ML17209A842

Forwards Update to 800806 Response to Suppl 3 of IE Bulletin 79-01B, Environ Qualification of Class IE Equipment. Info Completes Response.New & Revised Component Evaluation Sheets & Master List Pages Encl

ML17209A842
Person / Time
Site:	Saint Lucie
Issue date:	02/06/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-79-01B, L-81-42, NUDOCS 8103230274
Download: ML17209A842 (42)

Text

vI p."g l(

p(i FLORIDA POWER 8 LIGHTCOMPANY February 6, 1981 Mr. James P. O'Reilly, Director, Region-II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Rei lly:

Re:

RII:

-335 u letin'79-01B (Supplement 3) gpss/p@'8(~

e Enclosed as attachments to this letter are new and revised Component Evaluation Sheets, Master List pages, and attachments which supplement FPL's response to NRC IE Bulletin 79-01B, (FPL letter L-80-259) dated August 6, 1980., Master List pages 1-16, 1-17, 12-3, and 12-3A, Components Evaluation sheets

12M13, 12M14,

12M15, 12M16, lI17, 1I18, 1I19, lI20, lI21, lI22, 1I33, lI37, 1I55, lI56, lI57, and E9, and Attachment III (2 sheets) are applicable to installed and operating equipment required as a result of TMI and complete our response to Supplement No.

3 of the Bulletin.

Component Evaluation Sheets 15I1, 15I2, 17M10, and E-12 have been revised to correct errors in our original response.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems 8 Technology REU/PLP/mrs Attachments cc:

Director, Office of Inspection and Enforcement Harold Reis, Esquire SX03230>>'t PEOPLE... SERVING PEOPLE

h

'J F ~

'4 II

'I C

FLORIOA POWER Il LIGHT COMPANY INTERFFICE CORRESPONDENCE TO R.

E. Uhrig LOCATION OATF Miami, Florida February 3, 1981 FRQM A.

DE Schmidt suoJFOT:

ST.

LUCIE UNIT 1

IE BULLETIN 79-01B (Supplement 3)

COPIES TO K. N. Harri s D.

K. James R.

R. Jennings C.

S.

Kent H. N..Paduano/922 SL H. S. Ruff C.

M. Wethy PRN-LI-81-58 A reply to the subject Bulletin is attached for your review and forwarding to the NRC.

This information was prepared by Power Plant Engineering and has been reviewed by Finance.

PLP/mrs Attachment l

PEOPLE... SERVING PEOPLE FORM 1008 REV. 1/78

Facgjty:

St Lucie Unit

'ocke,t No.:.

50-335 NRC BU~TW 79-01B MASTER.LIST (Class IE Electrical EquiPment Required to =unct'on Under Postulated Acc.'dent Conditions)

SVSm:

RCS 1-16 COMPONENTS Location Occurrence Plant ID No.

FE-1402 Generic Name ccelerometer Inside Containment Outs ide Containment PA f CES No.

1I55 Notes FE-1402 ardline cable ith associated

'oftline cable assembly lI56 FT-1402 100"3A B5 10083A Charge Conv Cable P enetration Cable l?57 E9 E2 E9 FE-1404 Manuf Cabl or FE-1404 Accelerometer Hardline" cable with associated softline cable assembly 1I57 lI56 fanuf Cable Hardline~le ror FE-1404 with;associated softl' assembly T-1404.

Charge Conv lI)7'

Fa~li~:

St L cie Unit

.. RC ZULL"Tel.79-0V Doc1 No.:

50-335

~

MASER LIST

(

L Electrical EguiFment Baaui ed to r.'nct'on Under Postula ed ~cc den Condi ions)

SrSaZ..

"CS 1-17 COiiOh~~'TS Loca ion Occ

~

ence Plant ID No.

FE-1200 Generic Accelerometer Inside Containment Outs ide Contai~nt CES

'.io.

1I55 Notes Manuf Cabl FE-1200 Hardline Cable wa n associate softline cable assembly 1156 FT-1200 FE

'3l Charge Conv Accelerometer lI57 1I55 Manuf Cabl for FE-Hardline cable with associated assembly 1I56 FT-1201 FE-1202 Charge Conv Accelerometer 1I57 X

1I55 Manuf Cabl FE-1202 Hardline cable wa.

assocxa e

softline cable assembly lI56 FT-1202 Charge Conv 1I57 I

I

Facility:

St Lucie Unit 1

Docket No.:

50-335 NRC BULLETIN 79-01B MASTER LIST,

-~

12-3 (Class IE Electrical Equipment Required to Function Under Postulated Acc'dent Conditions)

.-.SYSTEM:, AUXILIARYFEEDWATER'YSTEM COMPONENTS Location Occurrence Plant ID No.

IC Turbine 1C Generic Name: Pump Inside Containment Outs ide Containment X

CES No.

Notes B-102B Local Control PNL E24 12M05 Delete C12-7 Rl 10631K 1063 lH B<<1665 10631N

" 103B B101B B-100B Cable Cable coca est us Button Station Cable Signal Conv &

Turb Trip & Throttl Turb Tr'ip & Throttl E6, E9,E29 D3-11 E6, E9,E29 4

7 12M06 E,

E9,E29 D3-11 12M07 k3,'Z29 D4-7 12M12 12M08 E14 10631M by Mfr I-MV-09-11 Cab Cable from Turb ri

& Throttle va V Aux FWP 1C D

ch ocal Push E6 12M16 12M09 E6 E9 12M09 E6 E9 E29 E17 D10-44 C10-3 R2 E6 E9 3

7

Facility:

St Lucie Unit 1 Docket No.:

50-335 NRC BULLETIN 79-01B MASTER LIST (Class IE Electrical Equipment Required to Function Under Postulated Accident Conditions)

SYSTEM:

AUX FEEDWATER SYSTEM AUX FW TURB 1C COMPONENTS Location Occurrence Plant ID No.

LS2 Generic Name rLp Lim Sw Inside Containment Outs ide Containment CES No.

12M-14 Notes y MFR Cable 12M-16 0638A Cable E-29

'FR Trip VA Lim Sw Cable 12M-13 12M-16 0638B Cable E-6 S3 y MFR 0638C Mech 0/S SW Cable

. Cable 12M-15 12M-16 E-6

-102B 74 Relay E-24 0638J Cable E9

Facility:

St Lucia Unit 1

Docket:

50-335 SYSTEM COHPOHENT EVALUATION WORK SIIEFT Piacci CIIECK BY:

DATE:~II>%

OATK:~L 12H13 EQUIPNENT DESCRIPTION Parameter ENVIRODENT Specification Qualification DOCUHEIrfhTIOH REF*

Quail ficatl on Specification r

QUALIFICATION NETIIOD OUTSTAHDINC ITEHS System:

Auxiliary Fccdwater System Plont ID No. (For Aux FH Pump 1C Turbine)

Operating Time 4 llours See Notes (2) 6

~

(4)

Sec Note (3)

See Notes (2)

(4)

See Hote (3).

See Note (3)

Hone Component:

Turbine Trip and Throttle Valve Limit'witch LS-1 Temperature

( F) 320 F for 95 sec See Note (3)

See Note (3)

FSAR Appendix 3C See Note (3)

See Note (3)

See Note (3)

Hone Nanufacturc: National Acme Pressure (PSIA) 14 '

See Note (1)

FEAR Section 3

11 See Note (1)

Hone Node 1 Number:

AE-17035100 Function:

Accident Honitoring Accuracy:

Spec:

N/A Demon:

Relative Humidity (7.)

