ML19351F466
| ML19351F466 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck, Millstone File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/30/1980 |
| From: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| A00898, A898, NUDOCS 8101130138 | |
| Download: ML19351F466 (66) | |
Text
NORTHEAST UTII.ITIES ww.e, o c,o wmmyw,
HARTFORD, CONNECTICUT 06101
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3 December 30, 1980
.N Docket Nos. 50-213 70 2
5 50-245 Q
3 Cf A00898
'y Director of Nuclear Reactor Regulation Attn:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 U. S. Nuclear Regulatory Commission Washington, D.C.
20555
References:
(1) D. L. Ziemann letter to W. G. Counsil dated February 15, 1980.
(2) W. G. Counsil letter to D. L. Ziemann dated April 29, 1980.
(3) W. G. Counsil letter to D. G. Eisenhut dated October 31, 1980 (Docket No. 50-213).
(4) W. G. Counsil letter to D. G. Eisenhut dated October 31, 1980 (Docket No. 50-245).
Gentlemen:
Haddam Neck Plant Millstone Nuclear Power Station, Unit No.1 Environmental Qualification of Electrical Equipment In Reference (1), the NRC Staff transmitted guidance for performing an evaluation of the environmental qualification of Class lE electrical equipment. In Appendix I
A to Enclosure 1 of Reference (1), the Staff identified typical systems utilized to perform the necessary functions of emergency reactor shutdown, containment isolation, reactor core cooling, containment and reactor heat removal, and pre-vention of significant releases of radioactive material to the environment.
l Connecticut Yankee Atomic Power Company's (CYAPCO's) and Northeast Nuclear Energy i
Company's (NNECO's) initial response to Appendix A was provided in Reference (2),
j wherein plant-specific equipment and functions necessary to achieve the above-identified objectives were identified.
)
As a result of numerous changes in interpretations of Staff guidance, which are documented in References (3) and (4), the Reference (2) information is hereby l
superseded by the revised lists provided as Attachments 1 and 2 for the Haddam l
l Neck Plant and Millstone Unit No. 1, respectively. These attachments were not a part of the Staff's request for information by November 1,1980, but they are l
being docketed to update Reference (2) and to more accurately reflect the content of References (3) and (4).
I
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_. l Included as Attachment 3 to this submittal are revised pages to Reference (4).
The majority of the changes are editorial in nature and do not substantively alter the information provided in Reference (4). In one instance additional qualification documentation is being provided rather than justification for its ab'aence.
It is emphasized that the attached information is not vital to the development of the Staf f's Safety Evaluation Report scheduled for February 1,1981.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMPANY
[/4LA '
W. G. Counsil Senior Vice President
DOCKET NO. 50-213 l
l l
ATTACHMENT 1 HADDAM NECK PLANT ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT l
l t
l l
December, 1980
RESPONSE TO APPENDIX A Typical Equipment / Functions Plant Specific (CY)
From Appendix A Equipment / Functions Engineered Safeguards Actuation Pressurizer pressure transmitters, containment pressure switches and associated 4A/4B lockout relays.
Reactor Protection Reactor Protection System Containment Isolation CY has 39 automatic containment isolation valves which are:
1.
Air Operated Valves 2.
Trip Valves 3.
Flow Control Valves 4.
Motor Operated Valves 5.
Solenoid Operated Valves 6.
Hand Indicating Control Valves Main Steamline Isolation Main Steamline Isolation System Main Feedwater Shutdown and The main feedwater shutdown and Isolation isolation is performed by:
1.
Main Feedwater Regulation Valves 2.
Back-up Motor Operated Valves Emergency Power Diesel generators, 4160 V and 480 V switchgear, 125 volt DC system, 120 V vital and semi-vital AC systems, and their associated switchgear, raceway, and cable.
Re:ponte to Appendix A Psga 2 Emergency Core Cooling Emergency Core Cooling is performed by:
1.
High Pressure Safety Injection 2.
Low Pressure Safety Injection 3.
Charging Pumps 4.
Residual Heat Removal System 5.
Heat Trace System Containment Heat Removal Containment heat removal consists of the following systems:
1.
Air Recirculation System 2.
Adams Filter 3.
Spray System (Back-Up)
Containment Fission Product Removal Filtration System Containment Comiastible Gas Control Hydrogen Purge System (Manual System)
Auxiliary Feedwater Auxiliary Feedwater System Containment Ventilation Air Recirculation System, Purge System Containment Radiation Monitoring Containment radiation monitoring consists of the following:
1 1.
Reactor Containment Air Particulate Monitor l
l 2.
Reactor Containment Gas Monitor l
Control Room Habitability System The control room ventilation and smoke ejection systems.
l l
l I
Response to Appendix A Page 3 Ventilation for Areas Containing The heating and ventilation systems at Safety Equipment Of are not Category 1.
The environments will be determined assuming its failure.
Component Cooling Component Cooling System Service Water Service Water System Emergency Shutdown Emergency shutdown is achieved by:
1.
Pressure Control System 2.
Chemical & Volume Control System 4.
Main Steam System 5.
Primary Water Storage System 6.
Auxiliary Feedwater System 7.
Residual Heat Removal System 8.
Component Cooling System 9.
Service Water System Post Accident Sampling & Monitoring Sampling System Radiation Monitoring Radiation Monitoring System Safety Related Display All instrumentation which displays Instrumentation information used by operators for essential decision making.
1 i
l l
DOCKET No. 50-245 ATTACHMENT 2 MILLSTONE NUCLEAR POWER STATION, UNIT NO.1 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL EQUIPMENT l
l l
i December, 1980
RESPONSE TO APPENDIX A Typical Equipment / Functions Plant Specific (MP1)
From Appendix A Equipment / Functions F.ngineered Safeguards Actuation The following engineered safeguards systems are considered Category I and are actuated by independent Category I controls which are part of that system:
1.
Emergency core cooling system 2.
