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

FLORIDA POWER 8 LIGHT COMPANY vI p."g l( p(i February 6, 1981 Mr. James P. O'Reilly, Director, Region- II Office of Inspection and Enforcement gpss/p@'8(~

U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 e

Dear Mr. O'Rei lly:

Re: RII:

-335 u letin'79-01B (Supplement 3)

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

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'J F~

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FLORIOA POWER Il LIGHT COMPANY INTERFFICE CORRESPONDENCE LOCATION Miami, Florida TO R. E. Uhrig OATF February 3, 1981 FRQM A. DE Schmidt COPIES TO K. N. Harri s D. K. James suoJFOT: ST. LUCI E UNIT 1 R. R. Jennings IE BULLETIN 79-01B (Supplement 3) 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 NRC BU~TW 79-01B No.:. 50-335 'ocke,t MASTER. LIST (Class IE Electrical EquiPment Required to =unct'on Under Postulated Acc.'dent Conditions)

RCS SVSm:

1-16 COMPONENTS Location Occurrence Plant ID Inside Outs ide CES No. Generic Name Containment Containment PA f No. Notes FE-1402 ccelerometer 1I55 ardline cable lI56 ith associated FE-1402 cable 'oftline assembly FT-1402 Charge Conv l?57 100"3A Cable E9 B5 P enetration E2 10083A Cable E9 FE-1404 Accelerometer 1I57 Manuf Cabl Hardline" cable lI56 or with associated FE-1404 softline cable assembly fanuf Cable Hardline~le ror with; associated FE-1404 softl' assembly T-1404. Charge Conv lI)7'

Fa~li~: St L cie Unit 50-335

.. RC ZULL"Tel.79-0V Doc1 No.: ~ 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 Inside Outs ide CES No. Generic Containment Contai~nt '.io. Notes FE-1200 Accelerometer 1I55 Manuf Cabl Hardline Cable 1156 wa n associate FE-1200 softline cable assembly FT-1200 Charge Conv lI57 FE '3l Accelerometer 1I55 Manuf Cabl Hardline cable 1I56 for with associated FE-assembly FT-1201 Charge Conv 1I57 FE-1202 Accelerometer X 1I55 Manuf Cabl Hardline cable lI56 wa. assocxa e FE-1202 softline cable assembly FT-1202 Charge Conv 1I57 I

I

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12-3 Facility: St Lucie Unit 1 NRC BULLETIN 79-01B Docket No.: 50-335 MASTER LIST, (Class IE Electrical Equipment Required to Function Under Postulated Acc'dent Conditions)

.-.SYSTEM:, AUXILIARYFEEDWATER'YSTEM COMPONENTS Location Occurrence Plant ID Inside Outs ide CES No. Generic Name Containment Containment No. Notes

Pump IC Turbine 1C X Delete Rl E24 B-102B Local Control PNL 12M05 C12-7 E6, 10631K Cable E9,E29 D3-11 E6, 1063 lH Cable E9,E29 4 7 coca est us B<<1665 Button Station 12M06 10631N Cable E,

E9,E29 D3-11

" 103B Signal Conv &

12M07 k3,'Z29 D4-7 Turb Trip & Throttl 12M12 Turb Tr'ip & Throttl B101B 12M08 E14 B-100B 10631M Cab E6 D10-44 R2 Cable from Turb by Mfr ri & Throttle va 12M16 V Aux FWP 1C I-MV-09-11 D ch 12M09 E6 E9 12M09 E6 E9 E29 ocal Push E17 C10-3 E6 E9 3 7

Facility: St Lucie Unit 1 NRC BULLETIN 79-01B Docket No.: 50-335 MASTER LIST (Class IE Electrical Equipment Required to Function Under Postulated Accident Conditions)

SYSTEM: AUX FEEDWATER SYSTEM COMPONENTS AUX FW TURB 1C Location Occurrence Plant ID Inside Outs ide CES No. Generic Name Containment Containment No. Notes rLp LS2 Lim Sw 12M-14 y MFR Cable 12M-16 0638A Cable E-29 Trip VA Lim Sw 12M-13

'FR Cable 12M-16 0638B Cable E-6 S3 Mech 0/S SW 12M-15 y MFR Cable 12M-16 0638C . Cable E-6

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

SYSTEM COHPOHENT EVALUATION WORK SIIEFT Piacci DATE:~II>%

Facility: St Lucia Unit 1 Docket: 50-335 CIIECK BY: OATK:~L 12H13 r

ENVI RODENT DOCUHEIrfhTIOH REF*

QUALIFICATION OUTSTAHDINC EQUIPNENT DESCRIPTION NETIIOD ITEHS Parameter Specification Qualification Specification Quail ficatl on System: Auxiliary Fccdwater System Operating 4 llours Plont ID No. (For Aux FH Pump 1C Time Turbine) See Notes (2) 6 Sec Note (3) See Notes (2) & See Hote (3) . See Note (3) Hone

~ (4) (4)

Component: Turbine Trip and Throttle Temperature 320 F for 95 sec FSAR Valve Limit'witch LS-1 ( F)

See Note (3) See Note (3) Appendix 3C See Note (3) See Note (3) See Note (3) Hone Nanufacturc: National Acme Pressure (PSIA) 14 ' See Note (1) FEAR See Note (1) Hone Section 3 11 Node 1 Number: AE-17035100 Relative Humidity (7.) IOOX See Note (1) FSAR Appendix 3C See Note (1) Hone Function: Accident Honitoring Accuracy: Spec: N/A Chemical Demon: Spray Hot required Hone Service: Auxiliary Feed{ster Pump Radiation IC Turbine Hot Required Hone Incarlon: Stcam Trestle (Floor EL 19. )ging Turbine C.L. is 3'-8" Above Not Rcquircd Floor Level Flood IA'vel Elev: Not Applicable Submerging Above Flood Level: Yes No 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.