Chemical Spray IOOX Hot required See Note (1)

FSAR Appendix 3C See Note (1)

Hone Hone Service:

Auxiliary Feed{ster Pump IC Turbine Radiation Hot Required Hone Incarlon:

Stcam Trestle (Floor EL 19. )ging Turbine C.L. is 3'-8" Above Floor Level Not Rcquircd Flood IA'vel Elev:

Not Applicable Above Flood Level:

Yes No Submerging Hot Required None

• Documentation

References:

Notes:

(1)

Pressure and humidity are not considered significant parameters for evalua (2)

Hot specified

~ per FSAR; conservative Engineering Judgement, per FShR 10 ~ 5.

(3)

Rapid cooldown to ambient temperature is expected since trestle is exposed the outside envirorimcnt.

Because of thermal lag in hest transfer from shoi lived high temperature environment for affected electrical component with tcctive casing, no significant temperature increase is experienced.

(<<)

From Figure 10.5-1 in FEAR, RCS is cooled down to 300 F in 3.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when

Facility:

St Lucia Unit 1

Docket:

50-335 SYSTEH COHPONEHT EVALUATION MURK SHEET BY:

o CLEAL CllECK BY:

DATE~IZC/Zr DATE~lr 12H14 EQUIPHENT DESCRIPTION Parsmctcr ENVIRONHFNT Specification Qualification DOCUHfHTATION REF*

Qualification Spccificntlon QUALIFlCATIOH HETNOD OUTSTAHDING ITDLS System:

Auxiliary Feedwater System Plant ID Ho. (For Aux FW Pump 1C Turbine)

Operating Time 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> See Notes (2) 6 (4)

See Note (3)

See Notes (2) 6 (4)

See Note (3)

Sce Note (3)

None Component: Turbine Trip and Throttle Valve Limit Switch LS"2 Tcmpcraturc

( F) 320 F for 95 Secs See Note (3)

Sce Hote (3)

FSAR Appendix 3C Sce Note (3)

See Note (3)

Scc Note (3)

Hanufacturc:

National Acme Pressure (PSIA)

14. 7 See Note (1)

FSAR Section 3.11 Sec Note (1)

None Hodcl Nllsbcr:

02400K-ST2 Relative Humid ity (X) 1002 Sce Note (I)

FSAR Appendrx 3C Sce Note (1)

None Function:

Accident Honitoring Accuracy:

Spec:

N/h Demon:

Chemical Spray Hot Required None Scrvlcc:

Auxiliary Feedwater Pump 1C Turbine Radiation Not Required

• ~

Location: Stcam Trestle (Floor El 19 5) Aging Turbine C.L. is 3'-8" Above Floor Level HotRequired'one Flood Level Elev:

Hot APPlicable Above Flood Level:

Ycs No Submerging Not Required Hone

• Documentation

References:

I,

~

(1)

Pressure and humidity are not considered significant parameters for cvaluaticl (2)

Not spccificd, pcr FSAR; conservative Engineering JudgcmcntD per FSAR 10.5.3.

(3)

Rapid cooldown to ambient temperature is expected since trestle is exposed tc the outside environment.

Because of thermal lag in best transfer from'short-livcd high temperature environment for affected electrical component with prc tcctive casinRE no significant temperature increase is experienced.

(IE)

From Figllre 10.5-1 in FSAR, RCS rs cooled down to 300oF rn 3.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when shutdown cooling begins.

Foci ll.ty:

St Lucio I!nit I Dock;ct:

50-335 SYSTEII COHI'ONENT EVhI,NATION WORI: SIIIIFT CHECK BY:

DATE~I/2D 8/

DATE I I I

12H15 Etlt!IPIIENT DESCRIPTION Pa rome tet

- ENVIRUI'IIEHT Sp<<c I C. Ica t ion Quail CI<<at I ~ >>

SpeciCI<<ation tkoalification DOCUHI:.STATION PZFo tlt'hLIFIChTI OH kkETIIOD OUTSTAND1litt ITEk!S System:

Auxiliary Fcedwatcr System Plant 1D Ho. (For hux FW Pump 1C Turbine)

Operating Time 4 bours See Notes (2) 6 (4)

See Note I".t See Notes (2) 6 (4)

See Note (3)

Sce Note (3)

None

) Component:

Turbine Trip and Throttle Valve Limit Switch LS-3

! Hanuiartur<<: National Acme Temperature (op)

Pressure (PSIA) 320 F for 95 Secs See Note (3) 14 '

See Nots See Note (1)

FSAR Appendix 3C See Note (3)

FSAR Section 3.11 See Note (3)

See Note (1)

See Note (3)

None None

• Nod<> Above Floor Level Not Required None Flood Level I.'cvt Not Applicable Above Flood Level:

Ycs No Submerging Not Requtred None

• Documentation

References:

Notes:

(I)

(2)

(3)

(4)

Prcssure and humidity are not considered significant parameters for evaluation.

Not specified, per FSAR; conservative Engineering Judgement, pcr FSAR 10.5.3.

Rapid cooldown to ambicnf temperature is expected since trestle is exposed to the outside environment.

Because of"thermal lag in heat transfer from short-lived high temperature environment for affected electrical component with pro-tective casing, no significant tqmpcrature increase is.experienced.

From Figure 10.5-1 in FSAR, RCS ts cooldd down to 300oF rn 3.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when shutdown cooling btgins.

Facility:

St Incic Unit 1

Docket:

SYSTEH COHPONENT EVALUATION WORK SIIEET BY:

cAPn,m.a!~

CIIECK BY:

DATE: I/Zc/S DATE~i (nl 12HI 6 EQUI PHEHT DESCRIPTION Parameter ENVIROIIHENT Speci fles tion Qualification Specification Qualification DOCUHENTATION REF*

QUALIFICATIOH HETIIOD:,

OUTSTANDING ITEHS System:

Auxiliary Feedwater System Plant ID No. (for Aux FW Pump 1C Turbin Component: Turbine Trip and Throttle Valve Limit Switch and Solenoid Valve Cable Opera ting

)

Time Temperature

( f) 4 Hours See Hates (2)

(4) 320 F for 95 Secs See Note (3)

See Note (3)

See Note (3)

See Notes (2)

(4)

FSAR Appendix 3C See Note (3)

See Note (3)

See Note (3)

See Note (3)

See Note (3)

Hone Hone Hanufacture:

Principal Vcridors Byron Jackson Turbine: Terry Steam Turbine Corp (5)

Hodcl Humbcr:

Scc Note (5)

Function:

Accident Hitigation Accuracy:

Spec:

H/A Demon:

Prcssure (PSIA)

Relative Ilumidity (7)

Chemical Spray

14. 7 100X Not Required See Note (1)

See Note (1)

FSAR Section 3.11 FSAR=

Appendix 3C See Note (1)

See Note (1)

None Hone None Service:

Auxiliary Feedwater Pump 1C Turbine Radiation Hot Required Hone Location:

Steam Trestle (Floor El 19.5 Turbine C.L. is 4'-2" Above Floor Level Aging Not Required None Flood Level Elev:

Not Applicablc Above Flood Level:

Yes No Submerging Not Required None

• Documentation

References:

Note: (1)

(2)

(3)

(4)

(5)

Pressure snd humidity are not considered significant parameters for evaluation.

Not specified pcr FSAR; conservative Engineering Judgement, pcr FSAR 10.5.3.

Rapid cooldown to ambient temperature is expected since trestle is exposed to the outside environment.

Because of thermal lag in heat transfer from short-lived high temperature cn.

vironment for affected electrical component within protective casing (II inch watertight conduit system),

no significant temperature increase is experienced.

From Figure 10.5-1 in FSAR, RCS is cooled down to 300 F in 3.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when shutdown cool-ing begins.

Thc turbine manufacturer has been contacted for thc cable manufacturer name and model number.

i ~ (3

('IL!

-2Z W nl r q 'r;~y5 SYSTFM COMPONKHI':

CATION HOIU: SIICE"r Facility:

St Iacic Unit 1

Docket:

50-335 BY/DATE Cll/DATE R

E V I S

Z.

