:

W /

)

Rev.:

2 l

Checked by:

.MofA - y Dates p/>/O i

1 l

Plant I.D. No.:

l PT2001 Manufacturers Components Foxboro Pressure Transmitter Model No.:

l EllAH*

l_

l l

THERMAL AGING l

l_

Parts List l

Materials List l

Qualification l

RADIATION l

I

{

l Blocks I

l Reference l Qualification l Steel I

I l Reference l l Lever l

40 Years l Steel l

AA l

N/A l

I l

l Clamp Spring l Steel l

40 Years l

AA l

N/A l

l Eushings l Steel l

40 Years l

AA l

N/A l

j l Coil Assembly l Steel l

40 Years l

AA l

N/A l

l Zaro screw Assembly l Steel l

40 Years l

AA l

N/A l

l Spring Assemblies l Steel l

40 Years l

AA l

N/A l

l Tubing l Steel l

40 Years l

AA l

N/A l

l Clamps l

40 Years l

AA l

N/A l

l Steel t l Lubricant l

40 Years l

AA l

N/A l

l Silicone Oil i l Transmitter Anplifier l Solid State Electronics l

1.19 Years 0 104*F l CAL-74 l

N/A l

l Not Affected l

AA l

N/A l

[ l Assembly l

1l O-Rings l Viton l

l N/A l

N/A l

l I

l Nylon Washer l Nylon (Polyamide) l

% Years' S 120*F l CAL-74 l

N/A l

l 40 Years 9 265'F l CAL-74 l

N/A l

[l Cable l Nylon (Polyamide) l

% Years 9120*F l CAL-74 l

N/A l

jl Insulator l Nylon (Polyamide) l 96 Years 9 120*F l CAL-74 l

N/A l

}l Scalant l Silicone RTV (Silastic) l 40 Years 8 302*F l CAL-74 l

N/A l

i l Force Motor Assembly l Formvar Insulation l

40 Years 0 122*F l CAL-74 l

N/A l

l Armature Assembly l Formvar Insulation l

40 Years 8 122*F l CAL-74 l

N/A l

3 il Tar..inal Block l Phenolic 1l Column l

40 Years 8 230*F l CAL-74 l

N/A l

1l l Phenolic i

1 l

40 Years @ 230*F l CAL-74 l

l N/A l

N/A l

l l

Materials & Parts List Reference :

AA 1

i j

The EllGH materials list is applicable to the EllAH and EllG j

junction box, and electronics.

M transmitters because these transmitters have identi i

cal topworks,

{Notela Conservative value based on the fact that the transmitt aging (see Reference AA, CAL-38).

er amplifier assembly is the most limiting component for the rmal 1,

,~

Facility: L do-Be co Unit 1 SYSTDi COMPONENT ATION WORKSHEET Index L..-/ 219H-005 Dockrt:

50-346 Rev.:

2 s

Date:

//

[3 Prepar6d bys 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 lPltnt ID No.

Pr2002 ll 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 ll l

l 1

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 S/N 319-2423l l l

l l

l Function:

Transmits ll Relative 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 Accuracy: Spect 1.0%

ll l

l l

l Demon: 0.94%

ll l

l l

l ll Chemical l

N/A l

None l

lStrvice: Containment ll Spray l

l l

l Pronure Input to SFAS ll l

l l

l Channel 3 and Indication ll l

l l

lLocItion: Auxiliary Bldg.ll l

l l

l nm, 500 llRadiaticn l 2. 0 x 10 RADS l 7.6 x 10 RADS l

'I l

v,hbh l Sequential Testl None l

2 7

l ll l

l 1

I l

l l

l Flood Level Elev N/A ll 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 Hot Shutdown lX l ll l

l l

l ll Submergence l N/A l

N/A l

None l

l Cold Shutdown lX l ll l

l l

l ll l

l l

(

)

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 O

CJ N

Facilitys~ c vio-Becco Unit 1 COMPONENT MATERIALS EVALUATION SHEET Docket 50-346 Index No.: 219H-005B Rev.:

2 Prepared by:

Dater //

Checked by: g#j Dater ///>[4 4

l Plant I.D. No.:

PT2002 Component:

Pressure Transmitter l

l Manufacturer:

Foxboro Model No.:

EllAH*

l l

THERMAL AGING l

RADIATION l

l l

Parts List l

Materials List l

Qualification l Reference l Qualification l Reference l l

l l

t I

i l Cover l Aluminum 214 l

40 Years l

AA l

N/A l

l Screws and Nuts l Steel l

40 Years l

AA l

N/A l

i l Washers l Steel l

40 Years l

AA l

N/A l

l Bate Assembly l Cast Iron l

40 Years l

AA l

N/A l

l Zaro Shaft l Steel l

40 Years l

AA l

N/A l

l Siseve l Steel l

40 Years l

AA l

N/A l

l Zaro Coupling Assembly l Steel l

40 Years l

AA l

N/A l

l Ritaining Rings l Steel l

40 Years l

AA l

N/A l

l Force Bar and Base l Steel l

40 Years l

AA l

N/A l

N/A' l

l Assembly l

l l

l N/A l

N/A l

l Junction Box l Cast Iron l

40 Years l

AA l

N/A l

l Coupling l Stainless Steel l

40 Years l

AA l

N/A l

l Brackets l Steel l

40 Years l

AA l

N/A l

l Flcxure Assemblies l Steel l

40 Years l

AA l

N/A l

l Columns l Steel l

40 Years l

AA l

N/A l

l Bare l Cast Iron l

40 Years l

AA l

N/A l

l Cover Plate Molding l Steel l

40 Years l

AA l

N/A l

l Terminal Block Assembly l Steel l

40 Years l

AA l

N/A l

I Detector Assembly l Steel l

40 Years l

AA l

N/A l

l Plates l Steel l

40 Years l

AA l

N/A l

l Level Assembly l Steel l

40 Years l

AA l

l l

1

O

>219 H-005C Facilityr \\oavic-Bessa Unit 1 COEPONENT MATER 1.

J EVALUATION SHEET Index sg Rev.:

2 Dock 2t 50-346 Prepared by:

Date

[/

Checked by:

2?_L 12-_

H Date MV.Qth l

Plant I.D. No.:

PT2002 Component :

Pressure Transmitter l

l Manuf acturer Foxboro Mode 1 No.

