ML18018B292

Appendix a, Justification for Continued Operation, Component Review Summary Sheet

ML18018B292
Person / Time
Site:	Nine Mile Point
Issue date:	01/18/2018
From:	Niagara Mohawk Power Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML18018B292 (200)

Text

APPENDIX A NINE MILE POINT 'UNIT 1

JUSTIFICATION FOR CONTINUED -OPERATION

NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET EcCEui ment:

Control Rod Drive Scram Dump Control (SV NC-15A, SV NC-16A, SV NC-15B, SV NC-16B)

FRC E ui ment Item No.:

13 Manufacturer:

ASCO Model:

HVA904058A

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ualification Discre anc:

A, gM, QT Justification for Continued 0 eration:

During a reactor scram the scram discharge volume isolates by the closure of two air operated vent valves and two air operated drain valves which are in series.

Solenoid operated valves NC 15A and 158 control the operation of only one set of isolation valves (one drain and one vent).

The redundant set of isolation valves is controlled by solenoid operated valves NC 15C and 15D.

These valves were not included in the original program but are now included.

Simultaneous failure of both systems due to aging is highly improbable.

Solenoid operated valves NC 16A and B (Backup Scram Valves) perform a function which is redundant to the two (2) scram valve pilots on each of the 129 Control Rod Drive Hydraulic Units.

Instrument air will be vented from the scram valve pilot air header, during a scram initiation, by either the Backup Scram Valves or the Scram Valve Pilots.

Failure of solenoid operated valves NC 16A & B to operate would not adversely affect the scram function.

Loss of power causes the valves to go to the correct position.

Simultaneous failure of the scram valve pilots and the backup scram valves is highly improbable.

Based on the above, continued operation is justified until the SOV's are qualified or replaced with documented qualified valves.

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II NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET Equipment:

Solenoid Valve (SV201.2-32, SV201.2-03)

FRC Equi ment Item No.:

16 Manufacturer:

ASCO Model:

WPLB300872F Safety Function:

Drywell N2 Makeup and bleed valve operation Qualification Discrepancy:

QM, Qualified Life Justification for Continued Operation:

These valves are used to makeup and bleed N2 following a loss of coolant accident.

These valves are normally closed and the solenoids fail closed on loss of power.

This makeup and bleed path has a redundant path connecting to the torus which is in a lower elevation in the Reactor Building.

Simultaneous failure of both systems due to aging is highly improbable.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

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Equipment:

Master Trip Unit FRC E uipment Item-No.:

19 Manufacturer:

Rosemount Model:

510 DU Safety Function:

Drywell Pressure Trip Unit/Emergency Condenser High Flow Trip/Main Steam Line Flow Trip

/uglification Discrepancy:

Radiation, qualification time, aging, qualification method.

Justification for-Continued 0 eration:

These instruments are located in the Reactor Building at elevation 281'ne in each of the four corners.

Drywell Pressure Trip Unit For breaks within the drywell temperature, pressure or humidity does not increase in the Reactor Building where these trip units are located.

Radiation is the only effect that these units would experience after a

loss of coolant accident.

Only the drywell pressure trip units are needed to mitigate a loss of coolant accident.

These units automatically perform their safety function within seconds.

Once they have initiated their safety function no fai lure could negate it.

They fail safe on trip unit failure or loss of power.

Emer ency Condenser Hi h Flow Tri The Emergency Condenser Flow trip units for PT-36-06A, B,

C, 8

D are needed to mitigate an emergency condenser steam line break outside of containment'.

These trip units are not in close proximity to the break locations and automatically perform their safety function within the first few seconds of the event.

Main Steam Line Flow Tri Main steam line flow trip units are not exposed to the harsh environment of a steamline break since they are not located near the breaks.

These instruments automatically perform their safety function by isolating the steam line at the start of the event and once performed, instrument failure cannot open these valves.

Subsequent instrument/trip unit failure has no effect on the operator's response.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET EcCEui ment:

Trip Units for LT 36-03A, 8, C,

D; LT 36-04A, 8, C,

D; LT 36-05A, B, C,

D; PT 36-07A, B,

C, D;

PT 36-08A, B,

C, D.

FRC E ui ment Item No.:

20 Manufacturer:

Rosemount Model:

510 DU

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11 1

1 11 1

high and low reactor pressure Qualification Discre anc QT, A, QI Justification for Continued 0 eration:

These trips units are located in the Reactor Building, one in each of the four ATS cabinets.

These cabinets are located in the four corners of the building, one per corner.

They are all de-energized to actuate and provide inputs to the RPS.

Their safety functions are automatically performed early in the event sequence as a

result of process conditions or as the result of a trip unit failure.

Failure of these level and pressure transmitter trip units can only affect long term monitoring and will not affect accident mitigation.

Therefore, justification for the continued safe oper ation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E ui ment:

Temperature Switches located in Steam Tunnels TS lB-10A thru 10H, J thru N, P, Q,

R FRC E ui ment Item No.:

28 Manufacturer:

Fenwal Model:

1700240

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Qualification Discre anc:

QT, A

Justification for Continued 0 eration:

The temperature switches monitor steam tunnel temperature and initiate main steam isolation valve closure on high steam tunnel temperature.

If the break is in the main steam line, increased pressure drop across the main steam line flow limiter will initiate main st'earn isolation valve closure.

The pressure drop is measured by instruments PT 01-26A thru H

located outside the steam tunnel (Reactor Building El. 237 North Instrument Room) which are not subject to the harsh environment.

A main steam line break in the tunnel will result in low reactor water level which will cause a scram and low low water level which will initiate both main steam isolation valve closure and containment isolation.

This instrumentation is located in the Reactor Building which is not subjected to a harsh environment from a high energy line break in the steam tunnel.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E ui ment:

Pressure Switches PS 40-07, 08 FRC E ui ment Item No.:

34 Manufacturer:

Mercoid Model:

OA 5432

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ualification Oiscre anc:

gT Justification for Continued 0 eration:

These pressure switches have been deleted from the environmental equipment qualification program since operation of the core spray pumps can be verified by pump flow measurement (FT RV-26A, B).

NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET f

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~E ui ment:

Vacuum Switches VCS63-11A,

11B, 12A, 12B,

13A, 13B FRC Equi ment Item No.:

37 Manufacturer:

Mercoid Model:

CP 4122 Safety Function:

Controls Air Operated Isolation Valves 68-08, 09, 10 to admit building atmosphere to drywell/torus.

ualification Discrepancy:

A, gI Justificat'ion for Continued=Operation:

The function of Vacuum Switches VCS68-11A, llB, 12A,

12B, 13A, 13B is to open air operated isolation valves 68-08, 09 and 10 when torus pressure is negative with respect to the reactor building.

This will admit reactor building atmosphere to the torus, thus equalizing the pressure.

There are two (2) vacuum switches associated with each valve.

The switches are installed in parallel so that either switch can operate the valve.

Simultaneous failure of both switches due to age-related degradation is highly improbable.

In addition, air operated check valves can provide the isolation function should these valves fail.

Based on the above, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET Equipment:

Level Transmitter FRC Equipment Item No.:

38 Manufacturer:

General Electric Model:

553 HB 3456 19079

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Y Qualification Discrepancy:

A, QI Justification for Continued Operation:

LT IA-12 is a wide range reactor vessel level monitor.

The monitor does not provide a safety function and its failure would not prevent any safety related equipment from performing its intended safety function.

It is used by the operator to monitor vessel water level during normal operation and Curing vessel filling prior to refueling.

Therefore, justification for the continued safe operation of the plant is demonstrated.

NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E uipment:

Radiation Detector located in the Turbine Building Condenser Area (RE RNOSA, B,

C, C)

FRC Equipment Item No.:

51 Manufacturer:

General Electric Model:

19492792 Safety Function:

Isolates MSIV on high radiation ualification Discrepancy:

R, QT, A, QM Justification for Continued Operation:

These radiation detectors monitor radiation levels in the main steam line and initiate a reactor scram and main steam isolation valve closure on high radiation level.

Their only purpose is to detect major fuel failure and initiate main steam isolation valve closure to minimize the release of fission products.

This equipment is not required to detect high energy pipe breaks and has been deleted from the environmental equipment qualification program.

The equipment required to detect high energy line breaks which occur in the Turbine Building are reactor vessel instrumentation which is located in the drywell and reactor building and is not subjected to a harsh environment.

This redundant equipment also scrams the reactor and closes the main steam isolation valve.

In addition, temperature switches located in the main steam line tunnel initiate main steam isolation.

If somehow there is major fuel damage without a pipe break, the probability is extremely small that these detectors, whose only function is to detect radiation, will fail as a result of radiation exposure without initiating a scram and main steam isolation valve closure.

Instrument failure is alarmed in the control room.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~Eui ment:

Terminal Boards Inside the Drywall FRC Equi ment Item-No.:

53 Manufacturer:

General Electric Model:

EB5 and EB25 Safety Function:

Terminal Boards ualification Discrepancy:

A, gI Justification for Continued 0 eration:

Testing of EB-5 and EB-25 terminal boards for conditions exceeding those at Nine Mile Point Unit 1 has been performed within the industry.