0 N

,."/'

I 17M-10 BY

(

rl /rb 3r~

DATE Sids/n C11ECK BY w.

~

~ - r ~-r' DATF.s -$0.80 EQUIPMEHT DESCRIPTIOH System; Contalnmcnt Purge System Plant ID Ho.

ZS-25-10 and ZS-25-11 for Valve I-FCV-25-5 parameter Operating Time ENVIRONMENT Specification 15 Min Qua 1 1 f1col 1 on l~

. See Note (4)

Speclflcnti.in Qualification FSAR 3.11.1.3b See Note (4)('OCUMENTATION REF-QUALIFICATION METIIOD I.

c See Note (4) <

OUTSTAHDIHO ~

ITEMS

'l None Component:

I.lmit Switches Tempo tn Lure (OF) 0 150 L

. See Note (4) tt FSAR See Note (4) l.

See Note (4)

None Manufacture.:

National Acme Co.

Prcssure (PSIA) 14.7 See Note (1)

FSAR Section 6.2.3 Seo Note (1)

None Model Number:

D2400X Function:

Accident Mitigation Accuracy:

Spec:

N/A Demon:

Relative Humidity (X)

Cbcmf ca I Spray 100X Post-LOCA Below 70X after 2 mtns.

Hot Required See Note (1)

FSAR Section 6,2 3 See Note (1)

None None Service:

Containmcnt Purge Isolation Valve I-FCV-25-5

~cation:

Annulus Elcv.

54'adiation Aging 4.5 N 10 Rads 5

ee Notes (2)6(3)

Not Required 6

10 Rads See Notes (2)&:(3) See Note (4); t See Note (4)

None Hone Flood level Elcv:

H/A Abovc Flood Lcvc 1 1 Submerging Hot Required Hone

• Documcutntlon Rcfcrcnces:

Notes:

1)

Pressure and relative lnuaidity are not considered significant parameters for eval 2)

Not specified per FSAR; conservative Engineering Judgement.

3)

Estimated fran dose maps.

(4)

Qualification established by Engineering Analysis Ho, M-lg.

Factlttyt St Lucia Untt 1

Docket: 50-335 R

EQIIPHENT DESCRIPTION b7-3:XII fX 13/

ds

~'

A II >so CH/DATE nae W +4>

OATE~~~

~/

/.

p+YC( 5:+~//J 1I17 BY/DATE F

y I 5 I 0

N DOCUHEHTATION REF*

Spectftcation

'ualification ENVIRONNE HT Spcctftcatton OUTSTANDING ITEHS QlhLlF ICATION HETIIOD Parameter qua IIftea t i on SYSTEH COHPONENT EVALUATION MURK SIKET BY V /': >/lM/~

/ I CHECK BY rc ~r-, ~lfvs~

RE,-CIIeCKFsn u8/

Systemt Reactor Coolant System Plant ID Ho.

TE-1112CA Operating Time Sec Scion Scc Note (I)

See Bcluv Scc Bc)ou Nono Component:

Temperature Element Temperature

( F)

Scc Attaclusent I &II Sce Note (3)

FSAR Table 3 11-1 Ftg 6,2-12 & llI See Note (3)

'cc Note (3)

None Hanufscture:

Roscmount Pressure (PSIA) s Sec h [cp chmcnt I &II Sce Note (3)

FSAR T blc 3.11-1 Fig $.2-12 & 14 Scc Note (3)

Sce Nato (3)

None iHodcl Number t 104VC Serial Humbert 57147 Rolative Humidity (2)

See Note (3)

PSAR Table 3.11-1 See Note (3) 5ce Note (3)

None Functton:

AH Accuracy:

Spec:+ 52 (Note 2)

Demons (Note 3)

Chemical Spray 1720-2450 PPH of Boron PII 8.5-10.5 0.24-0

~ 8 Mt% NaOH Cce Note (3)

PSAR Table 6.2-22 See Note (3)

See Note (3)

Nona Servtco:

RPS-Reactor Coolant Temperature Loop IA2-Cold Le

& Input gc,gubcooltng Margin/

Honttor/Rev 3.

nstdc Containment; Locattont Loc on Dtsch Pipe of RCP-IA2; un Top Section of Ptne 30" RC-115, 1'-0" from Center Line & 5'-6" from Primary Shield Mall at Kiev of 29'A'lood Level Elcv: 27.3'ax.

Above Flood Level:

Yes-Radiation Aging Submerging Scc A)tschmcnt 40 Years Not Required See Note (3) 40 Years Scc Rotc (4)

Assumed Sce Note (3)

Sce Note (3)

See Note (3)

Scc Note (3)

A Soc Note (3)

None None

• Documentation

References:

/> J'

/s! /."

BY/DATE CN/DATE Notes:

((I)

Conservative enginccring judgement indicates that thc Subcooling Ha'igin Honitor I requires this sensor input as long as the plant is in hot standby..

(2)

FSAR 3.112 (s)

(3)

Qualification established by Engineering Anat~ate No. 1.24.

((4)

Utitiatng Large break LOCA radiation doses> td.k R

E y I S

I 0

N

"I II

Facility:

St Lucia Unit I Docket: 50-335 2

/r/7 y.gn'go g4. 7>/g0 BY/DATE R

K V I S I 0

H PV SYSTKH COMPONENT EVALUATION CH/DATE WORK SHEET BY DATE ance sv.KI~&ew'ip'aTe~azs lrc'6-C1dCCKC-d3 fbY Cif~/

A,Y

~

5 1o'io lllg EQUIPHKNT DESCRIPTION Foram'ster ENVIRONMENT Specification Qualification Specification qualification DOCUHFNTATION REFs QUALIFICATION METHOD OUTSTANDING ITEMS Sys<<m: Reactor Coolant System Plant ID Ho. TE-1122MB Operating Time 30 Days Scc Below Sca Note (1)

Sea Below Seo Below None Component:

Temperature Element Temperature Sco Attachments I & II Sec Nota (3)

FEAR Tablo 3.11-1 Fig 6.2-12 1k 14 Sec Note (3)

Scc Nota (3)

Hone Manufacture:

Roscmount Hod I Numb Serial Nuekei:

57165 Function:

AM Accuracy:

Spec: + 52 01ote 2)

Demon: (Hots 3)

Pressure (PSIA)

Relative lkusidity (2)

Chemical Spray Sch Attac1vacnts I & II I Sec Nota (3)

Scc Note (3) 1720-245P PPM of Boron PH 8'-10.5 See Nota (3) 0.24-0.8 WtX HaOH FEAR Table 3.11-1 Fi 6.2-12 5 14 FEAR Table 3.11-1 FEAR Table 6.2-22 Scc Nota (3)

See Note (3)

Sce Note (3)

Sce Note (3)

Sce Note (3)

See Note (3)

None None None Service:

RPS-Reactor Coolant cmporsture Loop IB-Hot Lcg

& Input to Siibcoolin'I, 11argi~n onito~r P y Inside Containmcnt.

Location:

Loc on Top r/f Inlet to SC 18 from Reac 1 -11" from C.L. of Pipe snd 1>-8" from Primary Shield Wall> El 13'-8" above Floor El 18 -0" in RCB Plood Lovel Klcv: 27.3'1ax, Above Flood Level:

Ycs Radiation Aging Submerging

(

Sce Attach-ment I 40 Years Hot Required See Nore (3) 40 Years Sca Note (4)

Assumed Sec Note (3)

Sec Note (3)

See Note (3)

Sca Note (3)

( Sec Note (3) )

wane None

• Documentation

References:

p) 1/ r(c.

BY/DATE Subcooling Hargin Monitor >

hot standby.

