ML20039D646
| ML20039D646 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/28/1981 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0588, RTR-NUREG-588 NUDOCS 8201050306 | |
| Download: ML20039D646 (69) | |
Text
__
Malting Address A!abama Power Company j
600 MortM 18th Street Post Offee Bon 2641 i
Birmingham, Alabama 35291 Tetephone 205 7834081 F. L Clayton, Jr.
%;'J70*7,*"t AlabamaIbwer em sour?wn,3n c miem December 28, 1981 Docket No. 50-364 REL31VED D
Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 9.:
JAN4 1984 3 Washington, D.C.
20555 samu %
C mum 3
- sa Attention: Mr. S. A. Varga
/
t' Joseph M. Farley Nuclear Plant - Unit w
Environmental Qualification of Safety Related Electrical Equipment
Reference:
Joseph M. Farley Nuclear Plant - Unit 2 Response to NRC NUREG-0588 Revision 4, dated July 1,1981 Gentlemen:
Alabama Power Company has prepared the enclosed Revision 5 to our September 12, 1980, submittal " Joseph M. Farley Nuclear Plant - Unit 2 Response to NRC NUREG-0588" to satisfy the commitments of the reference letter.
The enclosure demonstrates Alabama Power Company's continuing efforts to assure electrical equipment necessary to protect the public health and safety is capable of perforning its intended function when subjected to a harsh environment.
If you have any questions, please advise.
Yours ver tr, y, l
l l
T vy F. L. Clayton, Jr.
p%
FLCJr/ MAL:awm Enclosure cc: Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly
[ 6k(
Mr. E. A. Reeves Mr. W. H. Bradford h
h) lEN%NissgG PDR N
bec: Mr. W. O. Whitt Mr. R. P. Mcdonald' Mr. H. O. Thrash (w/ attachment)
Mr. O. D. Kingsley, Jr.
(w/ attachment)
Mr. W. G. Hairston, III Mr. R. L. George Mr. D. E. Mansfield a
Mr. K. W. McCracken
'Mr. R. D. Rogers a
'Mr.'J. Hudspeth Mr. R. E. Hollands a
Mr. O. Batum Mr. H. H. Stone Mr. A. A. Vizzi Mr. G. M. Langford a
'i
e=
.g e O e
hTREG 0588 RESPONSE REVISION 5 i
I l
i t
i
-W f
e v
'ey-
I i
I t-NUREG 0588 RESPONSE REVISION 5 PACKAGE s
TABLE OF CONTENTS j
1.
Introduction
-2.
Appendix 5.' Summary of Aging Evaluation 3.
Component Evaluation Worksheets, Revision 5: Revised Sections B.2 C.2.1-C.2.20 i
i m.
l
1.
INTRODUCTION Alabama Power Company has committed to aging evaluations and schedules in ", Joseph M. Farley Nuclear Plant - Unit 2 Response to NUREG 0588" Revision 4, dated July 1, 1981. Chapter 2 Appendix 5, Summary of Aging Evaluations discusses the evaluations performed to extend the qualified life of equipment with a life of less than 40 years which, in all aspects of documentation, is determined to be acceptable for use at Farley-Unit 2.
The results of the evaluations will be reflected in surveillance and maintenance procedures. The procedures will ensure that age-related degradation will be identified, and that the components or equipment is replaced as necessary to verify the qualified status of the equipment throughout the life of the plant. Many qualification test programs have not been completed at this time and final test reports are unavailable for review and evaluation. Alabama Power Company will monitor the test programs, will review the test results when completed and will make j
modifications to the surveillance and maintenance procedures as necessary.
Chapter 3, Component Evaluation Worksheets, Revision 5, provides the revised CEWS which reflect the results of the aging evaluations.
Additional CEWS address various typographical errors and minor corrections required to the 0588 response.
Alabama Power Company is cognizant of the requirements of NUREG 0588 and is committed to assuring the electrical equipment necessary to protect the public health and safety is capable of performing its intended function when subjected to a harsh environment. The following sections of this enclosure demonstrate the continuing efforts of Alabama Power Company in this regard, and are to be inserted / replaced in the 0588 response binder.
-...- ~
2.
APPENDIX 5 -
SUMMARY
OF AGING EVALUATIONS This chapter is intended to be inserted into the 0588 response.
l l
l l
l
f l
i l
APPENDICES i
1.
NUREG 0588 Review Implementation Procedure r
2.
Emergency Operating Procedures Review and Results 3.
Procedures for Maintaining Equipment Qualification 4.
Response to NRC Equipment-Qualification Safety Evaluation 5.
Summary of Aging Evaluations l
--e mm:
,,w-a---
Revision 5 APPENDIX 5
SUMMARY
OF AGING EVALUATIONS i
u
[
l l
I I
o l
1 I
i
>e---n-
- - -a,,,-<
e,,-,
T 2
A APPENDIX 5 i
TABLE OF CONTENTS i
I.
Summary of Aging Evaluations A.
Barton Transmitters B.
GEMS Delaval Level.Switche.s/ Transmitters 1
C.
Rosemount Wide Range RTD D.
NAMCO Limit Switches j
E.
ASCO Solenoid Valves F.
Rosemount Narrow Range RTD e
i 1
I
.,e n
f c:
f APPENDIX 5 I.
Summary of Aging Evaluation Alabama Power Company, as part of its commitments in Revision 4 of the NUREG 0588 response, has undertaken a program to extend the qualified life of equipment with a limited life (less than 40 years).
The program consists of an evaluation of new test reports and information addressing the specific aging characteristics of component material and equipment, and the re-evaluation of the environmental exposure of equipment presently installed. A qualified life beyond June 30, 1982 and to at least the first refueling outage presently scheduled for late 1982 has been established for all equipment addressed in this evaluation.
The results of the evaluation pertaining to the specific aging characteristics of the component material and equipment are being included in surveillance and maintenance procedures. These procedures ensure that thermal and radiation age-related degradation of components will be identified and that the components or equipment will be replaced, to verify the continuing qualified status of each com-as necessary, ponent as indicated in the CEWS sheets throughout the life of the plant.
(
Qualification programs presently in progress will be monitored, the test results will be reviewed and modifications to the surveillance and maintenance procedures made as necessary.
i The evaluations have been summarized for the equipment categorized by vendor type, l
Appendix 5 I-1
4 A.
Make:
Barton Instrumnt Co.
Model'No.:
763,764 (Lot 2)
Instrument:
Level, Flow and Pressure Transmitters Location:
Containment Results of Evaluation Thermal aging was not a requirement in the qualification program for the Barton (Lot 2) transmitters, which was developed to address IEEE 323-1971. Radiation aging requirements of FSAR Section 3.11, however, have been met by the Lot 2 qualification program. The material and components of these transmitters have been previously mechanism evaluated and were found not to have a known thermal agins as compared to Appendix C of I.E. Bulletin 79-OlB.- A review of the operating experience of the transmitters also does not indicate a deleterious thermal aging mechanism. A re-evaluation of-the environ-mental exposure of the material and components would not be definitive because of the lack of a known thermal aging mechanism. Preliminary information indicates that these transmitters may be similar to a more recent vintage of Barton transmitters presently undergoing environmental qualification testing.
APCo Position i
A favorable operating history, the lack of known thermal-aging mechanism, a successful radiological-aging test, and recent vendor i
information supports APCo's opinion that the transmitters would be capabla of completing their intended function at least beyond the first refueling outage.
Surveillance and maintenance procedures are being implemented which ensure that thermal age-related degradation Appendix 5 I.A-1
will be identified and the necessary action taken to verify the con-tinuing qualified status of the transmitters throughout the life of the plant.
Qualification test programs are in progress which will establish a qualified life for Barton transmitters of a different lot than in-stalled at Farley-Unit 2.
APCo will review the results of these tests, the last of which is expected to be completed by June,1982, and determine if similarity exists between the test specimen and the 4
installed model. The results of the test programs are expected to establish a qualified life for this equipment.
I 1
'l Appendix 5 I.A-2
B.
Mak31 GEMS Deltv 1 Model No.:
LS-36497/XM-36495 Instruments: Level Switches / Transmitters Location:
Containment and Main Steam Room Results of Evaluation Thermal aging was not a requirement in the qualification program for these instruments, which was developed to address IEEE 323-1971.
Radiation aging requiremen'.s of FSAR Section 3.11, however, have been adequately met by the vendor qualification program. A material list of the equipment and a complete material list of the manufacturer's analogous equipment has been previously evaluated and found to contain thermal age-susceptible materials. A review of the key aging data of i
the materials in comparison to the Farley environmental requirements has indicated an expected life beyond June 30, 1982 and beyond the next few refueling outages. Furthermore, the operating history of the instruments does not indicate a short-term deleterious thermal aging mechanism. No new test reports or information is available at this time.
APCo Position A favorable operating history, a successful radiological-aging test, a review of the thermal aging characteristics of the material, and the A/E evaluation supports APCo's opinion that the instruments would be capable of completing their intended function at least beyond the first refueling outage. Surveillance and maintenance procedures are being implemented which ensure the thermal age-related degradation will be identified and the necessary action taken to verify the con...nuing qualified status of the instruments throughout the life of the plant.
Appendix 5 I.B-1
... ~... - -
f APCo io pr2sently comp 1 sting cn e.cluntion cf various makao cnd models of instruments to determine a suitable replacement if needed.
The selection, if required, will be made in a timely manner to support the surveillance and maintenance procedures.
f I
I I
l Appendix 5 I.B-2
. - -.. -.-...=_= = =-:-._,_.
C.
Make:
Rosemount Model:
176 KS Instrument:
Wide Range RTD Location:
Containment Results of Evaluation Thermal aging was not a requirement in the qualification program for these instruments, which was developed to meet the requirements of IEEE 323-1971. Radiation aging of these items has been determined to y
be the limiting factor. Such qualified life has been shown to be at i
least beyond June 30, 1982 and the next few refueling outages. A
. previous material analysis has revealed the use of an age-susceptible i
material as compared to Appendix C of I.E. Bulletin 79-OlB, and based l
on this analysis, no significant thermal or radiological degradation will occur during this extended qualified life. Additionally, a review of the operating experience of the instrument does not indicate an unexpected aging mechanism.
1 APCo Position A favorable operating history, the large amount of tests and reviews performed on this instrument, and our NSSS. vendor evaluation supports l
APCo's opinion that the RTD's would be capable of completing their 4
l intended function beyond June 30, 1982 and beyond the next few refuel-ing outages. Surveillance and maintenance procedures are being imple-l mented which ensure that radiation and thermal age-related degradation l'
will be identified and the necessary action taken to verify the continu-ing.oalified status of these instruments throughout the life of the l
plant.
I Appendix 5 I.C-1 i
+
APCo is presently completing an evaluation of various makes and models of RTD's which would be a suitable replacement for the Farley instruments. The selection will be made in a timely manner'to support d
the scheduled replacement of the installed RTD's in accordance with their qualified life.
t 1
l Appendix 5 I.C-2 t
... _. _.., _.. - -. -, ~...
, ~. - -..
D.
Make:
Namco Controls Model No.
EA-180 Instrument:
Limit Switch Location:
Containment and Main Steam Room Results of Evaluation-Type test accelerated aging techniques were used to age these instruments. Radiation aging requirements of FSAR Section 3.11 have been met by the vendor qualification program. The thermal age sus-ceptible material was identified and a material analysis was performed to aid in establishing a qualified life. A re-evaluation of the past environmental exposure compared to the ve.ndor thermal aging qualifica-i tion program has demonstrated a qualified life beyond June 30, 1982 and beyond the next few refueling outages. No new test reports or information is available at this time.
4 APCo Position Surveillance and maintenance procedures are being implemented which reflect the results of the above evaluation, and will verify the continuing qualified status of the instruments throughout the life of the plant.
i Appendix 5 I.D-1
-~,+
+
r +e s
,,,..e~,
,nn,.
,,+
._-,-----,,n~.
n
, n n-,
v w e -,. -
E.
Make:
ASCo Model No.
NP-1 Series, 206-Series Instrument:
Solenoid Valve Location:
Containment and Main Steam Room Results of Evaluation Type test accelerated thermal and radiation aging techniques and material analysis using a conservative approximation to the Arrhenius modelhave established a qualified life for these solenoids. The sole-noids are used inside and outside the containment and, for both loca-tions, have a qualified life beyond June 30, 1982 and for at least the next few refueling outages. A new test report has indicated an elastomer component of these solenoids is not recommended for operation under the more limiting radiation aging conditions where the solenoids may be required to shift position following exposure to a total gamma radiation dose in excess of 20 megarads. APCo has completed an evalua-tion of the operational requirements of the solenoids containing this elastomer component. APCo has determined the solenoids would have completed their position shifts before receiving an exposure to a dose in excess of 20 megarads or would not be required to shift in order l
l to bring the plant to a safe shutdown condition. Therefore, the elas-i j
tomer component has been determined as acceptable for the harsh environ-l I
mental conditions at Farley-Unit 2.
APCo Position:
Surveillance and maintenance procedures are being implemented which reflect the results of the above evaluations, and will verify the continuing qualified status of the instruments throughout the life of the plant. The vendor is completing a material analysis in an attempt to f
j further extend the qualified life of these solenoids. The results of this 1
i evaluation will be incorporated in the surveillance and maintenance procedures as necessary.
Appendix 5 I.E-1
F.
Maka:
Rosemount Model No.:
176 KF Instrument:
Narrow Range RTD Location:
Containment Results of Evaluation Thermal aging was not required to be addressed in the qualifica-tion program which was developed to meet the requirements of IEEE 323-1971.
Radiation aging requirements of FSAR Section 3.11 have been met by the vendor qualification program. The materials and components of this instrument have been previously evaluated and potential thermal age-susceptible material was identified. A re-evaluation of the past t
environmental exposure of the instrument compared to the qualification testing conducted on this material has demonstrated a qualified life beyond June 30, 1982 and beyond the next few refueling outages.
Vendor evaluation of longer term potential thermal aging is underway.
APCo Position Surveillance and maintenance procedures are being implemented which ensure that the age-related degradation will be identified and the necessary action taken to verify the continuing qualified status of the instruments throughout the life of the plant.
APCo is presently completing an evaluation of various makes and models of RTD's which would be a suitable replacement for the Farley l
instrument. The selection will be made in a timely manner to support l
the scheduled replacement of the installed RTD's in accordance with their qualified life.
Appendix 5 I.F-1 l
l l
i I
m,
.c..,
m r,._.
.r
3.
Component Evaluation Worksheets, Revision 5 This section contains the CEWS and Master List whf:h have been revised to reflect the status of the aging evaluations described in Appendix 5.
Additional CEWS have been corrected to resolve typographical errors and minar deviations identified in the 0588 response as follows:
0588 Response-Section Correction C.2.6, Sheet 1 Q2E12SV3999A and Q2E12SV3999B were inappropriately listed as ASCo solenoids. The CEWS have been corrected to indicate AVC0 as the proper manufacturer.
The qualification status and corrective action schedule for these solenoids have not been affected by this typographical error.
C.2.13, Sheet 2 The model for Q2N11SV3976C was incorrectly listed. The Master List has been revised to indicate the correct model number which is fully qualified to the Farley environmental requirements.
A re-evaluation of the operational requirements of Q2N11ZS3369AJ, BJ, CJ and Q2N11ZS3370AJ, BJ, CJ has indicated their design function is to actuate non-safety related turbine controls which are not necessary to bring the plant to a safe shutdown condition or to i
mitigate the accident. Although these limit switches are fully qualified to the Farley environ-ment requirements, they have been l
deleted from the Master List of i
equipment requiring qualification.
C.2.16, Sheet 1 The model numbers for Q2N23SV3228CA
(
and Q2N23SV3227AA, BA, CA were in-correctly listed. The Master List has been revised to indicate the correct model numbers which are l
fully qualified to the Farley environmental requirements.
l The attached Master List and CEWS are intended to replace the corresponding pages of Sections B.2 and C.2.1-C.2.20 of the 0588 response.
l L
MASTER LIST, REVISION 5 SECTION B.2
m_
i C" ASTER LIST d.
section C.2. 6 Joseph M. Farley Nuclear Plant Unit 2
M 1
gCLAs3 IE ELECTRICAL 80UIPMENT REOulRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITION $l SYSTEM; COYTAINMENT COOLIFC AND PURCI E-12.~ E -14. P-13 l
COMPONINTS l
FLANT.-ID NUMBER GENIRIC MAME MANUTACTURIR ICDEL LOCATION 3tDC Eirr Q2E14V' 02 (Nov3660:
, (0perated ot 0
1,imiterove SM3-000 l
Q2Il4V004-1" Moter Operated i
(McV33185) 01obe Valve limitorque SM3-000 DELETED-SEE SECTION 3-2 FOR EXPLANATION Q2P13253196 (HV3196)
Limit Switch NAMCO EA-180
(
Q2P135V28673 l
(MV2867)
Solenoid valve ASCO NP831654v Q2P13252 8673 (MV2867)
Limit Svitch NAMCO ZA-180 t
DELETED - SEE SECTION B-2 FOR EXPLANATION Q4f13Z53197 (MV3197)
Limit Suitch NANCO EA-180-Q4rin uaoom (HV2866)
Solenoid valve ASCO NP831654V W 132528663 i
I (HV2866)
Limit Switch NAMCO EA-180
_Q2E12SV3999A See Sec. 3 l
(MV3999A)
Solenoid valve AVC0 cg3g l
l Q2E12253999A (MV3999A)
Lielt Switch NASCO EA-180 Q2E12SV3999B I" 8'C' 3 AVCO (HV39993)
Solenoid _vstve C%39 Q2E122S39993 (HV39993)
Limit _Svitch NAMCO EA-180 Q2E12M001A (H001A)
CTMT C1r. Tan Motor Jev Mft. Co.