EllAH*

l I

l l

THERMAL AGING l

RADIATIGI l

l Parts List l

Materials List l

Qualification l Ref erence I Qualification l Reference l l

l l

1 1

I I

l ' Blocks l Steel l

40 Years l

AA l

N/A l

l Leve r l Steel l

40 Years l

AA l

N/A l

l Clup Spring l Steel l

40 Years l

AA l

N/A l

l Bushings l Steel l

40 Years l

AA l

N/A l

l Coil Assembly l Steel l

40 Years l

AA l

N/A l

l Zaro Screw Assembly l Steel l-40 Years l

AA l

N/A l

.l Spring Assemblies l

Steel l

40 Years l

AA l

N/A 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

l Lubricant-l Silicone Oil l

Not Affected l

AA l

N/A l

l Transmitter Anplifier l Solid State Electronics l

1.19 Years e 104*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 9 265'F l

CAL-74 l N/A l

N/A l

l Nylon Washer l Nylon (Polyamide) l 96 Years 0 120*F l

CAL-74 l N/A l

N/A l

l Cable l Nylon (Polyamide) l

% Years 9 120*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 Rrv (Silastic) l 40 Years e 302*F l

CAL-74 l N/A l

N/A 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 Tarminal Block l Phenolic l

40 Years 9 230*F l

CAL-74 l N/A l

N/A l

l Column l Phenolic l

40 Years @ 230*F l

CAL-74 l l

l l

I I

I 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).

j'^N ln

,m N)

\\

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

50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Prepared by:

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

Rev.:

Ch;cked by:

M ;% % f d [ Date:

2 g//N5 ll l EQUIPMENT DESCRIPTION l l_

l_

ENVIRONMENT l

l ll Parameter l Specification [

l l

DOCUMENTATION REF.

l Qualification lSpecificationl0ualificationil Qualification l Outstanding l ll l

lSystsm:

l Safety Features llOperating l

l l

Method i

Items l

l 1 Year i 1.19 Years Note 1 I

CAL-30 l

Analysis l

None l

Actuation llTime 1

l J-6 l

l l

l 1 l__

l l

l lPIsnt ID No.

PT2003 ll i

l V-16A i

l l

I llTemperaturel l

I 1

l I

l l Component:

Pressure ll

(*F) l N/A i

N/A l

Note 2 l

N/A I

N/A l

None l

l I

l l

l

_l Transmitter l l_.

1 l

I ll I

l l Manufacturer:

1 I

l I

l l

Foxboro llPressure i

N/A l

Note 2 l

N/A I

t l

I l

l l

l l Modal Number:

ll(PSIA) l l

l

_l l

EllAH l l_

1 l

l S/N 319-242411 l

l N/A l

None l

IFunction:

Transmits l

1 l

l 1

I 1

l ll Relative l

N/A l

Note 2 l

N/A l

None l

Pressure Signals ll Humidity l

I l

l

_l l

l l

11. (%)

I l

l lAccurney: Spec:

1.0%

ll l

l 1

l l

t Demon: 0.94%

ll l

I 1

l l

l 1

1 l

ll Chemical i

N/A l

N/A I

N/A l

None l

1 l

l' lSarvica: Containment I

l I

l flSpray I

l Pressure Input to SFAS I

ll i

l l

I l Chtnnel 4 and Indicationll_

1 l

l l

l ILocation: Auxiliary Bldg.ll I

l l

1 I

l l

l Rm. 426 l

I l

1 llRadiation l4.17 x 105 l

I l

I RADSl7.6 x 107 l

J-6 l

_I l l_

l RADS l T

l V-16A l

] Flood Level Elev:

N/A ll l

l IAbova Flood Level:

l I

ISequential Testl l

l None l

N/A IIAging l

40 Years l

1.19 Years l

I l

CAL-74 l

Analysis i

None i

l 1

I l

l ll l

l

' NM.dEd f or:

l l

l Note 4 l

l l l_

l Hot Shutdown 11l ll l

-l Note 3

)

l 1

l l

l llSubmergencel l

l l

Cold Shutdown 111 lI N/A l

N/A I

N/A l

None l

l l

_l l

l

_l l_

l l

-l I

l l

_l

- _ ~..

/

l Fccility d vis-Besca Unit 1 Docksta 50-346 SYSTDI COMPONENT EVALUATION WORKSHEET Index No.: 219H-0064 4

Prtpared by:

Re v. :

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

1.

One year operating time is used as a conservative maximum specificatio n.

2.

The only harsh environment seen is increased radiation due to recirculat d fl id t

e u

s.

j 3

Materials evaluation conducted.

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

ached evaluation.

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

}

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

of 1.19/0.54 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 common mode aging failurThe on and proper es predominate.

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:

Dates

//

O a

Ch;cked by: A&/JLs/

Dates e/////3 l

Plant I.D. No.:

PT2003 Component:

Pressure Transmitter l

Manufacturer:

Foxboro l

Model No.:

EllAH' l

l l

THERMAL AGING l

RADIATION l

l l

Parts List l

Materials List l

Qualification l Reference l Qualification l Reference l l

l l

l Cover l Aluminum 214 l

40 Years l

AA l

N/A l

l Screws and Nuts l Steel l

40 Years l

AA l

N/A l

l W:shers l Steel l

40 Years l

AA l

N/A l

l Base Assembly l Cast Iron l

40 Years l

AA l

N/A l

l Zaro Shaft l Steel l

40 Years l

AA l

N/A l

l Sleeve l Steel l

40 Years l

AA l

N/A l

l Zaro Coupling Assembly l Steel l

40 Years l

AA l

N/A l

l Rstaining Rings l Steel l

40 Years l

AA l

N/A l

l Force Bar and Base l Steel l

40 Years l

AA l

N/A l

l Acsembly l

l l

l N/A l

N/A l

l Junction Box l Cast Iron l

40 Years l

AA l

N/A l

l Coupling l Stainless Steel l

40 Years l

AA l

N/A l

l Breckets l Steel l

40 Years l

AA l

N/A l

l Flcxure Assemblies l Steel l

40 ears l

AA l

N/A l

l Columns l Steel l

40 Years l

AA l

N/A l

l Eaae l Cast Iron l

40 Years l

AA l

N/A l

l Cover Plate Molding l Steel l

40 Years l

AA l

N/A l

l Terminal Block Assembly l Steel l

40 Years l

AA l

N/A l

l Detector Assembly l Steel l

40 Years l

AA l

N/A l

l Plates l Steel l

40 Years l

AA l

N/A l

l Level Assembly l Steel l

40 Years l

AA l

l l

l

m Facilitys ke.vis-Be na Unit 1 CCMPONENT MATERIALS EVALUATION SHEET Dockst:

50-346 Index No.: 219H-00GC Re v. :

2 Prepared by:

Dater

(/ /

Checked by: 9 : & _ V Date:

I st/A'//1 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 Qualification l Reference l l

l l

I i

l t

l l Blocks l Steel l

40 Years l

AA l

N/A l

l l Leve r l Steel l

40 Years l

AA l

N/A l

l l Clcmp Spring l Steel l

40 Years l

AA l

N/A l

l Bushings l Steel l

40 Years l

AA l

N/A l

l Coil Assembly l

Steel l

40 Years l

AA l

N/A l

l Zaro Screw Assembly l Steel l

40 Years l

AA l

N/A l

l Spring Assemblies l Steel l

40 Years l

AA l

N/A l

l Tubing l Steel l

40 Years l

AA l

N/A l

l Clapps l Steel l

40 Years l

AA l

N/A l

l Lubricant l Silicone Oil l

Not Affected l

AA l

N/A l

l Transmitter Applifier l Solid State Electronics l

1.19 Years 0 104*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 e 265'F l

CAL-74 l N/A l

N/A l

l Nylon Washer l Nylon (Polyamide) l 96 Years 0 120*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 0 120*F l