The only differences were in the number of terminals.

Therefore, continued operation is justified.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET E ui ment:

Coaxial Instrument Cable located in Drywell FRC E ui ment Item No.:

54 Manufacturer:

Raychem Model:

RG59B/U

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I <<C 1Cb1 ualification Discre anc:

A, gI Justification for Continued 0 eration:

Coaxial instrument cable is used to transmit signals from detectors inside the drywell to signal processing equipment located outside the drywell.

The cables are connected to the neutron flux detectors, LPRM's, which are inputs to the APRM's.

The APRMs trip the reactor on high power.

Loss of the APRM as a result of a loss of coolant accident does not present a safety hazard since high drywell pressure or low vessel level will initiate a reactor trip.

These transmitters are located outside the drywell and are not affected by the same environment.

Small breaks which do not cause high drywell pressure or low vessel level but increase the drywell temperature will be detected by the drywell temperature monitors.

The drywell temperature monitors (thermocouples) do not use coaxial cable.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E ui ment:

Ground Connector located in the Drywell FRC E ui ment Item No.:

56 Manufacturer:

Burndy Model:

GZ Safety Function:

Ground Connector

/uglification Discre ancy:

gI Justification for Continued 0 eration:

The connector is manufactured with metallic components.

The physical properties of the metallic components are not affected by the environment which they are subjected to.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~Equi ment:

Connection Terminal in the Steam Tunnel at Elev. 240'-0" FRC E ui ment Item No.:

57 Manufacturer:

Burndy Model:

gA-8 Safety Function:

Cable to Terminal Connection ualification Discrepancy:

A, gI Justification=-for Continued Operation:

The connector is manufactured with metallic components.

The physical properties of the metallic components are not affected by the environment which they are subject to.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE NILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET Equipment:

Ground Connector located in the Drywell FRC Equipment Item No.:

58 Manufacturer:- Burndy Model:

QASC-B Qualification Oiscrepancy:

A, QI Justification for Continued Operation:

The connector is manufactured with metallic components.

The physical properties of the metallic components are not affected by the environment which they are subjected to.

Therefore, justification for the continued safe operation of the plant is demonstrated.

NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~fui ment:

Cable Splice located in the Steam Tunnel at flev. 240'-0" FRC E uipment-Item No.:

59 Manufacturer:

AMP Inc.

Model:

Pre-Insulated Safety Function:

Butt Connector gualification Discrepancy:

A, gI check Justification for Continued Operation:

The failure of equipment which is fed by cable routed through the steam tunnel at elevation 240'oes not prevent safe shutdown or result in unacceptable off-site doses as a result of a main steam line break inside the steam tunnel.

A large break in the main steam line, causes increased pressure drop across the main steam flow limiter which initiates main steam isolation valve closure.

The pressure drop is measured by instruments PT 01-26A thru H

located outside the steam tunnel (Reactor Building El.

237 North Instrument Room) which are not subject to the harsh environment.

The inboard main steam isolation valve and its related electrical components are not subject to the harsh environment as they are located in the drywell.

The outboard main steam isolation valves which are located in the steam 'tunnel are air operated valves which fail closed on loss of air or power.

A main steam line break in the tunnel will result in low reactor water level which will cause a scram, and low low reactor water level which will initiate main steam isolation valve closure and containment isolation.

The motor operated feedwater isolation valves do not receive any isolation signal.

In addition, there is a check valve in series which serves the isolation function.

Failure of the steam tunnel temperature

switches, or main steam line radiation detectors does not prevent safe shutdown or result in unacceptable off-site doses.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E oi ment:

Electrical Connector located inside the Drywall FRC E ui ment Item No.:

60 Manufacturer:

AMP Model:

RING Tongue Terminal

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C ualification Discre anc A, gI Justification for Continued 0 eration:

Testing has been performed within the industry on cable terminations.

These terminations are insulated with nylon, polyvinyl chloride or polyvinylidene fluoride.

Test data on polyvinylidene fluoride, which is designed for nuclear applications has been tested at conditions which exceed those of Nine Mile Point Unit l.

Therefore, continued operation is justified.

NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET EsSEui ment:

Circuit Breakers FRC E ui ment Item No.:

62 Manufacturer:

General Electric Model:

AK05

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P C

Sp V1 d

Generator Cooling ualification Discre anc:

gualification Not Established Justification for Continued 0 eration:

These circuit breakers provide power to P81618 and PB1718 which are needed for loss of coolant accident/high energy line break mitigation and also provide power to various other non-loss of coolant accident/high energy line break electrical loads.

The circuit breakers are passive in the safe guard

mode, that is they are normally closed and are not required to operate during the course of the loss of coolant accident/high energy line break.

The operation of these breakers is mechanical in nature.

Therefore, justification for continued operation is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET EcCEui ment:

Electrical Tape located in the Steam Tunnel at Elev. 240'-0" FRC E ui ment Item No.:

63 Manufacturer:

3M Electro Products Model:

83

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C b1 C

/uglification Discre anc:

A, (}I (check)

Justification for Continued 0 eration:

The failure of equipment which is fed by cable routed through the steam tunnel at elevation 240'oes not prevent safe shutdown or result in unacceptable off-site doses as a result of a main steam line break inside the steam tunnel.

A large break in the main steam line, causes increased pressure drop across the main steam flow limiter which initiates main steam isolation valve closure.

The pressure drop is measured by differential pressure instruments PT 01-26A thru H located outside the steam tunnel (Reactor Building El. 237 North Instrument Room) which are not subject to the harsh environment.

The inboard main steam isolation valve and its related electrical components are not subject to the harsh environment.

The outboard main steam isolation valves which are located in the steam tunnel, are air operated valves which fail closed on'oss of air or power.

A main steam line break in the tunnel will also result in low reactor water level which will cause a scram, and low low reactor water level which will initiate main steam isolation valve closure and containment isolation.

The motor operated feedwater isolation valve do not receive any isolation signal.

In addition, there is a check valve in series which provides an isolation function.

Failure of the steam tunnel temperature

switches, or main steam radiation detectors does not prevent safe shutdown or result in unacceptable off-site doses.

Therefore, justification for the continued safe operation of the plant is demonstrated.

NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E ni ment:

Electrical Cable located inside the Drywall FRC E ui ment Item No.:

65 Manufacturer:

General Electric Model:

Vulkene a

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P dC 1600V d1000V Qualification Discre anc CS, A, QI Justification for Continued 0 eration:

Vulkene insulated cable without a jacket and with Neoprene and Irradiated Crosslinked Polymer jackets have operated properly under conditions exceeding the environment at Nine Mile Point Unit 1

have been tested with the industry.

Unjacketed Vulkene cable and Vulkene insulated cable with a PVC jacket are utilized at Nine Mile Point Unit 1.

The addition of a PVC jacket would further improve the environmental resistance of the overall system.

Therefore, continued operation is justified.

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NINE, MILE POINT'NIT 1

COMPONENT REVIEW

SUMMARY

SHEET

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i* d V

1 A<<(I 80-115)

FRC E ui ment Item No.:

73 Manufacturer:

Limitorque Model:

SMB-000 HlBC Function:

Primary Containment Isolation (Containment Spray to Waste Building) ualification Summar This valve operator is judged to possess a 40 year qualified life based on Patel Engineers Report PEI-TR-l2-7.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E ui ment:

Motorized Yalve Actuator (IY 80-114)

FRC E ui ment Item Number:

74 Manufacturer:

Limitorque SMB-000 HlBC and SMB-000-2 Model:

SMB-000-MlBC Function:

Primary Containment Isolation (Containment Spray to Waste Building) gualification Summar This valve operator is judged to possess a 40 year qualified life based on Patel Engineers Report PEI-TR-l2-8.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~Eui ment:

Motorized Yalve Actuator (IY 110-127)

FRC E ui ment Item Number:

75 Manufacturer:

Limitorque Model:

SMB-000-2 Function:

React'or Coolant Sample Isolation Valve

(}uglification Summar This valve operator is judged to possess a 40 year qualified life based on Pastel Engineers Report PEI-TR-12-8.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET EcCEui ment:

Motorized Va1ve Actuator (IV 110-128)

FRC E ui ment Item Number:

76 Manufacturer:

Limitorque Model:

SMB-000-2 Function:

Reactor Coolant Sample Isolation qualification Summar This valve operator is judged to possess a

10 year qualified life based on Patel Engineers Report PEI-TR-12-11.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E ui ment':

Motorized Yalve Actuator (IY 80-118)

FRC E ui ment Item Number:

77 Manufacturer:

Limitorque Model:

SMB-0 Function:

Flow Control Valve for Torus Cooling qualification Summar This valve operator is judged to possess a 10 year qualified life based on Patel Engineers Report PEI-TR-12-11.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

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FRC E ui ment Item Number:

78 Manufacturer:

Limitorque Model:

SMB-000 Function:

Emergency Condenser Vent to Torus gualification Summar This valve operator is judged to possess a

10 year qualified life based on Patel Engineers Report PEI-TR-12-11.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E oi ment:

Solenoid Yalve FRC E ui ment Item No.:

79 Manufacturer:

ASCO Model:

HT 8317A29

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1:

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0 02.