Tyne P Q2E12M3013 l
(H0013)
CTMT Ctr. Tan Motor lov Mfr. co.
Tv ne__ P l
Q2E12M001C
~
~
(H001C)
CTMT C1r. Tan Motor Joy Mfr. Co.
Type ?
i I
Q2E12M001D (H001D)
CTMT Cir. Tan Noter Joy Nfr. Co.
Tyme P General Q27523005 Fenetration Electrie 100 series General Q27523007 Fen,tration Electrie 103 Series General
~~
02T523019 Penetration Ylectrie 100 Series General Q27523002 Penetration Electrie 100 Series General Q27523006 Penetration rieetrie 100 series I
General Q27523041 Penetration Electrie 100 Series
' ~, ' '
General 1
Q27523020 Fenetration Electrie 100 Series i
9 t
ea.-...
l s
NIR N d
hostisaC.2.13 2
Joseph M. Feriey Nuclear Plant Unit 2
ICLAss IE ELECTRICAL EOulPa4ENT REQUIRED TO FUNCTION UNDER POSTULATED AC 3-11 p as _ '
MAIN 8 TEAM FLANT ID NUMBER GENERIC SAME T
RER WDEL LOCATION BLDC tirv i
EA-180 QZN11Z33376A (Rv3976A*)
Limit Switch NAMCO Q2NilSV397oB i
(Ev39763)
Solenoid Yalve ASCO NP8321A2V
'Q2N112S39763 (HV39763)
Limit Switch NAMCO yA.1ao Q2511SV3976C NP8321A2V (Hv3976C)
Solenoid Yalve ASCO Q2N11253976C (Hv3976C)
Limit Switch NAMCO EA.igo Q2N11Sv3369AA-A/JB Terminal Stock States Co.
Twpe ZvM Q2N11Sv3369BA-A/J3 Terminal 31ock States Co.
Type IVM Q2N11Sv3369CA-A/J3 Terminal Block States Co.
Type ZUM i
l Q2N11Sv3370AA-3/JB Terminal Block States Co.
Tepe ZUM Q2N11Sv3370BA-3/JB Terminal 31ock States Co.
Twpe ZUM t
Q2N11Sv3370CA-3/JB Terminal Block States Co.
Twee ZUM 1
I l
1 l
1 1
Q2N11SV3368AA-A/JS Terminal Block States Co.
Tree 2VM 1
Q2N11SV33683A-A/JB Terminal Stock States Co.
Tvee TVM f
I T p TUw Q2N11Sv3368CA-A/JB Terminal Block States Co.
y 02N11sV39763-1/JE Terminal Block States Co.
TvDe__ZUM Q2N11573976C-3/JB Terminal Block Statae Co.
Type ZUM 2VALSO19E, 7 Control Cables Okonite None 2 VAL 3043C Control Cable Okonita sona 2VAQSO134 Control Cable Okonite None GFD.1374 leg 3
. -.. - 2:::. 2 L,_
MASTER UST Seetion C.2.16 Sheet I
Joseph M. Farley Nuclear Plant Unit 2
glass II ELECTRICAL SOUlPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT W-23 MEW MWAm SYSTEM: _
CO@0NENTS FLANT ID NLH5ER GENERIC EAME MANUFACTURER PODEL -
LOCATION BLDG ELD' 4'IMotor Operated Q2N23V011A (Nov3350A)
Stop_-Check C*sbe VI 1,imiterous; SMB-1 Q2N23V0013 4" Motor Operated (MOV33503)
Stoo-Check Clobe VI 1.imitoroue SMB-1
'Q2N23VOO1C 4" Motor Operated Stoo-Check Clobe Y1 1.imiteraue sws-1 30V3350C)
Q2N23ZS3228A
_JHV3228A)
Limit Switch WAMCO EA-180 Q2N235V3228AA NP8320A186V (MV3228A)
Solenoid Valve ASCO -
Q2N23ZS32283 (Hv32285) 1,imit Switch WAMCO EA 180
'~
~Q2N235V3228BA NP8320A186V (MV32285)
Solenoid valve ASCO I
Q2N23ZS3228C
~
EA 180 (MV3228C)
Limit Switch NAMCO l
Q2N235V3228CA (HV3228C)
Solenoid Valve ASCO NP8320A186V 2N23ZS3227A EA 180 Q
(MV3227A)
Limit Switch WAMCO l
Q2N235V3227AA NP8320A186V (MV3227A)
Scienoid Valve ASCO
~ 2N232S3227B Q
(MV32278) 1,imit Svitch WAMCO EA 180
-Q2N23SV3227BA NP8320A186V; (HV32273)
Solenoid Valve ASCO
'Q2N23ZS3227C (Hv3227C)
Limit Swiech NAMCO EA 180 Q2N235V3227CA NP8320A186Vf (MV3227C)
Solenoid Valve ASCO Q2N235V3228AA-A/JB Terminal Block States Co.
Tyne W M Q2N23Sv3228BA-A /JB Terminal Block states ca.
Tyne me Terminal 31ock States Co.
Twee ZUM Q2N23SV3228CA-A/JB 1
__02N235V3227AA-A /JBTerminal Block States Co.
Tvoe ZUM 02N235V3227BA-A/JB Terminal Block States Co.
Tyne 2VM 1
02N235V3227CA-A/JB Terminal Block States Co.
Tree ZVM 2VAFU-UI.0 Power Cable Okonite None 2VAFU-U50 Fever Cable Okonite None
/
2VAM7-120 Fover Cable okonice hn, 1
I 2VAFU-U4A D Control Cablee Okonita Wone G9o.9314 S/S)
.-.,---;'.,,N___..[.-_.___.-..
. ~..
p COMPONENT EVALUATION WORKSHEETS, REVISION 5 SECTIONS C.2.1-C.2-20 I
l l
l l
~
a SYSTEM COMPONENiedA1.UATSON WORK SHEET d
~.
Sectless C.2.1 1
Sheet 1 i
Joseph M. Feeley Nuclear Plant Unit 1
a l
I
'DOCUMENTATSON REF.
OUAL.
DUTSTA8eceNo ENVIRONMENT ITEMS PARAMET E R SPEC.
.OU AL.
SFfC.
OUAL.
RAE TitOO,
EOUlFMENTDESCRtPT90N j
Simultaneous I hr. +
OPE R ATING 30 sea.
1 TIME Foot SLB Over 30 4
Test 30 ees. not i
SYSTEM: Reactor Coolant last.
l Note 1 Sec. SLB jfgte &
a- - _-trate<
e,li,c ilmultanonut w
TEMP.
b20 i
5 g;t COMPONENT:Nerrow Range Resistance'
)
eel u,e _ ter.et..cer j
.a,b,e Simultaneout 2
5 Test None MANUFACTURER: Rosemount PRESSURE 62.2 h6 pet) ges 43 Note 3 Note 6 multaneout (100Ma,l.,c 3
eet Nees 0000EL NUMBER: 876K]***
RELATIVE 100 HUMIDITY (1M Note 6 II* ACIJ 3
Me"e"t None j
puMCTION: Roseter Trt*
O L
N 903 plus 3
Note 6 NEON Ne04 Separate a
g a 1,.c NADIATION 1 x 10
'l x 10 3
5 Test hae l
ACCURACY: SPEC: 40.2%
' {.00a2hn,b,e maes Rede.I Note 6 DEMON 1
S*Perate SERVICE:
AOING Note 4 Note 7 Note 4 5
Test Nene f
CTNT El. 1248-0" Note 6 LOCATION:
E r
f 4
l FLOOD LEVEL ELEY:
115' sueMER.
Note 5 N/A IIete 5 N/A N/A None l
A80VE FLOOD LivEL: Yee GENCt:
NOTES:
DOCUMENTATION REF ERENCES:
j Specifled time plue I hour for equipment with ehert operating tiene ((l beer).
- 3. J.M. Farley FSAR Figure 6.2-6 8.
Maximasse temperature of time dependent temperature profile from Reference 1.
l
- 2. J.H. Farley FSAR Figure 6.2-4 2.
e (See Figure C.3.t)
- 3. J.H. Farley FS AR Telste 3.II-I Haut=use pressure of time dependent pressure profile f rom Reference 2. (See
- 4. J.M. Farley FSAR Section 7.2.1.2 3.
Figure C.3.2)
- 5. WCAF-9157 Antna requiremente in accordance with MUREC 0588, Sectiose 4. Cet egory II.
4 Sul==ergence requiremente In accordence witle tsuny.C 0588, Section 2.7(5),
5.
Category 11 6'. Separate test qualification mothed used. See Section D, Report Eniwetion No. I for juottfication
- 7. The qualified life is being determined and will be reflected in the Surveillance and Maintenance procedures. See Appendix 5 Section I Summary of Aging Evaluations.
~
T
SYSTEC 00.APONEh e EM44.UATION WORK SHEET %
J Sectien C.2. 2 Sheet 3
i Joseph M. Farley Nuclear Plant Unit 2
Tm]
EttVIRONME NT DOCUMENTATION ME,.
m OUTfitMs i
l RAETitOO EOutresENT DEScalFTIOft PAR AME TE R SPE C.
.OUAL.
SPEC.
OUAL.
.uM:
se..t Co.is.
,se-arg,7, Na 2 ; R, 2 ee,e s
..ei,sie No.e Note 1 Foot SLB i
k203 *
- I 5
Analyste Nome l'
c0aar0NENT: Wide Range Restatence T
300 l
%ersometer Detector Note 2
.e 2
i.ei,sie No.e g,ege.
7,S;=
.2.2 A o, Acro.:
.e.e
,ot. 3 3
5 Analysis Nome (00%
t00 DEL NUMSER: {176Kg} '
RELATIVE 100 HUMIDlIY tui i
Borio Acti 3
5 Analyste Name FUNCIBOft:
Reacter Tyl,
CH M L
19 30} plue
+ MeGet
- 3. 0i e, i,c 1 x 108
' t x 10 3
S Analyste Nome f
ACCURACY: SPEC: 40,21 RADIATION j
DEMON (40.2j g,a, g de l
.t AGING Note 4 Note 6 Note 4 5
Analysis None t
7:. CTMT El. 1228-9,,
8 susMER.
N/A N/A N/A N/A N/A None l
FLOOD LEVEL ELEV: 115 GENCE AsOVE FLOOD LEVEL: Yee NOTE 5; DOCUMENTATION REF ERENCES:
j Specified time plus I hour for equipment with ehert operating times ((1 heur).
j
- 1. J.M. Farley FSAR Figure 6.?-6 1.
Manimuse teegerature of time dependent temperature profile free Reference 1.
]
- 2. J.M. Farley FSAR Figuro (.J-4 2.
e (See Figure C.3.1)
- 3. J.N. Farley FSAR Table 3.11-1 Hautaman Pressure of time dependent preesdr6 profile free Reference 2. (See 1
- 4. J.M. Farley FSA81 Tetrie 6.2-19 3.
Figure C.).2)
- 5. WCAP-9157 4.
Aging requiremente in accordance with MUREC 0588, Sect toe 4. Category II.
l Siilimergence requirements in accordence with MUREC 0588. Section 2.2(5),
5.
Category II f
The qualified life is being determined and will be reflected in the 6.
j Surveillance and Maintenance procedures. See Appendix 5.Section I, j
Summary of Aging Evaluations
l d
SYSTEM COMPONENT EVA1.UATION WORK SHEET Section C.2. 3 f
Sheet _ _2..
I Unit 7
bd. M. Farley Nuclear Plant DOCUMENT ATION REF.
QUAL.
OUTSTANDING ITEMS
)
ENVIRONMENT METHOO
{
EQUIPMENT DESCRIPflON
-PARAMETER SPEC.
.OUAL.
SPEC.
OUAL.
t 4
5 simultaneoes None l
OPERATING 30 sec.
30 days l'est Reactor Coolant Systess -
TIME I
SYSTEM:
Pressuriser Note 1 T MP.
300 346 1
5 Staultaneous pone Test COMPONENT: Solenoid Valve Note 2 2
5 simultaneous None RE 62.2 110
- f. mi-I Automatic Switch MANUFACTURER:
i, Note 3 3
5 bimultaneous None Company l
RELATIVE 100 100 Test MODEL NUMBER: NP831654E HUMIDITY l%I H 803 plus 3 3+
3 5
Simultaneous Nees H 80 CH M L
3 Test Actuate Air Operated i
FUNCTION:
MaOli NaOH Valve for Isolation I
8 3
5 Sequential goes 4
5 X 10 2 x 10 Test ACCURA m Not ePP11 cable RADIATN)N Reds Rede D
Note 4 5
Sequential yo Note 4 Note 6 Test AGING L
Containment E1. 118'-0" FLOOD LEVEL ELEV: 115'-0" SU6ME R-Note 5 N/A' Note 5 N/A N/A Mone Tl :
GENCE ABOVE FLOOO LEVEL: ye, h
NOTES:
i
(( 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
l Specified time plus I hour for equipment with sh l
- DOCUMENTATION REF EllENCES:
f ce 1.
1.
- 1. J.M. Farley FSAR Figure 6.2-6 f
- 2. J.M. Farley FSAR Figure 6.2-4 2.
- 2. (See Maximusa preuure of time dependent pressure profile from Reference (See Figure C.3.1)
- 3. J.H. Farley FSAR Table 3.11-1 3.
l
- 4. J.M. Farley FSAR Table 6.2-19 11.
Submergence requirements in accordence with Figure C.3.2) l
- 5. ASCO Test Report AQS21678/TR 2.2(5),
4 1
Rev. A dated July 1979 j
S.
The qualified life is being determined and will be reflected in the Catgury 11.
l See Appendix 5,Section I, 6.
l Surveillance and Maintenance procedures.
l Summary of Aging Evaluations, l
i 1
SYSTEWI CORAPONENT EVALUATION WORK SHEET Q
Settion C.2. 3 Sheet 3
Unit 2
ha, M. Farley Nuclear Plant DOCUMENTATION REF.
- ogAL, HM OUTSTANDl000 ENVIRONMENT METHOO f
SPEC.
OUAL.
.OUAL.
PARAMETER
- SPEC, 5
8I"ultaneous None OPERATING 30 sec.
30 days 4
Test Reactor Coolant System TIME SYSTEM:
Mote i None t
8 1
5 Simutteneous Pressuriser TEMP
- 300 340 Test COMPONENT: Limit Switch i Fl Note 2 None 2
5 Simultanema PRESSURE 62.2 84.7 Test RSAMUFACTURER: NAHCo Controle (PSIAI bte 3 None 3
5 Sisultoneous RELATlvE 100 100 MODEL NUMBER: EA-180 HUMIDITY (%I None HM3+
3 5
Simultaneous CHEMICAL M 903 plue 3
Velve Poettien SPRAY y
FUNCTION:
in:thetion 8
3 5
Sequentist None 5 X 10 2 x 10 Test M/A RAOIATION Rede Rede Wome D
Note 4 5
Sequential Hete 4 Note 6 Teet AGING Contal nt El. 118'-0
,g il :
FLOOD LEVEL ELEV: 115'-0" SUBMER.
g,5 GENCE ABOVE FLOOD LEVEL: Yes NOTES:_
i
((1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
Specified tisme plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipeent with short operating t mes from Reference I.
DOCUMENTATION REF ERENCE5:
Maxismem temperature of time dependent temperature prot 11e 3.
- 1. J.M. Farley FSAR Figure 6.2-6 2.
(See Figure C.3.1)
Reference 2. (Ste
- 2. J.M. Farley PSAR Figure 6.2-4 Maxiseum pressure of time dependent preneure profile from
- 3. J.H. Farley FSAR Table 3.11-1 3.
4 Category II.
- 4. J.H, Farley FSAR Table 6.2-19 Aging requiremente in accordance with HUREG 0588, Section Figure C.3.2) i 2.2(5),
- 5. NAMCo Test Report dated 4.
Subenergence requireanente in accordance with NUREC 0588, Sect on November 21 1977 And 5.
t;rR-lOS dat$d Aug,ust Catgory 11.
h The qualified life is being determined and will be reflected in t eSee Apne C
28,1980 6.
Surveillance and Itaintenance procedures.
(
of the Aging Evaluations.
l L.
e SYSTEM cot 4PONEN EVALUATION WORK SHEET * % Sect ton C.2. 3 Sheet 5
.loseph M. Farley Nuclear Plant Unit 2
ENVIRONMENT DOCUMENT ATION REF.
guat.
OUTSTAssONeG NETHOO HEW PAR AME TE R SPE C,
.OU AL.
SPE C.
GUAL.
Trip IIME 5 min.