~

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(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

SYSTEH COHPONEHT EVALUATION MURK SHEET BY: o CLEAL DATE~IZC/Zr Facility: St Lucia Unit Docket: 50-335 1

CllECK BY: DATE~lr 12H14 ENVIRONHFNT DOCUHfHTATION REF*

QUALIFlCATIOH OUTSTAHDING EQUIPHENT DESCRIPTION HETNOD ITDLS Parsmctcr Specification Qualification Spccificntlon Qualification System: Auxiliary Feedwater System Operating Plant ID Ho. (For Aux FW Pump 1C Time 4 hours Turbine) See Notes (2) 6 See Note (3) See Notes (2) 6 See Note (3) Sce Note (3) None (4) (4)

Component: Turbine Trip and Throttle Tcmpcraturc Valve Limit Switch LS"2 ( F) 320 F for 95 Secs Sce Hote (3) FSAR See Note (3) Appendix 3C See Note (3) Scc Note (3)

Sce 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 i ty (X) 1002 Sce Note (I) FSAR Appendrx 3C Sce Note (1) None Function: Accident Honitoring Accuracy: Spec: N/h Chemical Demon: Spray Hot Required None Scrvlcc: Auxiliary Feedwater Pump Radiation Not Required

• 1C Turbine

~

Location: Stcam Trestle (Floor El 19 5) Aging Turbine C.L. is 3'-8" Above Floor Level Flood Level Elev: Hot APPlicable Submerging Hot Required'one Above Flood Level: Ycs Not Required Hone No

• 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 300oFis experienced.

(IE) From Figllre 10.5-1 in FSAR, RCS rs cooled down to 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.

SYSTEII COHI'ONENT EVhI,NATION WORI: SIIIIFT DATE~I/2D 8/

Foci ll.ty: St Lucio I!nit I Dock;ct: 50-335 CHECK BY: DATE II I 12H15

'

- ENVIRUI'IIEHT DOCUHI:.STATION PZFo Etlt! IPIIENT DESCRIPTION tlt'h LIF ICh TI OH OUTSTAND1 litt Pa rome tet Sp<<c I C. I ca t i on Quail CI<<at I~ >> SpeciCI<<ation tkoalification kkETIIOD ITEk!S System: Auxiliary Fcedwatcr System Operating Plant 1D Ho. (For hux FW Pump 1C Time 4 bours Turbine) See Notes (2) 6 See Note I".t See Notes (2) 6 See Note (3) Sce Note (3) None (4) (4)

)

Component: Turbine Trip and Throttle Temperature Valve Limit Switch LS-3 (op) 320 F for 95 Secs See Nots FSAR See Note (3) Appendix 3C See Note (3) See Note (3) None See Note (3)

!

Hanuiartur<<: National Acme Pressure (PSIA) 14 ' See Note (1) FSAR Section 3.11 See Note (1) None

• Nod<> Above Not Required Floor Level None Flood Level I.'cvt Not Applicable Submerging Above Flood Level: Ycs No Not Requtred None

• Documentation

References:

Notes:

(I) Prcssure and humidity are not considered significant parameters for evaluation.

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

(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.

(4) 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.

SYSTEH COHPONENT EVALUATION WORK SIIEET BY: cAPn,m.a!~ DATE: I/Zc/S Facility: St Incic Unit 1 Docket: CIIECK BY: DATE~i (nl 12HI 6 ENVIROIIHENT DOCUHENTATION REF*

EQUI PHEHT DESCRIPTION QUALIFICATIOH OUTSTANDING Parameter Speci f les t ion Qualification Specification Qualification HETIIOD:, ITEHS System: Auxiliary Feedwater System Opera ting 4 Hours Plant ID No. (for Aux FW Pump 1C Turbin ) Time See Hates (2) & See Note (3) See Note (3) Hone (4) See Note (3) See Notes (2) &

(4)

Component: Turbine Trip and Throttle Temperature FSAR Valve Limit Switch and ( f) 320 F for 95 Solenoid Valve Cable Secs See Note (3) Appendix 3C See Note (3) See Note (3) See Note (3) See Note (3) Hone Hanufacture: Principal Vcridors Prcssure Byron Jackson (PSIA) 14. 7 See Note (1) FSAR Turbine: Terry Steam Turbine Section 3.11 See Note (1) None Corp (5)

Hodcl Humbcr: Scc Note (5) Relative Ilumidity (7) 100X See Note (1) FSAR= See Note (1) Hone Function: Appendix 3C Accident Hitigation Accuracy: Spec: H/A Chemical Demon: Spray Not Required None Service: Auxiliary Feedwater Pump Radiation 1C Turbine Hot Required Hone Location: Steam Trestle (Floor El 19.5 Aging Turbine C.L. is 4'-2" Above Floor Level Not Required None Flood Level Elev: Not Applicablc Submerging Above Flood Level: Yes No Not Required None

• Documentation

References:

Note: (1) Pressure snd humidity are not considered significant parameters for evaluation.

(2) Not specified pcr FSAR; conservative Engineering Judgement, pcr FSAR 10.5.3.

(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.

(4) 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.

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

nl i ~ (3 ('IL!

r q 'r;~y5 SYSTFM COMPONKHI': CATION HOIU: SIICE"r

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/rb 3r~ Sids/n 17M-10 BY/DATE Cll/DATE BY ( DATE Facility: St Iacic Unit 1 Docket: 50-335 - r ~-r' -$ 0.80 C11ECK BY w. DATF .s R E V I S Z. 0 N

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ENVIRONMENT REF- ~

QUALIFICATION OUTSTAHDIHO  !

EQUIPMEHT DESCRIPTIOH 'l METIIOD ITEMS parameter Specification Qua 1 1 f1 col 1 on Speclflcnti.in Qualification (4)('OCUMENTATION System; Contalnmcnt Purge System Operating l~

I.

c Plant ID Ho. ZS-25-10 and ZS-25-11 Time 15 Min . See Note (4) FSAR See Note See Note (4) <

for Valve I-FCV-25-5 3.11.1.3b None Component: I.lmit Switches Tempo tn Lure 0 L tt l.

(OF) 150 . See Note (4) FSAR See Note (4) See Note (4) None Manufacture.: National Acme Co. Prcssure (PSIA) FSAR 14.7 See Note (1) Section 6.2.3 Seo Note (1) None Model Number: D2400X Relative 100X Post-LOCA Humidity (X) Below 70X after FSAR 2 mtns. See Note (1) See Note (1)

Section 6,2 3 None .