122-08 through -ll) ualification Discr e anc gualification Not Established Justification for Continued 0 eration:

These valves were recently installed as part of Niagara Mohawk's Post Accident Sampling System.

Failure of these valves would not prevent safety related equipment from performing its intended function.

Failure would not affect the plants'ccident mitigation capability or its capability to prevent the release of radioactive material to the environment.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~Eui ment:

PT 36-23A, 6

FRC E ui ment Item No.:

Sl Manufacturer:

Rosemount Model:

1153GA9

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9 effects on LT-36-24A, B

ualification Discre anc qualification Not Established Justification for Continued 0 eration:

These pressure transmitters were recently installed as required by NUREG 0737 item II.F.2.3, Instrumentation for Detection of Inadequate Core Cooling.

This level monitoring system does not provide for actuation of any safety systems.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E ui ment:

Containment Pressure Indication (PT201.2-483, 484)

FRC E ui ment Item No.:

82 Manufacturer:

Rosemount Iiodel:

1153 Series A

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<<C 1R operator following a LOCA equal ificati on Disere anc:

A, gT Justification for Continued 0 eration:

Pressure transmitters, PT 201.2-483 and 484, provide the'ontrol room operator with indication of pressure inside the primary containment following a loss of coolant accident.

These transmitters do not initiate any safety systems, they provide indication only.

In the event of failure of one of these devices due to age-related degradiation, the same function will be provided by the redundant transmitter.

Simultaneous failure of both components due to aging is highly improbable.

In addition, both devices are located outside of the primary containment and wi 11 not be subjected to a steam environment during a Loss of Coolant Accident.

Therefore, justification for the continued safe operation of the plant is demonstrated.

NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET Equipment:

LT 36-24A, B

FRC E ui ment Item No.:

83 Manufacturer:

Rosemount Model:

1153DAS Safety Function:

Monitor reactor vessel level in fuel zone ualification Discrepancy:

gualification Not Established Justification for Continued Operation:

These pressure transmitters were recently installed as required by NUREG 0737 item II.F.2.3, Instrumentation for Detection of Inadequate Core Cooling.

This monitoring system does not provide for actuation of any safety systems.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET Equipment:

Flow Switch, FET-664 FRC E uipment Item No.:

84 Manufacturer:

Foxboro Model:

El 3DL Transmitter Safety Function:

Flow Control qualification-Discre ancy:

qualification Not Established Justification for Continued 0 eration:

This flow switch was recently installed as required by NUREG 0737 item II.B.3, Post Accident Sampling System.

The system does not provide information to indicate whether any plant safety functions are being accomplished.

Failure of this flow switch would not prevent any safety-related equipment from performing their intended safety function.

Failure would not affect the plant's accident mitigation capability or its capability to prevent the release of radioactive material to the environment.

Therefore, justification for the continued safe oper ation of the plant is demonstrated.

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NINE NILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET Equipment:

Pressure Switch (PS 122-14)

FRC E ui ment Item Number:

85 Manufacturer:

Static-0-Ring Model:

5NNKK351ClA Function:

Post Accident Sampling Pump By-Pass

/uglification Summary:

This pressure switch is judged to possess an 11 year qualified life based on Patel Engineers Report PEI-TR-82-12-18.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

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~E ui ment:

Radiation getector located in Reactor Building Elev. 261'201.7 36A, 37A)

FRC Equi ment Item No.:

86 Manufacturer:

General Atomic Model:

RD23 Safety Function:

High Range Radiation Monitor

/uglification Discre ancy:

Equipment gualification Not Established Justification for Continued 0 eration:

These radiation detectors were recently installed as required by NUREG 0737 item II.F.1.3.

The system does not provide either actuation or indication that a safety system is performing its intended function.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET Equipment:

Limit Switch FRC Equipment-Item No.:

87 Manufacturer:

Micro Switch Model:

F Safety Function:

Position Indication for valves 122-04 through 06, 122-08 through ll Qualification Discre ancy:

Qualification Not Established Justification for Continued-Operation:

These limit switches were recently installed as required by NUREG 0737 item II.B.3, Post Accident Sampling System.

The system does not provide information to indicate whether the plant safety functions are being accomplished.

Failure of these limit switches would not prevent safety related equipment from performing its intended safety function.

Failure would not affect the plant's accident mitigation capability or its capability to prevent the release of radioactive material to the environment.

Therefore, justification for the continued safe operation of the plant is demonstrated.

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NINE MILE POINT UNIT 1

COMPONENT REVIEW

SUMMARY

SHEET

~E ui ment:

Tnermocouple FRC Equi ment Item No.:

88 Manufacturer:

Omega Model:

HWANSA22312DH114T834 Safety Function:

Temperature Measurements (TE-70-269A, TE-70-276A) Note:

TE-70-269A has been deleted from system.

gualification Discre ancy:

gualification Not Established Justification for Continued Operation:

This thermocouple was recently installed as required by NUREG 0737 item II.B.3, Post Accident Sampling System.

The system does not provide information to indicate whether the plant safety functions are being accomplished.

Failure of this thermocouple would not prevent safety related equipment from performing its intended safety function.

Failure would not affect the plant's accident mitigation capability or its capability to prevent the release of

~

~

~

radioactive material to the environment.

Therefore, justification for the continued safe operation of the plant is demons'trated.

~

P I

I th ll'I h

II lf

SYSTEM:

Reactor Building Closed Loop Cooling System (09)

BASES FOR INCLUSION ON MASTER=LIST:

The Reactor Building Closed Loop Cooling System provides deminer alized water at 85-95F to cool auxiliary equipment located in the Reactor and Waste Disposal Buildings.

The closed loop permits isolation of systems containing radioactive liquids from the service water which is returned to the lake.

The system has a heat removal capability of 136xl06 BTU/hr and a flow capability of 9,000 gpm.

The system consists of three half-capacity horizontal centrifugal pumps rated at 4500 gpm with a total developed head of 65 psi each three half-capacity counterflow shell and tube heat exchangers.

The Reactor Building Closed Loop Cooling System provides cooling water to the following major components:

Fuel Pool Heat Exchangers Instrument Air Compressors Electric Feedwater Pumps Condensate Pumps Feedwater Booster Pumps Control room, Laboratory, and Administration Building Air Conditioning Equipment Recirculation Pump Coolers Cleanup System Nonregenerative Heat Exchangers Drywell Air Coolers Waste Disposal System Heat Exchangers Shutdown Cooling System Heat Exchangers and Pump Coolers Off-Gas Vacuum Pump Coolers H2 - 02 Monitoring Systems Following a loss-of-coolant accident or high energy line break, the special operating procedures require the following systems or equipment cooled by the Reactor Building Closed Loop Cooling System to be operational:

High Pressure Coolant Injection System (electric feedwater

pumps, condensate

pumps, feedwater booster pumps)

Instrument Air Compressor H2 - 02 Monitoring Systems The Reactor Building Closed Loop Cooling System is required to support Functions 3 and 6, Reactor Core Cooling and Prevention of Significant Release of Radioactive Material to the Environment.

It should be included on the list of all safety-related systems requiring environmental equipment qualification in accordance with IE Bulletin 79-01B.

Note:

High Pressure Coolant Injection provides Safety Function 3

Instrument Air to CRD System (function 3),

Emergency Condenser (function 3) and Reactor Building Emergency Ventilation (Function 6)

Hp - 02 coolers - Safety Function 6

1 LI If ls II

SYSTEM:

Service Water (10)

BASES FOR INCLUDING OR DELETING FROM MASTER LIST'he Service Water System is designed to provide strained lake water for cooling the reactor and turbine building closed loop cooling systems, the steam jet air ejectors precooler, ejector vent cooler, the building local air coolers and other building services.

The system is designed to be available to cool the reactor building cooling water system under all conditions of operation.

The cooling water requirements during shutdown mode represent the most severe condition and is used as the design basis.

Following a loss-of-coolant accident or high energy line break, the Service Water System is required to provide a heat sink for the Reactor Building Closed Loop Cooling System.

The station Service Water System is required to support functions 3 and 6, Reactor Core Cooling and Prevention of Significant Release of Radioactive Material to the Environment, and should be included on the list of all safety-related systems requiring environmental equipment qualification in accordance with IE Bulletin 79-01B.

Note:

Reactor Building Closed Loop Cooling Water Supports Functions 3 and 6.

SYSTEM:

Containment Atmospheric Dilution (11)

BASES FOR INCLUSION ON MASTER LIST:

The Containment Atmospheric Dilution System is designed to limit the oxygen concentration of the primary containment atmosphere to less than 4.05 during a

loss-of-coolant accident (Updated FSAR, Section VII-G.3.0).