Steam flow restrictors (passive system)
Reactor Protection Reactor protection system Containment Isolation Primary containment isolation system Steamline Isolation Part of primary containment isolation system l
Main Feedwater Shutdown and MP1 utilizes Category I check valves to Isolation provide this function Emergency Power Gas turbine generator, diesel generator, 4,160 and 480 volt switchgear, 120 volt vital and instrument AC systems, 125 volt DC system, and their associated switchgear, raceway and cable Emergency Core Cooling Core spray system l
Low pressure coolant injection /CnfT cooling system Automatic depressurization system l
Feedvater coolant injection system Isolation condenser system l
Containment Heat Removal LPCI/ containment cooling system Emergency service water system Containment Fission Product Removal Atmospheric control system Standby gas treatment system Containment Combustible Gas Control Atmospheric control system (inerting of containment)
Auxiliary Feedwater MP1 does not have an auxiliary feedwater s>y s tem. The condensate storage and transfer system provides alternate water for the FWCI system i
The containment ventilation system is Containment Ventilation not Category I at MPl.
It is not required to mitigate the consequences of a LOCA or MSLB accident.
(There is nothing in the drywell that requires ventilation for the above.)
Containment Radiation Monitoring Process radiation monitoring system The control room heating and ventilation Control Room Habitability system.
The turbine building heating and ventila-Ventilation for Areas Containing tion system at MP1 is not Category I.
The Safety Equipment environments will be determined assuming its failure.
Service water system Component Cooling Service water system Service Water LPCI system Emergency Shutdown Isolation condenser system Automatic depressurization system Post Accident Sampling and Process radiation monitoring system.
The sample system is not Category I at MPl.
Monitoring It is isolated by the prima *' containment isolation system, which is Lategory I.
Process radiation monitoring system Radiation Monitoring All instrumentation which displays informa-Safety-Related Display tion used by operators for essential deci-Instrumentation sion making (as called out in the emergency operating procedures for the LOCA, LNP, and MSLB accidents; i.e., level, pressure, temperature, flow indication, valve and breaker position, etc.)
DOCKET NO. 50-245 ATTACHMENT 3 l
l MILLSTONE NUCLEAR POWER STATION, UNIT NO.1 ELECTRICAL EQUIPMENT ENVIRONMENTAL QUALIFICATION REVISED SYSTEM COMPONENT EVALUATION WORK SHEETS
SUMMARY
SHEETS e
l December, 1980 l
l Facility: Millstone Nuclear Pr. Sta.
Page I-1 SYSTEM COMPONENT EVALUATION WORK SHEET Rev.
5 Unit One Docket:
50-245 Date 11-24-80 EQUIPMENT DESCRIPTION ENht.PMENT DOCUMENTATION REF*
QUAL.
OtITSTANDING
~
METHOD ITEMS Parameter Spec.
Qual.
Spec.
Qual.
vendor ADS Operating Systems Plant ID do.:1-MS-3A Time 90 min.
92 hrs.
S-3 Q-3 data (203-3A )
Component:
Temperature (OF)
Profile vendor Solenoid Valva 1
347 F S-1 Q-3 data Manufacture: Target Rock Pressure (PSIA)
Profile 65 psig S-1 Q-3 aa Model Numbers is SMS-A-01 anlative vendor (SN #100)
Humidity (%)
100%
100%
S-1 Q-3 data Function: Actuate relief valves
' chemical Spray Demin H 0 NR NR NR NR h acy:
NA k
Services Radiation 4.3 x 107 1.3 x 107 S-4 Q-3 da s
Pressure Relief of Rx 285 F life of vendor Drywell-R1 40 yrs.
480 hrs.
plant Q-3 data Flood Level Elev:
l'-8" N/A N/A N/A N/A Above Flood Imvel: Yes X Sulmargencs S-6 un M-H CDocumentation
References:
Notes:
1-MS-3B,C,D,E & F See attached reference list.
Facility: Millstone Nuclear Pr. Sta.
Page I-6 SYSTEM COMPONENT EVALUATION WORK SIIEET Rev.
5 Unita One Docket:
50-245 Date 11-24-80 EQUIPMEarr DESCPIPTION ENVIRONMENT DOCUMENTATION REF*
QUAL.
OUTSTANDINC MET 1tOD JTF.MS Parameter Spec.
Qual.
Spec.
Qual.
ven r see sum.
h Sy;temia PCI operating Plant ID No.: 1-SM-1 Time 5.5 sec.
S-5 Q-3 data sht. I-6
(
(220-44)
Component:
Temperature vendor see sum.
( F)
Profile
>300F Q 28 sht. I-6 data Solenoid Valve I
ananaifacture :
Pressure l-(PSIA)
Profile vendor p
Aktomatic 2
30 psig S-1 Q-28 data h
Model asumber:
Relative see sum.15-527 Humidity (%)
100%
S-1 sht. I-6 Function: Actuate Rx loop simple valve
'_Chesaical
{
Spray Accuracy: NA Demin II 0 NR NR NR NR 2
7 S-4 see sum.
SSEvice: CTMr Isolation Radiation 1.1 X 10 sht. I-6 Incation:
Aging life of see sum.
sht. I-6 40 yrs.
plant Drywe 11 -R1 Flood Imvel Eleva l'-8" N/A N/A S-6 N/A N/A Above Flood Level: Yes X Submergence un M-Il CDocumentation
References:
Notes:
See attached list.
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Stpe(ARY SEEET NO.
1-7
- mEr..
l REV. 5 11-24-80 7
f f
EQUIPMENT ENVIRoleENTA', QUALIFICATION DISCRIFANT F;JIPMENT EUMMARY f
Mill 5 TONE IntIT 1 N M 4:
1-SM-2 Solenoid Valves l
l MAEFACTURER:
Atkomatic Model 15-527 i
QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
SAFETY WNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Primary containment isolation.
The valves are redundant to other safety related equipment which is not 2.
simultaneously exposed to a harsh environment.
This equipment will have completed its safety function within the Based on our engineering evaluation, 3.
first 30 seconds of an incident.
considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perfom its design function.
4.
An independent laboratory has been retained by NUSCO to provide radia, tion and time / temperature aging analysis for this equipment..