CAL-74 l N/A l

N/A l

l Saaltnt l Silicone RTV (Silastic) l 40 Years 0 302*F l

CAL-74 l N/A l

N/A 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 0 122*F l

CAL-74 l N/A l

N/A l

l Torminal Block l Phenolic l

40 Ye'ars 0 230*F l

CAL-74 l N/A l

N/A l

l Column l

Phenolic l

40 Years @ 230*F l

CAL-74 l l

l l

l 1

I l

l l

Materials & Parts List

Reference:

AA

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

Note 1:

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

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

2 Date M

3 eparad by:

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

lant ID No.

PTRC2A3 ll 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

ll l

l I

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 S/N 266-0831ll l

l l

' unction:

Transmits ll Relative 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

i ccuracy: Spect 1.0%

ll 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

A l

V-16A l Simultaneous l None l

ervica RC Loop 2 HLG ll Spray 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 l

FAS Ch. 4 and Indication ll 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

' lood Level Elev: 572 '-2" 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 i Hot Shutdown lX l ll 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

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

- _ - _ _ _ _ _ _o O

O Ficility: MIvic-Be 03 Unit 1 COMPONENT MATERIALS EVALUATION SHEET Index N3.

219H-0078 Docket:

50-346 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

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 l

N/A l

l Screws and Nuts l Steel l

40 Years l

AA l

N/A l

l l Washers l Steel l

40 Years l

AA l

N/A l

)

l Bare Assembly l Cast Iron l

40 Years l

AA l

N/A l

l l Zero Shaft l Steel l

40 Years l

AA l

N/A l

l Sleeve l Steel l

40 Years l

AA l

N/A l

l Zaro Coupling Ascembly l Steel l

40 Years l

AA l

N/A l

l Rstaining Rings l Steel l

40 Years l

AA l

N/A l

l l

Force Bar and Base l Steel l

40 Years l

AA l

N/A l

l Assembly l

l l

l N/A l

N/A l

l Junction Box l Cast Iron l

40 Years l

AA l

N/A l

l Coupling l Stainless Steel l

40 Years l

AA l

N/A l

l Erackets l Steel l

40 Years l

AA l

N/A l

l Flexure Assemblies l Steel l

40 Years l

AA l

N/A l

l Columns l Steel l

40 Years l

AA l

N/A l

l Base l Cast Iron l

40 Years l

AA l

N/A l

l Cover Plate Molding l Steel l

40 Years l

AA l

N/A l

l Tarminal Block Assembly l Steel l

40 Years l

AA l

N/A l

l Detector Assembly l Steel l

40 ' rears l

AA l

N/A l

l Plates l Steel l

40 Years l

AA l

N/A l

l Level Assembly l Steel l

40 Years l

AA l

N/A l

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 Dater

//

N Prepared by:

Checked by:

M M s/

Dater

///.4//3 l

Plant I.D. No.:

PTRC2A3 Component Pressure Transmitter l

l Manufacturers Foxboro Model No.:

EllGH*

l 4

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 j

l Blocks l Steel l

40 Years l

AA l

N/A l

l Lever l Steel l

40 Years l

AA l

N/A l

)

l Clamp Spring l Steel l

40 Years l

AA l

N/A l

l Bushings l Steel j

40 Years l

AA l

N/A l

l Coil Assembly l Steel l

40 Years l

AA l

N/A l

l Z:sro Screw Assembly l Steel l

40 Years l

AA l

N/A l

l Spring Assemblies l Steel l

40 Years l

AA 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 l

Y /A l

l Lubricant l Silicone Oil l

Not Sensitive l

AA l

N/A l

l Transmitter Anplifier l Solid State Electronics l

0.54 Years @ 120*F l CAL-74 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

l Nylon Washer l Nylon (Polyamide) l 96 Years 9 120*F l CAL-74 l

N/A l

l Cable l Nylon (Polyamide) l 96 Years 0 120*F l

CAL-74 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

5 l Force Motor Assembly l Formvar Insulation l

40 Years 0 122*F l

CAL-74 l

N/A l

l Armature Assembly l Formvar Insulation l

40 Years @ 122'F l

CAL-74 l

N/A l

l Tarminal Block l

Phenolic l

40 Years @ 230*F l

CAL-74 l

N/A l

l Column l

Phenolic l

40 Years 9 230*F l

CAL-74 l

N/A l

4 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, junction box, and electronics.

t 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).

L)

Fccility: Davio-B:sse Unit 1 Dockst 50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Index No.: _219H-008 Prepared by: _

Dater [

d Rev.: _

2 Chseksd by: g h flM9 Dater /////A I

ll l EQUIPMENT DESCRIPTION ll_

ENVIRONMENT 1

l l

l ll Parameter l Specification l Qualification lSpecifiDOCUMENTATION REF.

l

~l l

l cationlQualificationll Qualification l Outstanding l ll l

ISystem:

l Safety Features ll Operating l 1 Year l

1.1 Years l

Note 2" l

Note 1 l Simultaneous l None l

i l

Method l

Items l

l J-10 l

Actuation ll Time l

l l

~l l

ll l

l l

V-16A l

Test l

1 l Plant ID No.

l PTRC2A4 ll 1

I l

l l

ll Temperature l l

l l

l Component:

Pressure ll

(*F) l 283.0 l

314.0 l

H, X l

J-10 l

l l

l Transmitter ll l

l Simultaneous l None l

l l

l V-164 l

Test l

l l

l Manufacturers ll l

l l

l Foxboro ll Pressure l

52.0 l

78.0 l

G, X

l J-10 l

l l

l lModel Number:

ll(PSIA) l l

l

~l E11GH ll l

l l Simultaneous l None l

l S/N 266-0832ll l

l V-16A l

Test l

l l

l l Function:

Transmits ll Relative l

100.0 l

A l

J-10 l Simultaneous l None l

l l

I l

Pressure Signals ll Humidity l

l l

~l ll (s) l l

l V-16A l

Test l

lAccursey: Specs 1.0%

ll l

l l

Demon: 0.94%

ll l Boric Acid l Boric Acid l

l J-10 l

l l

~l ll Chemical l

1800 ppm l

A l

V-16A l Simultaneous l None l

llSarvicer RC Loop 2 HLG ll Spray l

pH 5.0 l

l CAL-40 l

Test, l

l llWida Range Pressure for l

l ll llSFAS Ch. 2 and Indication ll l

l l

Note 3 l

Analysis l

LOLocation: Containment ll l

l l

l O

Rm 410 l

9 ll Radiation l4.60 x 106 l

l J-5 l

l l

~l RADS l1.0 x 107

)Plood Level Elev ll_

l RADS l AP l

V-16A l Sequential Test l l

572'-2"ll l

l l

}Abova Flood Level None l

l Yes ll Aging l

40 Years l

0.54 Years l

I l

CAL-74 l

Analysis l

None l

l l

l

}

ll l

l 1

l l

Nasdad fors l

Note 5 l

ll l

Hot Shutdown lYl ll l

l l

Note 4 l

l

~

l l l Submergence l 572' - 2" l

606' - 0" l

B l

J-ll l

N/A l

None l

l l

l Cold Shutdown lYl ll l

l l

~l

~

ll 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:

h Date:

Nl

.7

hecksd bys M&&f Date

///aff)

L.