Function: Accident Mitigation Accuracy: Spec: N/A Cbcmf ca I Demon: Spray Hot Required None Service: Containmcnt Purge Isolation Valve I-FCV-25-5 54'adiation 4.5 ee Notes 5

N 10 Rads (2)6(3) 6 10 Rads See Notes (2)&:(3) See Note (4); t See Note (4)

None

~cation: Annulus Elcv. Aging Not Required Hone Flood level Elcv: H/A Submerging Hot Ab ovc Flood Lc vc 1 1 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.

b7-3:XII fX 13/ ds

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Factlttyt St Lucia Untt 1 BY/DATE II CH/DATE

>so SYSTEH COHPONENT EVALUATION MURK SIKET BY V /':

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Docket: 50-335 CHECK BY R F y I 5 I 0 N RE,-CIIeCKFsn u8/ p+YC( 5:+~//J 1I17 I

ENV RONNE HT DOCUHEHTATION REF*

Qlh LlF ICATION OUTSTANDING EQIIPHENT DESCRIPTION ITEHS Parameter Spcctftcatton qua II ftea t i on Spectftcation 'ualification HETIIOD Systemt Reactor Coolant System Operating Plant ID Ho. TE-1112CA Time Sec Scion See Bcluv Scc Bc)ou Nono Scc Note (I)

Component: Temperature Element Temperature Scc F SAR

( F) Attaclusent Sce Note (3)

Table 3 11-1 Ftg 6,2-12 & llI See Note (3) 'cc Note (3) None I &II Hanufscture: Roscmount Pressure s Sec FSAR (PSIA) h [ cp chmcnt Sce Nato (3) None Scc Note (3)

I &II Sce Note (3) T blc 3.11-1 Fig $ .2-12 & 14 iHodcl Number t 104VC Rolative PSAR Serial Humbert See Note (3) See Note (3) 5ce Note (3) None 57147 Humidity (2) Table 3.11-1 Functton: AH Accuracy: Spec:+ 52 (Note 2) Chemical 1720-2450 Demons (Note 3) Spray PPH of Boron Cce Note (3) PSAR See Note (3) See Note (3) Nona PII 8.5-10.5 Table 6.2-22 0.24-0 8 Mt%

~ NaOH Servtco: RPS- Reactor Coolant Radiation A Scc A)tschmcnt Soc Note (3)

Temperature Loop IA2- Cold Le See Note (3) Scc Rotc (4) Sce Note (3) See Note (3)

& Input gc,gubcooltng Margin/

Honttor/Rev 3.

nstdc Containment; Locattont Loc on Dtsch Pipe of RCP-IA2; Aging un Top Section of Ptne 30" Sce Note (3) Scc Note (3) None RC-115, 1'-0" from Center 40 Years 40 Years Assumed Line & 5'-6" from Primary Shield Mall at Kiev of Level Elcv: 27.3'ax.

29'A'lood Submerging Above Flood Level: Yes-Not Required None

• Documentation

References:

Notes:

Conservative enginccring judgement indicates that thc Subcooling Ha'igin Honitor I

((I) requires this sensor input as long as the plant is in hot standby..

/> J' /s! /." (2) FSAR 3.112 (s)

(3) Qualification established by Engineering Anat~ate No. 1.24.

BY/DATE CN/DATE ((4) Utitiatng Large break LOCA radiation doses> td.k R E y I S I 0 N

"I II

2 /r/7 y.gn'go g4. 7>/g0 PV SYSTKH COMPONENT EVALUATION WORK SHEET BY DATE BY/DATE CH/DATE Facility: St Lucia Unit I Docket: 50-335 I I ance sv.KI~&ew'ip'aTe~azs R K V S 0 H C1dCCKC-d3 fbY Cif~/ A,Y ~ 5 1o'io lrc'6-lllg ENVIRONMENT DOCUHF NTATION REFs OUTSTANDING QUALIFICATION EQUIPHKNT DESCRIPTION METHOD ITEMS Foram'ster Specification Qualification Specification qualification Sys<<m: Reactor Coolant System Operating Plant ID Ho. TE-1122MB Time 30 Days Scc Below Sca Note (1) Sea Below Seo Below None Component: Temperature Element Temperature Sco Attachments FEAR Scc Nota (3)

Sec Nota (3) Sec Note (3) Hone I & II Tablo 3.11-1 Fig 6.2-12 1k 14 Manufacture: Roscmount Pressure Sch (PSIA) Attac1vacnts FEAR Scc Nota (3) Sce Note (3)

I & II I Sec Nota (3) Table 3.11-1 Fi 6.2-12 5 14 None Hod I Numb Serial Nuekei: 57165 Relative lkusidity (2) FEAR Scc Note (3) Table 3.11-1 See Note (3) Sce Note (3) None Function: AM Accuracy: Spec: + 52 01ote 2) Chemical 1720-245P Demon: (Hots 3) Spray PPM of Boron FEAR PH 8 '-10.5 See Nota (3) Table 6.2-22 Sce Note (3) See Note (3) None 0.24-0.8 WtX HaOH Service: RPS- Reactor Coolant cmporsture Loop IB-Hot Lcg

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

Radiation

( Sce Attach-ment I See Nore (3) Sca Note (4) Sec Note (3) See Note (3) ( Sec Note (3) )

Location: Loc on Top r/f-11" Inlet to SC 18of Aging from Reac 1 from C.L. 40 Years 40 Years Assumed Pipe snd 1>-8" from Primary Sec Note (3) Sca Note (3) wane Shield Wall> El 13'-8" above Floor El 18 -0" in RCB Plood Lovel Klcv: 27.3'1ax, Submerging Above Flood Level: Ycs None Hot Required

• Documentation

References:

~

Notes:

(1) Conserva t xvu c.n1,rueerrug dudgemmnt rndrcatesplant that the Subcooling Hargin Monitor >

1/ r(c. requires this sensor input as long as the is in hot standby.

p) IIH f~ 1 (2)- 1'SAR 3.112 (o). No. 1-24 (3) Qualification established by Engineering Analysis >

BY/DATE 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 tQ. BY/DATE Cll/DATE BY V l u lI. 5 DATE~3~D":U I

Facility: St Lucic Unit 1 CIECK BY Docket: 50-335 R E V I S I 0 N l 1 19 ENVIRONHENT DOCUHEHTATION REF*

QUALIFICATfON OUTSTANDING EQUIPHENT DESCRIPTION ttuaffffcatfon Specification 'tualfffcatfon HETHOD I TENS Pgrnmcter Specificatfon System: Reactor Coolant System Plant ID No. TE-1122CA Operating Tice 30 ~Days See Below See Note (I) 'ee Below Sec Below Hone Component: Temperature Element Temperature See PEAR Attachment Table 3.11-1 Scc Note (3) None Sce Note (3)

I& II Sce Note (3) Figure 6.2-12 &

14 Hanufacturea Roscaeunt Pressure , Sce FEAR (PSIA) ht taclnaent Table 3.11-1 Sec Rotc (3) Scc Note (3) None 5&II Sec Note (3) Figurc 6.2-12 &

14

!Nodal Numbera 104VC Relative FEAR Serfal Nushera 57151 Humidity (Z) 100Z Table 3.11-1 See Note. (3) Sec Note (3) None Seo Note (3)

Functfon: AH Accuracy: Spec: +5K (Note 2) Chemical 1720-2450 FSAR Demon: (Note 3) Spray PPH hf Boron Table 6.2-22 Sce Note (3) Scc Note (3) None PH 8.5-10.5 See Note (3) 0.24-0.8 WtZ NaOU Service: RPS - Reactor Coolant Radiation Tcmperatqre Loop 181 - Cold ee httschaen Sce Note (3) See Note (4) See Note (3) Sec ltote (3) P Sce Note (3)

Lcg angdlnput Io SUBCObl~itli 3,

~Hargtta ttonf tor+(7~

Inside Contalnaent Location: Loc on Disch Pipe of RCP-181 Aging None to Reactor, Inside Prfmag 40 Years 40 Years See Note (3) Scc Note (3)

Assumed Shiold Wall at Elev 29'-6 '.