Following a loss-of-coolant accident, hydrogen and oxygen may be released within the primary containment from postulated metal-water reactions and radiolysis.

The initially inerted primary containment prevents the combustion of hydrogen evolved from a metal-water reaction.

However, radiolytic decomposition results in the release of both hydrogen and oxygen.

The Containment Atmospheric Dilution System functions by adding nitrogen to the primary containment atmosphere as the radiolytic formation of oxygen occurs.

Oxygen concentration is, therefore, diluted to remain below 4X by volume.

Since the radiolysis rate decreases with time as a result of fission product decay, the required nitrogen addition rate wi 11 also decrease.

Because the Containment Atmospheric Dilution System provides a means for limiting the oxygen concentration to less than 4.0 percent by volume (mitigates oxygen concentration produced by radiolysis after loss-of-coolant accident), it is concluded that the Containment Atmosphere Dilution System is required to achieve or support function 6, Prevention of Significant Release of Radioactive Material to the Environment.

It should be included on the list of safety-related systems requiring environmental equipment qualification in accordance with IE Bulletin 79-018.

SYSTEM:

Hydrogen and Oxygen Monitoring (12)

BASES FOR INCLUSION ON MASTER LIST:

The Hydrogen and Oxygen Monitoring System is a subsystem of the Combustible Gas Control System.

The Hydrogen and Oxygen Monitoring system provides hydrogen-oxygen concentration monitoring of the primary containment atmosphere.

Two redundant Hydrogen and Oxygen Sampling Systems monitor the hydrogen and oxygen concentrations in the drywell and suppression chamber to minimize stratification and sampling errors.

Five sampling probes check the drywell atmosphere (including the downcomer ring header),

while two sampling probes check the suppression chamber atmosphere.

An indication of hydrogen concentration (0-20 percent) and oxygen concentration (0-5 percent and 0-25 percent) in the primary containment atmosphere is provided in the control room.

5 In accordance with Nl-SOP-01, "Continual Loss of Coolant and 115 kV", the plant operator is required to monitor containment oxygen and maintain containment atmosphere at less than 4 percent oxygen.

The operator, therefore, uses the Hydrogen and Oxygen Monitoring Systems following a line break in the drywell to assist him in limiting oxygen concentration.

Because the Hydrogen and Oxygen Monitoring Systems assist the operator in limiting the oxygen concentration to less than 4.0X by volume, it is required to support function 6, Prevention. of Significant Release of Radioactive Material to the Environment.

It should be included on the list of safety-related systems requiring environmental equipment qualification in accordance with IE Bulletin 79-018.

SYSTEM:

Station Electric Distribution (13)

BASES FOR INCLUSION ON MASTER LIST:

The Station Electrical Power System provides normal and emergency sources of electrical power for normal plant operation and for prompt shutdown.

It also maintains the plant in a safe condition under various events.

Following a loss-of-coolant accident or high energy line break, portions of the Electrical Power Systems support accident mitigating, containment isolation, and post-accident systems and components by providing electrical power for accomplishment of design basis safety-functions.

The electrical power system is required to support functions 1 through 6, and shall be included on the list of all safety-related systems requiring environmental equipment qualification in accordance with IE Bulletin 79-01B.

SYSTEM:

Containment and Reactor Vessel Isolation (14)

BASES FOR INCLUSION ON MASTER LIST'solation valves are provided on lines penetrating the drywell and pressure suppression chamber to assure integrity of the containment when required during emergency and post-accident periods.

Isolation valves which must be closed to ensure containment integrity immediately after a major accident are automatically controlled by the reactor protection system.

Reactor vessel isolation valves are also included in this system.

The design objective of the containment isolation system allows the normal or emergency passage of fluids through the containment boundary while preserving the ability of the boundary to prevent or limit the escape of fission products that may result from postulated accidents.

The containment isolation system is required to support functions 2 and 6, Containment Isolation and Prevention of Significant Release of Radioactive Material to the Environment, and,should be included on the list of safety-related systems requiring environmental equipment qualification in accordance with IE Bulletin 79-01B.

SYSTEM:

Post-Accident Sampling (15)

BASES FOR INCLUSION ON MASTER LIST:

Post-Accident Sampling meets the requirements of NUREG 0737.

This system and its electrical components are not required to be environmentally qualified by IE Bulletin 79-01B.

However, environmental qualification of electrical equipment located in harsh environments is required for some TMI Lessons Learned requirements (NUREG 0737).

Action Item II.B.3 "Post-Accident Sampling Capability of Reactor Coolant and Containment" is such an item.

Consequently, the post-accident sampling system should meet environmental equipment qualification in accordance with IE Bulletin 79-01B, Supplement 3.

SYSTEM:

Instrument Air (16)

BASES-FOR DELETION FROM. MASTER LIST:

The Instrument Air System is a subsystem of the service, instrument and breathing air systems.

The Instrument Air System provides a reliable source of clean dry air for use in instruments and controls.

It functions as, a backup to the breathing air system.

Compressed air is supplied by one or a combination of three air compressors.

Two can be powered from the emergency diesel generators.

The Instrument Air System provides air to safety-related components.

Although safety-related equipment that uses instrument air is designed to fail to its fail safe position on loss of instrument air, there are some safety-related components that require air in order to mitigate the consequences of a design basis accident.

Following a loss-of-coolant accident Special Operating Procedure Nl-SOP-1 requires the operator under "Immediate Operator Action" to start an Instrument Air Compressor.

Air provided by this Instrument Air Compressor is used for the following components:

Reactor Building Emergency Ventilation E/P converters for FCV 202-50 and FCV 202-51.

Control Rod Hydraulic System E/P converters for FCY-NC-30A and FCV-NC-30B.

Emergency Cooling System condensate return valves IV-39-05 and IV-39-06.

These valves are to be cycled open and close to limit cooldown rate as described in Nl-OP-13.

H2 -02 System number 11 sample stream supply and return valves as well as System ll analyzer.

H2 -02 System number 12 Analyzer Containment N2 inverting and purge valves BV 201.2-02 BV-201.2-04 BV-201.2-46 FCV-201.8-02 PCV-201.8-01 IV-201.1-14 IV-201.1-16 PIC 201.2-532A IV-201.2-32 IV-201.2-03 Post Loss-of-Coolant Accident Sampling System Valves IV-122-03 BV-122-04 BV-122-05 BV-122-06 BV-122-08 BV-122-09 BV-122-10 BV-122-11 Vacuum Relief Valves require air to open IV 68-08 IV 68-09 IV 68-10

4 4

~

V 4

SYSTEM:

Instrument Air (cont'd)

The Instrument Air System is required to support functions 1, 2, 3, 5 and 6; and it should be included on the list of safety-related systems requiring environmental equipment qualification in accordance with IE Bulletin 79-01B.

Electrical components of the Instrument Air System are located in the Turbine Building.

Therefore, for postulated breaks within the drywell and the reactor building, the Instrument Air System can be exempted from environmental equipment qualification because it is in a "mild" environment.

For steam or feedwater line breaks in the Turbine Building, not all of the safety-related components supplied with air wi 11 need to operate.

Only equipment from the control rod drive hydraulic and emergency condenser systems are required.

For a major steam line break and feedwater line break inside the steam tunnel or condenser bay area, the control rod drive hydraulic and emergency cooling systems are not required to maintain adequate core cooling.

For less severe high energy line breaks the conditions inside the general area of the turbine building are less than 133F (maximum temperature of turbine building general area from major steam line break).

Since the temperature rise post-accident for less severe high energy line breaks is smaller (and negligible for small breaks),

both systems are expected to operated.

The control rod drive hydraulic system provides makeup flow for small high energy line breaks (i.e. less than 0.003 ft.2) when off-site power is not available.

As stated

above, a high energy line break of this size would not be large enough to cause a harsh environment in the Turbine Building.

The emergency core cooling system provides heat removal capability for both small and medium size breaks.

Although the Instrument Air System is expected to function following a medium size break, the loss of instrument air to the emergency condenser will not prevent the system from removing decay heat.

The emergency cooling system only requires instrument air for cycling open and closed the condensate return valves to regulate cooldown rate.

Upon loss of air these valves move to their fail safe position of open permitting continuous cooldown.

Based upon the above discussions, it is concluded that the Instrument Air System is exempt from environmental equipment qualification because its equipment is not exposed to a harsh environment.

SYSTEM:

Common Electrical Equipment (17)

BASES FOR INCLUSION ON LIST:

Electrical equipment common to systems provides or facilitates normal and emergency electrical power distribution to system equipment which perform required safety-functions.

Following a loss-of-coolant accident or high energy line break, electrical equipment items common to all safety-related systems support accident mitigating, containment isolation, and post-accident systems and components by providing or facilitating electrical power distribution for accomplishment of design basis safety-functions.

The electrical equipment common to systems is required to support functions 1

through 6, and should be environmentally qualified in accordance IE Bulletin 79-018.

For convenience and accountability, this equipment has been compiled into a "system" and is included on the list of safety-related sytsems.