Note 6 4
5 Simultaneous Non.
SYSTE M: Reactor Coolant System tFF RA TING Test Fressuriser Note i a,b,c I'"'
COMPONENT: Level Tranesettter TF MP.
o I
- taneous, bI y,","t N e2
~
{75petR] **'2 3
Simultaneous None MANUFACTURER: Barton ITT SURE g,2. 2 Test Note 3
- a,le,c
- 8"'
r 3
5 MODEL NUMOER: 764 (Lot 2)
RELA 100 100,
sgitaneous l.4 ut of boric acteo 3
Simultaneous None Pressertser Level CHEMICAL gg 3RO) plus FUNCTION:
0*h"**
Test NaClt 7,b,c
,b i4)lATION 5 K 10
. 5 if 10 3
5 Sequential lie ACCURACY: SPEC:
- 4257, e
R Test DEMON: Max. error 157-leads Ifede SERvlCE-AGING Note 4 Note 7 Note 4 5
Sequential N,,,
Test LOCATION: Containment El. 116'-0.,
a N/A Mate 5 N/A N/A None FLOOO L EVE L E LEV: 115' sueMER.
Note 5 GE NCE A80VE F tOOO LEVEL: Tee ES:
DOCUMENTATOON REF ERENCE5:
S ecified time plus I hour for equipment th short operating times (( t hour).
1.
Farley FSAR Figure 6.2-6 8.
- 2. J.M. Farley FSAR Figure 6.2-4 2.
Maulamm temperature of time dependent tesaperature profile from Referesece I.
P (See Figure C.I.8)
- 1. J.M. Farley FSAR Telste 1.11-1 Maulemese pressure of tiene dependent pressure profile from lieference 2. (See
- 4. J.M. Farley FSAR Table 6.2-19 3.
4 Figure C.3.2)
Aging requirements in accordance with MilRF.C O5AR, Section 4. Category II.
- 5. WCAP 9885 4
Sutectmente requirements in accordence with NUREC 058R, Section 7.7(5),
5.
Category 11 Opernlillity demonstrated, trip 5 min. and post psE 4 months.
6.
in the The qualified life is being determined and will be reflected 7.
Surveillance and Maintenance procedures. See Appendix 5 Section I Summary of Aging Evaluations.
w SYSTEM COMPONEN) = VALUATION WORK SHEETSectton C.2.3 Sheei g I
2 f
Joseph M. Farley Nuclear Plen. Unli DOCUesENTAT90N REF*
- guat, HEM OUTSTANOONG ENVIRON 8 MENT MTMOg OUAL.
.OUA L.
SPEC.
PARAMETER SPEC.
Note 6 4
5 S1multeneous Nome Trip OPERATING 5 min.
Test Iteactor Coolant System TIME SYSTEM:
Note i y,,,,,, g,,,,
,~ a,b, s4giten...
T 300 e
COMPONENT: Pressure Transmitter i
simultaneous None
~
2 5
~
PRES ME 62.2 75 peig b Test MANUFACTURER: Barton Note 3 c
N 1"
"a 3
5 M M tam ous N.Ie,b, RELATIVE Test MODEL MUMBER:
763 (tot 2)
HUMIOl1Y l%I None 1.4 wt. of
)
5 ilmgitaneous bor c act 18 803 plus Ts.t CH ICAL 3
Reactor Trip FUNCTION:
NaCli u,
5 x 10
'S x 10 bh, 3
5 sequential None 7
'reet ACCURACY: SPEC: 110% for 5 min. nAnlAT Oes DEMON: 0-5 min., 7.7%
Rede Jade Je ote 4 Note 7 Note 4 5
8 tial None 5 min.-4 me., 15.5%
AGING Containment El. 116, FLOOD LEVEL ELEV:
115' stalME R.
Note 5 N/A Note 5 N/A N/A None Tl GENCE ABOVE FLOOD LEVEL: yes
_NOTESL times ((1 heet).
i DOCUMENTATION
REFERENCES:
Specified time plue 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipment with short operat ngtengeratu 1.
l*
- 1. J.M. Farley FSAR Figure 6.2-6 Manisman temperature of time deperwient l f nce 2."(See 2.
- 2. J.M. Farley FSAR Figure 6.2-4 Maulemsm pressure of time dependent pressure profile from ie ere (See Figure C.3.1)
- 3. J.M. Farley FS AR Table 3.11-1 o
3.
- 4. Category II.
- 4. J.M. Farley FSAR Table 6.2-19 Aging requiremente in accordance with MUREC 05R8. Section Figure C.).7)
Section 2.2(5).
Sut==ergence requires =ents in accorelence with NtlREC 0588, 5.
WCAP 9885 4.
5.
Category 11 Trip 5 min. and poet nat 4 months. di the Operability demonstrated.
The qualified life is being determined and will be reflecte nSee Appendix 5 6.
7.
Surveillance and !!aintenance Procedures.
Summary of Aging Evaluations.
w
l SYSTEM COMPONENT EVAt.UATION WORK SHEET d
Section C.2.4 Sheet 4
.losoph M. Farley Nuclear Plant Unlt 2
~
ENVIRONMENT DOCUMENTATION REF.
OUAL OUTSTANDING i
MET g GEW EQUIPMENT DESCRIPTION SPEC.
OUAL 4
30 Days 3
4 Sisestteneous None SYSTEM: Feedwater Control OPERATING 10 min.
TIME Note 1 Test Systes.
I COMPONENT: Limit Switch TEMP.
308 340 1
4 Simultaneous None
(*F)
Note 2 Test Mons MANUFACTURER: Namco Controls PRESSURE 20.5 84.7 1
4 Sinultaneous i
(PSIA)
Note 3 Test i
Simultaneous i y,,,
j MODEL NUMBER: EA 180 RELATIVE 100 100 2
4 Test HUMIDITY (%I Simultaneou' None i
13B0 4He0H None
- 4 FUNCTION: Valve Position CHEMICAL None 3
Test SPRAY l
Indication Sequential y,,,
i 2 x 108 y,
4 j
ACCURACY: SPEC: N/A Re m HM Test Reds DEMON:
i 8*
" I*
AGING Note 4 Note 6 Note 4 4
None 1
O TION: Aux. Bldg. - E1. 121e f
FLOOD LLVEL ELEV: N/A SUBMER.
Note 5 N/A Note 5 N/A N/A None GENCE ABOVE FLOOD LEVEL:
j i
NOTES:
DOCUMENTATION
REFERENCES:
1 hout Specified time plus I hour for equipment with short operating times (<
1 Bechtel Calculation 525-25-7597 1.
Maximum temperature of time dependent temperature profile from Raft.tence 1.
from computer run T-10576 2.
(See Figure C 3.4) 4 2.
J. M. Farley FSAR Chapter 3, Maximum pressure of time dependent pressure profile from Reference 1.
(See j
Appendix 3K 3.
Figure C.3.3) i 3.
J. M. Parley FSAR Sect.
Aging requirements in accordance alth NUREC 0588, Section 4, category II 4.
3K-4.1.1.10 5.. Submergence requirements in accordance with NUREC 0588, Section 2.2(5),
4.
Namco Test Report grR 105 Category II 6.
The qualified life is being determined and will be reflected in the Surveillance and Maintenance Procedures. See Appendix 5 Section I Summary of Aging Evaluations.
SYSTEM COMPONENT EVALUATION WORK SHEET 8 Section C.2.4 Sheet 5
Joseph M. Farley Nuclear Plant Unit 2
OUTSTANDING ENVIRONMENT DOCUMENTATION REF.
OUAL.
REW METHOD PARAMETER SPEC.
QUAL.
SPEC.
- QUAL, 3
4 None SYSTEM: Feedwater Control OPERATING 10 min.
30 days Test TIME Note 1 1
4 liensitanoone None 308 346 COMPONENT: Solenoid Valve TEMP.
Test
(*F)
Note 2 MANUFACTURER: Automatic Switch PRESSURE 20.5 110 1
4 simultaneous None Test (PSIA)
Note 3 Company (ASCO)
MODEL NUMBER: NV-206-381-2RU RELATIVE 100 100 2
4 iisultaneous None Test HUMIDITY l%l 4 80 4NaOH None 4
simultaneous None FUNCTION: Activate air operated CHEMICAL None 3 3 Test SPRAY velve for isolation d
ACCURACY:
ot Applicable RADIATION None Z x 10 y,,,
4 y,,,
8 Rede
- equential None 8
AGING Note 4 Note 6 Note 4 4
Test SERVICE:
LOCATION: Aux. Bldg. Et,121 FLOOD LEVEL ELEV: N/A SUBMER-Note 5 N/A Note 5 N/A N/A None GENCE ABOVE FLOOD LEVEL:
i NOTES:
DOCUMENTATlON
REFERENCES:
Specified time plus I hour for equipment with short operating times (4 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
1.
Bechtel Calculation 525-25-7597 1.
Maximum temperature of time dependent temperature profile from Reference 1.
(See from computer run T-10576 2.
Figure C.3.4) 2.
J. M. Farley FSAR Chapter 3, Maximum pressure of time dependent pressure profile from Reference 1.
(See 3.
Appendix 3K Figure C.3.3)
Aging requiremente in accordance with NUREC 0588, Section 4, category II 3.
J. N. Parley FSAR Sect.
Submergence requiremente in accordance with NUREG 0588, Section 2.2(5), category 3K-4.1.1.10 4.
4.
ASCO Test Report AQS21678/TR 5.
The qualified life is being determined and will be reflected in the Rev. A dated July,1979.
6.
Surveillance and Maintenance Procedures. See Appendix 5.Section I, Summary of Aging Evaluations.
SYSTEM COMPONENT EVALUATION WORK SHEET d
section C.2.4 Sheet 9
Joseph M. Farley Nuclear Plent Unit 2
ENVih0NesENT DOCUMENT ATOON MEF.
M-OUTSTANOlg00 IAE1HOO lTEass PARApsETER SPE C.
.OUAL.
SPEC.
GUAL.
I EOUIPMENT DESCfuPTIOft Trip Trip 5 min.
TIME 5 min.
Post psE 4
5 Simultanean Mose SYSTEM: Feedwater Control OPERATING Test Note t 4 months
- a,b, o
t 5
Simultaneous Nome
~
TEMP.
300 330 e
CODAPONENT: Imvel Transultter gan Test Note 2,
~
1
- a,b, I.
2 5
Simultaneales None PRESSURE 62.2 89.7 e
l MANUFACTUflER:
Barton ITT Test geseng Note 3 l
a,b, 3
5 Simultaneous leone
~
l aAODEL NURISEft: 764 (Imt 2)
RELATIVE I
100 c
HUGAIDITY l%l L
Test f * "c cd 3
5 1
h-
%.he FUNCTION: Feedwater Control CH MICAL.
g p p,,
y Na-a T..
5 K lo?
'5 x 10 3
5 Sequential None 7
,b,e AEWAA" Note 6 RADIATION Test Rede uRede i
j SERVICE:
AGING Note 4
' Note 7 Note 4 5
seguentist None Test LOCATION: Containment El.121s-0" FLOOD LEVEL ELEv:
115' SUBMER.
Note 5 N/A Note 5 N/A N/A hone i
ABOVE F LOOD LEVEL: Yee GENCE NOTES;,
j DOCUMENTATION
REFERENCES:
Specified time plus I hour for equipment with short operating times ((1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- 1. J.M. Farley FSAR Figure 6.2-6 1.
- 2. J.M. Farley FSAR Figure 6.2-4 2.
Maxismsm temperature of time dependent temperature profile from Reference I.
{
(See Figure C.3.1)
Nexionan preuure of time dependent pressure profile from Reference 2. (See
- 3. J.M. Farley FSAR Tehte 3.11-1
- 4. J.M. Farley FSAR Table 6, 2-19 3.
Figure C.3.2)
Aging requirements in accordance with NUREC 0588, Section 4. Category II.
- 5. WCAP 9885 4.
Sulimergence requirements in accordence with NilREC 0588 Section 2.2(5),
5.
6.
Accuracy requirements: 410%, (-)OO for 5 min. to 4 moe., 125%
f Category 11 max. error 0-5 min., 5%; 5 min, to 4 mos., 17%
Accuracy demonstrated:
The qualified life is being determined and will be reflected in the j
7.
Survaillance and !!aintenance Frocedures.
See Appendix 5.Section I, 1
Summary of Aging Evaluations.
I i
^
SYSTEM COMPONENT EVALUATION Vv0RK SHEET ld i
f Section C.2.4 i
Sheet 6 I
Ja -ah M. Farley Nuclear Plant Unit 2
OUAL OUTSTANDING i
^
ITE M METHOO PARAMETER SPEC.
OUAL.
SPEC.
QUAL i
EOulPMENT DESCRIFTION l
i Feedwater Control OPERATING 10 min.
Simultaneoui None j
SYSTEM:
TIME Note 1 30 days 3
4 Test PLANT ID NO.
4 COMPONENT: Solenoid Valve TEMP.
308 Simultaneous j
l'F)
Note 2 34 6 1
4 H*""
Test MANUFACTURER: Automatic Switch PRESSURE 20.5 110 1
4 simultaneous Test INAI Note 3 Company (ASCO) l MODEL NUM8ER: EV-206-381-4U RELATIVE 100 100 2
4 Simultaneous None f
HUMIDITY (%I Teet Bimultencous FUNCTION: Actuate Air Operated CHEMICAL M BOpaM None 4
3 Test WRAY one f.
Valve for Isolation RADIATION None 2X108 Reds None 4
Sequential None ACCURACY: SPE Not Applicable Test i
,"*t I
AGING Note 4 Note 6 Note 4 4
h Tl
- Aux. Blds. E1.121e 5
g GENCE Note 5 E
Note 5 m
E None l
FLOOD LEVEL ELEV: E SUOMER-ABOVE FLOOO LEVEL:
NOTES:
DOCUMENTATION
REFERENCES:
l
- 1. Specified time plus i hour for egetpuent with short operating times (< 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- 1. sechtel Calculation 525-25-7597
- 2. Maximum temperature of time dependent temperature profile from Reference 1. (See from computer run T-10576 Figure C.3.4)
(See
- 2. J. M. Farley FSAR Chapter 3,
- 3. Hardmum pressure of time dependent pressure profile from Reference 1.
Appendix 3K Figure C.3.3)
- 4. Aging requiremente in accordance with NtmEC 0588, Section 4, category II
- 3. J.
M., Farley FSAR Sect.
- 5. Submergence raquiremente in accordance with NtmEC 05s8, Section 2.2(5), Category 3K-4.1.1.10
- 4. ASCO Test Report AQS21678/TR The qualified life is being determined and will be reflected in the Rev. A dated July, 1979.
6.
Surveillance and Maintenance Procedures. See Appendix 5,Section I, Summary of Aging Evaluations.
e l
SYSTEM COMPONENT EVALUATION WORK SHEE1 s.etie. C.2. 4 l
30'8'l _ 10 i
I i
3 asiM. Farley Nuclear Plant Unit 7
GUTSTANOWIG DOCLMAENTAitON MF.
- agat, MM i
ENVtMON84ENT 00ETM I
PARAmeETER SPE C.
.OUAL.
SPEC.
OUAL Trip Trip 5 min.
5 Sa teneoes OPE AtlNO 5 stn.
Foot pac a
SYSTERA: Feedwater Control 4 moe.
Note g r-Nome I
5
,disultaneous ll l?
CORAFONENT:
Flow Tremonitter T, esp.
300 q'
e,I.c Test Note 2 I'
c 2
5 simultaneone Item
'~
~
GAANUFACTUMR:
Barton ITT 89 7"**b PRESSURE 62 2 i
Test 4 PSIA)
Note 5 Ilene 5
5 Simultaneou i
~
RELATIVE 100 100,m,b, c I
RAODEL NUMBEN:
764 (Lot 2)
HUtelDITY HM Test f
g i.4 wt.
IIene 5
Simultaneem i M 003 plue 0kw f
Test Feedwater Centrol CHEtt A4-3 FUNCTION:
NeOM Neost.
j.
e,=,6 y 3
5 seguentist IIene l
~
5 K 10 5 m to Test
{
ACCURACY: SPEC:
Note 6 NADIAT90ss Rede
.pede l
MacON:
Note 4 5
sequeettet None Note 4 Note 7 Test E
AGING
- Containment El.121'-On Y
Note 5 N/A N/A No'ne FLOOO LEVEL ELEV: 115' SuseAER.
Note 5 N/A GE NCE AsOVE FLOOO LEVEL: Tee NOffS:_
((l hour).
l Specified time plus I hour for equipment with ehe DOCUMENTAT90N REFEME00CES:
1.
8.
- l. J.M. Farley /SAR Figure 6.2-6 2.
- 2. J.M. Farley FSAR Figure 6.2-4
- 2. (See (See Figure C.3.1)
Menimman pressure of time dependent preneure profile from Weference
- 3. J.M. Farley FSAR Telste 3.11-1 3.
- 4. J.M. Farley FSAR Table 6.2-19 II.
Aging requiremente in accordance with HUREC 0588, Section 4. Catego Figure C.3.2) i 2.2(5),
- 5. WscAF 9985 4
Siilisiergence requirements in accorelence wtth MilREC 0588, Sect on 5.
5 min. to 4 mos.,125%
category II 410%, (-)OO for men. error, 0-5 min., 51, 5 min. to 4 mes.,17%
l 6.