Due to the desirability of long term operability of this equipment, they will 5.
This will be accomplished as soon as be replaced with qualified equipment. assuming that procurement delays do not practicable, prior to June 30, 1982, preclude replacement by that date.
(
I Facility: Millstone Nuclear Pr. Sta.
page
,_q SYSTEM COMPONENT EVALUATION WORK SHEET Rev.
5 Unit One Docket:
50-245 Date 11-24-80 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF*
QUAL.
OUTSTANDING METHOD ITEMS Parameter Spec.
Qual.
Spec.
Qual.
see sum.
Sy;tems ATMOS. Cont.
Operating Clant ID No. : 1 AC-ll Time 11 sec.
S-5 sht. I-9 (v12-ll)
Ocuponent:
Temperature
( F)
manufactures Pressure (PSIA)
ASCO teodel m=he Relative LB831615 Humidity (%)
Functions Actuate entl.
vent valves b enical Spray Accuracy:
NA see sum.
Service: CTNT Isolation Radiation 6
S-4 1.3 X 10 sht. I-9 Incation: Reactor Aging sht. I-9 building-R6,R8 40 yrs, plant Flood Imvel Elev: NA Above Flood Level: Yes Sulmargence un M-H Notes:
cDocumentation
References:
Sea attached list.
1-AC-6 1-AC-5 1-AC-4 1-AC-10
I-16 SIDHARY SHEET NO.
I 1-16 SCEW SHEET NO.
l REV. 5 11-24-80 l
EQUIPMENT ENVIRONMENTAI, QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
l MII.I. STONE UNIT 1 EQUIPMEn:
1-CU-2A Solenoid Valves f
I i
l l
MANUFACTURER:
ASCO Model HT 8320 f
I l
l f
QUALITICATION DISCREPANCY:
l f
Lacks documented qualification test data.
I SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
l 1.
Primary containment isolation.
2.
The valves are redundant to other safety related equipment which is not simultaneously exposed to a harsh environment.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, 3.
considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its design function.
4.
The valve is nomally closed and stay closed.
Due to the desirability of long term operability of this equipment, they will 5.
be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30,1982, assuming that procurement delays do not preclude replacement by that date.
I
l I
II-3 Facility: Millst:ne Nuclear Pr. Sta.
Page SYSTEM COMPOHENT EVALUATION WORK SHEET p,y,
5 Units One Docket:
50-245 Date 11-24-80 EQUIPMENT DESCRIPTION ENVIBONMEffT DOCUME!TIATION REF*
QUAL.
OtTrSTANDING ME'ntOD ITEMS Parameter Spec.
Qual.
Spec.
Qual.
Sy0 tem: FWCI Operatin9 Continuous 5-3 See Summ.
Plant ID No.: 1-MW-96A Time Sheet II-3 (V7-143)
Oomponent:
Temperature Motor Operator
( F)
Manufacture: Teledyne Pressure (PSIA) l Model mamber: T-4-25 Relative Humidity (%)
Function: Emergency condensate transfer pump
' Chemical discharge valve Spray Accuracy:
NA Service: Fdwtr. supply Radiation 2.1 x 10 S-4 Sheet 11-3 Iccation: Reactor Aging Building R6 40 Years Life of See Summ.
Plant Sheet II-3 Flood Imvel Elev NA Above Flood Imvel: Yes Sulanergence un M-H Notes:
CDocumentation Refert 3:
See attached lise S.N. #11947
II-6
SUMMARY
SHEET N00 II-6 SCEW SHEET NO.
REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 1-LP-15A & B H.O. Volve MANUFACTURER:
Teledyne Model T40-80 QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
1 SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Primary Containment Cooling during LOCA, ONLY.
2.
This equipment is not required to operate during a llELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time dependent phenomena whfch could not reasonably be expected to result in equipment failure in the short term.
3.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
4.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
(
II'7
SUMMARY
SHEET NO.
II-7 SCEW SHEET NO.
REV. 5 11-24-80 EQUIPMENT ENVIR0hMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 1-LP-16A 6 B M.0. Valve EQUIPMENT:
MANUFACTURER:
Teledyne Model T4-25 QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Primary Containment Cooling during LOCA ONLY.
2.
Thi equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
4.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
l l
Facility: Millstone Nuclear Pr. Sta.
page 11-9 SYSTEM COMPONENT EVALUATION WORK SHEET Rev.
5 Units One Docket:
50-245 Date 11-24-80 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF*
QUAL.
OLTTSTANDING ME*DIOD ITEMS Parameter Spec.
Qual.
Spec.
Qual.
See Sum.
Syntesa Core Spray Operating 30 sec.
S-3 Sheet II-9 Plant ID Mo.:
Time l-CS-4A (V10-13A)
Component:
Tesaperature Profile See Surm.
(OF)
Motor operator 6,9 S-2 Sheet 11-9 Manufacture Pressure (PSIA)
Profile See Surca.
Teledyne 10 S-2 Sheet 11-9 Relative Model msnber:
T-10-40 Profile 8 S-2 See Sunn.
usmidity(s)
~
Function:
- N Injection Valvc Spray N/A Accuracy: N/A Service:
Emergency Radiation S** 8"***
6 Core Cooling 1.3 x 10 S-4 Sheet II-9 Incation:
Aging See Surra.
40 Years Life of Rx Bldg. R17, R19 Sheet 11-9 Plant Flood I4 vel Eleva l'-8" N/A N/A Above Flood Imvel Yes X Sulmargence un M-H EDocumentation
References:
Notes:
S e attached list.
1-CS-4A
~
II-11 Facility: Millstone Nuclear Pr. Sta.
Page SYSTEM COMPONENT EVALUATION WORK SHEET Rev.
S Unit One Dockets 50-245 Date 11-24-80 EQUIPMEbrF DESCRIPTION ENVIRONMENT DOCUMENTATION REF*
QUAL.
OUTSTANDING MEntOD ITEMS Parameter Spec.
Qual.
Spec.
Qual.
See Summ.
Sy;tema Service Water Operating (30sec.