1-24 Notes:

~

t (1)

Conserva xvu c.n1,rueerrug dudgemmnt rndrcates that the IIHf~

1 requires this sensor input as long as the plant is in (2)-

1'SAR 3.112 (o).

(3)

Qualification established by Engineering Analysis No.

CH/DATE, t(4) Utiliring large brcak lAKh radiation doseao P, >

R K

V I S I 0

H

fz OZ-S~ gtt EE'y/pt>

~ 714 SYSTEH COHPOHENT EVALUATIOfl WORK SHEET Facility:

St Lucic Unit 1

Docket:

50-335 tQ.

BY/DATE Cll/DATE R

E V I S I 0

N BY V

CIECK BY l u l.

5 DATE~3~D":U I

I l 1 19 EQUIPHENT DESCRIPTION System: Reactor Coolant System Plant ID No. TE-1122CA Pgrnmcter Operating Tice ENVIRONHENT Specificatfon 30 ~Days ttuaffffcatfon See Below DOCUHEHTATION REF*

Specification

'tualfffcatfon See Note (I) 'ee Below QUALIFICATfON HETHOD Sec Below OUTSTANDING ITENS Hone Component: Temperature Element Hanufacturea Roscaeunt Temperature Pressure (PSIA)

See Attachment I& II

, Sce ht taclnaent 5&II Sce Note (3)

Sec Note (3)

PEAR Table 3.11-1 Figure 6.2-12 14 FEAR Table 3.11-1 Figurc 6.2-12 14 Sce Note (3)

Sec Rotc (3)

Scc Note (3)

Scc Note (3)

None None

!Nodal Numbera 104VC Serfal Nushera 57151 Functfon: AH Accuracy:

Spec:

+5K (Note 2)

Demon:

(Note 3)

Service:

RPS - Reactor Coolant Tcmperatqre Loop 181 - Cold Lcg angdlnput Io SUBCObl~itli

~Hargtta ttonftor+(7~

Inside Contalnaent Location:

Loc on Disch Pipe of RCP-181 to Reactor, Inside Prfmag Shiold Wall at Elev 29'-6 '.

Quad IV Relative Humidity (Z)

Chemical Spray Radiation Aging 100Z 1720-2450 PPH hf Boron PH 8.5-10.5 0.24-0.8 WtZ NaOU ee httschaen 40 Years Seo Note (3)

See Note (3)

Sce Note (3) 40 Years FEAR Table 3.11-1 FSAR Table 6.2-22 See Note (4)

Assumed See Note. (3)

Sce Note (3)

See Note (3)

See Note (3)

Sec Note (3)

Scc Note (3)

Sec ltote (3)

Scc Note (3)

None None P

Sce Note (3) 3, None flood Level Elevt 27.3'ax.

Above flood Level:

Yes Subae rging Not Required None

• Documentation

References:

'l )f/iz'z/t (

BY/DATE CH/DATE Notes:

(1)

Conservative engineering judgement indicates that the

(

requires this sensor input as long as the plant is in (2)

I'SAR 3.112 (a)

(3) quafificatiou established by a".wsiuvering analysis tto.

~ (4) ntilialng targe trank I.nCA radiation doses.

subcooling Hargin tlonitur hot standby/

1-24.

R E

V I S

I 0

H

&Di W$'0 ll 7a',>,

I/- -. I /rf'",cI SYSTEM COMPONENT EVAUIATION WORK SHEET I

/'-

Facility:

St Lucis Unit 1 Docket:

50 335 BY/DATE CN/DATE VIS IO l Eul CHECK BL !

74rrADATE~J>O 1120 EqOIPHEHT DESCRIPTION Parameter

- EHVIROIOIENT Specification Elualificstion Specification Qualification DOCUMENTATION REF*

QIALIFICATION HETIIOD OOTSTAHDINC ITEMS System:

Reactor Coolant System Plant ID No. TE-1112IIA Component:

Temperature Element Manufacture:

Roscmount Oporsting Time Temperature

( P)

Prcssure (PSIA)

(30 Days/

Scc Attachment I &II Seel Attachment 16 II.

See Bclou See Note (3)

Sec Note (3)

Sce Note (I)

FSAR

'lablc 3 11 1

Fig. 6,2-12 & 14 FSAR Table 3.11-1 Fig. 6.2-12 & 14 See Belou Sce Note (3)

See Note (3)

Sce Bclou See Note (3)

Scc Note (3)

Nona I

Hone None IMod el Number Serial Nunhert 57161 Relative ltumidity (2)

Sec Note (3)

FSAR Table 3. 11-1 See Note (3)

See Note (3)

None Punction:

AH hccurscyI Specs+

5> (Note 2)

Demon:

(Hate.I)

ScrviceI RPS - Reactor Coolant Temperature Loop IA - Not Leg snd/Input to Subcoolrng Ha@gin (Monitor) P g Inside Containment Location:

Loc on Inlet to SG-IA Top Sect. of Pipe I'-ll"from C-Lof Pipe

& i'-La frcxa Primary Shield Walll 13'-8" above Floor El 18'-0" Flood Lcvcl Kiev: 27.3'ax.

Above Flood Level:

Ycs Chemical Spray Radio t ion Aging Submerging 1720-2450 I

ppH of Boron PII 8 ~ 5-10.5 0.24-0 '

WtX NaOII Sec Attachmcn~t I P.5 40 Years Not Required Sce Note (3)

See Note (3) 40 Years FSAR Table 6.2-22 Sce Moto (4)

Assumed Sce Note (3)

See Note (3)

Sce Note (3)

See Note (3)

See Note (3)

Sce Note (3)

Hone Scc Note (3) )

None None

• Documentation

References:

~ 1() I//I IT BY/DATE l)ilogjt CN/DATE Notes:

r(I)

Conservative engineering judgement indicates that thc Subcooling Margin Monitor 7 I

rcquircs this sensor input as long as the plant is in hot standby/ fv Q (2)

FSAR 3.112 (a)

(3). Qualification established by Engineering Analysis No.1-24.

'(4)

Dtilising large break LOCA radiation doses.~ P $

I a

I

~ 0 R

E V I S I 0

2

-D P3P-gfz

~ 7 lg pg SYSIXN COHPONENT EVALUATION WORK StlEET '

Facility:

St Lucie Unit I Docket'0 335 BY/DATE R

E V I S

CN/DATE 0

N BY 7 DATE CHECK BYF<~~~W c 74u 4 DATE +Z6~8~

1ZL CBEClCGI3 6\\

dtdi 8'n d'o tl2t EQUIPHENT DESCRIPTION ENVIRONHENT Paraictcr Specification Qualification DOCUHENTATION REF*

Specification

'ualification QUALIFICATION HETIlOD OUTSTANDING ITEHS System:

Reactor Coolant System Plant ID No. TE-1112CB Operating Time Pso nay See Below Scc ttote (1)

See Below See Below ttonc Component:

Temperature Elcmcnt Tcmporature (OF)

See Attachment IS II Sce Note (3)

FEAR Table 3.11-1 Fig 6,2-12 g: 14 Sce Note (3)

Sec Note (3)

None Hanufscture:

Rosemount Prcssure (PSIA)

Sce ht tacttpcnt I &II See Note (3)

FSAR Fig tz.2-12 Vc 14 Sec Note (3)

Sec Note (3) ttone tHode1 Number:

104VC Serial Nuaber, 57148 Relative Humidity (2)

See Note (3)

FEAR Table 3.11-1 See Note (3)

See Note (3)

None Function:

AH Accuracy; Spec: + 52 (Note 2)

Demons (Note 3)

Service:

RPS - Reactor Coolant Temperature Loop IAI - Cold Lcg and.)input to Sugcooling}.

( Hargin Hnnitozi P>

inside Containmcnt; Location:

Loc on Disch Pipe of RCP-IA1, on Top Sect. of Pipe 1'-0" from CL of Pipe and I'-6u from Primary Shield Wall; 13'-Ou above Floor El 18'-Ou Flood Level Elevz 27.3'ex.