Quad IV flood Level Elevt 27.3'ax. Subae rging Not Required Above flood Level: Yes None

• Documentation

References:

Notes:

Conservative engineering judgement indicates that the subcooling Hargin tlonitur

( (1) requires this sensor input as long as the plant is in hot standby/

'l )f/iz'z /t ( (2) I'SAR 3.112 (a)

(3) quafificatiou established by a".wsiuvering analysis tto. 1-24.

BY/DATE CH/DATE

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

R E V I S I 0 H

&D i W$'0 ll 7a',>,

I/- -. I /rf'",cI

/'- SYSTEM COMPONENT EVAUIATION WORK SHEET I BY/DATE l Eul Facility: St Lucis Unit Docket: 50 335 1

VIS IO CN/DATE CHECK BL  ! 74rrADATE~J>O 1120

-

EHVI ROIOIENT DOCUMENTATION REF* OOTSTAHDINC QIALIFICATION EqOIPHEHT DESCRIPTION HETIIOD ITEMS Parameter Specification Elualificstion Specification Qualification System: Reactor Coolant System Oporsting Plant ID No. TE-1112IIA Time (30 Days/ Sce Note (I) See Belou Sce Bclou Nona See Bclou Component: Temperature Element Temperature Scc FSAR

( P) Attachment 'lablc 3 11 1 I I &II See Note (3) Fig. 6,2-12 & 14 Sce Note (3) See Note (3) Hone Manufacture: Roscmount Prcssure Seel FSAR (PSIA) Attachment Table 3.11-1 See Note (3) Scc Note (3) None 16 II. Sec Note (3)

Fig. 6.2-12 & 14 IMod el Number Relative FSAR Serial Nunhert 57161 ltumidity (2) Table 3. 11-1 See Note (3) See Note (3) None Sec Note (3)

Punction: AH hccurscyI Specs+ 5> (Note 2) Chemical 1720-2450 I Demon: (Hate .I) Spray ppH of Boron FSAR Sce Note (3) See Note (3) Hone Sce Note (3) Table 6.2-22 PII 8 ~ 5-10.5 0.24-0 ' WtX NaOII ScrviceI RPS - Reactor Coolant Radio t ion Temperature Loop IA - Not Leg (3) snd/Input to Subcoolrng Ha@gin Sec Attachmcn~t I See Note (3) Sce Moto (4) See Note (3) See Note Scc Note (3) )

(Monitor) P g P.5 Inside Containment Location: Loc on Inlet to SG-IA Top Aging Sect. of Pipe I'-ll" from 40 Years 40 Years Assumed (3) Sce Note (3) None C-Lof Pipe & i'-La frcxa Sce Note Primary Shield Walll 13'-8" above Floor El 18'-0" Flood Lcvcl Kiev: 27.3'ax. Submerging Above Flood Level: Ycs Not Required None

• Documentation

References:

Notes:

I r(I) Conservative engineering judgement indicates that thc Subcooling Margin Monitor 7 rcquircs this sensor input as long as the plant is in hot standby/ fv Q (2) FSAR 3.112 (a)

~

1() I//I IT l)ilogjt (3) . Qualification established by Engineering Analysis No.1-24.

'(4) Dtilising large break LOCA radiation doses.~ P $

BY/DATE CN/DATE R E V I S I 0 I

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~ 7 lg pg SYSIXN COHPONENT EVALUATION WORK StlEET

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BY 7 DATE BY/DATE Facility: St Lucie Unit I CN/DATE

+Z6~8~

Docket'0 335 CHECK BYF<~~~W c 74u 4 DATE R E V I S 0 N 1ZL CBEClCGI3 6\ dtdi 8'n d'o tl2t ENV IRONHENT DOCUHENTATION REF*

QUALIFICATION OUTSTANDING EQUIPHENT DESCRIPTION ITEHS Paraictcr Specification Qualification Specification 'ualification HETIlOD System: Reactor Coolant System Operating Plant ID No. TE-1112CB Time See Below ttonc Pso nay See Below Scc ttote (1) See Below See FEAR Component: Temperature Elcmcnt Tcmporature (OF ) Attachment Sce Note (3) Table 3.11-1 Sce Note (3) Sec Note (3) None IS II Fig 6,2-12 g: 14 Hanufscture: Rosemount Prcssure Sce FSAR (PSIA) ht tacttpcnt See Note (3) Sec Note (3) Sec Note (3) ttone I &II Fig tz.2-12 Vc 14 tHode1 Number: 104VC Relative FEAR Serial Nuaber, 57148 Humidity (2) See Note (3) Table 3.11-1 See Note (3) See Note (3) None Function: AH Accuracy; Spec: + 52 (Note 2) Chemical 1720-2450 FSAR Demons (Note 3) Spray PPH of Boron See Note (3) Table 6.2-22 See Note (3) Sec Note (3) none Plt 8.5-10.5 0.24-0.8 WC, NaOtt Service: RPS - Reactor Coolant Radiation Temperature Loop IAI - Cold See Attachment I Sce Note (3) Scc Note (4) Sec Note (3) Scc ttotc (3) ('Scc ante (3) )~z Lcg and.)input to Sugcooling}.

Hnnitozi P>

( Hargin inside Containmcnt; Location: Loc on Disch Pipe of RCP-IA1, Aging on Top Sect. of Pipe 1'-0" from CL of Pipe and I'-6u 40 Years 40 Yrnra Assumed Scc Note (3) Sce Note (3) Nnne from Primary Shield Wall; 13'-Ou above Floor El 18'-Ou Flood Level Elevz 27.3'ex. Submerging None Above Flood Level: Ycs Not Required

• Documentation

References:

Notes:

Conscrvatibe engineering judgement indicates that the Subcooling Haz'gin Honitnrp

((1) requires this sensor input ss long as tbe plant is. in hot standby./Q P (2) FSAR 3.112 (a) rib/ i/IO .Fq, <Jg (3) Qualification established by Engineering Analysis tlo. 1-24.