S-3 Sheet II-11 Plant ID Mo.: I-SW-9 Time (V4-21)
Component:
Temperature See Summ.
Profile Motor operator
( F)
S-2 12 Sheet I1-11 asarmfartnare : Limitorque Pressure S"" S""
(PSIA)
Profile S-2 Sheet 11-11 13 Relative Model n=har: SMB-0 Profile S-2 See Summ.
H dity(s)
Sheet 11-11 14 Function: Isolation Valve Chemical for Non-Essential Equip.
Spray N/A N/A N/A N/A N/A Accuracy:
NA Services Emerg. water Radiation 2.8 x 10 S-4 See Summ.
Sheet 11-11 Incation: Turbine Aging Building-TSC 40 Years Life of See Summ.
Sheet 11-11 Plant Flood Level Elev: NA N/A N/A N/A N/A N/A Above Flood Imvel: Yes Sulanergence nan M-Il CDoctamentation
References:
Notes:
See attached list.
II-I3 Facility: Millstone Nuclear Pr. Sta.
page SYSTEM COMPONENT EVALUATION WORK SHEET Rev.
5 Unit:
One Docket:
50-245 Date 11-24-80 EQUIPMENT DESCRIPTION ENVIRONMENT DOCUMENTATION REF*
QUAL.
OUTSTANDING MEDIOD ITEMS Parameter Spec.
Qual.
Spec.
Qual.
Isolation Cond.
Operating 21 sec.
S-5 See Summ.
Sy; tem:
Time Sheet II-13 Plant ID No.: 1-IC-4 Component:
Temperature
( F)
Profile 1 S-1 See Summ.
Valve Sheet 11-13 Manufacture Teledyne Pressure Profile 2 S-1 See Summ.
(PSIA)
Sheet II-13 Model Number: T-10-60 Relative See Summ.
Humidity (t) 100%
S-1 Sheet II-13 Function: Isolation Valve
" Chemical Demin.
Spray H
!^
"!^
"!^
"!A Accuracy: N/A 2
Service Ctmt. Isolation Radiation 7
0 S-4 See Summ.
Sheet II-11 Location: Drywell R1 Aging 40 Years Life of See Summ.
Plant Sheet 11-13 Flood Imvel Elevs.l'8" Above Flood Imvel: Yes X Sulmergence N/A N/A S-6 N/A N/A un M-H CDocumentation
References:
Notes:
See attached liat.
II-14 I
SUMMARY
SHEET NO.
II-10 SCEW SHEET NO.
REV. 5 11-24-8@
EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
1-MS-5 M.0. Valve MANUFACTURER:
Limitorque Model SMB-000 QUALIFICATION DISCREPANCY:
Lacks documented qualification test data SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Primary Containment Isolation for a MSLB.
2.
This valve is normally closed and stays closed.
It is used to drain steam l
lines to the condenser only when less than 5% power (start-up and shutfown).
l 3.
This valve is redundant to other safety related equipment which is l
not simultaneously exposed to a harsh environment.
4.
This equipment will have completed its safety function within l
the first 30 seconds of an incident.
Based on our engineering l
evaluation, considering the equipment operating time and expected i
effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its l
design function.
5.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as j
soon as practicable, prior to June 30, 1982, assuming that procurement l
delays do not preclude replacement by that date.
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II-16
SUMMARY
SHEET NO.
SCEW SHEET NO.
II-16 REV. 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
1-MS-6 M.0, Valve MANUFACTURER:
Limitorque Model SMB-000 QUALIFICATION DISCREPANCY:
l Lacks documented qualification test data for radiation & aging.
I I
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
l 1.
Primary containment isolation for a MSLB.
2.
This valve is normally closed and stays closed.
It is used to drain steam lines to the condenser only when less than 57. power (start-up and shutdown).
3.
This valve is redundant to other safety related equipment which is not simultaneously exposed to a harsh environment.
4*
This equipment will have coupleted its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its design function.
5.
Due to the desirability of long term operability of this equipment, they I
will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
l l
'~
SM MARY SHEET NO.
y SCEW SHEET NO.
REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANI EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
1-LP-14A & B M.0. Valves MANUFACTURER:
Teledyne Model T40-10 QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Suppression Chamber (Torus) Cooling during LOCA, only.
2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
4.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
V U
s 11-29 StBSIARY SHIET NO.
SCEW SHEET NO.
REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPAFI EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
1-LP-13A & B M.O. Valves MANUFACTURER
- Teledyne Model T40-10 QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Suppression Chamber (Toru;) Cooling during LOCA, only.
2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns I
radiation and aging considerations. The deleterious affects resulting from these parameters are time dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
4.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as j
soon as practicable, prior to June 30, 1982, assuming that procurement l
delays do not preclude replacement by that date.
l l
f
\\
0
-30
SUMMARY
SHEET NO.
SCEV SHEET NO.
REV. 5 11-24-80 EQUIPMENT EhVIRONMENTAL QUALIFICATION DISCREPANT BQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
1-LP-43A & B M.O. Valve MANUFACTURER:
Teledyne Model T10-25 QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Emergency Core Cooling Test Valve.
I 2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
4.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
Y s
II-33 SIDetARY SHEET NO.
II-33 SCEV SHEET NO.
REV. 5 11-24-80 EQUIPMENT ENVIROMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSIONE UNIT 1
-A
.0. Valves EQUIPMENT:
Teledyne Model T10-60 NAN:
QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
l.
Energency Core Cooling during LOCA.
The valves are in the heat exchanger by-pass line and any malfunction is 2.
l inconsequential.
I 3.
This equipment is not required to operate during a HELB outside containment.
l For a LOCA, the only deficiency in the qualification documentation concerns
[
radiation and aging considerations. The deleterious affects resulting from these parameters are time dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
4.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
- 5. Due to the desirability of long ters operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
l
j' II-34 SIDMARY SHEET NO, II~
SCEW SHEET NO.
REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
1-LP-44A & B M.O. Valve 1
MANUFACTURER: Teledyne Model T40-100 QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1*
Emergency Core Cooling Test Valve.