Accuracy requiremente:
- Accuracy demonstrated:
The qualified life is being determ16ed and will be reflected in theSee App I'.
7.
Surveillance and !!aintenance Procedures.
Summary of Aging Evaluations.
T
y SYSTEM COMPONENT EVALUATION WORK SHEET
.Section C.2.5 Joseph M. Farley Nuclear Plant Unit 2
OUTSTANOttoG ENVIRONMENT DOCUMENTATION MEF.,
- ogAL, METHOO MEW EMMNMMMM PARAMETER SPEC.
.OU AL.
SPEC.
OUAL SYSTEM:
RHR/111SI 10 Min.
4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 3
5 timultaneous None OPE ATING Test Note 1 5
timultaneous None COMPONENT:
Level Transmitter T MP.
300 300 1
Test Note 2 MANUF ACTURE R: DeLaval PRESSURE 62.2 69.7 2
5 simultaneous None Cens Sensor Division (PSIAl 3
3 5
simultaneous None RELATIVE 100 g
MODEL NUM8ER: XM-36495 HUMIDITY (%)
Tant H 903 plus 3 3+
3-5 simultaneous None N 50 FUNCTION:
Post-Accident Level CHEMICAL 3
I SPRAY w
Monitor NaOH m
RADIATION 5 K 10 1 x 10 3
4 Sequential Mone I
8 ACCURACY: SPEC:
10.5" Test DEMON:
10.5" Rads Rads I'**
f SERVICE:
AGING Note 4 Note 7 Note 4 4
, Analysis Containment E1.116e i
LOCATION:
FLOOD LEVEL ELEV:
115' SUBMER.
M/A N/A N/A N/A N/A None
{
l GENCE ABOVE FLOOD LEVEL:
ye.
J NOTES; DOCUMENTATION
REFERENCES:
Specified time plus I hour for equipment with short operating times ((1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- 1. J.M. Farley FSAR Figure 6.2-6 1.
- 2. J.51. Farley FSAR Figure 6.2-4 2.
Maxlanum temperature of time dependent tesaperature profile from Reference 1.
(See Figure C.3.1)
- 3. J.M. Parley FSAR Table 3.11-1 Maximium pressure of time dependent pressure profile from Reference 2. (See
- 4. FIRL Test Report F-C3834 dated 3.
Figure C.3.2) 3-74 and Bechte'1/Cens telecon Aging requiremients in acLardance with NUREC 0588, Section 4. Category II.
4.
in accordence with HUREC 0588, Section 2.2(5).
of 4-3-80 Isomedix Test Report for Cem 5.
Sulwergence requirements 5.LiquidLevelSensorDated11f75 Category it The qualified life is being determined and will be reflected in the 6.
Surveillance and Maintenance Procedures.
See Appendix 5,Section I, Summary of Aging Evaluationa.
4
CASTER LIST Sheet 1
2 __
w he. Farley Nuclest Plant Unit D ACCCENT CONDITIONsl glass is ELECTalCAL soutresENT caouCED TO FUNCT40:2 UNDER POSTU 1-12." E -14. P-13 i
CONTAINMENT Co0 LING AND FURCI sysTsu: -
COMPONENTS LOCATION GENERIC MAME MANUTACTURER PODEL BLDc I
Etn-FLANT ID NUMBER CTMr 134'-6" ot(0perated SMB-000 Limitercue Q2E14V002 (NOV3660:
1" Notor Operated SMB-000 CTMT 116'-0" QZLl6VD04 limitercue (NOV33185)
DELr.u.u-SEE SECTICH B-2 FOR EXPLANATION EA-180 CTMT 129'-0"
~Q2P13ZS3196 NAMCO Limit Switch GV3196)
NPS31654V CTMT 129'-0" _
Q2P135V28673 ASCO Solenoid Valve (HV2867) 129
-0" 8
EA-180 CTMT TlP132525675 NAMCO Limit Switch (HV2867)
~
DELETED - SEE SECTION B-2 FOR EIPLANATION
(
ZA-180 CTMT 129'-0" 4
T4 1J45J19/
Limit Switch NANCO (HV3197)
NPB31654V CIMI 129'-0" _
ASCO w AJs uecom Solenoid Valve (HV2866)
EA-180 CTMT 129'-0" __
l
'Q2P13ZS28665 Limit Switch See Sec. 5 CTMT 89'-4" NAMCO QV2866)
AVCO c$43o Q2E12SV3999A Solenoid Valve GV3999A)
CTMT 89'-4" _
EA-180 C2E12ZS3999A tiett Switch See Sec. B CTMT 91'-4" _
NAuCD mV3999A)
C5439 Q2E12SV3999B Solenoid Valve AVCO (MV39995)
CTMT j 91' 4" EA-180
_ E122S39995 NASCO Q2 Limit Switch mV39995)
CTMT 155'-0" Jov Mf e. Co.
Twee y t
~Q2E12M001A C1NT Cir. Tan Meter (H001A)
CiMT 155'-0" _
Tvec_y f ev Mf e. ce _
_Q2E12M3013 CTMT Ctr. Tan Meter Joy Nfr. Co.
Type F C MT 155'-0" _
JH0015)
Q2E12M001C, CTMT Cir. Tan Motor Joy Nfr. Co.
Tvpe F CTMT 155'-0" _
G001C)
Q2E12M001D CTMT Cir. Tan Meter G001D)
General CTMT 143'-0" 100 Series Zieetrie Penetration Q2T325005 General CTMT 143'-0" _
103 Series Electrie Penetration Q2T525007 General C MT,
143 ' -0",,,,,,,,
100 Series Eteetrie Penetration Q2T525019 General CTMT 143'-0" _
100 Series Electrie Penetration Q2T525002 General C7MT 143' 0" 100 Series Electrie 1
Penetration 027525006 General 143'-0" 100 Series C;wr Electric Penetration 143'-0" Q2T323041 Generst 100 Series CINT Electric Penetration Q2T323020 GPD.137a ligg
+
1 d
q j
SYSTEst CORIPONENT EVAltJATION WORK SHEET Seetles C.2.4 d
,$esepit R$. Farley NucteerPlant LJuls 9
- fg DOCUMENTAT9000 REF.
N l
ENWlMONMENT get H00 i
}
toptreetlefut9CMtPDOI6
-PARAMETER SPEC.
.OUAL.
SPEC.
OUAs.,
l' 5
sleuttaneena Nees OPERATING 30 eee.
30 daye 4
SYSTEts: Centetsueemt Coelleg and Test
=
1 TIME More 1 i
Purge Y
300 340' I
5 simsiteneena Wees Test CORIPOIGEffft Lielt'Settch Note 2 BAAflufACTUflER: IIAllCe Centrole PftESSURE 62.2 84.7 2
5 Simultaneena pene feet J
"I Note 3 J
I 5
5 simultaneena Wees RELATIVE 100 100 Teet I
ISODELflUIIgEN: EA-100 HumalDtTYlEl
- 883+
3 5
sleettseeems IIene W 303 plue 3
CHEastCAL Test Volge feettism SPMAY M
3 FusecT10N:
l 8
5 5
segmentist uses 1edicotten 5 x 10 2 s 10
- y. g l
ACCURACT: srEC:
N/A NADIAT1001 4
g,g, y,g, DEneON:
l IIste 4 5
segusettet Itsee l
Note 4 Note 7 fe.t i
AGING Centetnesol '" me.4a s
Isote 5 Ifene N/A IIsme 115' SusesER.
II*te 5 Note 6 a
7LOOO LEvf L ELEV:
GENCE l
AeOVE P1000 LEVEL: Note 6 o
8007ft:_
(4(1 best).
i If Specified time plus I hour for equipment with ehe OOCUMENTATION REFEREseCES_:
f e 1.
- 1. J.M. Farley FsAn Flaure 6.2 6 2.
- 2. J.M. Farley F5AR Figure 6.2-4
- 2. (See Monts ee preneure of time dependent preeewre profile tree Seferomee (See Figure C.3.1)
- 3. J.M. Farley FS AR Tetste 3.II-I 3.
- 4. J.M. Farley FSAR Yable 6.2-19 Ef.
An ns requiremente in accordence with MtimEC 0580 Secties 4. Cates Fanure C.3.0) 2.2(5),
- 5. MAHco Test soport deced 4.
Submergence requirements in accordence with sninEC e588, section a
l November 21,19f 7, and QTR-105 5.
dated August 28, 1980 Category 11.
Imented in Reactor Cavity, not euhject to flooding.
l
- 7. The qualified life is being determined and will be reflected in the 6.
See Appendix 5,Section I, Surveillance and Maintenance Procedures.
Summary of Aging Evaluations.
i i
~
fA SYSTEM COMPONENT EVAI.UATION WORK SHEET Seetten C.f 4 l
Jessph M. F ky Nedeer Plant Unit DOCUBAENT ATSOs, NEF.
g ggggy m
?
f MS88 ENWlMONMENT SSETHOO
.OUAL.
SPEC.
GUAR.
FARAMETER SPEC.
- ;i---
30 e.e.
30..
Cg C.eu, e.
g l'=
.T.T M:
340-i 5
a-i=s -
T..t u,,.
300 L
Co, l.....
..I, i-
,,,,e,
Steulteneend IIsme p
3 3
f asANurACTURER: MAMCo Centrole PRES 5URE 62.2 84.7 Test irsiAl Hote 3 3
Simitseeema IIene RELATavE 100 100 Teet as00El.3,unattW: EA-100 HUMID 4YYIEl gg gg) p ue 3
3+
3 3
Simiteneese b
NN CHEtHCAL g
Test Velve Peettlee g
Me0H Me0N i
FUNCTIOpe:
i 2 x 10 3
5 Se tiet pose todicottee 8
~
5 X lo l
AcCuMACY: SPEC:
ypg nAguaywys pode Rede DEMON:
aa "e = 6
~~*
5 Test
'
l o""a'lJ.: m t.i.e.t..u,.-0..
N/A flame l
IIete 5 yfg 115' sueMER.
Itete 3 N/A FLOOO LEVEL ELEV:
GENCE ASOVE FLOOO LEVEL: Yes i
t 880TESL i
((l bouF).
i f f BPecified time plue I hour for equipment with DOCUMENTATl004
REFERENCES:
f I.
- 1. J.M. Farley FSAR Figure 6.2-4 2.
- 2. J.H. Farley FSAR Figure 6.2-4
- 2. (Sed Hemiseen pressure of time dependent pressure praffle from Referenc (See Figure C.3.1)
- 3. J.H. Farley FS AR Totale 3.11-1 3.
II.
- 4. J.H. Farley FSAR Tebte 6.2 89 Assas requirements in accordance with NUREC 0580, Secties 4.
Figure C.3.2) i 2.2(5),
- 5. HAMCo Test Report dated 4.
Submergence requirements in accordence with NUREC 0508, Sect on November 21,19fl and QTR-105 5,
The qualified life is being determined and will be reflected in the deled August 28, l'980 Category it.
6.
Surveillance and Maintenance Procedures.
Summary of Aging Evaluations.
l' I
1 SYSTEM COMPONENT EVALUATION WORK SHEET Section C.2.6 Sheet 6 Joseph M. Farley Nuclear Plant Unit 2
4 i:
ENVIRONMENT DOCUMENTATSON REF.
00AL.
OUTSTANDN00 f
METHOD ITEMS EOUIPMENT DESCRIPTION OUR E
OUR i;
P Simultasseous SYSTEM:
Containment Cooling OPERATING 30 see*
TIME 30 days 4
5 Test and Purge g
Simultaneous
}
COMPONENT: Solenoid Valve TEMP.
300 l
I fI Test Note 2 i!
Simultaneous MANUFACTURER: Automatic Switch PRESSURE 62.2 110 2
5 Test (PSIAI Note 3 Company (ASCO)
Simultaneous 1
l MODEL NUM8ER: NF831654V RELATIVE 100 100 3
5 None HUMIOITY (%)
FUNCTION: Actuate Air Operated CHEMICAL H 803+
3 3+
Simultaneous HM 3
3 5
SPRAY NaOH HaOH Test Valve for Isolation j
I 8
8]***I*I 5x10 2 x 10 h
D RADIATION 3
5 AGING Note 4 Note 6 Note 4 5
Tl
- Containment E1. 129s T
O.
l FLOOD LEVEL ELEv: 115'-0" SUBMER.
1 ABOVE FLOOO LEVEL: Yes GENCE Note 5 N/A Note 5 N/A N/A Mone 6
NOTES:
DOCUMENTATION REFERENCliS:
Specified time plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipment with short operating times (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- 1. J.M. Farley FSAR Figure 6.2-6 1.
- 2. J.M. Farley FSAR Figure 6.2-4
'7.
Maximimi temperature of time dependent temperature profile from Reference 1 (see Figure C.3.1).
- 3. J.M. Farley FSAR Table 3.11-1 Maximum pressure of time dependent pressure profile from Reference 2 (see Fig. C.3.2)c
- 4. J.M. Farley FSAR Table 6.2-19 3.
Aging requirements in accordance with NUREC 0588, Section 4, category II.
- 5. ASCO Test Report AQS21678/1R 4
Submergence requirements in accordance with NUREC 0586, Section 2.2(5), Category II.
]
Rev. A dated July 1979 5.
6.
The qualified life is being determined and will be reflected in the Surveillance and Maintenance Procedures. See Appendix 5 Section I, Summary of Aging Evaluations.
.{
l I
j
)
SYSTEM COMPONENT EVALUATION WORK SHEET Section C.2.6 Sheet 7 1
Joseph M. Farley Nuclear Plant Unit
?
DOCus4ENTATSON REF.
QUAL OUTSTA8eDING
?
ENVIRONMENT ITEtes 50ETHOgp EQUIPt4ENT DESCRIPTION PARAMETER SPEC
.OUAL.
SPEC.
QUAI
)
Containslgnt Cooling and OPE R ATING 4
Note 6 Note 6 Note 6 30 sec.
Note 6
$YSTEM:
TIME Furge Note i 300 Note 6 1
Note 6 Note 6 Note 6 f
COMPONENT: Solenoid Velve T M,P.
Note 2 MANUFACTURER: Autometic Valve PinESSURE 62.2 Note 6 2
Note 6 Note 6 Note 6 i
IPSIA) gg3 Co.pany (AVCO) l RELATIVE 100 Note 6 3
Note 6 Note 6 Note 6 l
MODEL MUMBER: C5439 HUM 10liY t%1 l
15 903 plus Note 6 3
Note 6 Note 4 Note 6 i
Actuate Air Operated CHEMICAL 3
l FUNCTION:
SPRAY Valve for leolation NaOH ACCURACY: SPEC: Not opp 11 cable RADIATION 5 X 10 Note 6 3
Note 6 Note 6 Note 4 I
I DEteON:
Rade NG Note 4 Note 6 Note 4 Note 6 Note 6 Note 6 Containment E1. 89'-4" T1 FLOOD LEVEL ELEV: 115'-0" SUBMER.
Note 5 Note 7 Note 5 Note 7 Note 7 Note 7 I
No GENCE I
A80VE FLOOD LEVEL:
)
NOTES:
Specified time plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipment with short operating timme ((1 h DOCUMENTATION REF ERENCES:
- 1. J.M. Farley FSAR Figure 6.2-6 Maximum temperature of time dependent temperatura profile from Reference 1.
1.
2.
- 2. J.M. Farley FSAR Figure 6.2-4 (See Figure C.3.1)
- 3. J.M. Parley FSAR Table 3.11-1 Maximusa pressure of tlw dependent pressure profile from Reference 2. (See 3.
- 4. J.M. Parley FSAR Table 6.2-19 Figure C.3.2)
Aging requirements in accordance with NUREC 0588, Section 4, Category II.
Sulmergence requirements in accordance with NUREG 0588, Section 2.2(5),
4.
- 7. Although this component may 5.
become submerged'following a Category 11 postulated accident, its safety 6.
Refer to Section B.2.
function will have been performed prior to its becoming submerged, and its further operation is not required...
-w.-
m
~.
SYSTEM COMPONENT EVALUATION WORK SHEET h
Section C.2.9 Sheet 5
Joseph M. Farley Nuclear Plant Unit 2
ENVIRONMENT DOCUMENTATION REF.
QUAL.
OUTSTANDONG METHOO REW PARAMETER SPEC.
QUAL.
SPEC.
QUAL.
siemitoneous SYSTEM: CHEMICAL AND VOLUME OPERATING 30 sec.
TIME "I"
i Test None CONTROL SAFETY INJECTION Note 1 linultaneous COMPONENT: Solenoid Valve TEMP.
300 I FI I
Note 2 51emitoneous MANUFACTURER: Automatic Switch PRESSURE 62.2
~
(PSIAI Note 3 2
Test None Company (ASCO)
Simultaneous MODEL NUMBER: yF831654V RELATIVE 5
HUMIDITY l%I 100 100 3
Test None bbm FUNCTION: Actuate Air Operated CHEMICAL HM NM+
3 34 3 3 3
5 Test None SPRAY Valve for Isolation NaOH NaOH ACCURACY: SPEC: Not applicable 5 x 10 2 x 10 3
Sequential 8
RADIATION 5
Test None DEMON.