SYSTEM:

Reactor Vessel Instrumentation (18)

BASES FOR INCLUSION ON MASTER LIST:

The Reactor Vessel Instrumentation System is a subset of a redundant fail-safe reactor protection system.

It consists of instrumentation which automatically initiates safety-related systems and equipment whenever pre-established limits are exceeded.

The reactor protection system consists of two independent logic channels (channels ll and 12).

Each channel has its own input sensors.

Within each logic channel are two identical,subchannels (Channels A and B in Channel 11 and Channels C and D in Channel

12) consisting of trip devices.

Thus, the system has a total of four independent subchannels.

Each subchannel has an input from an independent sensor monitoring each of the critical parameters.

The outputs of two of the subchannels are combined in a one-out-of-two logic.

The outputs of the remaining two channels are also combined in a one-out-of-two logic.

The'utputs of the two logic channels are combined so that they both must be tripped to initiate a scram or other protective function.

During normal operation, sensor and trip contacts are closed and=vital relays are energized.

Thus, the protective system is designed to fail safe.

Following a loss-of-coolant accident or high energy line break, the instrumentation and sensors of the Reactor Vessel Instrumentation System automatically provide signals to the reactor protection system logic channels to actuate systems and components required to perform design basis safety-functions.

The Reactor Vessel Instrumentation system is required to support functions 1,

2, 3, 4 and 6, and should be included on the list of safety-related systems requiring environmental equipment qualification in accordance with IE Bulletin 79-01B.

SYSTEM:

Support Instrumentation (19)

BASES FOR INCLUSION ON MASTER LIST:

Additional instrumentation is a subset of instrumentation in various systems that have not been accounted for during the review of the respective system and placed on the master list of safety-related equipment.

The instrumentation in this "system" consists of equipment which provides various safety-related functions to support accident mitigation, containment isolation, or post-accident monitoring.

Following a loss-of-coolant accident or high energy line break, the instrumentation included herein supports accident mitigation, containment isolation, or post-accident monitoring.

This instrumentation is required to support functions 1, 2, 3, 4 and 6, and should be included on the list of safety-related systems requiring environmental equipment qualification in accordance with IE Bulletin 79-018.

APPENDIX C

NINE MILE POINT UNIT 1

ENVIRONMENTAL EQUIPMENT QUALIFICATION COMPONENT CORRECTIVE ACTION LIST

0

LIST OF TABLES Table Title Pa e

1 2

3 4

5 6

7 8

9 10 ll 12 13 14 16 17 18 19 20 21 22 23 24 25 26 System Codes Locations Codes Corrective Action Codes Schedule Codes Solenoid Actuators for Pressure Relief Valves Solenoid Valves Position Limit Switches Electronic Trip Units Cable Motor Control Centers, MG Sets, Panels Electrical Insulation/Tape Electrical Terminal Blocks Electrical Terminals Temperature Switches Temperature Elements E/P Converters Transmitters Valve Actuators Motors Radiation Detectors Pressure Switches Penetrations/Connectors Electric Heaters H2 2 Monitors Deleted Equipment gualified Equipment 1

2 3

4 5

6 10 13 14 15 16 17 18 19 20 21 22 24 26 27 28 29 30 31 32 33

TABLE 1

System Code

~Set em 01 02 03 04 05 06 07 08 09 10 ll 12 13 14 15 16 17 18 19 Core Spray (CS)

Containment Spray (COS)

High Pressure Coolant Injection (HPCI)

Raw Water System Automatic Depressurization System (ADS)

Emergency Cooling (EC)

Reactor Building Emergency Ventilation (RBEV)

Control Rod Hydraulic System (CRD)

Reactor Building Closed Loop Cooling Water (RBCLC)

Service Water Containment Atmospheric Dilution (CAD)

Hydrogen and Oxygen Monitoring (H202)

Electrical Power Distribution (PD)

Containment and Reactor Vessel Isolation Reactor Vessel Post Accident Sampling Instrument Air Electrical Equipment Common to All Systems (CEE)

Reactor Vessel Instrumentation (RVI)

Additional Instrumentation

0

TABLE 2 LOCATION CODE Location Code Location Steam Tunnel Condenser Bay Area of Turbine Building Remainder of Turbine Building Emergency Cooling Condenser Area Elevation (ft) 2'40 243-297 All Elevations 340

~8ui ldin Turbine Turbine Turbine Reactor Containment Spray Heat Exchanger Area Emergency Condenser Isolation Valve Cubicle 318 298 Reactor Reactor 10 12 13 14 16 17 18 19 Emergency Condenser Return Valve Cubicle Clean-up System Cubicles Floor Area (general)

Floor Area (general)

Floor Area (general)

Floor Area (general)

Floor Area (general)

East Instrument Room West Instrument Room Instrument Room (North)

Floor Area (general)

Floor Area Drywe1 1 281 261 340 318 298 281 261 281 281 237 237 198 Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Reactor Containment

TABLE 3 CORRECTIVE ACTION COOE Replacement with available qualified equipment Equipment modification Equipment relocation Replacement pending determination of suitably qualified equipment gualification by additional testing gualification testing of equipment in progress gualification by additional/supplemental analysis (other than qual ified 1 ife) gualification by supplemental analysis of qualified life or modification of maintenance/surveillance program requirements.

Obtain'qualification report from vendor and evaluate qualification.

Obtain technical information from manufacturer and evaluate.

gualify the equipment by supplemental analysis or replace with qualified equipment.

TABLE 4 SCHEDULE CODES Code Date September 30, 1983 December 30, 1983 March 30, 1984 June 29, 1984 September 28, 1984

TABLE 5 SOLENOID ACTUATORS FOR PRESSURE RELIEF VALVES Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code GE GE GE GE GE GE Unimax Unimax Unimax Unimax Unimax Unimax 1525VX 1525VX 1525VX 1525VX 1525VX 1525VX KBL7HB-5 KBL7HB-5 KBL7HB-5 KBL7HB-5 KBL7HB-5 KBL7HB-5 PSV-NR-108A PSV-NR-108B PSV-NR-108C PSV-NR-108D PSV-NR-108E PSV-NR-109F POS-NR-108A POS-NR-108B POS-NR-108C POS-NR-108D POS-NR-108E POS-NR-108F 05 05 05 05 05 05 05 05 05 05 05 05 19 14 N/A 7 8 2

19 14 N/A 7 8 2

19 14 N/A 7 8 2

19 14 N/A 7 8 2

19 14 N/A 7,8 2

19 14 N/A 7 8 2

19 14 N/A 7,8 2

19 14 N/A 7,8 2

19 14 N/A 7,8 2

19 14 N/A 7,8 2

19 14 N/A 7,8 2

19 14 N/A 7 8 2

Manufacturer Model No.

Plant ID No.

TABLE 6 SOLENOID VALVES System Location Code Code New/

Corrective TER Deleted Action Schedule No.

Item Code Code ASCO ASCO ASCO ASCO Decco Decco Decco Decco ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO Valcor Valcor Valcor Valcor ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO HT8360A90 HT8360A90 HT8350A90 HT8350A90 24166 24166 24166 24166 8300 Series 8300 Series 8300 Series 8300 Series HT8300B58BU HT8300B58BU HT8300858BU HT8300B58BU NP8344A71E*

NP8344A71E*

NP8344A71E*

NP8344A71E*

NP8344A71E*

NP8344A71E*

NP8344A71E*

NP8344A71E*

NP8344A71E*

NP8344A71E*

NP8344A71E*

NP8344A71E*

V70900-21-1 V70900-21-1 V70900-21-1 V70900-21-1 8315B3F 8315B3F 831533F 831533F 831533F 831533F 831533F 831533F SOV-40-32B SOV-40-32C SOV-40-33B SOV-40-33C SOV-80-15 SOV-80-16 SOY-80-35 SOV-80-36 SV-39-05E SV-39-05E SV-39-06E SV-39-06E SV/IV-39-05 S V/IV-39-05 SV/IV-39-06 SV/IV-39-06 SV/IV-05-01R SV/IV-05-01R SV/IV-05-02R SV/IV-05-02R SV/IV-05-03R SV/IV-05-03R SV/IV-05-04R SV/IV-05-04R SV/IV-05-11 SV/IV-05-11 SV/IV-05-12 SV/IV-05-12 60-17E 60-17D 60-18D 60-18E SOV-39-11C SOV-39-11D SOV-39-12C SOV-39-12D SOV-39-13C SOV-39-13D SOV-39-14C SOV-39-14D 01 01 01 01 02 02 02 02 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 13 13 13 13 12 12 12 12 7

77' 7

7 7

7 2

2 2

5 5

5 2

2 2

2 2

2 2

2 9

9 06 6

6 6

6 6

6 6

N/A N/A N/A N/A 12 12 12 12 17 17 17 17 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A New New New New N/A N/A N/A N/A N/A N/A N/A N/A New New New New New New New New New New New New New New New New New New New New New New New New New New New New 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 1

1 7,8 7,8 7,8 7,8 1

1 1

1 1

1 1

1 Model number is for qualified replacement solenoid

Model Manufacturer No.