2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
An independent laboratory has been retained by NUSCO to provide radiation '
and time / temperature aging analysis for this equipment.
4.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
SUMMARY
SHEET NO.
II-37 SCEW SHEET NO.
11-37 REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
1-CS-21A & B M.0. Valve MANUFACTURER:
Teledyne Model T4-10 QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
l.
Emergency Core Cooling Test Valve.
2.
A normally closed and stays closed valve except during a 30 second surveillance operation.
3.
Malfunction of these valves is only credible upon the coincident happenings l
of:
(
a.
The Iso-Condenser Break l
b.
An LNP c.
Failure of the Diesel Generator d.
Surveillance Testing in progress 4.
This equipment will have completed its safety function within the first 30 seconds of an incident.
Based on our engineering evaluation, l
considering the equipment operating time and expected effects t
associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its design function.
5.
Due to the desirability.:f long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement l
delays do not preclude replacement by that date.
l
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)
SIDMARY SHEET NO.
IV-9a SCEW SHEET NO.
IV-9a REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
Cable MA!MFACTURER:
G. E. Vulkene QUALIFICATION DISCREPANCY:
Lacks fully documented qualification test data for radiation.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Electric continuity.
2.
In addition to the 4x107 rad exposure for which the samples were tested they were taken from a plant in service for 10 years. Thus the actual radiation exposure for 10 years of normal life should be included.
3.
An independent laboratorj has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
4.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its design function.
5.
Due the the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practible, prior to Juen 30, 1982, assuming that procurement delays do not preclude replacement by that date.
)
SUMMARY
SHEET NO.
IV-9b SCEW SHEET NO.
IV-9b REV. 5 11-24-80 EQUIPMENT ENVIRO'NMENTAL QUALIFICATION DISCREPANT EQUIPMENT GUMMARY MILLSTONE UNIT 1 EQUIPMENT:
Cable MANUFACTURER:
G. E. Vulkene QUALIFICATION DISCREPANCY:
Lacks fully documented qualification test data for radiation.
I SAFETY F'JNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Electric continuity.
2.
In addition to the 4x107 rad exposure for which the samoles were tasted they were taken from a plant in service for 10 years. Thus the actual radiation exposure for 10 years of normal life should be included.
3.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
4.
This equipment will have completed its safety function within the first 30 seconds of an incident.
Based on our engineering etaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded tha*. this equipment would satisfactorily perform its design function.
5.
Due to the desirability M lyn term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practible, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
I
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(
w SIDMARY SHEET No. IV-10 SCEW SHEET NO.
IV-10 REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EwUIPMENT SIBMARY MILLSTONE UNIT 1 EQUIPMENT:
Cable MANUFACTURER:
GE QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Electric continuity.
Components are copper /constantan temperature elements which provide signals to a temperature recorder in control room.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in qualification documentation, concerns radiation and aging considerations. The deletected affects resulting from these parameters are time-dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
An independent laboratory has been retained by NUSCO to provide radiation and time /
temperature aging analysis for this equipment.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment.
Reference letter from Northeast Utilities to NRC Docket No. 50-245 dated June 20, 1980. This will be accomplished as soon as practible, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
e Facility: Millstone Nuclear Pr. Sta.
Page Iy_11 SYSTEM COMPONENT EVALUATION WORK SHEET Rev.
5 Unit One Docket:
50-245 Date 11-24-80 i
E@~IPggyr nantanTDTION ENVIRONMENT DOCUME1TATION REF*
QUAL.
OtTISTANDING ME'niOD ITEMS Parameter Spec.
Qual.
Spec.
- Qual, test Operating Continuous 96 hrs.
S-3 Q-19' 20 similarity System:
VARIOUS Plant ID No. : Kl-16 Time Component:
Temperature test fF)
Profile 340 F S-1 Q-19,20 similarity Cable 1
1 Manufacture:
Pressure test G.E.
(PSIA)
Profile 62 psig S-1 Q-19,20 similarity 2
Model m=har:
Relative test S1-58073 Humidity (%)
100%
100%
'S-1 Q-19,20 similarity Function: Elec. circuitry
" Chemical i
Spray Demin H 0 N/A N/A N/A N/A 2
Accuracy: NA Service Cttnt. isolation Radiation test see sum.
9.4 x10
>4 x 107 S-4 Q-19,20 similarity sht. IV-11 Iocation:
Aging 268"/54 days +
11fe of Q-19,20 test DRYWELL R1 40 yrs.
.10 yr.
plant similarity Flood Imvel Elev Above Flood Invol Yes Sulmargence N/A N/A N/A N/A N/A un M-H CDocumentation
References:
Notes: K1-16=1/C #4(62 vulkene)
C1460 Sen attached list.
C1443
e SIDMARY SHEET NO.
IV-Il SCEW SHEET NO.
IV-11 REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
Cable MANUFACTURER:
G. E. Vulkene QUALIFICATION DISCREPANCf:
Lacks fully documented qualification test data for radiation.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Electric continuity.
2.
In addition to the 4x107 rad exposure for which samples were tested, they were taken from a plant in service for 10 years. Thus the actual radiation exposure for 10 years of normal life should be included.
3.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
4.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its design function.
5.
Due to the desirability of long term operability OF THIS EQUIPMENT, they will be replaced with qualified equipment. This will be accomplished as soon as practible, prior to June 30,1982, assuming that procurement delays do not preclude replacement by that date.
b b
y pa.ge IV-13 Facility: Millstone Nuclear Pr. Sta.
SYSTEM COMPONENT EVALUATION WORK SilIIT pe v.
5 Unit One lute 11-24-80 Docket 50-245 DOCUMEtrrATION REF*
Qt W.
m!Tr AllDING DNIRONMErrr EQUIPMENT DESCRIPTION Parameter Spec.
Qual.
r,pec.
Qual.
Sy; tem Various Operating similarity Plant ID No. K2-2 Ti"*
Continuous 500 hrs.