Rede Reds Se tial Note 6 Note 4 5
T None SERVICE:
AGING yote 4 LOCATION: Containment E1.129, FLOOD LEVEL ELEV: 115'-0" SU8MER-NA N'"*
GENCE Note 5 NA A80VE FLOOD LEVEL:yes Note 5 NA
_ NOTES:
DOCUMENTATION
REFERENCES:
Specificed time plus I hour for equipment with short operating times (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
1.
J.H. Farley FSAR Figure 6.2-6 1.
Maximum temperature of time dependent temperature profile from Reference 1 2.
J.M. Farley FSAR Figure 6.2-4 2.
(see Fisure C.3.1).
3.
J.M. Farley FSAR Table 3.11-1 Maximum pressure of time dependent pressure profile from Reference 2 (see Fig. C.3.0 4.
J.M. Farley FSAR Table 6.2-19 3.
Aging requiremente in accordance with NUREC 0588, section 4, Category II.
5.
ASCO Test Report AQS21678/TR 4.
Subs.ergence requirements in accordance with MUREC 0588, Section 2.2(5), Category 11.
Rev. A dated July 1979 5.
The qualified life is being determined and will be reflected in the 6.
Surveillance and Maintenance procedures. See Appendix 5.Section I.
Summary of Aging Evaluations.
~.
6 SYSTEM COMPONENT EVALUATION WORK SHEET Seetien C.2 9 Sheet i DUTSTANDING Joseph M. Feeley Nuclear Plant Unit _ t DOCLMAENT ATION REF*
MEM guat IIE W d
ENVlRONMENT Ot#AL.
SPEC.
.OUAL.
PARAMETER SPEC.
Mene 5
sisenttanoeus 30 daye 4
Te.t OPE ATING 30 eee.
SYSTIM.
CVC8/Sofety injection gE
,o,e i None 340*
1 5
stamalteneous
/
l Test 1
300 I
COMPONENT: Lisett Switch Note 2 isone 2
5 simetteneeve i
S NE 42.2 84.7 Test MANCo Controle MANUFACTURER:
Note 3 i
mene sinutteneous 3
5 RELATIVE 100 100 j
EA-100 HUMIDtIY (%I l
MODEL HUMBEN:
None f
5 simultaneous U 903+
3 Test N 303 plus 3
CHEMICAL.
3 Velve poettien SPRAY NaOH NaOH FUNCTION:
Nene 5
sequential Indication 8
3 5 x 10 2 e 10 Test NADIATION ACCURACY-SPEC:
N/A Rede Rede None j
Note 4 Note 7 Note 4 5
seepsontist DEMON:
Test k,
i t
AGING Contetsument E1.111.On 8
Ilene N/A Tt :
& hava Note 5 Note 6 sueMER-Note 5 Note 6 1,
FLOOD LEVEL Et EV: 115 GENCE l
i i
i A80VE FLOOO LEVEL: g NOTESL l
times ((1 heer).
i DOCUMENTATION
REFERENCES:
Specified time plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipment with short operat ngfile fr Newlansas temperature of time dependent tempeistore pro 3.
f
- 1. J.M. Farley FSAR Figure 6.2-6 (See Figure C.3.1) from Reference 2. (See 2.
l
- 2. J.N. Farley FSAR Figure 6.2-4 Mexisnam pressure of tlane dependent pressure profile j
- l. J.H. Farley FSAR Table 1.11-1 4, Category 11.
3.
l
- 4. J.M. Farley FSAM Table 6.2-19 Aging requiremente in accordance with NUREC 0 Figure C.1.2) tion 2.2(5),
- 5. NAMCo Test Report dated
(
4.
Noveseber 21, 1977 end QTR-following a postulated accident, 5.
its becoming submerged, 105 dated August 28, 1980 Althougli this component may become submerged Category II.
les esfery function will have been performed prior to does not ef fect othe 6.
failure its further operation to not required, and its flected in the The qualified life is being determined and will be resee Appendix 5 eefety equipment.
Surveillance and Maintenance procedures.
7.
Summary of Aging Evaluations.
i E
SYSTE:2 COeAPONENT e.. ALUATION UWORK SHEET Sectlen C.2 9 Sheet 6e I
OUT8TANIMNG Unit _ ?
DOCuetENT ATION MF.
guat "I"I Joseph M. Farley Nuclear, Plant 88EI ENVinONaefMT OUAL.
SPEC.
i
.OUAL.
PARAa4ETEN '
SPEC.
None
'~
5 Steuttanoeus 30 doye 4
feet
^'
30 sec.
CVCS/Sefety injectlen ME IIene Mote g Simultaneous j
SYSTEM:
3 m'
1 T..t i
300 Limit Switch Note 2 Mene l
COtePONENT:
5 staultaneous 2
PRE
- SUME 62.2 84.7
- Teet, MAMCo Centrole O^I Note 3 IIene
'i MANUFACTURER:
5 Simultaneous 3
7,,g RELATIVE 100 100 EA-100 HUMIDilY 4%I llene teODElleutstEn:
5 Simultanesus
- 303+
3 Test N 903 pies 3
CHEMICAL 3
Velve Peettiess SPRAY NaOH Meott Sequenttel Itene FUNCTION:
3 8
3 Indtestten I
2 s 10 Test 5 X 10 MADIAft0N Rede Rede ACCunACY. SPEC:
N/A DEMON:
g Test IIene Contefament E1.129'-O' N/A g
IInte 5 None in :
sueMER.
Note 5 None FLOOD LEVEL Et EV: 115 GENCE AeOVE FLOOD LEVEL: yes NOTESL ting times ((l hour).
Spectited time pies I hour for equipment with ehert operaofile free R DOCut4ENTATlON REFERENCE 8:
Maulanini temperature of time dependent temperature" pr 3.
- 1. J.H. Farley FSAR Figure 6.2-6 file frase Reference 2. (See 2.
- 2. J.H. Farley FSAR Figure 6.2-4 (See Figure C.3.1)
Mentanum pressure of time dependent pressure pro 588, Sectio
- 3. J.M. Farley FSA" Totale 3.11-1 3.
- 4. J.M. Farley FSAR Table 6.2-19 Aging requiremente in accordance with NtfREG 0 0588, Section 2.2(5),
Figure C.3.2)
Sulemergence-requiremente in accordance with letfREC
- 5. MAMco Test Report deced 4.
Hovember 21, 1977,and QTR.
5.
d in the The. qualified life is being determined and will be reflecteSee Appendix 105 dated August 28, 1980 Category II.
Surveillance and Maintenance procedures.
6.
Summary of Aging Evaluations.
I
SYSTEM COMPONENT EVALUATION WORK SHEET d
Section C.2.9 Shoot 8 Joseph M. Farley Nuclear Plant Unit 2
ENVIRONMENT DOCUMENTATSON NEF.
QUAL.
OUTSTANEWWG METN0g ITE M PARAMETER
- SPEC, OUAL.
SPEC.
QUAL.
Simitammo SYSTEM: CIENICAL AND VOLUM OPERATING 30 sec.
l CONTROL SAFETY INJECTION TIME 30 days 4
5 g
Sisultaneous i
i COMPONENT: Solenoid Valve TE 300 346 1
5 Test None I I Note 2 i
Simultammi l
62.2 MANUFACTURER: Automatic Switch PRESSURE p
2 5
(PSIAI Note 5 Test None f
Company (ASCO) 1 RELATIVE Simultaneoun MODEL NUMBER: Np831654V 100 100 3
HUMIDITY l%I Test None i
H M) +
Hm+
3 CH M L
3 3 3
5 None FUNCTION: Actuate Air Operated g
Valve for Isolation NaOH NaOH l
ACCURACY: SPEC: Not applicable 5 x 10 2 x 10 sequential 7
RAD A ON 5
DEMON:
Rede Rede Test None
"'I*t A'
Note 4 Note 7 Note 4 5
h Ti
- Contaisusent E1.111 1
l FLOOD LEVEL ELEV: 115'-0" SUSMER-i ABOVE FLOOD LEVEL: No GENCE Note 5 Note 6 Note 5 Note 6
,g y,,,
3 i
NOTES:
i DOCUMENTATION REF ERENCES:
Specified time plus I hour for equipment with short operating times (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
}
1.
J.M. Farley FSAR Figure 6.Z-6
- 1. ";;'- ;-P; ;tg ' "- d a-d
- t-a- * - -"' '- " '--
t l
': ':": '"l:' ""A. L'""3 i':'
2-Nazimum pressure of time dependent pressure profile from Reference 2 (see Fig. C.E 4.
ASCO Test Report AQS21678/TR 3.
j Rev. A dated July 1979 4.
Aging requirements in accordance with MUREC 0588. See**on 4 Category II.
5.
Submergence requiremente in accordance with NUREC 0580 Section 2.2(5). Category E l
, 6.
Although this component may become submerged following a postulated accident. Its
{
safety function will have been performed prior to its becomina, submerged. Its furg operation is not required, and its failure does not affect other safety equipmentd I
7.
The. qualified life is being determined and will be reflected in the
{
Surveillance and Maintenance procedures. See Appendix 5.Section I.
}
Summary of Aging Evaluations.
i I
-m-3
ALUATlON WORK SHEET lg Section C.2.12 SYSTEM C00APONEh Sheet 2 _
i
.!- ph M. Farley Nuclear Plani Unil 2 DOCURAENTATSON REF.-
gigAL.
ITEMS OtfTST am m ann 4
ENVIRONMENT 90ETNOg Ouat.
.OUAL.
SPEC.
j FARAMETER '
SPEC.
None 4
5 slantteneous OPERATING 30 sec.
30 days rest Liquid Weste Disposal TIME SYSTEM:
Note I Wees 346 3
5 Simiteneous rest 1EteP*
300 COMPONENT: Solenoid Velve Nota 2 None 2
5 Simitoneses Automatic Switcle PRESSURE 62.2 110 rear f
MANUFACTURER:
I'I'"I Note 3 None Company 3
5 ilauttanoeue I
100 100 f* 82
- @EL NUMBER: WF8316A74E g,
gg,,,
R BO) plus 3
3+
)
3-gg,,gg,,,,,,
N 90 CHEMICAL j
Actuate Air Opereted SPRAY 3
FUNCTION:
f Velve for Isolation 8
3 5
Sequential None 5 X 10 2 m 10 Test ACNW:
Not applicable RAOIATION Rede Rede f
E***
E
~
Containment El. 109' 1
FLOOD LEVEL ELEY: 115'-0" SUBMER.
Note 5 Note 6 Ilote 5 Note 6
'N/A Wome 6
f 3
l t
GENCE No J
ABOVE FLOOD LEVEL:
i l
NOTES:
i
(( l hour).
l
- DOCUMENTATSON REF ERENCES:
Specified time plus I hour for equipment with ehert operating t i
/
I.
- 1. J.H. Farley FSAR Figure 6.2-6 Maxismun teeperature of time dependent 2.
Refer 6nce 2. (See
- 2. J.H. Farley FSAR Figure 6.2-4 (See Figiere C.1.1)
Nnalamiei pressure of time dependent press ef e profile f ree
- 3. J.H. Farley FSAN Table 3.11-1 3.
i 4 Category II.
- 4. J.H. Farley FSAM Table 6.2-19 Aging requirements in accordance with NilpEC 0588, Sect on Figure C.).2) l 8 Section 2.2(5),
- 5. ASCO Test Report AQS21678/11L Sule.rgence requirements in accordence with MUREC 058 4.
1 New A dated July 1979 5.
d in the 7.. The qualified life is being determined and will be reflecteSee Appendi Catfory II.
- 6. Although this component,may become submerged following a Surveillance and Maintenance procedures.
postulated accident, its safetyfunction will have imen performed Summary of Aging Evaluations.
I l
prior to its becoming sulumerged.
j its further operations is not re-quired, and its fatture eloes not effect other safety equipment, j
4 i
4 o
i I
SYSTEM COMPONENT EVALUATION WORK SHEETd section C.2.12 Sheet
- 3 Joseph M. Feeley Nuclear Plant tJnit 2
DOCUMENTAflON REP.'
OUAL OUTSTAfeelseo ENVIRONMENT EW my PARAMETER SPEC.
.OUAL.
SPEC.
GUAL.
5 Sinu 1Leneous None j
SYSTEM: Liquid Weste Disposal 30 sec.
30 days 4
DPfRATING Test TIME i
System Note 1 T
300 340 1
5 Simultaneous None ConsPONENT: Limit Switch Test Note 2 MANUFACTURER: MANCo Controle PRESSURE 62.2 84.7 2
5 Simultaneous None Test j
^I Note 3 l
3 5
simultaneous None MODEL NUMBER: EA-180 RELATIVE 100 100 i
Teet HUMIDITY (%I j
l 18 903 plue 3
3+
3 5
Simultaneous None H 50 i
FUNCTION: Valve Fooitton CHEMICAL SPRAY 3,
j Indication
{
I 0
3 5
Sequential None 5 X 10 2 x 10 Test ACCURA M MC:
N/A RADIATION DEM Rede Rede Note 4 5
Sequential Mone SERVICE:
AGING Mote 4 Note 7 Test i
I LOCATION: Containment Et, 109, FLOOD LEVEL ELEV: 115' SUBMER.
Note 5 Note 6 Note 5 Note 6 Note 6 None 4
GENCE ABOVE FLOOD LEVEL: No i
NOTES;_
Specified time plus I hour for equipment with short operating times ((1 DOCUMENTATION REF ERENCES:
i Maximusi temperature of time dependent temperature profile from Reference 1.
- 1. J.M. Farley FSAR Figure 6.2-6 f
- 2. J.M. Farley FSAR Figure 6.2-4 2.
(See Figure C.3.1)
~
Hamimum pressure of time dependent pressure profile from Reference 2. (See
- 3. J.M. Farley FS AR Table 3.11-1 3.
- 4. J.M. Ferley FSAR Table 6.2-19 Aalna requirements in accordance with MUREC 0588, Section 4, Category II Figure C.3.2) l dated l
- 5. NANCo Test Reporte 4.
Sule.orgence requiremente in accordance with NileF.C 0588, Section 2.2(5),
November 21,1977 and Q1R-105
^
5.
Although thle component may become submerged follouing a postulated ac I
dated August 28, 1980
- Catnory 11.
d, its safety function will have been performed prior to its becoming submerge 6.
i ffect its further operation is not required, and its failure will not a i
i other safety equipment.
l The qualified life is being determined and will be reflected in theSee App s
j 7.
Sureve111ange,andgjn}ntenance procedures.
i
~
.-s SYSTEM COMPONENT EVALUATION VWORK SHEET. A Section C.2.12
{
Sho6t' 4 J _. ' M. Farley Nuclear Plant Unit 2
DOCUMENT AflON REF.
- mat, OUTSTANDINO ENVIRONMENT HM METHOO EMME DNMW PARAMETER SPEC.
OUAL.
SPEC.
QUAL.
Simitenown OPE ATING 30 sec.
30 days 4
5 SYSTEM: Liquid Maste Disposal Test Note 1 Simulteneoun COMPONENT: Solenoid Valve TEMP.
300 340 I
3 Test l'F)
Note 2 l
Simultanemi.,,,,
MANUFACTURER: Automatic Switch PRESSURE 110 2
5 62.2 Test (PSIA)
Note 3 Company (ASCO)
Simultaneoun HUMIDITY 1%I 100 100 3
5 MODEL NUMBER: 206-381-6RF RELATIVE
.reet Simultaneour i
FUNCTION: Actuate Air Operated CHEMICAL H 30 +
H BO 4 SPRAY N!OH M$0H Test Valve for leolation 8
Sequent al y,,,
5 x 10 2 x 10 3
5 ACCURACY: SPEC: Not applicable RADIATION Test DEMON:
Rede Rede
" I*
AGING Note 4 Note 7 Note 4 5
None L
TION: Containment E1. 110, GENCE Note 5 Note 6 Note 5 Note 6 N/A Mene FLOOD LEVEL ELEV:
115'-0" SUBMER-A80VE FLOOD LEVEL: No NOTE 5:_
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
Specified time plus I hour for equipment with short operating times (
DOCUMENTATION
REFERENCES:
Maximuse temperature of time dependent temperature profile from Referencg 1 1.
J.M. Farley PSAR Figure 6.2-6 1.
S l
2.
J.M. Parley FSAR Figure 6.2-4 2.
Maxisms= press.sre of time dependent preasure profile fross Reference 2 (see Figure C.3.1).
3.
J.H. Farley FSAR Table 3.11-1 4.
J.H. Farley FSAR Table 6.2-19 3.
Aging requiremente in accordance with NilREC 0588, Section 4. Category II.
Submergence requiremente in accordance with NUREG 0588, Section 2.2(5), Category 11.
5.
ASCO Test Report AQS21678/TR 4.
RevtA dated July 1979 5.
f te '
Although this component may become submerged following a postulated accident.
6.
safety function will have been performed prior to its becoming submerged. Its furt quip t
operatfun is not required, and its f ailure will not af fect other safety [urveITSan. kc The qualified life is being determined and will be reflected in the and Maintenance procedures. See Appendix 5,Section I, Summary of Aging 7.
Evaluations.
l
e4
.g d.