TABLE 6 (Continued)

SOLENOID VALVES New/

Corrective Plant System Location TER Deleted Action Schedule ID No.

Code Code No.

Item Code Code ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO HVA ASCO HVA ASCO HVA ASCO HVA ASCO HVA ASCO HVA ASCO ASCO Valcor Valcor ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO 8300C68F 8300C68F 8300C68F 8300C68F 8300C68 8300C68 8300C68 8300C68 8300C68 8300C68 90-405-2A 83160 90-405-2A 83160 90-405-2A 83160 90-405-2A 83160 90-405-2A 83160 90-405-2A 83160 HVA 90 405 2A HVA 90 405 8A PNV 70900-21-1 PNV 70900-21-1 8300B61RU 8300B61RU WPLB 8300B72F WPLB 8300B72F WPLB 8300B72F WPLB 8300B72F WPLB 8300B72F WPLB 8300B72F WPLB 8300B72F WPLB 8300B72F WPLB 8300B72F WPLB 8300B72F NP8344A71E NP8344A71E NP8344A71E NP8344A71E HT8317A30 HT8317A30 SV/BV-202-15 07 SV/BV-202-15 07 SV/BV-202-16 07 SV/BV-202-16 07 SV/BV-202-31 07 SV/BV-202-31 07 SV/BV-202-32 07 SV/BV-202-32 07 SV/BV-202-34 07 SV/BV-202-35 07 SV/BV-202-36 07 SV/BV-202-36 07 SV/BV-202-37 07 SV/BV-202-38 07 SV/BV-202-74 07 SV/BV-202-75 07 SV NC-15A 08 SV NC-15B 08 SV NC-15C 08 SV NC-15D 08 SV 201-2-06 11 SV 201-2-33 11 SV 201-2-03 11 SV 201-2-32 11 SV/IV-201-10 11 SV/IV-201-10 11 SV/IV-201-08 11 SV/IV-201-08 11 SV/IV-201-16 11 SV/IV-201-16 11 SV/IV-201-16 11 SV/IV-201-16 11 SV/IV-201.1-09 11 SV/IV-201.1-09 11 SV/IV-201.1-11 11 SV/IV-201.1-11 11 SOV-201.9-91 11 SOV-201.9-92 11 3

3 3

3 3

3 3

3 3

3 3

3 3

3 3

3 17 17 17 17 17 17 6

6 17 17 17 17 17 17 17 17 6

6 6

6ll 17 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 13 13 N/A N/A 15 15 16 16 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A New New New New New New New New New New New New New New New New N/A N/A New New N/A N/A N/A N/A New New New New New New New New New New New New New New 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7~8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 1

1 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 1

1 1

1 1

7,8

R h

TABLE 6 (Continued)

Manufacturer Model No.

Plant ID No.

SOLENOID VALVES New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO Lawrence Lawrence Lawrence Lawrence Lawrence Lawrence Lawrence Lawerence ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO 8300B61F 8300861F HT80173 HT80173 HT80173 HT80173 HT80173 HT80173 HT80173 HT80173 LB8320A-25 LB8320A-25 LB8320A-25 LB8320A-25 26DCSWPS 26DCSWPS 26DCSWPS 26DCSWPS 26DCSWPS 26DCSWPS 26DCSWPS 26DCSWPS LB8320A-25 LB8320A-25 LB8320A-25 LB8320A-25 HT8300B6RU HT8300B6RU HT8300B6RU HT8300B6RU HT80173 HT80173 HT80173 HT80173 SOV-201.2-02 SOV-201.2-04 SOV-201.2-431 SOV-201.7-432 SOV-201.2-429 SOV-201.2-430 SOV-201.2-421 SOV-201.2-422 SOV-201.2-420 SOV-201.2-419 SV/IV-201.7-03 SV/IV-201. 7-03 SV/IV-201.2-04 SV/IV-201.2-04 IV-201.2-23 IV-201.2-23 IV-201.2-25 IV-201.2-26 IV-201.2-27 IV-201.2-28 IV-201.2-29 IV-201.2-30 SV/IV-201.7-01 SV/IV-201.7-01 SV/IV-201.7-02 SV/IV-201. 7-02 SOV-201.7-20 SOV-201.7-21 SOV-201.7-23 SOV-201.7-26 SOV-201.7-24 SOV-201.7-25 SOV-201.7-22 SOV-201.7-27 llll 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 11 11 17 17 17 17 17 17 17 17 17 17 17 17 16 16 16 16 16 16 16 16llllllllll 11 12 12 11 11 12 12 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 10 10 10 10 10 10 10 10 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A New New New New New New New New New New New New New New N/A N/A N/A N/A N/A N/A N/A N/A New New New New New New New New New New New New 1

1 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 1

1 1

1 1

1 1

1 1

1 1

1

TABLE 6 (Continued)

SOLENOID VALVES Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code Decco De'cco Decco Decco ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO

'SCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO ASCO 24166 24166 24166 24166 WPLB 8300B68F WPLB 8300B68F WPLB 8300868F WP8300B61RU WP8300861RU WP8300B61RU WPHTX 8300B61U WPHTX 8300861U WPHTX 8300861U WPHTX 8300B61U WP8300B61U WP8300B61U WP8300861U WP8300B61U 8300B61RU 8300861RU HT8320A90MB HT8320A90MB HT8317A29 HT8317A29 HT8317A29 HT8317A29 HT8317A29 HT8317A20 HT8317A29 SV/IV-01-05 SV/IV-01-05 SV/IV-01-06 SV/IV-01-05 SV 68-08C SV 68-09C SV 68-10C SV/IV-83.1-10 SV/IV-83. 1-12 SV/IV-83.1-12 SV/IV-01-03 SV/IV-01-03 SV/IV-01-04 SV/IV-01-04 SV/IV-83. 1-10 SV/IV-83.1-10 SV/IV-83. 1-12 SV/IV-83.1-12 SV/IV-58. 1-01 SV/IV-58. 1-01 SOV-122-03B SOV-122-03C SOV-122-04 SOV-122-05 SOV-122-06 SOV-122-08 SOV-122-09 SOV-122-10 SOV-122-11 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 15 15 15 15 15 15 15 17 17 17 17 17 17 1

1 1

1 17 17 17 17 18 18 17 17 12 17 17 12 12 12 17 ll 11,ll 11 18 18 18 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 79 79 79 79 79 79 79 N/A N/A N/A N/A N//A N/A N/A New New New New New New New New New New New New New New New N/A N/A N/A N/A N/A N/A N/A 7,8 7,8 7,8 7,8 7,8 7,8 1

1 1

1 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 1

1 1

1 1

1 1

TABLE 7 POSITION LIMIT SWITCHES Manufacturer Model No.

New/

Corrective Plant System Location TER Deleted Action Schedule ID No.

Code Code No.

Item Code Code Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque NAMCO Limitorque NAMCO Limitorque Limitorque NAMCO NAMCO NAMCO NAMCO Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque NAMCO NAMCO NAMCO NAMCO NAMCO NAMCO Limitorque Limitorque Limitorque Limitorque Fisher Control Fisher Control Fisher Control Fisher Control Limitorque N/A N/A N/A N/A N/A N/A N/A N/A SMB 3 SMB 3 SMB 000 17031100 N/A 17031100 N/A N/A D2400X-2 D2400X-2 D2400X-2 D2400X-2 N/A N/A N/A N/A N/A N/A N/A SL3L SL3L 180 32302 180 32302 180 32302 180 32302 N/A N/A N/A N/A 304 304 304 304 N/A POS-81-02 POS-81-01 POS-81-21 POS-81-22 POS-40-02 POS-40-12 POS-40-01 POS-40-09 POS-40-11 POS-40-10 POS-40-30 POS-40-32 POS-40-31 POS-40-33 POS-40-05 POS-40-06 POS-80-15 POS-80-16 POS-80-35 POS-80-36 POS-80-01 POS-80-02 POS-80-21 POS-80-22 POS-80-118 POS-80-114 POS-80-115 POS-39-05 POS-39-06 POS-05-04 POS-05-12 POS-05-01 POS-05-11 POS-39-07 POS-39-08 POS-39-09 POS-39-10 POS-39-11 POS-39-12 POS-39-13 POS-39-14 POS-05-05 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 01 02 02 02 02 02 02 02 02 02 02 02 06 06 06 06 06 06 06 06 06 06 06 06 06 06 06 18 18 18 18 17 17 19 19 19 19 19 13 19 13 17 17 12 12 12 12 18 18 18 18ll 12 12 07 07 2

2 2

2 6

6 6

6 6

6 6

6 18 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 50 50 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A New New New New New New New New New New New New New New New New New New New New New New New New New New New N/A N/A New New New New New New New New New New New New New 7,8 7,8 7,8 7,8 7,8 7,8 1

1 1

1 1

9 1

9 7/8 7/8 7

7 7

7 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7

7 8

8 8

8 7,8 7,8 7,8 7,8 1

1 1

1 7,8 5

5 5

5 5

5 4

4 4

4 4

2 4

2 5

5 2

2 2

2 2

2 2

~ 2 2

2 2

2 2

2 2

2 2

5 5

5 5

5 5

5 5

5

TABLE 7 (Continued)

POSITION LIMIT SWITCHES Model Manufacturer No.