According to Profiles G and H, containment conditions will return to ambient within seven days and remain there for the l

duration of the accident and ensuing cooldown.

At the completion of the 30-day LOCA simulation test, test conditions had rsturned to 150'F, 5 psig.

This test exposed the transmitter to an overall more severe environment than that which would razult 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.

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 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 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.

N/

\\

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

Index No.: _219H-008B i

Date:

Ch:cked byr M e O f Date: _

)

Rev.

<//s//5 2

l Plant I.D. No.:

l PTRC2A4 Manufacturer Components l

Foxboro Pressure Transmitter i

Model No.:

l l

EllGH*

l l

l l_

Parts List l

_ l THERMAL AGING l

Materials List l

l Qualification RADIATION l Cover l

Qualification

_l l Aluminum 214 t

l Reference l l Screws and Nuts l

l l Reference l l

40 Years l Steel l Wachers l

AA l

1

^l l Steel l

40 Years l Base Assembly N/A l

AA l

l N/A l

l Cast Iron l

40 Years l Zero Shaft N/A l

AA l

l N/A l

l 40 Years l Steel l Sleeve N/A l

AA l

l N/A l

l 40 Years I l l Steel N/A Zaro Coupling Assembly l Steel l

40 Years l

AA l

l N/A l

l Rstaining Rings N/A l

AA l

l N/A l

l 40 Years l Steel l Force Bar and Base N/A l

AA l

l N/A l

l Steel l

40 Years l

Anzembly N/A l

AA l

l N/A l

l l

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

l AA l

l N/A l

l Coupling l

N/A l

40 Years l

l N/A l

2 rackets l Stainless Steel

$ ll N/A l

AA l

l N/A l

l Steel l

40 Years N/A Flexure Assemblies l

AA l

l N/A l

l Steel l

40 Years

} ll N/A Columns l

AA l

l N/A l

Easo l Steel l

40 Years N/A l

AA l

l N/A l

l Cast Iron l

40 Years

,l N/A Cover Plate Molding l Steel l

AA l

l N/A l

j 40 Years l

N/A Tarminal Block Assembly l l

40 Years l

AA l

l N/A l

l Steel D0tector Assembly N/A l

AA l

l N/A l

l Steel l

40 Years Plates k ll N/A l

AA l

l N/A l

l 40 Years l Steel Leval Assembly N/A l

AA l

l N/A l

l Steel l

40 Years k l_

N/A l

AA l

l N/A l

I l

40 Years N/A l

l AA l

l N/A l

N/A l

l l

N/A l

l l

1

3 o

O Fccilitys ^Cavis-BeOS2 Unit 1 Docket:

50-346 COMPONENT MATERIALS EVALUATION SHEET Prepared by:

Index No.: 219H-008C Date: _N Rev.:

2

~

I Checked by:,Mo/A #

Dates p/2/6 l

Plant I.D. No.:

PTRC2A4 l

Manufacturer:

Components 1

Foxboro Pressure Transmitter Model No.:

l 1

l EllGH*

l l

}

l_

Parts List l

l THERMAL AGING l

l 3

l Materials List l

Qualification l Reference l Qualification RADIATION I

l i

l Blocks l Steel l

l Lever l

40 Years l-l l Reference l l Steel l

AA l

N/A l

l Clamp Spring l Steel l

l l

40 Years l

AA l

N/A l

N/A

l l Bushings I Steel l

40 Years l Coil Assembly l Steel l

AA l

l 40 Years l

AA l

l N/A l

N/A 1 l Z3ro Screw Assembly l Steel l

40 Years N/A l

N/A l

i l Spring Assemblies l Steel l

AA l

N/A l

40 Years l

AA l

l N/A l

i l Tubing l

40 Years l Steel N/A l

N/A l

)l Clamps l

40 Years l

AA l

N/A l

l Steel l

AA l

N/A l

l l Lubricant l

40 Years l Silicone Oil l Transmitter Amplifier l

l Not Sensitive l

AA l

N/A l

l AA l

N/A l

i l Assembly Solid State Electronics l

0.54 Years 9 120'F l l

,l O-Rings l Viton l

CAL-74 l

N/A l

(l Nylon Washer l

40 Years 9 265'F l CAL-74 l

l N/A l

l l

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

N/A l

! l Cable N/A l

N/A l

l Nylon (Polyamide) l 96 Years 9 120'F l CAL-74 l

l Insulator l Nylon (Polyamide) l 96 Years 9 120'F l CAL-74 l

N/A l

l l Sealant l Silicone RTV (Silastic) l 40 Years 9 302*F l CAL-74 l

N/A l

l Force Motor Assembly l Formvar Insulation l

40 Years 9 122*F l CAL-74 l

N/A l

?

l Armature Assembly l

ll Tarminal Block Formvar Insulation l

40 Years 9 122'r l CAL-74 l

N/A l

l Phenolic

l Column l

40 Years 9 230'F l CAL-74 l

N/A

, l__

l Phenolic l

l 40 Years 9 230'F l CAL-74 l

l N/A l

l l

N/A l

i

, Materials & Parts List

Reference:

AA l

l

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

M transmitters because these transmitters have identi cal topworks, Note l:

{

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

er amplifier assembly is the most limiting component f m

or the rma l

o

)

O Ficility: LJic-Bessa Unit 1 SYSTDI COMPONENT EVALUATION WORKSHEET Dockst 50-346 Index No.: 219H-009 Rev.:

2 Prepared by:

Date

/

2 Checkad by: gg)d/

Date: ar/J//7 l

ll l

l l

l l EQUIPMENT DESCRIPTION ll_

ENVIRONMENT U

DOCUMENTATION REF.

l Qualification l Outstanding l l

ll Parameter l Specification l Qualification SpecificationlQualificationi Method l

Items l

. l ll l

l 1

l J-10 l

l l

lSyctem: Safety Features ll Operating l 1 Year l

1.1 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 3

' l ll l

l l

1 l

l l Plant ID No.