Above Flood Level:

Ycs Chemical Spray Radiation Aging Submerging 1720-2450 PPH of Boron Plt 8.5-10.5 0.24-0.8 WC, NaOtt See Attachment I 40 Years Not Required See Note (3)

Sce Note (3) 40 Yrnra FSAR Table 6.2-22 Scc Note (4)

Assumed See Note (3)

Sec Note (3)

Scc Note (3)

Sec Note (3)

Scc ttotc (3)

Sce Note (3) none

('Scc ante (3) )~z Nnne None

• Documentation

References:

io.

rib/ i/IO BY/DATE

.Fq, <Jg Ctt/DATE Notes:

((1)

Conscrvatibe engineering judgement indicates that the Subcooling Haz'gin Honitnrp requires this sensor input ss long as tbe plant is. in hot standby./Q P (2)

FSAR 3.112 (a)

(3)

Qualification established by Engineering Analysis tlo. 1-24.

<(4)

Utilizing large brcak LOCh radiation dozes. P Q R

E<V I S I 0

N I

- Ck.'

~

I i

( ',

8P y-&.So

/le 7 5/ 1.>

Z8 7/l,.~ ~

SYSTEM COMPONENT EVALUATION NORE SHEET Facility:

St Lucic Unit I Docket:

50-335 EQUIPMENT DESCRIPTION BY/DATE CN/DAZE Para<setcr R

E V I S I 0

N ENVI'RONHENT Specification

+a ltfication DOCVHENTATION REF*

OUTSTANDING ITFHS qVALIFICATION METHOD Specification

'ualification BY DATE CHECK B'I

@.~~ ~94'~4'ATE Qg-C HEC V.rage Oa TC S'.<<< ~d 1122 Systcs<:

Reactor Coolant Systc<s Plant ID No. TE-1122CB Operating Ti<<<e See Belou See Note (1)

Sce Belou See Belou None Co<<<poncnt:

Te<<<pcrature Elc<acnt Tcs<perature (OF)

Scc Attach<<<cnt I

6< II See Note (3)

FSAR Table 3.11-1 Fig 6.2-12

& 14 Sce Hots (3)

See Note (3)

None Manufacture:

Rose<<<cunt

~Model No<<<her:

104VC Serial Nu<<<ber:

57152 Function:

Accuracy:

Spec: "+52 (Note 2)

De<<<on: (Hote 3)

Service:

Rpg - Reactor Coolant Tc<<<pcrature Loop IB2 - Cold Leg and.input'tb Subcoofing)

(Hsigin Honitor')P 4;

'Inside Containdc<lt Location:

Loc on Disch Pipe of RCP-192 on Top of Sect. 1'-2" fro<a g

of Pipe, 6'-0" fro<s Pri-Pressure (PSIA)

Rcla tive Ituc<<idity (2)

Chc<<<ical Spray Radiation Aging See Attaph<<<ent I 4 11

...,1002 1720-24/0 PPH of Boron PH 8.5-10 '

0.24-0.8 Nly. N Ol a

A<<>><<l 40 Years See Note (3)

Sce Note (3)

See Note (3)

Sce Nota (3) 40 Ye~ra FSAR Table 3.11-1 Ig>> 6<2 12 6 14 FSAR Table 3.11-1 FSAR Table 6.2-22 See Note (4)'ssuacd See Note (3)

Sec Note (3)

See Note (3)

Soe Note (3)

Sce Note (3)

See Note (3)

Sce Nota (3)

Sce Note (3)

Sec Note (3)

Scc Note (3)

None None None Scc Rotc (3) )

---

<<V)

None Flood Levol Elev:

27 3< Max.

Above Flood Level:

Ycs Sub<<<erging Not Required None

• Deca<<<cntstion Rcfcrcnccs:

V/ //': '/

BY/DATE CH/DATE Notes:

( (I)

Conservative engineering judge<<<ent indicates that the Subcooling Margin Honit<r )

requires this sensor input as long as the plant is in hot standby~p (2)

FSAR 331 (a)

(3)

Qualificatiou cstabiishcd by tngineering Analysis No. 1-24.

((4)

Ntili<<ing large break LOCA ra<liaton doies.) Q $

R E

V I S I 0

H

Facility:

St Lucfe Unlc I Docket:

50-335

2. ea/i//st nR l/>>/FO NO BT/DATE R

E V I 8 I 0

N Rc-fA Ifll<fff

'f(ff 1@7 SYSTEII OOIITOIIEET ETAUIATIOE SOEE SIIEET I

CH/DATE By (-U 2 Pu rl/r.rr5'ECK BTP'd~l~

You DhTE+A 80 DATE J/2 6 C 5

ado l

1133 EQUIPHENT DESCRIPTION Parameter ENVIRONffENT SpeciffcaCion Qualification Specificacfon Qualification DOCUHEllTATIOH REF e QUhLIFICATION HETllOD OUTSTANDIHC ITENS System: Reactor Coolant System Plant ID No.

PT-1102A Opere cfng Tfmc Sec Belou dote (5)

See Bclou Simultaneous Testing None Component:

Pressure Transmitter Temperature

( F)

See Accachslcflc 1&II 320

- I Hr 273

- 1.75 NL 228

- 21 ~ 25 NL FSAR Table 3.11-1 Ffg. 6.2-12 & 14 Pfscher

& Porter Test Report 2204-51-B-006 Dated Occ 1968 Simultaneous Testing None Hanufacture:

Ffschcr & Porter Pressure (PSIA)

See Actps)scent I &II 90 Psfa - 1Hr FSAR 60 Psia - 1.75Hr Table 3.11-1 20Psia-21.25Hr Pfg. 6.2-12

& 14 Fischer

& Porter TesC ReporC 2204-51-B-006 Daced Oct 1968 Simultaneous Testing None lHcdel Number:

50pp1041 (Note 3)

Serfal Number:

7411A2620A2 FuncCfon: AH, PAH Accuracy:

Spec:

+52 Demon: +3.52 Span Service:

RPS - Pressuriser Prcssuro sndflnpuc to Subcooling )

Margin Honitor /p 2 Inside Concafnmcnt; Location: On Rack 53-16, Base of PT-1102A Loc,at 4'-6" above Floor EL.

62'-0"; 6'-10" frofa SE Corner of PRZR Ease Mall & 8" from East Mall.

Rclativo Humidity (2)

Chemical Spray Radiation Aging IOOI 1720-2450 ppH of Boron pN 8.5-10 5

0.24-0.8 Mcy. NaOH See Atcachmcnt I

40 yrs Steafa 15000 PPH Boric Acid PN ~ 10 5 fa 77 F

~ 1 MCX NaON 1.2x10 RAD 8

40 yrs FEAR Table 3.11-1 FSAR Table 6.2-22 FEAR Table 3.11-1 Assumed Fischcr 6 Porter Test RcporC 2204-51-8-006 Dated Oct 1968 Amcron Letter Dated Nov 20

'972 Fischcr

& Porter Test Rcport 2224-II004 Same As For Temperature Plus Analysfs Sce Note (1)

I Simultaneous Tcscing Simultaneous Testfng Plus Analypfs Note (2)

Sequential Tescfng Simultaneous Testing Plus'.

Analysis See Hoce (1)

None Hone None

. None Flood Level Elev:

27.3'ax Above Flood Level; Tcs-Submerging Not Required None

• Documcncstfon

References:

Notes' IEf. '

~

~.)

(1)

Qualification Escablisncd by Engineering Analysts I-fc (2)

Qualiiicacfon Escabffsneu by Engineering Analysis I-15 (3)

Hodifccatfons co transmitters as described in Ffschr& Porter Test fpor) QO)-()-B-OOb.