New/

Corrective Plant System Location TER Deleted Action Schedule ID No.

Code Code No.

Item Code Code Limitorque N/A Limitorque N/A Limitorque N/A NAMCO D2400X NAMCO 02400X NAMCO D2400X NAMCO D2400X NAMCO D2400X NAMCO 02400X NAMCO 02400X NAMCO 02400X Limitorque H/A NAMCO 2-180C1302 NAMCO 2-180C1302 Limitorque N/A Limitorque N/A Limitorque N/A Microswitch LSD4L Microswitch LSD4L Microswitch 276 Microswitch E236 Lawrence 506WA26DC SW-PS Lawrence 506WA26DC SW-PS Lawrence 506WA26DC SW-PS Lawrence 506WA26DC SW-PS Lawrence 506WA26DC SW-PS Lawrence 506WA26DC SW PS Lawrence 506WA26DC SW PS Crouse Hinds CPS 026 NAMCO EA-17031100 NAMCO EA-17031100 NAMCO EA-17031100 HAMCO EA-17031100 Micro DTE6-2RN Micro DTE6-2RN Micro DTE6-2RN Micro DTE6-2RN NAMCO D2400X-2 NAMCO D2400X-2 NAMCO 02400X-2 POS-05-07 POS-70-94 POS-70-92 POS-201.2-32 POS-201.2-03 POS-201.32 POS-201-08 POS-201-10 POS-201-16 POS-201.2-33 POS-201.2-06 POS-201.31 POS-201.1-09 POS-201.1-11 POS-201-07 POS-201-09 POS-201-17 POS-201.9-46 POS-201.9-47 POS-201.2-02 POS-201.2-04 POS-201.2-24 06 09 09llllllllllllll 11llllllllllllll 11ll 12 POS-201.2-27 POS-201.2-28 POS-201.2-29 POS-201.2-30 POS-201.2-111 POS-201.2-110 POS-201.2-109 POS-201.2-112 POS-201.7-03 POS-201.7-04 POS-201.7-01 PS0-201.7-02 POS-201.7-08 POS-201.7-09 POS-201-7-10 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 POS-201.2-24 12 POS-201.2-25 12 POS-201.2-26 12 18 17 13 66' 17 17 17 17 17ll 6

6 17 17 17ll 17ll 17 17 17 17 17 17 17 17 17 17 17 17 17 19 19 11 11 11 11 12 N/A N/A N/A 47 47 47 45 45 45 45 45 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A New New New N/A N/A N/A N/A N/A N/A N/A N/A New New New New New New New New New New New New New New Hew New Hew New New New New New New New New New New Hew New 7,8 7,8 7,8 7

7 7

7 7

7 7

7 7,8 8

8 7,8 7,8 7,8 1

7 1

7 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 9

9 9

9 1

1 1

1 7

7 7

TABLE 7 (Continued)

POSITION LIMIT SWITCHES Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code NAMCO NAMCO NAMCO NAMCO NAMCO NAMCO NAMCO NAMCO NAMCO Microswitch Microswitch Microswitch NAMCO NAMCO NAMCO NAMCO NAMCO NAMCO NAMCO NAMCO Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Rockwell Limitorque Limitorque Microswitch Microswitch Microswitch Microswitch Microswitch Microswitch Microswitch 02400X-2 SL3C58TW SL3CSBTW SL3CSBTW SL3C58TW 02400X 02400X D2400X 02400X 11LS1 11LSl 11LS1 02400X 02400X-2 02400X-2 02400X-2 02400X-2 02400X-2 02400X-2 02400X-2 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A CWP2075-8 N/A N/A F

F F

F F

F F

POS-201.7-11 POS-01-01 POS-01-02 POS-01-03 POS-01-04 POS-01-05 POS-01-06 POS-83.1-12 POS-83.1-10 POS-68-08 POS-68-09 POS-68-10 POS-58.1-01 POS-68-01 POS-68-02 POS-68-03 POS-68-04 POS-68-05 POS-68-06 POS-68-07 POS-33-01 POS-33-02 POS-33-04 POS-38-01 POS-38-13 POS-38-02 POS-31-08 POS-31-07 POS-34-01 POS-83.1-09 POS-83.1-11 00 POS-122-03 POS-110-127 POS-110-128 POS-122-04 POS-122-05 POS-122-06 POS-122-08 POS-122-09 POS-122-10 POS-122-11 12 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 14 12 01 01 01 01 01 01 17 17 17 17 17 18 17 17 17 17 17 17 17 19 19 8

19 19 13 01 01 6

19 19 17 19 12 17 17 17 17 17 17 17 N/A 49 49 100 100 46 46 45 45 48 48 48 New N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 87 87 87 87 87 87 87 New New New New New New New New New New New New New New New New New N/A N/A N/A N/A N/A N/A N/A N/A New N/A New N/A New N/A New 7

7 7

7 7

7 7

7 7

7 7

7 7

7 7

7 7

7 7

7 1

1 7,8 1

1 7,8 7,8 1

7,8 1

1 7,8 1

7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8

TABLE 8 ELECTRONIC TRIP UNTIS Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 510DU 201.2-476A 201.2-476B 201.2-476C 201.2-476D 36-06A 36-06B 36-06C 36-06D 01-26A 01-26B 01-26C 01-26D 01-26E 01-26F 01-26G 01-26H 36-03A 36-03C 36-03D 36-04A 36-04B 36-04C 36-04D 36-05A 36-05B 36-05C 36-05D 36-07A 36-07B 36-07C 36-07D 36-08A 36-08B 36-08C 36-08D 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19

~

19 19 19 19 19 19 19 19 19 19 19 19 19 12 19 N/A 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 12 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 20 20 20 20 20 20 20 20 20 20 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 12 12 12 12 12 12 12 12 12 20 20 20 20 N/A N/A N/A N/A 20 N/A 20 N/A 20 N/A 20 N/A 20

'/A 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8

TABLE 9 CABLE Model Manufacturer No.

Raychem RG59BU GE Vulkene Rockbestos RSS6104 Kerite Power Plant ID No.

New/

Correct i ve System Location TER Deleted Action Schedule Code Code No.

Item Code Code 17 19 54 N/A 9

2 17 19 65 N/A 7,8,9 2

17 06 94 N/A 7,9 2

17 01 71 N/A 7,8,9 3

TABLE 10 MOTOR CONTROL CENTERS, MG SETS, PANELS Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code GE GE GE GE GE GE GE GE Gf GE GE GE GE GE GE IC 7700 IC 7700 IC 7700 5LS4404 A22Y25 51S4404 A22Y25 IC 7700 IC 7700 AKD5 AKD5 AKD5 AKD5 IC7700 IC7095 Control Panel Control Panel 167 1718 161B MG-172 MG-162 161A 171A PB-16A PB-17A PB-16B PB-17B PB-155 Battery Board 12 MG-162 MG-172 13 13 13 13 13 13 13 13 13 13 13 13 13 13 13 12 72 N/A 13 72 N/A 13 72 N/A 03 N/A New 03 N/A New 13 N/A New 13 N/A New 12 N/A New 12 N/A New 12 62 N/A 12 62 N/A 12 N/A New 03 N/A New 03 N/A New 03 N/A New 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8

TABLE 11 ELECTRICAL INSULATION/TAPE New/

Corrective Model Plant System Location TER Deleted Action Schedule Manufacturer No.

ID No.

Code Code No.

Item Code Code J-M Amp Amp'M/Electro GE GE GE Kerite Kerite Kerite Duxseal Pre-insul Ring 83 227 1309 8380 Cement Friction Splice Sealant splice Connector Tape Sealant Varnish Tape Sealant Tape Tape 17 01 55 N/A 7,8 2

17 01 59 N/A 7,8 2

17 19 60 N/A 7,8 2

17 01 63 N/A 7,8 2

17 01 64 N/A 7,8 2

17 01 66 N/A 7,8 2

17 01 67 N/A 7,8 2

17 01 68 N/A 7,8 2

17 01 69 N/A 7,8 2

17 01 70 N/A 7,8 2

TABLE 12 ELECTRICAL TERMINAL BLOCKS Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code GE GE EB-5 N/A 17 19 53 N/A 7

1 EB-25 N/A 17 19 53 N/A 7

1

TABLE 13 ELECTRICAL TERMINALS Manufacturer Burndy Burndy Burndy Model No.

GZ QAB QABCB Plant ID No.

N/A N/A N/A New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code 17 19 56 N/A 7,8 1

17 01 57 N/A 7,8 1

17 19 58 N/A 7,8 1

TABLE 14 TEMPERATURE SWITCHES Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal Fenwal United Elect.

United Elect.