<(4) Utilizing large brcak LOCh radiation dozes. P Q io. BY/DATE Ctt/DATE 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 BY DATE BY/DATE CN/DAZE Facility: St Lucic Unit I Docket: 50-335 CHECK B'I @ .~~ ~94'~4'ATE R E V I S I 0 N Qg- C HEC V.rage Oa TC S'.<<< ~d 1122 ENVI'RONHENT DOCVHENTATION REF*

qVALIFICATION OUTSTANDING EQUIPMENT DESCRIPTION ITFHS Para<setcr Specification +a ltfication Specification 'ualification METHOD Systcs<: Reactor Coolant Systc<s Operating Plant ID No. TE-1122CB Ti<<<e See Belou See Note (1) Sce Belou See Belou None Co<<<poncnt: Te<<<pcrature Elc<acnt Tcs<perature Scc FSAR (OF) Attach<<<cnt See Note (3) Table 3.11-1 Sce Hots (3) See Note (3) None I 6< II Fig 6.2-12 & 14 Manufacture: Rose<<<cunt Pressure See (PSIA) Attaph<<<ent FSAR I 4 11 See Note (3) Table 3.11-1 See Note (3) See Note (3) None Ig>> 6<2 12 6 14

~Model No<<<her: 104VC Rcla tive Ituc<<idity (2) ...,1002 FSAR Serial Nu<<<ber: 57152 Sce Note (3) Table 3.11-1 Sec Note (3) Sce Nota (3) None Function:

Accuracy: Spec: "+52 (Note 2) Chc<<<ical 1720-24/0 FSAR De<<<on: (Hote 3) Spray PPH of Boron Table 6.2-22 PH 8.5-10 ' See Note (3) See Note (3) Sce Note (3) None 0.24-0.8 Nly. Na Ol Service: Rpg - Reactor Coolant Radiation Tc<<<pcrature Loop IB2 Leg and

- Cold

.input'tb Subcoofing)

A<<>><<l >> <

Sce Nota (3) See Note Soe Note (3) Sec Note (3) ------<<V Scc Rotc (3) )

)

(Hsigin Honitor')P 4;

'Inside Containdc<lt Location: Loc on Disch Pipe1'-2" of RCP-192 Aging (4)'ssuacd on Top of Sect. fro<a g of Pipe, 6'-0" fro<s Pri- 40 Years 40 Ye~ra Sce Note (3) Scc Note (3) None Flood Levol Elev: 27 3< Max. Sub<<<erging None Above Flood Level: Ycs Not Required

• Deca<<<cntstion Rcfcrcnccs: 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 V/ //': '/ (2) FSAR 331 (a)

(3) Qualificatiou cstabiishcd by tngineering Analysis No. 1-24.

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

BY/DATE CH/DATE R E V I S I 0 H

2. ea/i//st fA Ifll<fff nR l/>>/FO 'f(ff 1@7 SYSTEII OOIITOIIEET ETAUIATIOE SOEE SIIEET I

Facility: St Lucfe Unlc I NO BT/DATE CH/DATE By (-U 2 Pu rl/r.rr5'ECK DhTE +A 80 Docket: 50-335 BTP'd~l~ You DATE J/2 6 C R E V I 8 I 0 N Rc- 5 ado l 1133 I

ENV RONffENT DOCUHEllTATIOH REF e QUhLIF ICATION OUTSTANDIHC EQUIPHENT DESCRIPTION HETllOD ITENS Parameter SpeciffcaCion Qualification Specificacfon Qualification System: Reactor Coolant System Opere cfng Plant ID No. PT-1102A Tfmc Sec Belou dote (5) See Bclou Simultaneous None Testing Component: Pressure Transmitter Temperature See 320 -

-

I Hr FSAR Pfscher & Porter

( F) Accachslcflc 273 1.75 NL Table 3.11-1 Test Report Simultaneous 1&II 228 - 21 ~ 25 NL Ffg. 6.2-12 & 14 2204-51-B-006 Testing None Dated Occ 1968 Hanufacture: Ffschcr & Porter Pressure See 90 Psfa - 1Hr FSAR Fischer & Porter (PSIA) Actps)scent 60 Psia - 1.75Hr Table 3.11-1 TesC ReporC Simultaneous I &II 20Psia-21.25Hr Pfg. 6.2-12 & 14 2204-51-B-006 Testing None Daced Oct 1968 lHcdel Number: 50pp1041 (Note 3) Rclativo FEAR Fischcr 6 Porter I Serfal Number: 7411A2620A2 Humidity (2) IOOI Table 3.11-1 Test RcporC Simultaneous Steafa 2204-51-8-006 Tcscing None FuncCfon: AH, PAH Dated Oct 1968 Accuracy: Spec: +52 Chemical 1720-2450 15000 PPH Amcron Letter Simultaneous Demon: +3.52 Span Spray ppH of Boron Boric Acid FSAR Dated Nov 20 Testfng Hone pN 8.5-10 5 PN ~ 10 5 fa 77 F Table 6.2-22 '972 Plus Analypfs

~ 1 MCX NaON Note (2) 0.24-0.8 Mcy. NaOH Service: RPS - Pressuriser Prcssuro Radiation See FEAR Fischcr & Porter Sequential sndflnpuc to Subcooling Margin Honitor /p 2

) Atcachmcnt I

1.2x10 8

RAD Table 3.11-1 Test Rcport 2224-II004 Tescfng None Inside Concafnmcnt; Location: On Rack 53-16, Base of PT- Aging Same As For Simultaneous 1102A Loc,at 4'-6" above Floor EL . 40 yrs 40 yrs Assumed Temperature Testing Plus'. . None 62'-0"; 6'-10" frofa SE Corner of PRZR Plus Analysfs Analysis See Ease Mall & 8" from East Mall. Sce Note (1) Hoce (1)

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

• Documcncstfon

References:

Notes' (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 IEf. '

~ ~

.)