S-3 Q-29 test Component Cable Temgerature o
90 C similarity
( F)
Profile 3 (202 F)
S-2 Q-29 test Manufactare: G.E.
Pressure similarity (PS1A)
Profile 4 40 psig S-2 Q-29 test gamle1 Number: SI-58081 Relative similarity Humidity (%) Profile 5 100%
S-2 Q-29 test Function: Elec. circuitry Chemical Spray NA NA NA NA NA Accuracy: NA Radiation similarity Service: Various 6
7 S-4 Q-29 test 2.9 x 10 5.4 x 10
- " ## Y I
^9 "9 Inc tion: Steam tunnel l'"'
Y'**
R-4 Flood Imvel Elev: NA Above Flood Invel Yes Sutmergence NA NA NA NA NA M-li Notes: K2-3 CDocumentation
References:
K2-5 Sra cttached list.
K2-21 See attached list.
k b
y Pa.J e IV-20 Facility: K111 stone Nuclear Pr. Sta.
SYSTEM COMPONENT EVALUATIOt3 WORK Sill'ET isev.
5 Unita One sute 11-24-80 Dockets 50-245 DOctrMEt3TATION REFe Qt AI.,
OirrSTATIDING ENVIRONMEtrT EQUIPMENT DESCRIPTION MimtOD ITV.M1 Parameter Spec.
Qual.
Spec.
0"8I-Sy_tes: Various Operating Time Continuous 96 hrs.
S-3 Q19,20 tesc Plant ID Ho. :Various components Cable Temperature P f Hes Fr) 6,9 3400'1 S-2 Q19,20 test Manufacture: C.E.
Pressure (PSI A)
Profile 10 62 psig S-2 Q19,20 test Relative Model Number: SI-58145 Humidity (g) Profile 8 100%
S-2 Q19,20 test Function:Elec. circuitry Osemical Spray NA NA NA NA NA Accuracy: NA Services Radiation 4
>4 x 107 S-4 Q19,20 test 2.8 x 10 268"F/54 1
A9 D9 location: Rx Bldg.
days +
life of 40 yrs.
10 yrs.
plant Q19,20 test Flood tavel E1*V:
Above Flood Imvel Yes Sutmergence NA NA NA NA NA un M-H Notes:
CDocumentation
References:
Sem attached list SI-58145-30 mil vulk./45 mil neop.
s
('
(
Pa.ic IV-23 Facility: Millstone Nuclear Pr. Sta.
SYSTEM COMPONENT EVALUATION WORK SilEET leev.
5 Unita One lute 11-24-80 Docket 50-245 W MENTATION W QHAI..
M W DING ENVIPONMEg MI'.T11OD ITEM..
EQUIPMENT DESCRIPTION Parameter Spec.
Qual.
r,pcc.
Qual.
Syntes: Various operating 500 h' Q-29 Similarity Continuous S-3 Test Plant ID No.:Various Tim Tesiperature 95 C Q-29 Similarity Ocuponents Cable Profile 12 S-2 Pressure Manufacture G.E.
Q-29 Similarity
Q-29 Similarity Model thauber: SI-58081 Test Humidity (%) Profile 14 S-2 Function:Elec. Circuitry
_chestical Pray NA NA NA NA NA Accuracy: N/A 7
Radiation 5.4 X 10 Q-29 Similarity Service: Various 4
S-4 Test 2.8 x 10 Similarity M I"9 life of Imcation: T. b1dg.
40 yrs.
40 yrs.
plant Q-29 Test Flood level Elev Above Flood Imvel Yes Sutmergence NA NA NA NA NA M-li Not e s_:
- Doctamentation References _:
SI-58081=30PE/15PVC/45PVC Sam attached list, s
Facility: Millstone Nuclear Pr. Sta.
page y_4 SYSTEM COMPONErr EVALUATION WORK SHEET hv. 5 Unita One Date 11-24-80 nachat:
50-245 m i? TION ENVIRObetENT DOCUMENTATION REF*
QUAL.
OUTSTANDING METHOD ITEMS Parameter Spec.
Qual.
Spec.
Qual.
Systems ISO Cond.
Operating Continuous S-3 See Sun.
Sheet V-4 Plant ID Mo. : 1-IC-6 Time (1301-17)
Component: Limit switch Temperatur S-2 See Sum.
Profile Sheet V-4 6&9 Profile S-2 See Sum.
Manufac hre Micro Pressure (PSIA)
Sheet V-4 10 Model Number:
nelative Profile S-2 See Sum.
DTF2-2RN2-RN Humiidity(t)
Sheet V-4 8
Function: Valve Positton Chemical N/A N/A N/A N/A N/A
- I Service Containment W iation 6
g_4 See Sum.
2.1 x 10 Isolation Sheet V-4 IAcation: R14 Aging Life of 40 Years Plant Reactor Building Flood Invoi slev: N/A N/A N/A N/A N/A N/A Above Flood Imvel Yes Su h rgence e
inn M-H Notes:
- Documentation
References:
See attached list.
1-IC-7 (1301-20)
7 V-Il
SUMMARY
SHEET NO.
SCEW SHEET NO.
REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
l-SS-3, 4, 13 & 14 Limit Switches PANUFACTURER:
Micro Switch #0TF2-2RN QUALIFICATION DISCREPANCY:
Lacks documented qualification Test Data for radiation & aging.
I SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Valve Position Indication 2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time-dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its design function.
4.
An independent laboratory has been retained by riUSCO to provide radiation and time / temperature aging analysis for this equipment.
5.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
g
0 8
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SUMMARY
SHEET NO.
V-12 SCEW SHEET NO.
V-12 REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
1-AC-5 Limit Switch MANUFACTURER:
Micro Model BAF1-2RN2 QUALIFICATION DISCREPANCY:
Lacks documented qualification test data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Valve Position Indication 2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time-dependent phenomena which could not. reasonably be expected to result in equipment failure in the short term.
3.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipMant operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its design function.
4.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
5.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not
[
preclude replacement by that date.
3
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SUM 4ARY SHEET NO.
V-13 V-13 SCEW SHEET NO.
REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUMMRY MILLSTONE UNIT 1 l
EQUIPMENT:
1-AC-6 & 11 Limit Switches f
MANUFACTURER:
Micro Model DTF2-2RN2 QUALIFICATION DISCREPANCY:
Lacks documented qualification Test Data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
4 1.
Valve Position Indication 2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time-dependent phenomena which could not reasonably be I
expected to result in equipment failure in the short term.
i i
3.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy. it is concluded that this equipment would satisfactorily perform its design function.
4.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
5.
Due to the desirability of long tenn operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not
(
preclude replacement by that date.
SUNtARY SHEET NO.
V-14 V-14 SCEW SHEET NO.
11-24-80 EQUIPMENTENVIR0ftMENTALQUALIFICATION DISCREPANT (QUIPMENT SUt94ARY MILLSTONE UNIT 1 EQUIPMENT:
1-AC-7 & 8 Limit Switches MANUFACTURER:
Micro Model DTF2-2RN2 I
QUALIFICATION DISCREPANCY:
Lacks documented qualification Test Data for radiation & aging.
I SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Valve Position Indication 2.
This equipment is not required to operate during a HELB outside containrent.
For a LOCA, the only deficiency., the qualification documentation concerns i
radiation and aging considerations. The deleterious affects resulting from l
these parameters are time-dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
This equipment will have completed its safety function within the 3.
first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perfom its design function.
. An indeprndent laboratory has been retained by NUSCO to provide radiation and 4.
time / temperature aging analysis for this equipment.
Due to the desirability of long term operability of this equipment, they will 5.
be replaced with qualified equipment. This will be accomplished as soon as practich* ole, prior to June 30, 1982, assuming that procurement delays do not k
preclude replacement by that date.
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M g
FUD
SUf94ARY SHEET NO.
V-15 V-15 SCEW SHEET NO.
REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUPfMRY MILLSTONE UNIT 1 EQUIPMENT:
1-AC-9 Limit Switch l
MANUFACTURER:
Micro Model 51MLT-6022 QUALIFICATION DISCREPANCY:
Lacks documented qualification Test Data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Valve Position Indication 2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from i
these parameters are time-dependent phenomena which could not reasonably be j
l expected to result in equipment failure in the short term.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, 3.
considering the equipment operating time and expected effects i
associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perfom its design function.
4.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
l 5.
Due to the desirability of long term operability of this equipment, they will l
be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to Jur.e 30, 1982, assuming that procurement delays do not
(
preclude replacement by that date.
l l
08 4
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F A
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FUD
SUMMARY
SHEET NO.
V-16 SCEW SHEET NO.
V-16 REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SU MARY MILLSTONE UNIT 1 EQUIPMENT:
1-AC-10 Limit Switch l
KANUFACTURER:
Micro Model BAF1-2RN2 QUALIFICATION DISCREPANCY:
Lacks documented qualification Test Data for radiation & aging.
1 SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Valve Position Indication 2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the c '
deficiency in the qualification documentation concerns radiation and agN onsiderations. The deleterious affects resulting from these parameters
- ime-dependent phenomena which could not reasonably be expected to resul, quipment failure in the short term.
This equipment will t._ve completed its safety function within the 3.
first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy. it is concluded that this equipment would satisfactorily perform its design function.
4.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
5.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
i
0 8
7 7
7 4
G 1
1 7
2 N
1 1
I mV mV 1
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t u
I V 5 1
NS S t S t AM e
e M
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T f
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S FUD SP C
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- ll
SUt94ARY SHEET NO.
V-17 SCEW SHEET NO.
V-17 REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION OISCREPANT EQUIPMENT SUt94ARY MILLSTONE UNIT 1 EQUIPMENT:
1-AC-12 Limit Switch MANUFACTURER:
Micro Model SlML7-6922 QUALIFICATION DISCREPANCY:
Lacks documented qualification Test Data for radiation & aging.
-(
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Valve Position Indication 2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time-dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its design function.
4.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
5.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not
(
preclude replacement by that date.
...~
08 8
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l
1 D
SUMARY SHEET NO.
V-18 SCEW SHEET NO.
V-18 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT SUMARY MILLSTONE UNIT 1 EQUIPMENT:
1-AC-17 Limit Switch MANUFACTURER:
Micro Model BAF1-2RN2 QUALIFICATION DISCREPANCY:
Lacks documented qualification Test Data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Valve Position Indication 2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from I
these parameters are time-dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its design function.
4.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
- 5..Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplisned as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not f(
preclude replacement by that date.
--,r-~
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SUP9tARY SHEET NO.
V-19 V-19 SCEW SHEET NO.
EQUIPMENT ENVIRONMENTAL QUALIFICATI N DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
1601-8A & B Limit Switches i
l t
MANUFACTURER:
Micro Model BAF1-2RN2 1
l QUALIFICATION DI.SCREPANCY:
Lacks documented qualification Test Data for radiation & aging.
I SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Valve Position Indication l
2.
This equipment is not required to operate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time-dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy. it is concluded that this equipment would satisfactorily perfom its design function.
i 4.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment..
5.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays.do not
(
preclude replacement by that date.
08 4
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SUMMARY
SHEET NO.
V 21 SCEW SHEET NO.
V-21 REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL Q'.lALIFICATION DISCREPANT EQUIPMENT SUPEARY MILLSTONE UNIT 1 EQUIPMENT:
1-AC 4 Limit Switch MANUFACTURER:
Micro Model BAF1-2RN2 QUALIFICATION DISCREPANCY:
Lacks documented qualification Test Data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Valve Position Indication 2.
This equipment is not required to olerate during a HELB outside containment.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging consideration;. The deleterious affects resulting from these parameters are time-dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
This equipment will have completed its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy, it is concluded that this equipment would satisfactorily perform its design function.
An independent laboratory has been retained by NUSCO to provide radiation and 4.
time / temperature aging analysis for this equipment.
Due to the desirability of long term operability of this equipment, they will 5.
be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
2
l VI-4 Facility: Millstone Nuclear Pr. Sta.
page SYSTEM COMPONENT EVALUATION WORK SHEET Rev.