PTRC2B3 ll l

l l

)

l

! l ll Temperature l 283.0 l

314.0 l

H, X

l J-10 l Simultaneous l None l

l Components Pressure ll

(*F) l l

l l

V-16A l

Test l

l I l Transmitter ll l

l l

I l

l l

l ll l

l t

i l

l

_i 1

l Manufacturers Foxboro ll Pressure l

52.0 l

78.0 l

G, X

l J-10 l Simultaneous l None l

l ll(PSIA) l l

l l

V-16A l

Test l

l l Modal Number:

E11GH ll l

l l

S/N 266-0832ll l

l l

lFunctic't Transmits ll Relative l

100.0 l

A l

J-10 l Simultaneous l None l

~

l Pressure Signals ll Humidity l

l l

l V-16A l

Test l

l l

ll (s) l l

l l

l l Accuracy: Spec:

1.0%

ll l

l l

l Demon: 0.94%

ll l Boric Acid l Boric Acid l

l J-10 l

l l

l ll Chemical l

1800 ppm l

A l

V-16A l Simultaneous l None l

lSarvicer RC Loop 1 HLG ll Spray l

pH 5.0 l

l CAL-40 l

Test, l

l l llWida Range Pressure for ll l

l l

l Note 3 l

Analysis l

l SFAS Ch. 3 and Indication ll l

l l

l I l Location: Containment ll l

l l

)

J-5 l

l l

l Rm. 407 l l Radiation l5.44 x 106 RADS l1.0 x 107 RADS l AF l

V-16A l Sequential Testl None l

l ll l

l l

l

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

l l

l j lAbova Flood Level: Yes ll Aging l

40 Years l

0.54 Years l

I l

CAL-74 l

Analysis l

None l

ll ll l

l Note 5 l

l Note 4 l

l l

lNacded for

ll l

I l

l l

l

{l Hot Shutdown lX l ll l

l l

]l l lSubmergencel 572' - 2" l

606' - 0" l

B l

J-ll l

N/A l

None l

l Cold Shutdown lX l ll l

l l

l ll l

l l

i

a Facility: L ds-Bezca Unit 1 SYSTEM COMPONENT w,1UATION WORKSHEET Index L as 219H-009A L

Dockat:

50-346 Rev.:

2 i

l NOTES g8"J N fl b l

Prsparsd by:

Dates j Checksd by:

,M W Dates ///J//7 5

E t

F 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.

t 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.

l 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 COMPONENT MATERIALS EVALUATION SHEET Docket:

50-346 Index No.: 219H-009B Rev.:

2 Prepared by:

N If /!f2 Date Checked by gh Date

///J//7 l

Plant I.D. No.:

PTRC2B3 Component:

Pressure Transmitter l

l Manufacturers Foxboro Model No.:

EllGH*

l l

THERMAL AGING l

RADIATION l

l Parts List l

Materials List l

Qualification l Referer,ce l Qualification l Reference l l

l 1

1 I

i l

l Cover l Aluminum 214 l

40 Years l

AA l

N/A l

l Screws and Nuts l Steel l

40 Years l

AA l

N/A l

l wxhers l Steel l

40 Years l

AA l

N/A l

l Bre Assembly l Cast Iron l

40 Years l

AA l

N/A l

l Zaro Shaf t l Steel l

40 Years l

AA l

N/A l

l Siceve l Steel l

40 Years l

AA l

N/A l

l Zaro Coupling Assembly l Steel l

40 Years l

AA l

N/A l

l R;taining Rings l Steel l

40 Years l

AA l

N/A l

l Force Bar and Base l Steel l

40 Years l

AA l

N/A l

l Assembly l

l l

l N/A l

N/A l

l Junction Box l Cast Iron l

40 Years l

AA l

N/A l

l Coupling l Stainless Steel l

40 Years l

AA l

N/A l

N/A l Crackets l Steel l

40 Years l

AA l

N/A l

l Flcxure Assemblies l Steel l

40 Years l

AA l

N/A l

l Columns l Steel l

40 Years l

AA l

N/A l

l Bare l Cast Iron l

40 Years l

AA l

N/A l

l Cover Plate Molding l Steel l

40 Years l

AA l

N/A l

l Tanninal Block Assembly l Steel l

40 Years l

AA l

N/A l

l Detector Assembl;'

l Steel l

40 Years l

AA l

N/A l

l Plettes l Steel l

40 Years l

AA l

N/A l

l Level Assembly l Steel l

40 Years l

AA l

N/A l

l l

l

q f

Fccilityi-Uavic-Becco Unit 1 1

Docket:

50-346 COMPONENT MATERIALS EVALUATION SHEET Index No.: 2198-009C f

mev. :

2 Prepared by: _h Dates b

Checked by:

M _s Dater ///J/r3 i

l Plant I.D. No.:

PTRC283 Components Pressure Transmitter l

l Nanufacturers Foxboro l

1 Model No.:

I EllGH*

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 Blocks l Steel l

40 Years l

AA l

N/A l

l Lever l Steel l

40 Years l

AA l

N/A l

l Clamp Spring l Steel l

40 Years l

AA l

N/A l

l Euzhings l Steel i

}

l Coil Assembly l Steel l

40 Years l

AA l

N/A l

{

l 4D Years l

AA l

N/A l

)

l Zaro Screw Assembly l Steel l

49 Years l

AA l

N/A l

j l Spring Assemblies l Steel l

40 Years l

AA l

N/A l

i l Tubing l Steel l

40 Years l

AA l

, N/A l

N/A l

}

l Clamps l Steel l

40 Years l

AA l

l N/A l

N/A l

fl Lubricant l Silicone Oil l

Not Sensitive l

AA l

' N/A l

N/A l

l Transmitter Amplifier l Solid State Electronics l

0.54 Years 9 120*F l CAL-74 l

N/A l

l Assembly l

l

)

! O-Rings l Viton l

l N/A l

N/A l

l 40 Years 9 265*F l CAL-74 l

N/A l

{

l Nylon Nasher l Nylon (Polyamide) l 96 Years 9 120*F l CAL-74 l

N/A l

l l Ccble l Nylon (Polyamide) l 96 Years 9 120*F l CAL-74 l

N/A l

l Insulator l Nylon (Polyamide) l 96 Years 9 120*F l CAL-74 l

N/A l

i l Saalant l Silicone RTV (Silastic) l 40 Years 9 302*F l CAL-74 l

N/A l

{ ll Force Notor Assembly l Formvar Insulation l

40 Years 9 122*F l CAL-74 l

N/A l

[

i Armature Assembly l Formvar Insulation l

40 Years 9 122*F l CAL-74 l

N/A l

!l Tarminal Block l

Phenolic l

40 Years 9 230*F l CAL-74 l

N/A N/A l

I i l Column l Phenolic l

40 Years 9 230*F l CAL-74 l

N/A l

1 l_

l 1

1 I

l l

Materials & Parts List

Reference:

AA 3

}

The EllGH materials list is applicable to the EllAH and EllGM transmitters because these tr I

)

junction box, and electronics.

ansmitters have identical topworks, i

Note 1:

Conservative value based on the fact that the transmitter amplifier assembly is the most limiting com j

aging (see Reference AA, CAL-38).

ponent for thermal 1

t Facility: b 12-Becco Unit 1 Dockst:

50-346 SYSTDI COMPONENF EVALUATION NORKSHEET Index No.: 219H-010

Prepared by

NM id</P1 Rev. :

2 Dates

Check: d by cMJ/

Date: es/A/PJ I l ll l l EQUIPMENT DESCRIPTION ll ENVIRONMElff l

l l

l t

l

{l_

ll Parameter l Specification l Qualification l Specification l Qualification ll Qualification l Outstandi I

DOCUMENTATION REF.

l l

_ll l

l l

l J-10 l

{

l

[

ISyctems Safety Features ll Operating l 1 Year l

1.1 Years l

Note 2 l

Note 1 l Simultaneous l Mone l

Method 1

Items l

l l Actuation ll Time 1

l l

l V-16A l

Test l

l

[

I il l

l l

l Plant ID No.

PTRC254 ll l

l l

l 2

j i llTemperaturel 283.0 l

314.0 l

H, X l

J-10 l Simultaneous l Mone l

j l Components Pressure ll

(*F) l l

l l

V-16A l

Test l

l I l Transmitter ll l

l l

l I

l l

i l 11 I

I I

l 1

l l

i l Manufacturers Foxboro ll Pressure l

52.0 l

78.0 l

G, X

l J-10 l Simultaneous l Mone l

j l ll(PSIA) l l

l l

V-164 I

Test l

l

{ lNodel Number EllGH ll l

l l

! l S/N 266-0834ll l

l l

l

[

l

_l IFunction:

Transmits ll Relative l

100.0 l

A l

J-10 l Simultaneous l Mone l

l l

l

{l Pressure Signals ll Humidity l

l

\\

l V-16A I

Test l

l

>l ll (t) l l

l l

l 1

l ll Accuracy: Spec 1.Os ll 1

I I

I l

l t

!l Demon: 0.94%

ll l Boric Acid l Boric Acid l

l J-10 l

l l

l llChemical l

1800 ppm l

A l

V-16A l Simultaneous l None l

jlSarvics: RC Loop 1 HLG ll Spray l

pH 5.0 l

pH 5. 0" l

l CAL-40 l

Test, I

l

[

1lNida Range Pressure for ll l

l Note 3 l

Analysis l

l lSFAS Ch. I and Indication ll l

l l

l Location: Containment ll l

l l

l J-5 l

l l

l Rm. 407 l l Radiation l4.89 x 106 t

RADS l1.0 x 107 l

RADS l AF l

V-16A l Sequential Test l None l

11 I

l l

l 1

l l

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

l l

{

e

)lAboveFloodLevel Yes ll Aging l

40 Years l

0.54 Years l

I l

CAL-74 l

Analysis l

Mone l

i jl l1 l

l Note 5 l

l Note 4 l

l l

IlNeeded fors ll l

l l

i l Hot Shutdown lXl ll l

l l

l l lSubmergencel 572' - 2" l

606' - 0" l

B l

J-11 l

N/A l

None l

l Cold shutdown lX l ll l

l l

l l!

l l

l 1

l l

l 1

l l

r

t N

Fccility: L vis-Becco Unit 1 Dockst:

50-346 SYSTDI COMPONENT EVALUATION WORKSHEET Index No.

_219H-010h Prcpared by: _b Rev.:

2 Dates.

I Checkzd bya hod Dates ///A//w r

l i

j 1.

According to Profiles G and H, containment conditions will retur duration of the accident and ensuing cooldown. At the completion of the 30-day LOCA simulation test,n to ambien rsturned to 150*F, 5 psig.

This test exposed the transmitter to an overall more severe envir test conditions had rasult from the postulated loss of coolant accident.

concluded that the transmitter will maintain functional operability during thSince the transmitter remained opera j

ler.g-term cooldown at ambient conditions.

e short-term accident environment and the

, it can be

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.

Materials sensitive to radiation and/or thermal aging summarised

)

5 Materials and/or components sensitive to thermal aging will be repl on attached evaluation.

assure that associated component will maintain functional operability in harsh enviraced as per maintenance and replace i

onments.

Th2 limiting material is the transmitter amplifier which has an aging lif L

(Reference CAL-74).

longer qualified life.However, there is operating experience at Davis-Besse Unit 1 and in e of 1.19/0.54 years at 104*F/120*F, respectively other nuclear plants to support a Although the 1.19/0.54 a longer life is justified. year qualified life is the best analyticelly

}

surveillance frequencies will be adjusted to ensure that no common mode aging failThe sur i

I egradation and proper ures predominate.

i 1

i l

i I

t i

i 1

l 4

1 i

4

(v3 n

4

\\

J Fccilithi Davic-Berta Unit 1 Docket:

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

Dates j /!82 Rev.:

2 Chsched by:

./WCW Dates

~

///>//)

l

' Plant I.D. No.:

PTRC2B4 l

Components Manufacturers Pressures Transmitter Foxboro 1

Model No.:

l EllGH*

l l_

l l

l i

THERMAL AGING l

l_

Parts List l

Materials List l

Qualification l Referenca l RADIATION 1

l l

Cover l

Qualification l Reference l l Aluminum 214 l

1 l Screws and Nuts l Steel l

40 Years l

AA l

N/A l

I l

l Washers l

40 Years l

AA l

N/A l

l Steel l Btse Assembly l Cast Iron l

40 Years l

AA l

N/A l

l Zaro Shaft l

40 Years l

AA l

N/A l

I l Steel l Sleeve l

40 Years l

AA l

N/A l

1 l Steel l Zero Coupling Assembly l Steel l

40 Years l

AA l

N/A l

l Rztaining Rings l Steel l

40 Years l

AA l

N/A l

l Force Bar and Base l Steel l

40 Years l

AA l

N/A l

l Assembly l

l 40 Years l

AA l

N/A l

l Junction Box l Cast Iron l

l N/A l

N/A l

l l Coupling l Stainless Steel l

40 Years l

AA l

N/A l

l 40 Years l

AA l

N/A l

l Brackets l Steel Fl'xure Assemt!

l Steel l

e l

40 Years l

AA l

N/A l

l Columns l

40 Years l

AA l

N/A l

l Steel l Base l

40 Years l

AA l

N/A l

j Cast Iron l Cavar Plate Molding l Steel l

40 Years l

AA l

N/A l

l Tarminal Block Assembly l l

40 Years l

AA l

N/A l

Steel l

Detector Assembly l Steel l

40 Years l

AA l

N/A l

l Plates l

40 Years l

AA l

N/A l

l Steel l Level Assembly l Steel l

40 Years l

AA l

N/A l

l l

l 40 Years l

AA l

N/A l

l l

1 l

l

_ _ _. _ _ _ - - ~

a

Fccilityt % 2vis-Cosza Unit 1 COMPONENT MATERIALS EVALUATION SHEET Docket 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