'Aping fl(LlSl ~

P q(~L gZ'YSTEM COMPONENT EVALUATION MORKSHEET M. BY/DATE CH/DATE I Facflity: St Lucia Unit N'137

~

Docket: 50-335 1

I CHECK BYE'l>>sf 0 2 V v,>Ca DATE j S<

R E V I S 0 H ENVIRONMENT DOCUMENTATION REF*

QIALIF I CATION OUTSTANDING EOUIPHENT DESCRIPTION METHOD ITEHS Parameter Specification 0uslfffcatfon Spcefffcntfon Oualificatfon Operating,- Simultaneous System: Reactor Coolant System 31 Days Testing Plant ID Ho. PT-1103 Tfme ~ None Sce Belou FSAR Sec Bolou Plus Analysis TABI/8 7.5-4 Note (1)

Pressure Transmitter Temperature - Note (1)

Component: See 320 F 1 hr FEAR Test Report

( F) Attachment 273 F - 1.75hr Table 3.11-1 Fischcr & Porter Simultaneous Hone I 6 II. 228 F - 21 ~ 25hr Fig. 6.2-12 6 14 2204-51-B-006 Tcstl.ng Dated Oct 1968 Plus Analysis Pressure psia- I hr Test Rcport Note (1) Hone Manufacture: Fischcr & Porter See 90 (PSIA) Attachment 60 psia-1 75hr FEAR Fischcr & Porter Simultaneous

~

Table 3.11-1 I & II 20 psia-21,25hr 2204-51-8-006 Dated Oct 1968 Testing Plus Analysis Fig. 6.2-12 & 14 Test Report model Number'0 Ep 1041BCHS (Note 3) Relative Ffsclicr & Porter Muwfdity (X) FSAR Scrfal No  : 7104A5544A95 Table 3.11-1 2204-51-B-006 Simultaneous 100X Steam Dated Oct 1968 Testing None Functfon: AN Accuracy: Spec:+5X (Note 4) Chemical 1720-2450 15000 PPN Amcron Lct ter Simultaneous PPH of Borak Boric Acid Dated Testing Demon:+3.5X Span Spray FSAR None PH 8 5-10.5 pH~10.5 La 77 Table 6.2-22 Hovcmbcr 20, 1972 Plus Analysis 0,24 0,8 MTX NaON .1 MtX NaOH Note (2)

Radiation I Service: Pressurircr Pressure Sec FSAR Test Report None (Lou Range) 8 Fischcr 6 Porter Sequential

,andflnput to Subcooling Margin Attachment I ~ 2x10 Rad Table 3.11-1 Tcstfnn I 2224-1 No. 004

( Monitor (( i y Inside Contafnmcnt Same As For Simultaneous Location:On Rack 53-16; Base of PT-1103 Aging Temperature 4'-6u above FL EL 62'-Ou 5'-9" Testing Plus None 40 yrs 40 yrs Assumed Plus Analysis Analysis See from SE Corner of PER East Sec Note (I)

Mall & 8u auay from ft. Note (1)

Flood Level Elcv: 27.3'ex Submerging None Above Flood Level: Ycs Not Requfred

• Documentation

References:

Note:

(I) Qualification Established by Engineering Analysis 1-16 (2) Qualff lection 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).

SYSTEH COHIVHENT EVALUATION NOkK SIIBFT

~/8~m /8 P/

v~

BY DATE Feel lity: St Lucia Unit 1 Docket: 50 335 CIIECK BY L ( m DATE I (L C l I55 ENVIROBHFHT DOCUHENTATION BKF*

QUAl IFICATIOH OUTSTANDLNC KQUIPHEHT DESCRIPTION Parawctcx' Spcciflrntiun Qun I I f I ration Speclflcntlou HETHOD ITDtg Qualification Sy<<cw: itcactor Coolant Systcw Operating Plant ID Hu FE-1402 Ti wc (I) 1202 15 win Sec Note BC 1.97 Bcv 2 Scc Hate (I) Scc Note (I) Sce Bute (I) 1404 Src Note (2) 1200 1201 Cowponcnt:Acccierowcter (Sensor) Tc ape rature Sce Attachecnt NURKC 0578 and

( f) Ill and Sce Note (I) 0737 See Note (1) See Note (1) Sec Note (1)

Note (3) FSAR Figure 6.2 11B KNDEVCO (TEC) Pressure NURKC 0578 and (PSIA) Sec Attachment See Note (I) 0737 See Note (1) Sce Note (I) See Note (1)

III and FSAR Table 3.11-Note (3)

Nodal Nuwbcr: 2273A Relative HUREC-0578 and liuwldlty (X) 100X Sce Rotc (1) 0737 Sce Note (1) See Note (I) See Note (1)

FEAR Table 3.11-1 function: PAN Accuracy: Spec: 31-5PC/8 Chcelcal 1720-2450 PPH of NUREC 0578 and Dewan:Sce Note (5) Spray Boron Sec liote (1) 0737 See Note (I) See Note (I) See Voce (I)

Serial No. Sensitivity (PC/ ) Pil 8.5"10.5 FSAR Table DK96 3.32 0.24-0.8WtX NsOli 6.2-22 DL23 3.33 Service:DR 21 'S ~ 63 3'32 ' '1 3 47 Radiation NUREC-0578 and PORV and SRV Position Sce Attachwcnt I See Hotc (I) 0737 Sec Note (I) See Hote. (1) Sec Note (1)

Indication and Note (4) FSAR Table 3.11-1 ication(nsidc Containment Aging KL 81'3/16" for FE 1402 & 04 40 years See Note (I) Assuwrd Scc Note (1) Scc Note (1) See Note (I)

EL 77'7/8" for FE 1200, Ol, 0 Flood Level Eleve Subec rging flood Level: 3'bove Yes Not rcquircd None

• Documentation

References:

Notes:

CII Final Qualification docuwrntation supplied by equipwent vendor (TEC) is expected by cnd of January 198L (5) Tested sensitivity (2) ln RC 1.97 Rcv 2 thc required operation purpose is to indicate operation status of the SRV's and PORV's to values werc verbally eonitor loss of coolant. Thc accident considcrcd is a stuck open PORV. 15 win post accident operating CP obtained frow TEC tice was chosen as on adequate tine, for thc operator to take necessary action such as closing the block and will be confirw- valve.

ed in writing. (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 POR'v. a Sonserva-tivc approach since this break isrsizably larger than a loss of coolant through a stucv. os n (4) This radiation is overly conservative since it utilizes largo brcal: LOCA source tcrws.

i 1

SYS1721 rXXNvlRENT EVAIllATION NuXK SNEET facility:50-33S St Luclc Unit I <<+/00 /tv<<< Ili<< ///~E/

Dock< t: ai<<<<<~LI'~<<<<~lt <<)