5 Unit One Docket:
50-245 Date 11-24-80 i
EQUIP 953FF DESCRIPTION ENVIRONMENT DOCUMENTATION REF*
QUAL.
OUTSTANDING i
MEDIOD ITEMS Parameter Spec.
Qual.
Spec.
Qual.
4 J
WCI Continuous S-3 See Summ.
Sy;tems Operating Sht. VI-4 I
Plant ID Mo.
Time Component:
Temperature Pump Motor FF) namanfacture Pressure General Electric (PSIA) i Model mambers nelative 5K818841A134 Humidity (t)
Function:
Chemical Emerg. Cond. Transf.
Spray Accuracy 8 N/A See Summ.
Services Radiation 6
S-2 Sht. VI-4 2.1 X 10 Rrplenish cond. H O 2
Incation:
Aging 40 yrs, life of Rx Bldg. R6 Plant I
Flood Imvel Elev: N/A Above Flood Imvel Yes Sutmergence e
CDocumentation
References:
Notes:
Ste attached list.
i
s SU) MARY SHEET NO. YI-4 VI-4 SCEW SHEET NO.
REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
Emergency Condensate Transfer Pump M7-28 MANUFACTURER:
GE Model 5K818841A134 QUALIFICATION DISCREPANCY:
Lacks documentated qualification test data for radiation & aging.
SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Emergency Core Cooling water supply during LOCA.
This equipment is not required to operate during a HELB outside containment.
2.
For a LOCA, the only deficiency in the qualification documentation concerns radiation and aging considerations. The deleterious affects resulting from these parameters are time-dependent phenomena which could not reasonably be expected to result in equipment failure in the short term.
3.
An independent laboratory has been retained by NUSCO to provide radiation and time / temperature aging analysis for this equipment.
4.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
(
Facility: Millstone Nuclear Pr. Sta.
Page VI-6 4
SYSTEM COMPONENT EVALUATION WORK SHEET Rev.
5 Unit One Dockets 50-245 Date 11-24-80 EQUIPMEbrF DESCRIPTION ENVIRONMENT DOCUMENTATION REF*
QUAL.
OUTSTANDING METHOD ITEMS Parameter Spec.
Qual.
Spec.
Qual.
Sy; tem:
LPCI operating 12 hrs.
S,3 Q-18 Test Plant ID No.:
Time M8-75A (1502A)
Component:
Temperature S-2 Q-18 Test Ptrrp (Motor) 50011.P.
(Oy)
Profiles 212 F 6,9 asamdacture Pressure G.E.
(PSIA)
Profile O psig S-2 Q-18 Test 10 gendel n=har:
Relative Profile 8 100%
S-2 Q.-18 Test 5K6329XC3A Humidity (%)
Function:
Emer. Core /CTMT. CoolinF " Chemical Pumps Spray N/A N/A N/A N/A N/A Accuracy: NA 6
See Sum, Service: Emerg, core Radiation 2.1 x 10 S-4 Sheet VI-6 cooling Location:
Aging Q-18 Test See Sum.
40 Years Life of Sht. VI-6 Rx Bldg. R7 & R9 Plant Flood Level Elev:
NA Above Flood Imvel: Yes Sulmargence N/A N/A N/A N/A N/A un M-H (Documentation
References:
Notes:
Sen attached list.
M8-75B M8-75C M8-75D i
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i Facility: Millstone Nuclear Pr. Sta.
Page VIII-l SYSTEM COMPOh2Nr EVALUATION WORK SHEET Rev.
5 Unita One Date 11-24-80 Docket:
50-245 ENVIRONMENT DOCUMENTATION REF*
QUAL.
OLTISTANDING EQUIP 9sNT DESCRIPTION MEDIOD ITEMS Parameter Spec.
Qual.
Spec.
Qual.
System: LPCI Operating
( 30 sec.
S-3 See Stn.
Sh. VIII-1 Clant ID No.: V10-5A Time Component: Relay Temperature Profile S-2 See Sum.
II Sh. VIII-1 6&9 m
a Ros m e See Sum.
Profile 10 S-2 Chromalox (PSIA)
Sh. VIII-l Model Number:
asiative Profile 8 S-2 Se Su D2936-25 Contactor Humidity (t)
Ftanction: Actuate Cooline Water
" M cal spray N/A N/A N/A N/A N/A N/A Accuracy: N/A Services LPCI Pump Motors Radiation S-4 See Sum.
Sh. VIII-1 2.1 x 10 I4 cation: Rx Bldg. R7 &
Aging lif*
I S** S""*
R9 40 Years Sh. VIII-l PI at 1 i Flood Imvel Elev N/A N/A N/A N/A N/A N/A N/A Above Flood Imvel: Yes Submergence un M-li Notes:
- Documentation
References:
V10-5B See attached list.
V10-4A and B (Core Spray) 4
SUMMARY
SHEET NO.
Vlll-1 SCEW SHEET NO.
Vill-1 REV. 5 11-24-80 EQUIPMENT ENVIRONMENTAL QUALIFICATION DISCREPANT EQUIPMENT
SUMMARY
MILLSTONE UNIT 1 EQUIPMENT:
Relay MANUFACTURER: Chromalox Model D2936-25 Contactor SN-K320FU
~
QUALIFICATION DISCREPANCY:
Lacks documented qualification test data
'l SAFETY FUNCTION AND JUSTIFICATION FOR CONTINUED OPERATION:
1.
Transfer LPCI and C.S.P.P.S. from space heaters to water cooling.
2.
This equipment will have cogleted its safety function within the first 30 seconds of an incident. Based on our engineering evaluation, considering the equipment operating time and expected effects associated with the qualification discrepancy. it is concluded that this equipment would satisfactorily perform its design function.
3.
Due to the desirability of long term operability of this equipment, they will be replaced with qualified equipment. This will be accomplished as soon as practicable, prior to June 30, 1982, assuming that procurement delays do not preclude replacement by that date.
l 08 4
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