((5) conservative engineering judgesscnt indicates chat the snbcuoling Hartin 1'onitor rcquircs this sensor input as long ss the plant is fn~>

+hot standby./

p 2

Facflity:

St Lucia Unit 1

Docket: 50-335 M.

BY/DATE R

E V I S I 0

H

'Aping fl(LlSl

~

P q(~L gZ'YSTEM COMPONENT EVALUATION MORKSHEET CH/DATE I ~

CHECK BYE'l>>sf 0 2 Vv,>Ca DATE j S< N'137 EOUIPHENT DESCRIPTION Parameter ENVIRONMENT Specification 0uslfffcatfon Spcefffcntfon Oualificatfon DOCUMENTATION REF*

QIALIFI CATION METHOD OUTSTANDING ITEHS System:

Reactor Coolant System Plant ID Ho. PT-1103 Component:

Pressure Transmitter Manufacture:

Fischcr & Porter model Number'0 Ep 1041BCHS (Note 3)

Scrfal No

7104A5544A95 Operating,-

Tfme Temperature

( F)

Pressure (PSIA)

Relative Muwfdity (X) 31 Days See Attachment I 6 II.

See Attachment

~

I & II 100X Sce Belou 320 F - 1 hr 273 F - 1.75hr 228 F - 21 ~ 25hr 90 psia-I hr 60 psia-1 75hr 20 psia-21,25hr Steam FSAR TABI/8 7.5-4 FEAR Table 3.11-1 Fig. 6.2-12 6

14 FEAR Table 3.11-1 Fig. 6.2-12

& 14 FSAR Table 3.11-1 Sec Bolou Test Report Fischcr & Porter 2204-51-B-006 Dated Oct 1968 Test Rcport Fischcr

& Porter 2204-51-8-006 Dated Oct 1968 Test Report Ffsclicr & Porter 2204-51-B-006 Dated Oct 1968 Simultaneous Testing Plus Analysis Note (1)

Note (1)

Simultaneous Tcstl.ng Plus Analysis Note (1)

Simultaneous Testing Plus Analysis Simultaneous Testing

~ None Hone Hone None Functfon:

AN Accuracy:

Spec:+5X (Note 4)

Demon:+3.5X Span Chemical Spray 1720-2450 PPH of Borak PH 8 5-10.5 0,24 0,8 MTX NaON 15000 PPN Boric Acid pH~10.5 La 77

.1 MtX NaOH FSAR Table 6.2-22 Amcron Lctter Simultaneous Dated Testing Hovcmbcr 20, 1972 Plus Analysis Note (2)

None Radiation Aging Service: Pressurircr Pressure (Lou Range)

,andflnput to Subcooling Margin

( Monitor(( i y Inside Contafnmcnt Location:On Rack 53-16; Base of PT-1103 4'-6u above FL EL 62'-Ou 5'-9" from SE Corner of PER East Mall & 8u auay from ft.

Sec Attachment I

40 yrs I~ 2x10 Rad 8

40 yrs FSAR Table 3.11-1 Assumed Test Report Fischcr 6 Porter 2224-1 No. 004 Same As For Temperature Plus Analysis Sec Note (I)

Sequential Tcstfnn Simultaneous Testing Plus Analysis See Note (1)

I None None Flood Level Elcv: 27.3'ex Above Flood Level:

Ycs Submerging Not Requfred None

• Documentation

References:

Note:

(I)

Qualification Established by Engineering Analysis 1-16 (2)

Qualfflection Established by Engineering Analysis 1-15 (3)

Modifications to transmitters ss described in Fischcr Porter Test Rcport 2204-51-8-006.

(4)

FSAR 3.11.2(a).

Feel lity: St Lucia Unit 1

Docket: 50 335 SYSTEH COHIVHENT EVALUATION NOkK SIIBFT BY

~/8~m DATE

/8 P/

v~

CIIECK BY L (

m DATE I (L C l I55 KQUIPHEHT DESCRIPTION Parawctcx' ENVIROBHFHT Spcciflrntiun Qun I I fI ration DOCUHENTATION BKF*

Qualification Speclflcntlou QUAl IFICATIOH HETHOD OUTSTANDLNC ITDtg Sy<<cw: itcactor Coolant Systcw Plant ID Hu FE-1402 1202 1404 1200 1201 Cowponcnt:Acccierowcter (Sensor)

Operating Tiwc Tcape rature

( f) 15 win Sce Attachecnt Ill and Note (3)

Sec Note (I)

Sce Note (I)

BC 1.97 Bcv 2 Src Note (2)

NURKC 0578 and 0737 FSAR Figure 6.2 11B Scc Hate (I)

See Note (1)

Scc Note (I)

See Note (1)

Sce Bute (I)

Sec Note (1)

KNDEVCO (TEC)

Pressure (PSIA)

Sec Attachment III and Note (3)

See Note (I)

NURKC 0578 and 0737 See Note (1)

FSAR Table 3.11-Sce Note (I)

See Note (1)

Nodal Nuwbcr:

2273A function:

PAN Accuracy:

Spec: 31-5PC/8 Dewan:Sce Note (5)

Serial No.

Sensitivity (PC/

DK96 3.32 DL23 3.33 Service:DR 21'S ~ 63 3'32 ' '1 3 47 PORV and SRV Position Indication Relative liuwldlty (X)

Chcelcal Spray

)

Radiation 100X 1720-2450 PPH of Boron Pil 8.5"10.5 0.24-0.8WtX NsOli Sce Attachwcnt I and Note (4)

Sce Rotc (1)

Sec liote (1)

See Hotc (I)

HUREC-0578 and 0737 FEAR Table 3.11-1 NUREC 0578 and 0737 FSAR Table 6.2-22 NUREC-0578 and 0737 FSAR Table 3.11-1 Sce Note (1)

See Note (I)

Sec Note (I)

See Note (I)

See Note (I)

See Hote. (1)

See Note (1)

See Voce (I)

Sec Note (1) ication(nsidc Containment Aging KL 81'3/16" for FE 1402

& 04 EL 77'7/8" for FE 1200, Ol, 0 40 years See Note (I)

Assuwrd Scc Note (1)

Scc Note (1)

See Note (I)

Flood Level Eleve 3'bove flood Level:

Yes Subec rging Not rcquircd None

• Documentation

References:

i 1

(5) Tested sensitivity values werc verbally obtained frow TEC and will be confirw-ed in writing.

Notes:

CII Final Qualification docuwrntation supplied by equipwent vendor (TEC) is expected by cnd of January 198L (2) ln RC 1.97 Rcv 2 thc required operation purpose is to indicate operation status of the SRV's and PORV's to eonitor loss of coolant.

Thc accident considcrcd is a stuck open PORV.

15 win post accident operating CP tice was chosen as on adequate tine, for thc operator to take necessary action such as closing the block valve.

(3) A stuck open PORV is considered equivalent to a snail break IA)CA.

The pressure and tewpcraturc transient curves rcfcrcnccd are for thc swallest brcak evaluated in the FSAR.

This is considered to be a Sonserva-tivc approach since this break isrsizably larger than a loss of coolant through a stucv. os n POR'v.

(4) This radiation is overly conservative since it utilizes largo brcal: LOCA source tcrws.