SYSTEM COMPONENT EVALUATION WORK SHEET Sectism C.2.12 Sheet 5
Unit 2
a.
,,h M. Faeley Nuclear Plant DOCUMENTATION REF.
- gunt, OUTSTANDON0 g gggg ENVIRONMENT 90ETH00 EQUIPMENT DESCRIPTION PARAMETER SPEC.
.OUAL.
SPEC.
OuAL.
OPERATING 4
5 Simultaneous None
)
SYSTEM: Liquid Weste Disposal TIME 30 sec.
30 days feet Note I l
Systesa l
- TEMP, 100 346 1
5 sinuttennene None feet CuesPONENT: Solenoid Velve l'F)
Note 2 j
2 5
stansiteneeve None MANUFACTURER: Automatic Switch PRESSURE 62 2 110 rest gesing Note 3 Company j
3 5
simultaneous None L I 100 100 rest MODEL MUMRER: MF6316A54E g,
J CHEMICAL ll 803 plue 3
3+
3
$lenaltaneenes None H 80 i
FUNCTl3N: Actuate Air Operatee SPRAY yg I
Velve for Isolation I
2 m 10' 3
5 segueettet Wene 5 X 10 Test I
ACCURACY: SPE
,Not app 1tceble fqAOfATNN4 Rede Rede 4
Note 4 5
se tiet None Note 4 Note 6 AGING Containment E1. 117, L
Tl :
FLOOD LEVEL ELEV: 115'-0" sueMER.
Note 5 N/A Note 5 N/A N/A IIone GENCE A80VE FLOOD LEVEL: Yes L
NOTESL i
Specified time plus I hour for equipment with short operating DOCUMENTATION REF ERENCES:
I.
temperature of time dependent temperature profile from Reference 1.
- 1. J.H. Farley FSAR Figure 6.2-6 l
- 2. J.M. Farley FSAR Figure 6.2-4 2.
Healmust (See Figiere C.1.1)
(See Maxismum pressure of time dependent pressure profile f ree Reference l
- 3. J.H. Farley FSAR Table 3.11-1 1.
- 4. J.H. Farley FSAR Telete 6.2-19 it.
Figure C.J.2)
Aging requirements in accordance with NUREC 0588, Section 4, Categor
- 5. ASCO Test Report AQS21678/TR Sulmeergence requirements in accordance with NUllEC die 8, Section 4.
Rev. A dated July 1979 4
5.
Catgary 11.
The qualified life is being determined and will be reflected in the 6.
Surveillance and Maintenance procedures. See Appendix 5 Section I, Summary of Aging Evaluations.
Joseph M. Farley Nuclest Pteret Unit __ 2 N#
I Sutton C.2.13
$ hest 2
gCLAss it ELECTRICAL EcutMcENT CEQUCED 70 FUNCTION UNDER POSTU 13TInd UAIN ITEAM t.ATED ACCIDENT CONorTM3essl i
W-11 FLANT ID NLHBER COMPONENTS
~
GENERIC EAME MANLTALWRIR 7
ICDEL Q2N11Z339764 LOCATION
~
(ava976A)
BLDC i
tf=ft switch NASCO EA-180 C.rv
~
Q2N11SV39763 (NV39763) g,ta.
~
q 333,,7, t
Q2N112S39763 Solenoid Yalve ASCO Mn (ava 9763)
NP8321A2V Roo. S tm.
~
I' m
Limit Switch 131'.7n Q1N11SV3976C NAMCO Mn.Stm.;
~
Cava976C)
YA-1 en
' Room
- ist'.7n Q2N11253976C Solenoid Yalve Mn.Stm.
ASCO NP8321A2V Room (HV3976C)
Limit Switch 131'.7a NAMCO Mn.Stm.
~
EA-180 Room
_ tit'.in Q2N11Sv3369AA-A/JB Terminal BlockStates Co.
%.Stm.
Type ZUM Room Q2N11SV33693A-A/J3 Terminal Block 131'.0" States Co.
t.S tm.
Type 2LH toom tit'.nn Q2N11Sv3369CA-A/JB Tarminal Block t
States Co.
Type ZbH too.Stm.j131'-0"
~
m I
_ t Q2N11Sv3370AA-3/JB Tereta=1 Block L
States Co.
Ms.Sem.
Q Type IVM Room 137 '.nu
_iN11Sv33703A-3/J3 Termisal Block States Co.
Tvoe ZLH Mn.Sem.
Q2N11573370CA-3/JB Terminal Block 9
137'.on States Co.
Mn.Sem.
Woe TVM R o c-.
137'-0"
' Q2N11Sv3368AA-A/JBTersfn=1 Block States Co.
Mn.Sem.
Tyve ZUM Room 137'-n" 02N115733681A-A/JB Terminal Block States Co.
Mn.Sem.
~
Twee tw Room 1 77'.0" Q2N11Sv3368CA-A /J3 Terminal 31ockStates Co.
Mn.Sem.
! D2N11 tv39763-3/JBTer inal 11ock Mn.Sem.
~
Ne 7W Po e**
li.a"
~
States Co.
Tvoe 2LH Room 137'.nu Q2N11573976C-3/J3 Terminal 31ock Mn.Sem._
States Co.
Type ZbH
' Room 137'.nu 27AL5019E, ?
Control Cables Okenita None Mn.Sem. 135' 2 VAL 5045C Room
- r.. w..
Control Cable Okanita Nona Ma. Sem 135 '
2VAQS013A Room
& above 6
Control Cable Okonita Mn.Sem. 135' None GPa.1273 stap
, Room l & above y
, _ _,... _, _,... ~ -. _
.___,.___,_.,,_._.s..
~
s SYSTEM COMPONENT EVALUATION WORK SHEET d
faction C.2.13 Joseph M. Ferley Nuclear Plant Unit 2
M 5 l
ENVIRONMENT DOCUMENTATION REF.
OUAl-OUTSTANDING EQUIPMENT DESCRIPTION METHOD ITEMS PARAMETER SPEC.
QUAL.
SPEC.
QUAL.
8 I"I ""*"'
SYSTEM: Main Steam OPERATING 10 min.
30 days 3
4 None Test TIME Note 1 I
8 I" * * "* " '
COMPONENT: Limit Switch TEMP.
308 340 1
4 Mone Test goFl Note 2 i
8 I""II *"*"'
MANUFACTURER: Namco Controls PRESSURE 20.5 84.7 1
4 None Test i
(PSIA)
Note 3 i
8I""I"*"**"'
MODEL NUMBER: EA180 RELATIVE 100 100 2
4 Nm Teet HUMIDITY (%I Simultaneous "3
3*
None 4
FUNCTION: Valve Position CHEMICAL None NaOH Test Indication SPRAY I
ACCURACY: SPEC:
N/A 2 x 108 Sevential RADIATM None I
DEMON:
Rads 1
8
"'I*I SE RVICE-LOCATION: Mn. Stm. Rm. 135'-On AGING Note 4 Note 6 Note 4 4
None 4
FLOOD LEVEL ELEV: 130'-5" SUBMER-Note 5 N/A Note 5 N/A N/A Mone 0
l ABOVE FLOOD LEVEL: Yes GENCE i
DOCUMENTATION
REFERENCES:
NOTES:
l 1.
Bechtel Calculation 525-25-7597 1.
Specified time plus I hour for equipment with short operating times (<, I hou from computer run T-10576 2.
Naximum temperature of time dependent temperature profile from Reference 1.
2.
J. M. Farley FSAR Chapter 3, (See Figure C.3.3)
Appendix 3K 3.
Naximium pressure of time dependent pressure profile from Reference 1.
(!!ee 3.
J. M. Farley FSAR Sect.
Figure C.3.3) 3K-4.1.1.10 4.
Aging requirements in accordance with NUREG 0588 Section 4, Category II 4.
Namco Test Report GTR105 5.
Submergence requirements in accordance with NUREC 0588, Section 2.2(5),
Category II 6.
The qualified life is being determined and will be reflected in the Surveillance and Maintenance procedures. See Appendix 5,Section I.
Summary of Aging Evaluations.
I
_ _ _ _ =
o l
m I
SYSTEM COMPONENT EVAL.UATION WORK SHEET %section C.2.13 l
Sheet, 6 Unit 2
A, f,h M. Farley Nuclear Plant DOCUMENTATION REF.
QUAL.
OUTSTANOING ITEMS ENVIRONMENT METHOO EOulPMENT DESCRIPTION PARAMETER SPEC.
QUAL.
SPEC.
QUAL.
l OPERATING 10 Min.
30 Days 3
4 Simultaneouii None i
Test SYSTEM: Hein Steam TIME Note 1 8I""II*"**""
Nm COMPONENT: Limit Switch
(
TEMP.
308 340 1
4 Test
( FI Note 2 8L"*I"*"**""
h MANUFACTURER: Namco Controle PRESSURE 20.5 84.7 1
4 Test i
(PSIA)
Note 3 Simulteneouo i
MODEL NUM8ER: EA180 RELATIVE 100 100 2
4 Teet HUMIDITY (%)
Simultaneoua
.l H BO CHEMICAL
'ya yhg3+ -
4 None Test
)
FUNCTION:
Velve Position SPRAY Indication g
None ACCURACY: SPEC: N/A RADIATION i
DEMON:
8 Mone AGING Note 4 Note 6 Note 4 4
Hn. Sta. Rm. 127'-See 5
L TION:
Sequentiel None 10 feet -
Note 5 5
l
,7,,,
FLOOD LEVEL ELEv: 130'-5" SU8MER.
Note 5 for 24 hre.
GENCE l
ABOVE FLOOD LEVEL: No 1
NOTES:
DOCUMENTATION
REFERENCES:
Specified time plus I hour for equipment with short operating times i
1.
Bechtel Calculation 525-25-7597 1.
I Maxinnun temperature of time dependent temperature profile from R (d. I hour).
from computer run T-10576 2.
2.
J. M. Farley FSAR Chapter 3, i
(SeeFigureC.3.4)ld (See Maximum pressure of time dependent preseure profile from Reference 1.
1 Appendix 3K 3.
3.
J. M. Parley FSAR Sect.
Aging requirements in accordance with NUREC 0588 Section 4. Ca Figure C.3.3) 3K-4.1.1.10 4.
Submergence requiremente in accordance with NUREC 0588, Section l
Namco Test Report GTR105 4.
5.
j Change Notice Number 2BE-1049 Rev. 3 Category II 5.
The qualified life is being determined and will be reflected in the l
Surveillance and Maintenance procedures. See Appendix 5.Section I.
l 6.
Summary of Aging Evaluations.
M
e SYSTEM COMPONENT EVALUATION WORK SHEET lA l
I I2 Seetton C.2.13 1
Joseph M. Farley Nuclear Plant Unit 2
sheet 7
i i
ENVIRONMENT DOCUMENTATION REF.
OUAL.
OUTSTANDING j
METHOD ITEMS
{
EQUIPMENT DESCRIPTION PARAMETER SPEC.
QUAL.
SPEC.
QUAL.
8 I"I " *"*"'
SYSTEM: Main Steam OPERATING 10 min.
30 days 3
4 None Test TIME Note 1 308 Simultsnoous COMPONENT: Solenoid Vahra TEMP.
346 1
4
('F)
Note 2 Test None 8I""IE***""'
20.5
)
MANUFACTURER: Automatic Switch PRESSURE 110 1
4 l
Company (ASCO)
(PSIA)
Note 3 Test None 1
8I""I"*"**"'
MODEL NUM8ER: HP8321A2V RELATIVE 100 100 2
4 Tast None HUMIDITY (%1 Simultaneous FUNCTION: Acuate Air Operated pHEMICAL None 3 3+
None 4
y,,,
valve for Isolation SPRAY NaOH Test l
2 x 108 g,q,,,gg,g ACCURACY: SPEC: N/A RADIATION Nm None l
DEMON:
Rede Test Sequential LOCATION: Hn. Ste. Rs. 131'-7ee AGINO Note 4 Note 6 Note 4 4
None f
SERVICE:
i Test k
i FLOOD LEVEL ELEV: 130'-5" SUOMER-ABOVE FLOOD LEVEL: Yes GENCE Note 5 N/A Note 5 N/A N/A Mone 6
i NOTESL l
DOCUMENTATION
REFERENCES:
l 1.
Bechtel calculation 525-25-7597 1.
Specified time plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipment with short operating times (4. I hou l
from computer run T-10576 2.
Maximum temperature of time dependent temperature profile from Reference 1.
2 J. M. Farley FSAR Chpater 3, (See Figure C.3.4)
Appendix 3K 3.
Maximum pressure of time dependent pressure profile from Reference 1.
(See 3.
J. M. Farley FSAR Sect. 3K-4.1.1.10 Figure C.3.3) 4.
ASCO Test Report AQS21678/TR Rev. A 4.
Aging requirements in accordance with NUREC 0588, Section 4, Category II dated July, 197f 5.
Submergence requirements in accordance with NUREC 0588, Section 2.2(5),
Category 11 6.
The qualified life is being determined and will be reflected in the Surveillance and Maintenance procedures. See Appendix 5.Section I, Summary of Aging Evaluations.
l
SYSTEM COMPONENT EVALUATION WORK SHEET section C.2.13 Sheet 8 Joseph M. Farley Nuclear Plant Unit 2
ENVIRONMENT DC 'UMENTATION REF.
OUAL OUTSTANDING METHOD iEMS EQUIPMENT OESCRIPTION PARAMETER SPEC.
QUAL.
SPEC.
1 OUAL I" I ""* "'
30 day::
3 4
Mone SYSTEM: Nain Steam OPERATINO 10 min.
Test TIME Note 1 I"I E*"* "'
346 1
4 None COMPONENT: Solenoid Valve TEMP.
308 Test
(*F)
Note 2 Simultaneous 20.5 110 1
0 Na MANUFACTURER: Automatic Switch PRESSURE Test (PSIA)
Note 3 Company (ASCO) 8 I"II*"*"'
MODEL NUMBER: NP8316E36V RELATIVE 100 100 2
4 None Teot HUMIDITY (%I I"
"3 3+
None 4
None FUNCTION: Actuate Air Operated CHEMICAL None SPRAY NaOH Test Valve for Isolation OM.
RADIATION None None 4
(equential.
None Sequentist None Note 4 4
SERVICE:
AGING Note 4 Note 6 Test LOCATION: Nn. Stm. Rm.135 8-0 e b
FLOOD LEVEL ELEV: 130'-5" SUBMER.
Note 5 N/A Note 5 N/A N/A Mone ABOVE FLOOD LEVEL: Yes GENCE E
NOTES:
DOCUMfNTATION
REFERENCES:
It 1.
Bechtel calculation 525-25-7597 1.
Specified time plus I hour for equipment with short operating times (d.
Haximum temperature of time dependent temperatura profile from Reference 1<
froni computer run T-10576 2.
(See Figure C.3.4) 2.
J. H. Farley FSAR Chapter 3, Maximum pressure of time dependent pressure profile frem Reference 1.
(See 3.
Appenwix 3K 3.
J. H. Farley FSAR Sect. 3K-4.1.1.10 Figure C.3.3) 4.
ASCO Test Report AQS21678/TR Rev. A 4.
Aging requirements in accordance with NUREC 0588, Section 4, Category II dated July,1979.
5.
Submergence requirements in accordance with NUREC 0588, Section 2.2(5),
Category II
- 6. The qualified life is being determined and will be reflected in the Surveillance and Maintenance procedures. See Appendix 5,Section I, Summary of Aging Evaluntions.
j
~
s SYSTEM CONIPONENT EVALUATION WORK SHEET l4 f
Section C.2.13 Sheet 11 i
j Joseph M. Ferley Nuclear Plant Unil 2
DOCU8sENTATION MEF.
- empal, OUTETANDING ENVIRONMENT
- NETHnO, HEMS j
FARAMETER SPEC.
.OUAL.
SPEC.
GUAL.
Ne**
5 Simultaneou.
f OPE ATING n
4 Test n.
SYSTEM:
Nata Steams Note 1 4 monthe m,
e,b.c j
T 300 COMPONENT: 1Avel Transettter Test Note 2 2
5 Simultaneous Wees MANUFACTURER:
Berton ITT SURE 62.2 89.7 Test l
Mote 3 100]a,b.c l
~
RELATIVE 100 MODEL NUMBER: h Teet HUMIDITY 1%1 5
b'4 wt 'cto +
1 Simultaneoui Ween ric s 3
5 Imvel indicetton CHEMICAt.
18 903 plus 0.17 wt. of Test 3
FUNCTION:
SPitAY MaOH Haunt j
-e,b c 7
3 5
Segmential None 3 x 10 5 K 10 Te.t j
ACCURACY:
Mots 6 MAO!ATION
. l.
y..m.
j Note 4 5
sequential Noes Note 4 Note 7 Test i
AGING
- Containment E1.116'-Oee T
115' sUeMER.
Isote 5 N/A Note 5 N/A N/A None FLOOD LEVEL ELEV:
GENCE Yee l
ABOVE FLOOD LEVEL:
h NOTE 3:_
t j
Spectfled time plus I hour for equipment with short operating tim DOCUMENTATION
REFERENCES:
l Hulouse temperattere of time dependent tesquerature profile f ree R 1.
I
- 1. J.M. Farley FSAR Figure 6.2-6 2.