EIN I RONNENT EQUIP)AT DESCRIPTION OOCUNENTATIOil XFF>>

QUA LlfI GATI OW OUTSTANDING ttETI lOD ITQIS Parameter Spcclflcatlon Qual If i cat inn Spcclflcatlon Qualification System: Reactor Coolant System Opcfatlng RC 1.97 Rev 2 Plant I" No ~ Hanufacturer Cable for Time ,15 min Scc Note (I) Sce Note (2) Sec Note (I) See Rotc (1) S< c Note (1)

FE-1402, 1404, 1200, 1201 and 1202 ComPoncnt: Sensor Cables Tcmpcrature NUREC 0578 snd (of) Sec Attaclusent III and Src Note (1) 0737 FSAR Figure Sec Note (1) See Rotc (I) Sec Rotc (1)

Rotc (3) 6.2-118 Nanufacturc: TEC Prcssure (PS LA) See Attaclmiqnt NUREC 0578 and III and N:c Note (I) 0737 See Note (I) See Note (I) Src Note (I)

Note (3) FSAR Fig. 6.2-11 TEC 2273-Cl Assembly Rc lative 0578 and (2) 1002 Si <'ote (1)

NUREC (Edevco 3075-H6 Coaxial hard lb<midi ty 0737 See Note (I) Sec Note (I) See Note (I) line cable and thc RC-195A/U FSAR Table Function: softlinc coaxial cable) 3 ~ 11-1 PAN Accuracy: Spec: N/A Chemical Boric Acid, NUREC-OS78 and Dement N/A Spray 1720-24SOppm Scc Note (I) 0737 Sec Note (I) Sec Note (1) See Note (1)

PN 8.5-10.5 FEAR 0.24-0.84MtX NaO Table 6.2-22 Service: Connects TEC acoust ical Rad la t ion Sec Attachment < NUREC-0578 snd sensor with the charge and Rotc (4) Suc Note (1) 0737 Sce Note (1) Sce Note (1) Scc Note (I) converter FSAR Table 3.11-1 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 Submcrglnp, Abovu flood Level: Ycs 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 Docket: 50-335 1 EY~OPCCo.g~

CllECK DY

~~ DATE DATF. \

gP i I 1I ENV 1 RctalFNT DOCUHENIATION RFFn OUALIF1CATION ONTSTANDlNC El}UIPHENT DESCRIPTION HETHOD Paracoctcr Specification Qualification gpeclflcntlon quail f Ication IT@IS Systccu Reactor Coolant System Operating RG 1.97 Rev 2 Plant ID No. FT-1402 1202 Tine 15 min See Note (1) See Note (2) Sec Note (1) Sce Note (1) Sec Note (1) 1404 1200 1201 Conponent: Charge Converter Tesperaturc NUREG 057S, an (preamplifirc) ( F) See Attachmen Sec Note (1) 737 and FSAR See Note (1) Sec Note (1) See Note (1)

III Figure 6.2-118 And Note (3)

Manufacture l TEC Pressure NUREG-0578, an (PSIA) See Attachment Sce Note (I) 0737 Scc Note (1) Sce Note (1} Scc Note (I)

III and Note And FSAR (3) ~

Figure 6.2-11 Hadal Nosher: TEC Model 500 Relative NUREG 0578 and Humidity (2) 100% Sec Note (1) 0737 See Note (1) See Note (1) See Note (1)

FSAR Table Function: PAM 3.11-1 Accuracy: Spec Jlbsolute accuracy Chemical 1720-2450>PPM NUREG 0578 and f5% (0-185 F) S pray of Boron See Note (1) 0737 See Note (1) Sce Note (1) Sec Note (1)

Denoal + IX Note (5) Pll 8.5-10.5 FSAR Table 0.24-0.8Wtg Na ll 6.2-22 Service: PORV and SRV Position Radiation See Attach" HUREG-0578 and Indication ment I cc Note (1) 0737 See Note (1) Sec Note (1) Sec Note (1) and Note (4) FSAR Table 3.11-1 Location: Inside Containment hg,lng Ef 66'-6" for FT 1402 4 40 years ee Note (1) Assumed Sce Hote (1) See Hote (I) Sce Note (1) 1404 EI 67'or FT-1200, 1201 41202 Flood Lcvcl Elevl 27.3'ax Subne rg lag Above Flood Level: Yes Not Required None

.)'5)

• Docnannratlon

References:

Notes:

Tested sensitivitY 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 values vere verbally to monitor loss of coolant. The accident consblcred is a stuck open PORV. 15 min post accident opera+

obtained from TEC and tiag tine vas chosen as an adequate time, for the operator to take necessary action such as closing, the vill bc confirmed in block valve.

vriting. (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.

4' t

~ ~

~P~~ 7 / /de

.-l) l-l~-f9 <i~ .'.76 Jn SYSTEH COHPOHEHT EVALUATION WORK SHEET Facflfty: St Lucia Unit 1 BY/DATE CH/DATE Y u l V if/&5 I DhTE <-~+"~+

Docket: 50-335 CHECK BY grlCr J .~<'v/4DhTE R E V I S I 0 N 1511 ENVIROHHEHT DOCUMENTATION REF*

QUALIFICATIOH OUTSTANDING EQUIPMENT DESCRIPTION Pa rome to r Specification gualf f ication Specfffcntfon Oua lifI cat fon HETHOD ITFHS System Hydrogen Control System Operating 1 Year Plant ID No. Tfme See Belch Sce Note (1) WCAP7709-L Simultaneous Suppl.2, 3, 4 Testing None Component: Hydrogen Recombfner Tempera Cure (OF)

WCAP7709-L Simultaneous FSAR See Attachment 1700F Suppl.2 . Testing None I & II Table 3.11-1

~500. Mrs Ffg. 6.2-12 & 14 Manufacture: Westinghouse Pressure 77 Psia-4 Nrs WCAP7709-L (PSIA) See Attachment 35 Psia-1 FEAR Simultaneous Hone SuppL 2 I & II Table 3.11rl Testing Fi . 6.2-12 & 14 Hodcl Number: H/A Relative WCAP7709-L