SYS1721 rXXNvlRENT EVAIllATIONNuXK SNEET facility:

St Luclc Unit I Dock< t: 50-33S

<<+/00

/tv<<<

Ili<< ///~E/

ai<<<<<~LI'~<<<<~lt

<<)

EQUIP)AT DESCRIPTION Parameter EINIRONNENT Spcclflcatlon Qual Ifi cat inn OOCUNENTATIOil XFF>>

Spcclflcatlon Qualification QUALlfI GATI OW ttETIlOD OUTSTANDING ITQIS System:

Reactor Coolant System Plant I" No ~ Hanufacturer Cable for FE-1402,

1404, 1200, 1201 and 1202 ComPoncnt:

Sensor Cables Opcfatlng Time Tcmpcrature (of)

,15 min Sec Attaclusent III and Rotc (3)

Scc Note (I)

Src Note (1)

RC 1.97 Rev 2 Sce Note (2)

NUREC 0578 snd 0737 FSAR Figure 6.2-118 Sec Note (I)

Sec Note (1)

See Rotc (1)

See Rotc (I)

S< c Note (1)

Sec Rotc (1)

Nanufacturc:

TEC Prcssure (PS LA)

See Attaclmiqnt III and Note (3)

N:c Note (I)

NUREC 0578 and 0737 FSAR Fig. 6.2-11 See Note (I)

See Note (I)

Src Note (I)

TEC 2273-Cl Assembly (Edevco 3075-H6 Coaxial hard line cable and thc RC-195A/U Function: softlinc coaxial cable)

PAN Accuracy:

Spec:

N/A Dement N/A Rc lative lb<midi ty (2)

Chemical Spray 1002 Boric Acid, 1720-24SOppm PN 8.5-10.5 0.24-0.84MtX NaO Si <'ote (1)

Scc Note (I)

NUREC 0578 and 0737 FSAR Table 3 ~ 11-1 NUREC-OS78 and 0737 FEAR Table 6.2-22 See Note (I)

Sec Note (I)

Sec Note (I)

Sec Note (1)

See Note (I)

See Note (1)

Service:

Connects TEC acoust ical sensor with the charge converter Rad lat ion Sec Attachment and Rotc (4)

Suc Note (1)

NUREC-0578 snd 0737 Sce Note (1)

FSAR Table 3.11-1 Sce Note (1)

Scc Note (I)

Ix<cntfont Inside Containment Aging 40 years Sce Note (I)

Assumed Sce Nore (1)

Sec Rotc (1)

Src Note (I)

Flood licvcl Elcv:

27.3'ax Abovu flood Level:

Ycs Submcrglnp, Not rcquircd None

• Documentation

References:

Notes:

~I Pinal Qualification dncum<ntatinn supplied by e<p<ipmrnt vendor (TEC) is

< xprcted by md of January 19)I.

(2)

In RC 1.97 Rfv 2 tbc required op<ration purpose is to indicatr operation status of tbr SRV's and POXV's to monitor loss of coolant.

Thc accident con>>idcrcil is a stuck open PORV.

15 min pn>>t >>ccident oper-ating time uas chosen as an adequate time, for the operator to take n<ccssary action such a>> closing the block valve.

(3)

A stuck oprn pORV is considcrcd equivalent to a small break IA)CA.

'Ihc pressure and tcmpcraturc transient curves refcrcnccd are for tbc smallest break evaluated in thc FSAR. This i>> considered to be a conserva-tive approach since this break is siaably larger than a loss of coolant through a stuck open PORV.

(4)

This radiation is overly conservative since it utilises large brcak LOCA source terms.

SYSTFJl COHPONENT EVALUATION WORK SllFET Facility:

St Lucie Unit 1 Docket: 50-335 EY~OPCCo.g~ ~~ DATE g P CllECK DY DATF. \\

i I

1I El}UIPHENT DESCRIPTION Paracoctcr ENV 1 RctalFNT Specification Qualification gpeclflcntlon quail f Ication DOCUHENIATION RFFn OUALIF1CATION HETHOD ONTSTANDlNC IT@IS Systccu Reactor Coolant System Plant ID No. FT-1402 1202 1404 1200 1201 Conponent:

Charge Converter (preamplifirc)

Operating Tine Tesperaturc

( F) 15 min See Attachmen III And Note (3)

Sec Note (1)

NUREG 057S, an 737 and FSAR Figure 6.2-118 RG 1.97 Rev 2

See Note (1)

See Note (2)

Sec Note (1)

See Note (1)

Sce Note (1)

Sec Note (1)

Sec Note (1)

See Note (1)

Manufacture l TEC Hadal Nosher:

TEC Model 500 Function:

PAM Pressure (PSIA)

Relative Humidity (2)

See Attachment III and Note (3)

~

100%

Sce Note (I)

Sec Note (1)

NUREG-0578, an 0737 And FSAR Figure 6.2-11 NUREG 0578 and 0737 FSAR Table 3.11-1 Scc Note (1)

See Note (1)

Sce Note (1}

See Note (1)

Scc Note (I)

See Note (1)

Accuracy:

Spec Jlbsolute accuracy f5% (0-185 F)

Denoal + IX Note (5)

Chemical S pray 1720-2450>PPM of Boron See Note (1)

Pll 8.5-10.5 0.24-0.8Wtg Na ll NUREG 0578 and 0737 FSAR Table 6.2-22 See Note (1)

Sce Note (1)

Sec Note (1)

Service:

PORV and SRV Position Indication Radiation See Attach" ment I and Note (4) cc Note (1)

HUREG-0578 and 0737 FSAR Table 3.11-1 See Note (1)

Sec Note (1)

Sec Note (1)

Location:

Inside Containment Ef 66'-6" for FT 1402 4

1404 EI 67'or FT-1200, 1201 41202 Flood Lcvcl Elevl 27.3'ax Above Flood Level:

Yes hg,lng Subne rg lag 40 years Not Required ee Note (1)

Assumed Sce Hote (1)

See Hote (I)

Sce Note (1)

None

• Docnannratlon

References:

4' t

~ ~.)'5)

Tested sensitivitY values vere verbally obtained from TEC and vill bc confirmed in vriting.

Notes:

Tll Final Qualificstina docunentatioa supplied by cquipncat vendor (TEC) is expected by cnd of January 1981 (2) In RC 1,97 Ruv 2 the rcquireu uperatiuu purpusv is tu indicate vpvratiuu status uf thu SRV's and

-PORV's to monitor loss of coolant.

The accident consblcred is a stuck open PORV.

15 min post accident opera+

tiag tine vas chosen as an adequate time, for the operator to take necessary action such as closing, the block valve.

(3) h stuck open PORV is considcrcd equivalent to a snail break LOCA.

The pressure and tesperature trnsient curves referenced are for the sua1lest brcak evaluated in the FEAR ~ 'his is considered to be s conserva-tive approach since this break is sitabl> larger than a loss of coolant through a stuck open PORV.

(4)

This radiation is overly coaservative since it utilixes large break LOCA source terna.

Facflfty:

St Lucia Unit 1

Docket:

50-335 BY/DATE CH/DATE R

E V I S

I 0

N

~P~~

7 / /de

.-l)l-l~-f9 <i~

.'.76 Jn SYSTEH COHPOHEHT EVALUATION WORK SHEET Y

u l V if/&5 DhTE <-~+"~+

I CHECK BYgrlCr J

.~<'v/4DhTE 1511 DOCUMENTATION REF*

EQUIPMENT DESCRIPTION System Hydrogen Control System Plant ID No.

Pa rome tor Operating Tfme ENVIROHHEHT Specification 1 Year gualf fication See Belch Specfffcntfon Sce Note (1)

Oua lifIcat fon WCAP7709-L Suppl.2, 3, 4 QUALIFICATIOH HETHOD Simultaneous Testing OUTSTANDING ITFHS None Component:

Hydrogen Recombfner Tempera Cure (OF)

See Attachment I & II 1700F

~500. Mrs FSAR Table 3.11-1 Ffg. 6.2-12

& 14 WCAP7709-L Suppl.2 Simultaneous

. Testing None Manufacture:

Westinghouse Pressure (PSIA)

See Attachment I & II 77 Psia-4 Nrs 35 Psia-1 WCAP7709-L FEAR SuppL 2 Table 3.11rl Fi. 6.2-12

& 14 Simultaneous Testing Hone Hodcl Number:

H/A

Serial No.:

45 Spin Ho. Stf - GHREEE-02 Function:

Accident Hitfgation Accuracy:

Spec:

N<<e (2)

Demon:

Service:

Control Hydrogen Concentration in Containment After a IOCA Relative Humidity (X)

Chemical

.Spray Rad iation 100X 1720-2460 PPM Boron; 0.24-0.8 WtX NaON, pH 10.6 Hax.