THERMAL AGING l

RADIATION l

]

Parts List l

Materials List l

Qualification l Reference l Qualification l

l l

I l

Reference l l Blocks l Steel l

40 Years.

l AA l

N/A l

l Lever l Steel l

40 Years l

AA l

N/A l

l Clamp Spring l Steel l

40 Years l

AA l

N/A l

l Bushings l Steel l

40 Years l

AA l

N/A l

l Coil Assembly l Steel l

40 Years

]

AA l

N/A l

l Zsro Screw Assembly l Steel l

40 Years l

AA l

N/A l

l Spring Assemblies l Steel l

40 Years l

AA l

N/A l

N/A j

l Tubing l Steel l

40 Years l

AA l

N/A l

l Clamps l Steel l

40 Years l

AA l

N/A l

l Lubricant l Silicone Oil l

Not Sensitive l

AA l

N/A l

l Transmitter Amplifier l Solid State Electronics l

0.54 Years 9 120*F l CAL-74 l

N/A l

l Assembly l

l l

l N/A l

N/A l

l O-Rings l Viton

]

40 Years e 265'F l CAL-74 l

N/A l

l Nylon Washer l Nylon (Polyamide) l 96 Years @ 120*F l CAL-74 l

N/A l

l Cable l Nylon (Polyamide) l 96 Years 0120'F l

CAL-74 l

H,'A l

N/A l

l Insulator l Nylon (Polyamide) l 96 Years 0 120*F l CAL-74 l

N/A l

l Stalant l Silicone RTV (Silastic) l 40 Years e 302*F l CAL-74 l

N/A l

l Force Motor Assembly l Formvar Insulation l

40 Years @ 122'F l

CAL-74 l

N/A l

N/A

]

l Armature Assembly l Formvar Insulation l

40 Years @ 122'F l CAL-74 l

N/A l

l Terminal Block l

Phenolic l

40 Years 0 230*F l CAL-74 l

N/A l

l Column l

Phenolic l

40 Years @ 230'F l

CAL-74 l

N/A l

l l

1 l

l Msterials & Parts List

Reference:

AA

The E11GH materials list is applicable to the EllAH and EllGM transmitters because these transmitters have identical topworks, junction box, and electronics.

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 G

G O

Facilitys vic-Becca Unit 1 Doc ket :

50-346 SYSTEM COMPONENT EVALUATION WORKSHEET Index No. : ~219H-011 Rev.:

Prapared by:

Tj M Date:

9/28/N 0

Chec ked by :

D Date:

9,/2T,fff--

y l

ll l EQUIPMENT DESCRIPTION ll 1

I i

l l

ENVIRONMElfr l

DOCUMENTATION REF.

l Qualification l Outstanding l ll Parameter i Specification l Qualification ISpecification l Qualification l l

_ll l

l l

l l 1 Met hod l

Items l

lSyctem: Safety Features ll Operating l 26 Hours l

N/A l

F l

Note 3 l

N/A l

None l I l

Actuation l l Time l

l l

l ll I

I l

l l

lPlcnt ID No.

FI2004 ll l

l l

l l Temperature l 109.0 l

Ecempt l C-Annulus l Note 1 l

N/A l

None l

l Component:

Radiation ll

(*F) l l

l l

l l.

Detector ll l

l l

l ll l

l l

l Manufacturer Victoreen ll Pressure l

15 32 l

Exempt l C-Annulus l

Note 1 l

N/A l

None l

l ll(PSIA) l l

l l

l l Modal Number:

84 5 ll l

l l

l ll 1

l l

1 I

l l

l Function: Radiation iIRelative l

100.0 l

Exempt l

A l

Note 1 l

N/A l

None l

l Detection ll Humidity l

l l

l ll n) l l

l l

l I

l l Accuracy: Spec:

N/A ll l

I l

l l

l Demon: N/A ll l

l l

l l l Chemical l

N/A I

N/A l

None l

l Service: Input to SFAS l l Spray l

l l

l ll l

l l

l ll l

l l

l 1

l l

lIccr.tlon: Annulus ll l

l l

l

~l l

El. 585' l l Radiation l1.7 x 107 l

RADS l Exempt l

CAL-44 l

Note 2 l

N/A l

None I

ll l

l l

1 l

l Flood Level Eley:

N/A ll l

l l

lAbova Flood Level: N/A ll Aging I

40 Years l

N/A l

I l

Note 3 i

N/A l

None l

.I ll 1

l l

lNeedId for ll l

l l

l Hot Shutdown lXl ll l

l l

l l-l l

0 l lSubmergenc e l N/A l

N/A l

None l

0 Cold Shutdown l l

ll l

l l

0 ll.

l l

l

n f

Fac ility:

c-Becco Unit 1 SYSTDt COMPONE LUATION WORKSHEET Index 21CH-011A Rev. :

O Doc ket :

50-346 Prepared by:

,((

Date

7/28/d/

Check;d by:

gf M Date: 9/2f/g /

a p

This radiation detector provides an input into the safety features actuation system. The only safety-related furetion j

1.

performed by this detector is the initiation of the SFAS upon measuring high radiation levels resulting from a fueling l

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 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 Initiation of the emergency ventilation system (EVS).

a.

b.

Closure of ECCS Room Isolation Dampers.

Closure of the containment air sample isolation valves.

l c.

j d.

Closure of the Containment and Penetration Room purge isolation valves.

l Stops Control Room normal HVAC units.

e.

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 Closure of the ECCS Room's isolation dampers is of little corcern because the equipment located in these rooms that Rooms.

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-This radiation detector is exempt from qualification because its main furetion is to monitor containment radiation levels 2.

The detectors, which are located in the annulus, are moved inside the containment during re-fueling during re-fueling.

They will initiate the safety features actuation system upon sensing high radiation levels that may result f rom ope rations.

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 O

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

50-346 SYSTEM COMPONENT t. VALUATION NORKSHEET 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

DOCUMENTATION REF.

ll Parameter l Specification l Qualification ISpec ific ation l Qualific ation l Method l

Items l

l Qualification l Outstanding l l

ll l

l l System: Safety Features ll Operating l 26 Hours l

N/A l

F l

Note 3 l

N/A l

None l

1 l

l l

Actuation ll Time l

l l

l ll-l l

l l

l lPlent ID No.