Serial No.: 45 Humidity (X) 100X 100X Simultaneous

- FSAR Supple 1 None Spin Ho. Stf GHREEE-02 Table 3.11-1 Testing Function: , Accident Hitfgation Accuracy: Spec: N<<e (2) Chemical 1720-2460 PPM 2500 PPM Boric WCAP7709-L Simultaneous Demon: .Spray Boron; 0.24-0.8 Acid uith Sodi FEAR Suppl,l, 2, 4 Tesing None WtX NaON, pH Nydroxfde for TabIe 6.2-22 10.6 Hax. H~ 10 4 Hrs Service: Control Hydrogen Rad ia t ion WCAP7709-L Concentration in Containment 8 Simultaneous See Attachment 2 x 10 Rads FSAR Suppl.2 None After a IOCA I Table 3.11-1 Testing Loca tfon: Inside Containment Aging WCAP7709-L Sequential Elcv 62,00'n Approx Opposite 40 years 40 years Assumed Suppl. 6 Testing None Sides next to each Steam Generator Flood Level Kiev: (27.3') (Max) Submcrgfng Above Flood Level: Hone Yes Not Required

+ 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 ~ I ~

~ ~ ~ ~ ~ I

~ ~

I ~

I I 'I I ~ ~ I ~ ~

~ ~ ~

I ~ \ I I I ~

I '; ~

~ ~

~ I I I ~ I ~ I I ~ ~

I ~

I ~

I ~ 'I

~ I I ~

~ I

' I ~ ~ ~

~ ~

~ r I> ' c E9

~ IIIv 8( SYSTFBI QINPIRIENT EVALUATION ffORR SIIEET

(.

'I BY DATE~~

BY/DATE Clt/DATE Foci lltyl St Lucia Unit I

>A>>>~IILY 8 Docket> 50-335 R E V I S I 0 N I EINIROIUIEN1 UUCUNEHTATION REFe IIUAI.IFICATION OUTSTANDING EGUIPHENT DESCRIPTION ITENS Paraactcr 'pcclf lection; Itunttfication Spcclflcntion Qualification HETI IUD Systcsu Various D15,D1 7,D2 4 Operating FSAR Sinutnncous Tfa>e 1 year Section 3.11 Test plus ttonc D2 5>D2 7>D2+)D2+)DM>D2 10)D3 3> 1 Year D3-5)D34)D3-7,D3-8>D3-9D3-10)D3-11) Analysis D3-12,D4-'2,D44,D4-7 j D3-4) Q.I. .(See ttote 2)

Coc>P neat: Electrical Cables Tes)pcraturc FEAR Tested Sls)ultanc-( F) See httachnent Table 3.11-1 ously with Pres-. t tone I & II Figure 6.2-12&14 sure, Rtl &. Spray s c Nanufacturcl Pressure FEAR ously with tcc)p> ttone Gcncral Cable (FIRELLX) (PSIA) 50 Table 3.11-1 IBt and spray.

,See Attache>ends Figure 6.2-12&14 I f) II P.O..Order I >>) eeoc>>.uu,)))>,

>(I 422273. cs enc Nodal Nua>bert Cross-linked Polyethylene Relative FSAR ously with tcrrp Nunidl ty (X) Table 3.11-1 pressure & spray ttone vith PVC Jacket Function:

Boric Acid ron c es c>> 1 anc Accuracy: Spec: N/A Ches>Ical 1720-2450 oo>a ) 2000 PIII FSAR ou~ with pres- None Dcaonl N/h Spray pN B.5-10.5 Table 6.2-22 sure tc>cp & RH 0.24-0.S4 vtX (Sce ttotc 1.)

NaON Service> Various control, lov energy Radiation Sc)tuential Test and coeatunlcatfon circuits See Attach>)cnt I 5x10 FSAR Table 3.11-1 ttone

-

I~cation> Various Inside and Outside Aging Engineering 40 yrc Contalnnent - 150'L Analysis None 200 days (See ttotc 2)

Flood Level Eleve 27.3 Feet Sub))sr ging 951 days - 90 C Test Above Flood Level) No

• Oocu>>>entatlon

References:

Notes

l. St~1 Rualif. Data for General Cable Co. Cable (FFg 28) 1) F~ivalcncy docu>canted in Engineering Annlycis No. 1-15 Iiualification catat>lished by EnginccrinG Analysis g E-9.

2. Gcnora1 Cable Certified Teat Rcport (FF//l5C) 2)

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

F ilic Docket: 50-335 Sc LE I U it EQUIPHEHT DESCRIPTIOH 1

'H R E V I S I WYi 0 N I-S S-T I

/7'EA FF, I

SYSIEH COHFOHEHT EFAIHATTOH IIOIIK SIIEFT ENVIRONMENT BY 0 ~ ~.

CHECK BY DOCUHEHTATION REF<

DATE~EL DATE t QUALIFICATION

~'

hl DO Page OUTSTANDING 1 of Specification Qualification Specification METHOD ITEMS Parameter Qualification System: Aux Feedwater Operating Sequential Tests Plant ID Ho, Aux Feedwater Time 8 hours lus Analysis Pump No. 1A 1B ee Note (3) None fH Sce Note (2) 1000 hrs. + Section 10.5.3 Sce Note (2)

Component: 350hp, 4000V, Class IE En- Temperature equencial Tests 320 F for lus Analysis closed in an outdoor weather ( F) 320 F FSAR protected Type II outdoor 1 Hour + ec Note (3) enclosure Electric Motor for 95 secs Appendix 3C Manufacture: General Electric Company Pressure equential Tests PO NY-422208. (PSIA) FSAR lus Analysis None Specification FLO-8770-289 14.7 psia ee Note (3)

14. 7 Section 3.11 Item 2 Model Number: GE5K811043A21 Relative equential Tests Serial No.: 1AGH8382410 Humidity (X) 100X 100X FSAR None 1BGH8382409 Appendix 3C Func cion: AM Accuracy: Spec: N/A Chemical Demon: H/h Spray Hot Required None Service: Auxiliary Fcedwater Pump Radiation Sequential Tests Not Required 5 X 10 Rads Plus Analysis See Note (1) H*

Location: Steam Trestle Area HELD brea Aging per FSAR Appendix 3C Hot Required None Flood Level Elev: Submerging Above Flood Level: Hoc Required None O'K Documentation

References:

Notes:

1. Topical Report IEEE-323 Class IE Induction Motors Hodels (1) As reported in Reference 1, the lowest damage threshold for any material is 5 5K828840C81 and 5K811043C16 Horizontal Class B Insulated in motor construction.

January, 1977 (FFS102). (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

~ 2. Tooical Ho.port IEEE 323 Class IE Induction Motors

• indicates monthly tests for 15 minutes (0.25 hr X 12 mos. X 40 yrs. ~ 120 hrs).

yr.

HH ls 5K828840C81 and 5K811043C16 HOrizontal Class (3) Engineering worst case Judgement estimate mo.

1 worst case coolf per year for f 8 .sulated May 1979, Rev. 1 (FFI102A) . 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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