See Attachment I

100X 2500 PPM Boric Acid uith Sodi Nydroxfde for H~ 10 4 Hrs 2 x 10 Rads 8

FSAR Table 3.11-1 FEAR TabIe 6.2-22 FSAR Table 3.11-1 WCAP7709-L Supple 1 WCAP7709-L Suppl,l, 2, 4 WCAP7709-L Suppl.2 Simultaneous Testing Simultaneous Tesing Simultaneous Testing None None None Loca tfon:

Inside Containment Elcv 62,00'n Approx Opposite Sides next to each Steam Generator Aging 40 years 40 years Assumed WCAP7709-L Suppl. 6 Sequential Testing None Flood Level Kiev: (27.3') (Max)

Above Flood Level:

Yes Submcrgfng Not Required Hone

+ Documentation

References:

Notes:

(1)

Not specified per FSAR; Conservative engineering

)udgement used based on operati accident environmental conditions.

(2)

Hot required per FSAR.

I

~

I

~ I I

I

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SYSTFBI QINPIRIENT EVALUATION ffORR SIIEET

~ r E9 Foci lltyl St Lucia Unit I Docket> 50-335 BY/DATE Clt/DATE R

E V I S I 0

N BY

(.

DATE~~

>A>>>~IILY'I8 EGUIPHENT DESCRIPTION Systcsu Various D15,D1 7,D2 4 D2 5>D2 7>D2+)D2+)DM>D2 10)D3 3>

D3-5)D34)D3-7,D3-8>D3-9D3-10)D3-11)

D3-12,D4-'2,D44,D4-7 jD3-4) Q.I.

I EINIROIUIEN1 Operating Tfa>e 1 Year 1 year Paraactcr

'pcclflection; Itunttfication Spcclflcntion FSAR Section 3.11 Qualification UUCUNEHTATION REFe IIUAI.IFICATION HETIIUD Sinutnncous Test plus Analysis

.(See ttote 2)

OUTSTANDING ITENS ttonc Coc>P neat:

Electrical Cables Nanufacturcl Gcncral Cable (FIRELLX)

I>>) eeoc>>.uu,)))>,

P.O..Order

>(I 422273.

Nodal Nua>bert Cross-linked Polyethylene vith PVC Jacket Tes)pcraturc

( F)

Pressure (PSIA)

Relative Nunidlty (X)

See httachnent I & II

,See Attache>ends I f) II 50 FEAR Table 3.11-1 Figure 6.2-12&14 FEAR Table 3.11-1 Figure 6.2-12&14 FSAR Table 3.11-1 Tested Sls)ultanc-ously with Pres-.

sure, Rtl &. Spray s

c ously with tcc)p>

IBt and spray.

cs enc ously with tcrrp pressure

& spray ttone ttone ttone Function:

Accuracy:

Spec:

N/A Dcaonl N/h Service>

Various control, lov energy and coeatunlcatfon circuits Ches>Ical Spray Radiation Boric Acid 1720-2450 oo>a

)

pN B.5-10.5 0.24-0.S4 vtX NaON See Attach>)cnt I ron c

2000 PIII 5x10 FSAR Table 6.2-22 FSAR Table 3.11-1 es c>>

1 anc ou~ with pres-sure tc>cp & RH (Sce ttotc 1.)

Sc)tuential Test None ttone I~cation>

Various - Inside and Outside Contalnnent Flood Level Eleve 27.3 Feet Above Flood Level)

No Aging Sub))sr ging 40 yrc 200 days - 150'L 951 days - 90 C Engineering Analysis (See ttotc 2)

Test None

• Oocu>>>entatlon

References:

l.

St~1 Rualif. Data for General Cable Co. Cable (FFg 28) 2.

Gcnora1 Cable Certified Teat Rcport (FF//l5C) 3.

Gcncral Cable Letter Dated 32/17/1974 (FEAR Attactrccnt 3 to appendix 3A, pnrt D) (PFPS9)-

Notes 1)

F~ivalcncy docu>canted in Engineering Annlycis No. 1-15 2)

Iiualification catat>lished by EnginccrinG Analysis g E-9.

WYi I-S S-T I I

/7'EA FF, SYSIEH COHFOHEHT EFAIHATTOH IIOIIK SIIEFT Docket:

50-335 R

E V I S

I 0

N F ilic Sc LE I U it 1 'H BY 0

~ ~.

CHECK BY DATE~EL hl DO DATE t ~'

Page 1 of EQUIPHEHT DESCRIPTIOH System:

Aux Feedwater Plant ID Ho, Aux Feedwater Pump No.

1A fH 1B Parameter Operating Time ENVIRONMENT Specification 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Sce Note (2)

Qualification 1000 hrs. +

Specification Qualification Section 10.5.3 Sce Note (2)

DOCUHEHTATION REF<

QUALIFICATION METHOD Sequential Tests lus Analysis ee Note (3)

OUTSTANDING ITEMS None Component:

350hp, 4000V, Class IE En-Temperature closed in an outdoor weather

( F) protected Type II outdoor enclosure Electric Motor 320 F for 95 secs 320 F for 1 Hour +

FSAR Appendix 3C equencial Tests lus Analysis ec Note (3)

Manufacture:

General Electric Company PO NY-422208.

Specification FLO-8770-289 Item 2 Model Number: GE5K811043A21 Serial No.:

1AGH8382410 1BGH8382409 Func cion:

AM Accuracy:

Spec:

N/A Demon:

H/h Pressure (PSIA)

Relative Humidity (X)

Chemical Spray

14. 7 100X Hot Required 14.7 psia 100X FSAR Section 3.11 FSAR Appendix 3C equential Tests lus Analysis ee Note (3) equential Tests None None None Service: Auxiliary Fcedwater Pump Radiation Not Required 5 X 10 Rads Sequential Tests Plus Analysis See Note (1)

H*

Location:

Steam Trestle Area HELD brea per FSAR Appendix 3C Aging Hot Required None Flood Level Elev:

Above Flood Level:

Submerging Hoc Required None O'K Documentation

References:

1.

Topical Report IEEE-323 Class IE Induction Motors Hodels 5K828840C81 and 5K811043C16 Horizontal Class B Insulated

January, 1977 (FFS102).

~ 2. Tooical Ho.port IEEE 323 Class IE Induction Motors HH ls 5K828840C81 and 5K811043C16 HOrizontal Class 8

.sulated May 1979, Rev.

1 (FFI102A).

Notes:

(1)

As reported in Reference 1, the lowest damage threshold for any material is 5 in motor construction.

(2)

FSAR Scccion 10.5.3 indicates maximum 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> post reactor trip and Section 16.4 indicates monthly tests for 15 minutes (0.25 hr X 12 mos.

X 40 yrs.

~ 120 hrs).

mo.

yr.

(3)

Engineering worst case Judgement estimate 1 worst case coolf per year for f years (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s/yr.

X 40 yrs.

~ 320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br />).

Total operating tHAne 440 hours0.00509 days <br />0.122 hours <br />7.275132e-4 weeks <br />1.6742e-4 months <br /> u.

1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> to include significant margin.

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32 9/6/74 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT I CONTAIN~"-'il AT'IOSPHERE

& SL~P MATER TEMPERATURES VS TM FOR 0.5 ET2 SLOT BREAK FZCURE 6. 2-133

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