RE2005 ll l

l l

l l l Temperature l 109.0 l

Exempt l C-Annulus l Note 1 l

N/A l

None l

l Component:

Radiation ll

(*F) l l

l l

Detector ll l

l l

ll l

l l

l Manufacturer: Victoreen ll Pressure l

15.32 l

Exempt l C-Annulus l

Note 1 l

N/A l

None l

l ll(PSIA) l l

l l

l l Modal Number:

84 5 ll l

l l

l ll l

l 1

l l

1 l

lFuretion: Radiation ll Relative l

100.0 l

Exempt l

A l

Note 1 l

N/A l

None l

l Detection ll Humidity l

l l

l ll (s) l l

l l

l l l Accuracy: Spect N/A ll l

l l

' l Demon: N/A ll l

l l

!l ll Chemical l

N/A l

None l

l Service: Input to SFAS ll Spray l

l l

ll l

l l

l ll l

l l

lIocction: Annulus ll l

l l

l El. 585' ll Radiation 11.7 x 107 RADS l Exempt l

CAL-44 l

Note 2 l

N/A l

None l

l ll l

l l

l Flood Level Elev N/A ll l

l l

lAbova Flood Ievel: N/A ll Aging l

40 Years l

N/A l

I l

Note 3 l

N/A l

Hone l

l ll l

l l

lNerdId fors ll l

l l

l l Hot Shutdown lX l ll l

l l

l l Submergence l N/A l

N/A l

None l

l Cold Shutdown l l

ll l

l l

l ll 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 NE.O[Sf Prepa red by :

[

Dates 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

Indrx NQ,)19H-013

acility: D,au-Becse Unit 1 SYSTEM COMPONENT J ATION NORKSHEET.

2 Rev.:

0 Nx:ket :

50-346 m Date:

NM8)

Yepsr:d by: )

Y[

t 3mcked by:

~

47 ~)Afossf/ Date: f/Jf79/

e i

7 lI l

l l

l EQUIPMENT DESCRIPTION ll ENVIRONMENT l

DOCUMENTATION REF.

l Qualification 1 Outstanding l ll Parameter l Specification l Qualification Specification Qualif icathionl Method Items l

I ll l

I I

i l

System Safety Features ll Operating l 26 Hours l

N/A l

P l

Note 3 l

N/A l

Mone l

Actuation ll Time l

l l

ll l

l l

P1ent ID No.

RE2006 ll l

l l

ll Temperature l 109.0 l

Exempt l C-Annulus l Note 1 l

N/A

'l None l

Component:

Radiation ll

(*F) l l

l l

l Detector ll l

l l

l ll l

l l

l Manuf acturer: Victoreen ll Pressure l

15.32 l

Exempt l C-Annulus l Note 1 l

N/A l

Hone l

l ll(PSIA) l l

l l

Modal Ntamber:

845 II l

l l

ll l

l l

1

)

i Function: Radiation lIRelative I

100.0 l

Exempt I

A l

Note 1 l

N/A l

None l

Detection lIHumidity l

l l

ll (s )

l l

l Accuracy: Spec N/A ll l

l l

Demon: N/A ll l

l l

)

ll Chemical l

N/A l

None l

Servics: Input to SFAS ll Spray l

l l

r ll l

l l

ll l

l l

Ieccticn: Annulus ll l

l l

El. 585' ll Radiation i1.7 x 107 RADS l Exempt l

CAL-44 l

Note 2 l

N/A l

None l

ll l

l l

l I

I l

Flood Level Elev:

N/A ll l

l l

l

~

l l

l Abova Flood Level: N/A llAging l

40 Years l

N/A I

I l

Note 3 l

N/A l

None l

ll l

l l

Need:d for:

ll l

l l

I l

l Hot Shutdown lX l ll l

l l

l l l Suhnergencel N/A I

N/A I

N/A l

N/A I

None l

l Cold Shutdown l l

ll l

l l

1 ll l

l l

I I

l l

f Facility: (jc-Berse Unit 1 SYSTDI COMPONE UATION WORKSHEET Index\\

219H-013A Dec ket :

50-30 Rev.:

0 1

cb Date: _9/16[81 Prcpared by:

__ M 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 SYSTEM COMPONENT EVALUATIC1 WORKSHEET Doc ket :

50-346 Index No.: _219H-013B Rev.:

0 NOTES Prepared by:

o7 Date: _ f[26/fl chec ked by a f.

Dete:

9%f/f)

During normal plant operations, these SFAS detectors will also initiate the safety featur high radiation.

In the event of a loss of coolant ac ident,

es actuation system upon sensing j

signal or a high containment vessel pressure signal.

SFAS will be initiated by either a low reactor coolant pressure These, signals will initiate SFAS before initiation would occur due to high radiation levels. Because of this, failure of the 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 conta n

3.

Since these components are not required to operate during the postulated accidents qualification 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 f[Eh8I Date s 2

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 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 ll l

l 1

I l

l l

lPlcnt ID No.

RE2007 ll 1

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

Detector ll 1

l l

l ll 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 Mod 21 Number:

84 5 ll l

l l

ll 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 ll (s) l l

l I

l l Accuracy: Spec t N/A ll l

l l

l Demon: N/A ll l

l l

l l l Chemical l

N/A l

None l

l Service: Input to SFAS ll Spray l

l l

I ll l

l l

l ll l

l l

lIocction: Annulus ll 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 Flood Level Elev:

N/A ll 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

lNe: dad for ll l

l l

l Hot Shutdown lX l ll l

l l

l l lSubmergerx:e l N/A l

N/A l

None l

l Cold Shutdown l l

ll l

l l

l ll l

l l

(

p Index/

I

\\

( j'219H-014A Fac ility

'bs ic-Becse Unit 1 SYSTEM COMPONE UATION WORKSHEET Doc ket :

50-346 Rev.

O Prepared by:

7 Y M Date:

9M9/8 /

Chec ked by :

u H W. M Date

_-,/2f/f/

9 y.

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

.

ML20083A422

Contents

Text

References:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Navigation menu

Rev 2 to Procedure 1040-001-022, Safety Features Actuation Sys
Person / Time
ML20083A422
Site:	Davis Besse
Issue date:	11/02/1983
From:	TOLEDO EDISON CO.
To:
Shared Package
ML17150A231	List: ML17150A230 ML20083A206 ML20083A216 ML20083A222 ML20083A234 ML20083A237 ML20083A244 ML20083A252 ML20083A264 ML20083A269 ML20083A278 ML20083A283 ML20083A294 ML20083A298 ML20083A315 ML20083A322 ML20083A336 ML20083A365 ML20083A376 ML20083A396 ML20083A415 ML20083A422 ML20083A439 ML20083A454 ML20083A473 ML20083A486 ML20083A500
References
1040-001-022, 1040-1-22, IEB-79-01B, IEB-79-1B, NUDOCS 8312200283
Download: ML20083A422 (44)
v • d • e

ML20083A422

Text

References:

Reference:

Reference:

Reference:

Reference:

Reference:

Reference:

Navigation menu

Search