- 2. J.M. Farley FSAR Figure 6.264 Malmum preunte of time dependent pressure profile from Reference'2.
(See Figure C.3.1) j
- 3. J.M. Farley FS AR Table 3.11-1 3.
- 4. J.M. Farley FSAR Table 6.2-19 Aning requirem-ata in arenrdance with NUREG 0588, Section 4, Cate Figure C.3.2) f Sulmiergenre requiresnents in accorstence witle NUREC 0588, Section
- 5. WCAF 9885 4
I I5.
5 min. to 4 mes., f25ba,b,e Category 11
+107., (-)D0 for 5 min 1 max. error,0-5 min.,$7.; 5 min. to 4 mos., 17T._j j
- 6. [ Accuracy requiremente:The qualified life is being de 4
Accuracy demonstrated:
1 7.
See Appendix 5.Section I, l
. Surveillance and Maintenance procedures.
j Summary of Aging Evaluations.
4 i
f SYSTEM COMPONENT EVALUATION WORK SHEET Section C. 2.14 l
Sheet 3 Joseph M. Farley Nuclear Plant Unit 2
ENVIRONMENT DOCUMENTATION REF.
GUAL OUTSTANENNO METHOO ITN EQUIPMENT DESCRIPTION PARAMETER SPEC.
QUAL.
SPEC.
QUAL.
Simultaneous SYSTEM: Auxillary System OPERATING 10 Min TIME Note 1 30 Days 3
4 Test NONE PLANT ID NO.
Simultanoone 308 4
NONE COMPONENT:
Limit Switch TEMP.
340 1
Test
(*F)
Note 2 SI*"II*"
20.5 84.7
- I 4
'gg MANUFACTURER: NAMCO Controle PRES $URE Test (PSIA)
Note 3 f
2 4
Teet NONE MODEL NUM8ER: EA180 RELATIVE 100 100 HUMIDITY (%)
S I ""II* " ***
H BO FUNCTION: Valve Poeltion CHEMICAL NONE 3
3+
NONE 4
Test NONE Indication SPRAY NaOH 8
,sequenttal ACCURACY: SPEC:
N/A 2 x 10 NOME NONE 4
Test RADIATION NONE Rade l
DEMON:
l
4 4
NONE AGING Note 4 Note 6 Mn. Stm. Rm.134'-on Tl :
}
FLOOD LEVEL ELEV: 130'-5" SU8MER-Note 5 N/A Note 5 N/A N/A NONE 1
A80VE FLOOD LEVEL: Yes GENCE
[
}
NOTES:
DOCUMENTATION
REFERENCES:
- 1. Specified time plus I hour for equipment with short operating times (el hbor
- 2. Maximum temperature of time dependent temperature profile from Referd
- 1. Bechtel Calculation 525-25'-7597 from computer run T-10576
- 1. (See Figure C. 3.4)
- 2. J. M. Fa rley FS AR Chapter 3,
- 3. Maximum pressure of time dependent pressure profile from Reference 1.
4 Appendix 3K l
- 3. J. M. Farley FSAR Sect.
Figure C.3.3)
- 4. Aging requiremente in accordance with NUREG 0588. Section 4, Category 3 K-4.1.1.10
- 5. Submergence requiremente in accordance w.th NUREG 0588, Section Z.26
]
- 4. NAMCO Test Reptrt OTR 105 Category II
- 6. The qualified life is being determined and will be reflected in the d
Surveillance and Maintenance procedures. See Appendix 5,Section I, Summary of Aging Evaluations.
1 l
SYSTEM COMPONENT EVAu"ATION WORKSHEET Q
Section C.2.14 Sheet _ 4 Unit 2
OUTSTAND 0NG Joseph M. Farley Nuclear Plant DOCUMENT ATION REF.
QUAL.
ITEMS ENVIRONMENT METNOO EQUIPMENT DESCRIPTION
- *""*"**"* NONE Test 10 Min 30 Days 3
4 OPERATING Note 1 Simultaneone Ainxillary System TIME NONE SYSTEM:
4 Test PLANT ID NO.
308 346 g
TEMP.
Note 2 Solenold Valve l'FI Simultaneous NONE COMPONENT:
Test y
4 20.5 11 0 Automatic Switch PRESSURE Note 3 Simultan edus f
trSIAI MANUFACTURER:
Company (ASCO)
Test NONE 100 2
4 NP8321A2V RELATIVE 100 MODEL NUMBER:
HUMIDITY l%I 81*"I t*"**"'
NONE Test H3 3*
NONE 4
Activate Air Operated CHEMICAL NONE NaOH SPRAY 8*9"*"II"I NONE FUNCTION.
Valve For Isolation g
I NONE 4
NONE I
)
RADIATION Sequential NONE N/A Test D
Note 4 4
Note 4 Note 6 AGING SERVICE:
Mn. Stm. Hm.135'-On LOCATION:
N /A Note 5 N/A N/A NONE 130'-5" SUeMER-Note 5 FLOOD LEVEL ELEV:
GENCE
)
Yea t operating times (41 hour4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br />)
ABOVE FLOOD LEVEL:
i NOTES:
i
- 1. Specified time plus I hour for equipmeist witt profile from Reference L
DOCUMENTATION REF ERENCES:
l 4
525 25 7597
(. ee
- 1. Bechtel Calculation (See Figure C.3.4) from computer run T-10576
- 3. Maximum pressure of time dependent pressure prUREG 0 L
- 2. J.M. Farley FSAR Chapter 3, NUREG 0588, Eiction 2.2(5),
Figure C. 3.3)
- 4. Aging requirements in accordance with N5, Su Appendix 3K
- 3. J.M. Farley FSAR Sect.
3K 4.1.1.10
- 4. ASCO Test Report AOS21678/TR The qualified life is being determined and wiSee Appendix 5,Section I, Category 11 Rev. A Dared July,1979 6.
Sureveillance and Maintenance procedure.
Summary of Aging Evaluations.
a 1
w i
SYSTEM COMPONENT EVALUATION WORK SHEET Section C.2.15 i
Sheet 3
{
Joseph M. Farley Nuclear Plant Unit 2
ENVIRONMENT DOCUMENTATION REF.
QUA4 OUTSTANDING i
METHOO ITEMS
)
EQUIPMENT DESCRIPTION PARAMETER SPEC.
QUAL.
SPEC.
QUAL.
OPERATING 4 houre l
SYSTEM: Hein Feedweter TIME 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 3
4 rest None j
g i
E I'"'I ' *** **
- l COMPONENT: Level Switch TEMP.
308 300 4
rest None I
Note 2 Note 6 1
Stu tteneous MANUFACTURER: DeLevel Cens PRESSURE 20.5 I
rut None (PSIA)
Note 3 i
Sensors Division 1
Simitoneaus l
MODEL NUMBER: LS-36497 RELATlVE 2
4 rest None HUMIDITY l%I 100 100 i
FUNCTION: Main Feed Pump Trip CHEMICAL M B03+
N/A 4
Teet None SPRAY None 3
NaCil l
8 Sequential 1 x 10 ACCURACY: SPEC: Not Applicable RADIATION None Rads N/A 4
rest DEMON:.H). 5" SERVICE:
Flood b yel Sensor Sequential L OCATION: Main Steam Room 133'-5" Note 4 Note 7 Nota 4 4
Test None AGING I
FLOOD LEVEL ELEV:
130'-5" SUBMER-GENCE N/A N/A N/A N/A N/A None l
ABOVE FLOOD LEVEL: Yes i
NOTES:
l DOCUMENTATION
REFERENCES:
I
- 1. Specified time plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipment. with short operating times ( < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
j
- 1. Bechtel calculation 525-25-7597 from computer run T-10576
- 2. Maximum temperature of time dependent temperature profile from Reference 1.
I
- 2. J. M. Farley FSAR Chapter 3 (See Figure C.3.4)
Appendix 3K
- 3. Maximum pressure of time dependent pressure profile fran Reference 2. (See j
3.
1, M. Farley FSAR Sect.
Figure C.3.3) l 3K-4.1.1.10
- 4. Aging requirements in accordena with NURPA 0588, Section 4, category II.
- 4. Isomedix Test Report for
- 5. Submergence requirements in accordance with NUREG 0588, Section 2.2(5),
gems liquid level sensor
- 6. Although the peak MSlJl temperature (308 F) exceeds the qualification temperature dated 11/75.
the temperature peak is of such short duration ( < 1.5 sec) that no significant increase in equipment surface temperature will occur due to thernet lag.
'The MSLB temperature after 1.5 seconds is 214"F.
- 7. The qualified life is being determined and will be reflected in the g
Surveillance and Maintenance procedures. See Appendix 5 Section I, l
Summarv nf Aoina Evn1nnriona.
8 EASTER UST 5:ction C.2.16 Joseph M. Farley Nuclear Plant Unit 2
Sheet' 1
ca. Ass IE ELECTRICAL EOUlPMENT REQUCED TO FUNCTION UNDER POSTULATED ACC N-23 AUXILIARY FEEDiiATER sysTIM:
l COMPONENTS FLANT ID NUMBER GENERIC NAME MANUTACTURER IODEL LOCATION BLDG ELEY Q2N23V011A 4" Motor Cperated Mn.Sta.
De0V3350A)
Stop-Check Globe V1 Limitoreue SMB-1 Room 137'-5" Ma.Sta.
(
Q2N23V0013 4" Motor Operated Gui33503)
Stoo-Check clobe V1 Limitoreue SMB-1 n oem 117'-g" Mn.Sta.
Q2N23V001C 4" Motor Operated Ot0V3350C)
Ston-check Clobe V1 Tinitoraue sMn-1 naam 117'-q" Mn.Sta.
Q2N23ZS3228A jnv3228A)
Limit Switch NAMCO EA-180 neem 1ste-n" Mn.Sta.
Q2N235V3228AA NP8320A186V Room 135'-0" (Hv3228A)
Solenoid valve ASCO Mn.Sta.
Q2N23ZS3228B (RV3228B)
Limit Switch NAMCO EA 180 Room 135'-0" Mn.Sta.
Q2N235V3228BA NP8320A186V Room 135'-0" mV32288)
Solenoid Valve ASCO Mn.Sta.
Q2N23ZS3228C (HV3228C)
Limit Switch NANCO EA 180 Room 135'-0" l
Mn.Sta.
i Q2N235V3228CA
~
GV3228C)
Solenoid valve ASCO NP8320A1R6v! Room 135'-0" Mn.Sta.
Q2N23ZS3227A EA 180 Room 135'-0" (MV3227A)
Limit Switch NAMCO Pts.S ta.
l l
l Q2N23SV3227AA NP8320A186V Room 13 5'-0" (nv3227A)
Solenois Valve ASCO Mn.S ta.
Q2N23ZS32275 (HV32275)
Limit Switch NAMCO EA 180 Room 13 5'-0" Mn.Sta.
Q2N235V3227BA NP8320A1869 Room 135'-0" (Hv3227B)
Solenoid Valve ASCO Mn.Sta.
Q2N23ZS3227C (HV3227C)
Limit Svitch NAMCO EA 180 Room 135'-0" Mn.Stm.
Q2N233V3227CA NP8320A186VH Room 135'-0" (RV3227C)
Solenoid Valve ASCO Mn.Sta.
l Q2N23SV3228AA-A/JB Terminal Block States Co.
Tvon m Room 144'-0" Mn.Sta.
Q2N23SV3228BA-A/JB Terminal Block states t'n_
%, m Room 144'-0" Mn.S tm.
I 02N235V3228CA-A/JB Terminal Eleck States Co.
Type ZUM Room 144'-0" Mn.Stm,
,f 02N23SV3227AA-A/JB Terminal Block States Co.
Tvoo ZUM Room 144'-0" Mn.Sta.
02N23SV3227BA-A/JB Terminal Block States Co.
Tvoe ZUM Room 144 '-0" 1
Mn.S tm.
02N23SV3227CA-A/JB Terminst Block States Co.
Tvoe IWM
_ Room 144'-0" Mn.Sta 135'-0" 2VAFD-U40_
Power Cable Okonite None Room-
& above -
Mn.Sta 135'-0"
_2VAFU-U50 Power cable Okonite None Room
& above Mn.Sta 135'-0"
(
Room
& above 2VAFU-120 Power cable okontee h.
Mn.Sta.
135'-0" Roan
& above
(
2VAFU-U4A, D Control Cables Okonita None c-GPo.1374 IS I
. + -. -... -.,....,
SYSTEM COMPONENT EVALUATION WORK SHEET i
Joseph M. Farley Nuclear Plant Unit _
2 i
seetton C.2.16 Sheet __ _ 4 EQUIPMENT DESCRIPTION ENVIRONMENT PARAMETER DOCUMENTATION REF.
SPEC.
QUAL.
SPEC.
OUAL.
METHOD ITEMS QUAL
- OUTSTANOINO SYSTEM: Auxiliary Feedwater OPERATING 10 min.
j PLANT ID NO.
TIME I
Note 1 30 days 3
4 Test Mone Simultaneoui COMPONENT: Limit Switch TEMP.
308-(*FI
{
Note 2 340 1
4
' ""II""'*"'
[
MANUFACTURER:Namco Controls Test Mone PRESSURE (PSIA) 2 5 4
31multaneous E7 1
4 Test MODEL NUM9ER: EA-180 RELATlVE Nm HUMIDITY (%l 100 100 2
4 II""I FUNCTION: Valve Position
,, t Indication CHEMICAL SPRAY t
None Il 50 +NaOH None 4
Test 3 3 Simultaneoni j
ACCURACY: SPEC:
i Not Applicable j
None i
DEMON.
RADIATION None 2x10 rads None 4
'9"*" I*
d 8
i SERVICE:
Teat None j
LOCATION: Hn. Sta. Re. E1. 135'
^U '"0 Note 4 Sequential
~
FLOOD LEVEL ELEV:
Note 6 Note 4 4
Test None 130'-5" ABOVE FLCOD LEVEL:
SU6MER.
Note 5 yes J. GENCE NA Note 5 NA NA
_ DOCUMENTATION
REFERENCES:
None j
- 1. Bechtel Calculation 525-25-7597
_ NOTES:
- 2. Maximum temperature of time dependent tempe frora computer run T-10576
- 2. J. M. Farley FSAR Chapter 3 a
ng times (4.1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
Figure C.3.4) e from Reference 1.
(See Appendix 3K
- 3. J. H. Parley FSAR Sect.
- 3. Maximum pressure of time dependent pressure profile from Ref 3K-4.1.1.10 Figure C.3.3) erence 1.
(See
- 4. Namco Test Report Q11t105 4, Aging requirementa in accordance with NUREG 0588
- 5. Submergence requirements in accordance with NUREC 0588, Section 4, cat
- 6. The. qualified life is being determined and will b, Section 2.2(5), Category II Surveillance and Maintenance procedures e reflected in the Summary of Aging Evaluations.
See Appendix 5 Section I, g-I
SYSTEM COMPONENT EVAL.UATION WORK SHEET 1,
. Sheet 5
Seetton C.2.16 I
Joseph M. Farley Nuclear Plant Unit 2-ENVIRONMENT DOCUMENTATION REP.
QUAL.
OUTSTANOH00 METHOD gyggg EQUIPMENT DESCRIPTION PARAMETER SPEC.
OUAL.
SPEC.
QUAL Simultaneou i OPERATING 10 min.
SYSTEM: Auxiliary Feedweter TIME I"
PLANT ID NO.
Note 1 Simultaneou.
COMPONENT: Solenoid Valve TEMP.
308
( Fi Note 2 346 1
4 Test Simultaneou s MANUFACTURER: Automatic Switch PRESSURE 20.5 Company (ASCO)
(PSIA)
Note 3 110 1
4 Test None l
Simultencou e i
MODEL NUMSER: NP8320A186V RELATIVE HUMIDITY l%)
100 100 2
4 Test None FUNCTION: Actuate Air Operated CHEMICAL Sequential ll 503+NaOH None 4
Test pHAY Valve for Isolation None 3
Sequential ACCURACY: SPEC: Not Applicable 8
RADIATION Hone 2x10 rado.
None 4
Test None DEMON:
i I
AGING Note 4 Note 6 Note 4 4
H***
Mn. Sts. Rm. E1. 135s
.T
(
FLOOD LEVEL ELEV: 130'-5" SUBMER-MOVE FLOOD LEVEL:Yes GENCE Note 5 NA Note 5 NA NA None NOTES:
DOCUMENTATION
REFERENCES:
- 1. Bechtel calculation 525-25-7597
- 1. Specified time plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipment with short operating times (<1 hour).
- 2. Maximien temperature of time dependent temperature profile freen Reference 1. (Sea f rom computer can T-10576 l
- 2. J. M. Farley FSAR Chapter 3, Figure C.3.4)
- 3. Mexiseum pressure of time dependent preneure prof tie from Reference 1. (See l
Appendix 3K
- 3. J. M. Farley FSAR Sect.
Figure C.3.3)
- 4. Aging requiremente in accordance with NUREC 0588, Section 4, category 11 l
3K-4.1.1.10
- 4. ASCO Test Report AQS21678/1R
- 5. Submergence requiremente in accordance with NUREC 0538, Section 2.2(5), Category j
Rev. A dated July, 1979.
- 6. The. qualified life is being determined and will be reflected in the
)
Surveillance and Maintenance procedures. See Appendix 5,Section I, Summary of Aging Evaluations.
4
h SYST2M COMPONENT EVALUATION WORK SHEET Section C.2.17 Joseph M. Farley Nuclear Plant Unit 2
She'et 2
ENVIRONMENT DOCUMENTATION REF.
OUAL OUTSTANDINO PARAMETER SPEC.
QUAL.
SPEC.
QUAL.
METHOO ITEMS SYSTEM:
Chemical Injection OPERATING 10 min Simultaneous TIME "I'
Test Note 1 COMPONENT: Solenoid Valve TEMP.
308 Simultaneous i I Mote 2 Test MANUFACTURER: Automatic Switch PRESSURE 20.5 Simultaneous I
Company (ASCO)
(PSIA)
Note 3 Test MOOEL NUM8ER: NF8316A74V RELATIVE Simultaneous HUMIDITY l%I 100 100 2
4 Test FUNCTION: Actuate Air Operated CHEMICAL Simultaneoui Valve for Isolation SPRAY Nee N 80 MW Neo 4
3 3 Test 0
ACCURACY: SPE Not Applicable RADIATION None 2x10 Rade None 4
None AGING Note 4 he6 Me4 4
h Tl
130'-5" SUBMER-Note 5 N/A Note 5 N/A N/A None ABOVE FLOOD LEVEL: Yes GENCE DOCUMENTATION
REFERENCES:
NOTES:
- 1. Bechtel Calculation 525-25-7597
- 1. Specified time plus I hour for equipment with short operating times ( < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
from computer run T-10576
- 2. Maximum temperature of time dependent temperature profile from Reference 1. (See l
- 2. J. M. Farley FSAR Chapter 3 Figure C.3.4) l Appendix 3K
- 3. Maximum pressure of time dependent pressure profile from Reference 1. (See l
- 3. J. M. Farley FSAR Sect.
Figure C.3.3) 3K-4.1.1.10
- 4. Aging requirements in accordance with NIIREG 0588, Section 4, category II i
- 4. ASCO Test Report AQ521678/TR
- 5. Submergence requirements in accordance with NilREG 0588, Section 2.2(5), Category Rev. A dated July, 1979.
- 6. The qualified life is being determined and will be reflected in the Surveillance and Maintenance procedures.
See Appt_ndix 5.Section I, Summary of Aging Evaluations.
r SYSTEM COMPONENT EVALUATION WORK SHEET g
Sheel 3 Joseph M. Farley Nuclest Plant Unit 2
ENVIRONMENT DOCUMENTATION REF.
OUAL OUTSTANDING METHOD ITEMS PARAMETER SPEC.
OUAL.
SPEC.
OUAL.
imultaneous SYSTEM: Chemical Injection OPE ATING 10 min 30 days 3
4 rest Note 1 COMPONENT: Limit Switch T MP.
308 340 1
4 None rest Note 2 3imultaneous MANUFACTURER: NAMCO controls PRESSURE 20.5 I
rest (PSIA)
Note 3 Steutteneous MODEL NUMBER: EA 180 RELATIVE HUMIDITY 1%1 100 100 2
4 reot jfyltaneous FUNCTION: Valve Position CHEMICAL None SPRAY None H B0 +NaOH None 4
3 3 Indication 8
Sequentist ACCURACY: SPEC: Not Applicable RADIATION None 2x10 Reds None 4
re st DEMON:
Sequential SERVICE:
A ING Note 4 Note 6 Note 4 4
rest LOCATION: MN. STM. RM. EL. 141'-6" FLOOD LEVEL ELEV:
130'-5" SUSMER-GENCE Note 5 N/A Note 5 N/A N/A Mone A80VE FLOOD LEVEL: Yes l
NOTES:
DOCUMENTATION
REFERENCES:
- 1. Specified time plus I hour for equipment with short operating times ( ( 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- 1. sechtel calculation 525-25-7597
- 2. Maximum temperature of time dependent temperature profile from Reference 1.
from computer run T-10576 (See Figure C.3.4)
- 2. J. M. Parley FSAR Chapter 3
- 3. Maximum pressure of time dependent pressure profile from Reference 1. (See Appendix 3K Figure C.3.3)
- 3. J. M. Farley FSAR Sect.
- 4. Aging requirements in accordance with NUREC 0588, Section 4. Category II 3K-4.1.1.10
- 4. NAMCO Test Report QTR105
- 5. Submergence requirements in accordance with NUREG 0588, Section 2.2(5),
Category II
- 6. The qualified life is being determined and will be reflected in the Surveillance and Maintenance procedures. See Appendix 5.Section I, Summary of Aging Evaluations.
i 1
SYSTEM COMPONENT EVAt.UATION WORK SHEET d
Section C.2.18 i
- Sh'oet 4
l Joseph M. Farley Nuclear Plant Unit 2
'1 I
ENVIRONMENT DOCUMENTATION REF.
QUAL OUTSTANDH00 i
METHOD ITE M i
PARAMETER SPEC.
QUAL.
SPEC.
GUAL i
f ATING 8I'"IE*""""'
SYSTEM:
Sampling System 30 sec.
30 days 4
5 h
Note 1 Test t
Simultaneous COMPONENT: Solenoid Valve TEMP.
g y
l'F) 346 1
5 Test j
2 Simultaneous MANUFACTURER: Automatic Switch PRESSURE 62.2 4
(PSIA) 110 2
5 Tese
)
Company (ASCO)
Note 3 Simultaneous MODEL NUMBER: NF8320A184V RELATIVE 100 100 3
5 Test None j
HUMIDliY1%I 1
4 H 50 Simultaneous FUNCTION: Actuate Air Operated CHEMICAL H 803+
3 3+
3 3
y,,,
3 WRAY Test I
Valve for Isolation NaOH NaOH L
7 8
H uential ACCURACY: SPEC: Not Applicable RADIATION 5 x 10 2 x 10 y,,,
Test DEMON:
Rede Rads l
SERVICE:
9"*"
None AGING l
LOCATION: Containment El.129' Note 4 Note 6 Note 4 5
rest l
FLOOD LEVEL ELEV: 115'-On SU8MER-GENCE Note 5 N/A Note 5 N/A N/A None ABOVE FLOOD LEVEL: y,,
t DOCUMENTATION
REFERENCES:
__ NOTES:
j
- 1. J. M. Farley FSAR Figure 6.2-6
- 1. Specified time plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipment with short operating times ( < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- 2. J. M. Farley FSAR Figure 6.2-4
- 2. Maximum temperature of time dependent temperature profile from Reference 1
- 3. J. M. Farley PSAP Table 3.11-1 (See Figure C.3.1).
- 4. J. M. Farley FSAR Table 6.2-19
- 3. Maximum pressure of time dependent pressure profile from Reference 2 (See
- 5. ASCO Test Report AQS21678/TR Figure C.3.2).
Rev. A dated July 1979
- 4. Aging requirements in accordance with NUREC 0588, Section 4, Category II.
- 5. Submergence requirements in accordance with NUREG 0588, Section 2.2(5),
Category II.
- 6. The qualified life is being determined and will be reflected in the g
$urveillance and Maintenance procedures. See Appendix 5,Section I, l
Summary of Aging Evaluations.
4
m
^
a i
SYSTEM COMPONENT EVALUATION WORK SHEET '&
1 section C.2.18 Sheet 5
Je- ". M. Farley Nuclear Plant Unit 2
DOCUMENTATION REF.
aug OUTSTASIDWIG ENVIRONMENT ITEMS METHOg PARAMETER SPEC.
. OUAL.
SPEC.
GUAL.
SYSTEM: Sempting System 30 sec.
30 days 4
5 simultaneous None OPE ATING Test Note 1 (XNAPONENT: Limit Switch T
300 340 1
5 Simultaneood Neen Test Note 2 MANUFACTURER: NAMCo Centrole PR RE 62.2 84.7 2
5 Simultaneous None Test Note 3 es0 DEL NUMBER: EA-100 RELATIVE 100 100 3
5 sinutteneous Nome HUMIDITY 1%1 Teat FUNCTION: Velve Position CHEMICA1.
g3 g ) p,,
3 3+
3 5
simultamoeus Nome NM g
SPRAY Test Indication Ha0lt NaOH ACCURACY: SPEC:
N/A RADIATION 5 K 10 2 x 10 3
5 Sequentist Ilene I
Test DEMON:
Rede Reds l
SERVICE
- AGING Note 4 Note 6 Note 4 5
seguentist None Containment E1.129s Test k'
LOCATION:
115' hueMER-Note 5 None Note 5 None N/A None FLOOO LEVEL ELEV:
Yes GENCE ASOVE FLOOO LEVEL:
I NOTES:
1 Specified time plus I hour for equipment with short operating times ((1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
DOCUMENTATSON
REFERENCES:
Maximum temperaturs of time dependent temperature profile from Reference 1.
- 1. J.M. Farley FSAR Figure 6.2-6 1.
- 2. J.M. Farley FSAR Figure 6.2-4 2.
(See Figure C.3.1)
- 3. J.H. Farley PSAR Table 3.11-1 Maxiseum pressure of time dependent pressure profile from Reference 2. (Sed
- 4. J.M. Farley FSAR Table 6.2-19 3.
Figure C.3.2)
- 5. NAMCo Test Report dated Aging requirements in accordance with NUREC 0588, Sectia-4, Category II.
November 21,1977 and Q11t-105 Submergence requirements in accordance with NUREC 0588,.w ction 2.2(5),
4.
5.
dated August 28, 1980 Catgory II.
- 6. The qualified life is being determined and will be reflected in the Surveillance and Maintenance procedures. See Appendix 5,Section I, Summary of Aging Evaluations.
I
I
,f m
SYSTEM COMPONENT EVALUATION WORK SHEET l&
Se'tton C.2.20 e
ll Sheet 3
Joseph M. Farley Nuclear Plant Unit 2
1 ENVIRONMENT DOCUMENTATION MEF.
l
- guat, OUTSTAMOING PARAMETER SPEC.
.OUAL.
SPEC.
OUAL.
METHOO MEW f
SYSTEM: Component Cooling Water OP RATING 30 sec.
30 days 4
5 simultaneous None Note 1 Test
~
i COMPONENT: Solenoid Velve T
300 346 1
5 staulteneous nome Note 2 Test M '.NUF ACTUREM: Automatic SVite,h PRESSURE 62.2 110 2
5 simultaneove None ges:4; r
Note 3 rene l
Company MODEL NUMSER: NP8316A77V L i 100 100 3
3 Simultaneous None g
rest i
H 803 plue 3
3+
3 5
simultaneous done N 80 FUNCTION: Actuate Air Operated CHEMICAR.
3 j
SPRAY Valve for Isolation p
I 8
Not applicable RADIATION 5X10 2 x 10 3
5 Sequentist Noas ACCURAm MC:
DEMON:
Rede Rede Test i
m AGING Note 4 Note 6 Note 4 5
5 ntist None L
TION: Containment E1. 11Re R
FLOOD LEVEL ELEV: 115'-O" SUOMER-Note 5 N/A Note 5 N/A N/A Wone 7
ABOVE FLOOD LEVEL: Yes GENCE NOTES:
DOCUMENTATION
REFERENCES:
- 1. J.M. Farley FSAR Figure 6.2-6 1.
Specified time plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipment with short operating times ((1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- 2. J.M. Parley FSAR Figure 6.2-4 2.
Maximiuas temperature of time dependent temperature profile from Reference 1.
- 3. J.H. Farley FSAR Table 3.11-1 (See Figure C.3.1)
- 4. J.M. Farley FSAR Table 6.2-19 3.
Maximium pressure of time dependent pressure profile from Reference 2. (See
- 5. ASCO Test Report AQS21678/TR Figure C.3.2)
Rev. A dated July 1979 4.
Aging requirements in accordance with NUREC 0588, Section 4. Category ff.
5.
Suhmergence requirements in accordence w!th NUREG 0588. Section 2.2(5),
Cargory II.
6.
The qualified life is being determined and will be reflected in the Surveillance and Maintenance proceudres. See Appendix 5, Section 1 Summary of Aging Evaluations.
1 j
- ===
e
~
5 I
SYSTEM COMPONENT EVALUATION WORK SHEET d
Section C.2. 20 l
Joseph M. Farley Nuclear Plant Unit 2
Sheet 4
ENVlRONMENT DOCUMENTAYSO98 REF.
- guat, OUTSTamansaan PARAMETER SPEC.
.OUAL.
SPEC.
M8AL.
METHOD UEW i
SYSTEM: Component Cooling Water OPERATING l
TIME 30 sec.
30 doye 4
5 Sinnettaneous None
}
Note i Test COMPONENT: Limit Switch T
300 340 1
S Simultaneous None Note 2 Test MANUFACTURER: MANCo Controle pHESSURE 62.2 84.7 2
S Staultaneous None
^'
Note 3 Test 4
l MODEL NUMBER: EA-180 RELATIVE 100 100 3
S Sinuitoneena None HUMIDITY (%)
l Test i
l FUNCTION: Valve Position CHEMICAL H 303 plue 3 3+
3 Simultaneous None N 50 3
Indication SPRAY j
g g
g 1
f
^
I 0
D N/A RADIATION 5 x 10 2 x 10 3
S Segesentiet None Rede Rede Test i
i SERVICE:
AGlNG ote 4 l
LOCAllON: Containment El. 118 Note 6 Note 4 5
seguentist None 1
Test FLOOO LEVEL ELEV:
115' SusMER.
Note 5 None Note 5 None N/A None l
A80VE FLOOO LEVEL:
Tee GENCE l
l
{
DOCUMENTATION
REFERENCES:
NOTES:
- 1. J.M. Farley FSAR Figure 6.2-6 1.
Specified time plus 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for equipment with ehert operating Pines ((1 heur).
- 2. J.M. Farley FSAR Figure 6.2-4 2.
Maximum temperature of time dependent temperature profile from Reference 1.
- 3. J.M. Farley FSAR Table 3.11-1 (See Figure C.3.1)
- 4. J.M. Farley FSAR Table 6.2-19 3.
Maximum pressure of time dependent pressure profile from Reference 2. (San j
- 5. MAMCo Test Report dated Figure C,3.2) i November 21, 1977 and QTR-105 Aging requiremente in accordance with NUREC 0588, Section 4 Category II.
4.
dated August 28, 1980.
5.
Submergence requiremente in accordance with NUREC 0588, Section 2.2(5).
l "Catsory II.
6.
The qualified life is being determined and will be reflected in the
}
Surveillance and Maintenance procedures. See Appendix 5,Section I, j
Summary of Aging Evaluations.
i
==
w
i 8
SYSTEM COMPONENT EVAL.UATION WOntr 3HEET
, h 8ecaton C.2.20 i
Sheet
- 5 JW M. Farley Nuclear Plant Unit 2
ENVIRONMENT DOCUMENTATION REF.
QUAL.
OUTSTANDING METHOD IN PARAMETER SPEC.
QUAL SPEC.
OUAL EQUIPMENT DESCRIPTION i
8I""I"*"***'
30 days 4
5 None OPERATING 30 sec.
SYSTEM: Component Cooling Water Test TIME Note 1 i
Simultaneous COMPONENT: Solenoid Velve TEMP.
300 346 1
5 Test
("F)
Note 2 I'
i MANUFACTURER: Automatic Switch PRESSURE 62.2 110 2
5 s h iteneous None (PSIA)
Note 3 Company (ASCO)
Simultarmaus MODEL NUMBER: NP8316A74V RELATIVE 100 100 3
5 Test HUMIDITY (%I 8I""I"*"***'
3 3
5 ym H 503+
H B0 +
FUNCTION: Actuate Air Operated CHEMICAL Te.t SPRAY NaOH N OH Valve for Isolation 8
'S ntial 7
2 x 10 3
5 5 x 10 i
ACCURACY: SPEC: N/A RADIATION Rade Rade DEMON:
Sequential Nm 8
AGING Note 4 Note 6 Note 4 l
SERVICE:
Test LOCATION: Containment E1. 129 h
I FLOOD LEVEL ELEV: 115'-0"
/
Note 5 N/A N/A None d
8 I
ABOVE FLOOD LEVEL: Yes NC I
j.
t NOTES:
DOCUMENTATION
REFERENCES:
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
Specified time plus I hour for equipment with short operating times (
i 1.
J. M. Farley FSAR Figure 6.2-6 1.
Maximuen temperature of time dependent temperature profile frees Reference 1 l
2.
J. M. Farley FSAR Figure 6.2-4 2.
(See Figure C.3.2).
3.
J. M. Farley FSAR Table 3.11-1 Maximum pressure of time dependent pressure profile from Reference 2 (Ses Figure 4.
J. M. Farley FSAR Table 6.2-19 3.
C.3.2).
5.
ASCO Test Report AQS21678/TR Aging requirements in accordance with NUREC 0588, Section 4 Category II.
Submergence requirements in accordance with NUREC 0588 Section 2.2(5), Cate Rev. A dated July 1979 4.
5.
6.
The qual'ifie'd life is being determined and will be reflected in the
~
Surveillance and Maintenance procedures. See Appendix 5,Section I, Summary of Aging Evaluations.