1700240 1700240 1700240 1700240 1700240 1700240 1700240 1700240 1700240 1700240 1700240 1700240 1700240 1700240 1700240 1700240 1700240 829C 829C TS1B-10A TS18-108 TS18-10C TS1B-10D TS1B-10E TS1B-10F TS1B-10G TS18-10H TS1B-10I TS18-1 oj TS1B-10K TS18-10L TSlB-10M TS1B-10N TS1B-10P TS1B-10Q TS18-10R TIS-202-54 TIS-202-55 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 19 07 07 01 28 N/A 7,8 3

01 28 N/A 7,8 3

01 28 N/A 7,8 3

01 28 N/A 7,8 3

01 29 N/A 7,8 3

01 28 N/A 7,8 3

01 28 N/A 7,8 3

01 28 N/A 7,8 3

01 28 N/A 7,8 3

01 29 N/A 7,8 3

01 28 N/A 7,8 3

01 28 N/A 7,8 3

01 28 N/A 7,8 3

01 29 N/A 7,8 3

01 29 N/A 7,8 3

01 29 N/A 7,8 3

01 29 N/A 7,8 3

03 N/A New 7,8 1

03 N/A New 7,8 1

TABLE 15 TEMPERATURE ELEMENTS Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code Pyco Pyco Pyco Pyco Pall Trinity Minco Nickel Minco Nickel Minco Nickel Minco Nickel Minco Nickel Minco Nickel Minco Nickel Minco Nickel Pall Trinity Pall Trinity Pall Trinity Pall Trinity 0231710 820395 0231710 820395 0231710 820395 0231710 820395 CU/6 R-T-D R-T-D R-T-D R-T-D R-T-D R-T-D R-T-D R-T-D CU/6 CU/6 CU/6 CU/6 36-29D TE-70-23 TE IB06-13 TE IB06-14 TE IB06-23 TE IB06-24 TE IB06-15 TE IB06-12 TE IB06-21 TE IB06-22 TT IG01A TE IG01B TE IGOlC TE IG01D 18 09 06 06 06 06 06 06 06 06 06 06 06 06 36-29A 18 36-29B 18 36-29C 18 19 89 N/A 19 89 N/A 14 90 N/A 15 90 N/A 12 22 N/A 06 32 N/A 06 32 N/A 06 32 N/A 06 32 N/A 06 N/A New 06 N/A New 06 N/A New 06 N/A New 04 N/A New 04 N/A New 10 N/A New 10 N/A New

TABLE 16 E/P CONVERTERS Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code Fisher Fisher Fisher Fisher Fisher Fisher Fisher Fisher Fisher fisher Fisher Fisher Fisher 546 546 546 546 S/N 4247252 S/N 4354590 546 546 546/4154882 546 546 546 546 E/P 60-22A E/P 60-17A E/P 60-23A E/P 60-18A E/P 202-92D E/P 202-49D E/P NC-30A E/P NC-308 E/P 70-137 E/P 201.9-48A E/P 201.9-49A E/P 201.8-01A E/P 201.8-02A 06 06 06 06 07 07 08 08 09ll 11llll 04 04 04 04 03 03 17 17ll 13 13 13 13 N/A New N/A New N/A New N/A New N/A New N/A New N/A New N/A New 21 N/A N/A New N/A New N/A New N/A New 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 3

3 3

33' 3

3 3

3 3

3 3

TABLE 17 TRANSMITTERS New/

Corrective Model Plant System Location TER Deleted Action Schedule Manufactus er No.

ID No.

Code Code No.

Item Code Code Rosemount GE/MAC Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount GE/MAC GE/MAC GE/MAC GE/MAC GE/MAC GE/MAC GE/MAC GE/MAC Endevco Endevco Endevco Endevco Endevco Endevco Rosemount Rosemount

~

Rosemount Rosemount GE/MAC GE/MAC 1151OP 553-1120AA2 1153A 1153A 1153 1153 1153 1153 553-122BAAY2 553-122BAAY2 553-122BOLA2R-N 553-122BAAY2 553-122BAAY2 553-122BAAY2 553-122BAAY2 553-122BAAY2 2273AM20 2273AM20 2273AM20 2273AM20 2273AM20 2273AM20 1151OP 1151OP 11510pl 11510P1 553-112BAAY2 553-112BAAY2 FT-RV26A 01 FT-RV26B 01 LT-58-05 01 LT-58-06 01 DPT 201.2-476A 02 OPT 201.2-476B 02 DPT 201.2-476C 02 OPT 201.2-4760 02 FT-80-49A 02 FT-80-71A 02 FT-80-56A 02 FT-80-76A 02 FT-93-30A 02 FT-93-33A 02 FT-93-32A 02 FT-93-34A 02 FT-19 05 FT-20 05 FT-21 05 FT-22 05 FT-23 05 FT-24 05 DPT-36-06A 06 OPT-36-06B 06 OPT-36-06C 06 DPT-36-060 06 LT-IG06A 06 LT-IG06B 06 17 17 18 18 15 15 14 14 13 13 13 13 10 10 10 10 19 19 19 19 19 19 15 15 14 14 10 10 39 N/A 39 N/A 80 N/A 80 N/A 30 N/A 30 N/A 30 N/A 30 N/A N/A New N/A New N/A New N/A New N/A New N/A New N/A New N/A New N/A New N/A New N/A New N/A New N/A New N/A New 29 N/A 29 N/A 29 N/A 29 N/A New N/A New N/A

'10 7,8,10 7,8 7,8 7,8 7,8 7,8 7,8 7,8,10 7,8,10 7,8,10 7,8,10 7,8,10 7,8,10 7,8,10 7,8,10 9

9 9

9 9

9 10 10 10 10 7,8,10 7,8,10

TABLE 17 (Continued)

TRANSMITTERS Manufacturer Model No.

Plant IO No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code Rosemount Rosemount GE/MAC GE/MAC GE/MAC Rosemount Rosemount Fisher Fisher Fisher Fisher Fisher Fisher Foxboro Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount GE/MAC 551 GE/MAC 551 GE/MAC 553 Rosemount Rosemount Rosemount Rosemount 1153DA5 1153OA5 554 554 553 1153A 1153A 2340-390 2340-390 2340-390 2340-390 2340-390 2340-380 E130L 1151DP 1151DP 1151DP 1151DP 1151DP 1151DP 11510P 1151DP 1151DP 11510P 1151DP 1151DP 1151DP 1151DP 1151OP 1151DP JB394616611 JB394616611 HB345619079 1153GA9 1153GA9 11530A5 1153DA5 LT-60-22 LT-60-23 FT-202-52A FT-202-49A FT-RD-15 201.2-483 201.2-484 PT-201.9-26 PT-201.9-80 FT-201.9-31 PT-201.8-45 PT-201.8-35 FT-201.8-41 FET-664 PT-36-07A PT-36-07B PT-36-07C PT-36-070 PT-36-08A PT-36-08B PT-36-08C PT-36-08D LT-36-03A LT-36-03B LT-36-03C LT-36-03D LT-36-04A LT-36-04B LT-36-04C LT-36-04D PT-ID-46A PT-ID-46B LT-IA-12 PT-36-23A PT-36-23B LT-36-24A LT-36-24B 06 06 07 07 08 11 11llllll 11llll 15 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 18 2

9 3

3 17 12 12 13 13 13 13 13 13 15 15 14 14 15 15 14 14 15 15 14 14 15 15 14 14

'15 14 15 15 15 15 15 N/A N/A N/A N/A N/A 82 82 N/A N/A N/A N/A N/A N/A 84 27 27 27 27 27 27 27 27 35 35 35 35 35 35 35 35 25 25 38 81 81 83 83 New New New New New N/A N/A New New New New New New N/A N/A N/A N/A N/A N/A N/A N/A N/A llllllll N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 7,8 7,8 7,8,10 7,8,10 7,8,10 7,8 7,8 1

1 1

1 1

1 7,8 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 7,8,10 7,8,10 7,8,10 7,8 7,8 7,8 7,8

TABLE 18 VALVE ACTUATORS Manufacturer Model No.

New/

Corrective Plant System Location TER Deleted Action Schedule ID No.

Code Code No.

Item Code Code Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque SMB 3

SMB 3 SMB 00 SMB 00 SMB-3 SMB-3 SMB 00 SMB 00 SMB 00 SMB 00 SMB 3 SMB 3 SMO 0 SMO 0 SMB 0 SMB 0 SMBOOO HIBC SMB 000 SMB 0 SMB 00 SMB 00 SMB 00 SMB 00 SMB 2

SMB 2

SMB 2

SMB 2

SMB 000 SMB 000 SMB 000-5 SMB 000 SMB 000 SMB 000 SB 4 SB 4

SB 0 SB 0 SB 1

SMB 000 SMB 000 SMB 000 IV-40-11 IV-40-10 IV-40-05 IV-40-06 IV-40-09 IV-40-01 IV-81-01 IV-81-02 IV-81-21 IV-81022 IV-40-30 IV-40-31 BV-93-27 BV-93-28 BV-93-26 BV-93-25 80-115 80-114 80-118 IV-80-01 IV-80-02 IV-80-21 IV-80-22 IV-39-10 IV-39-08 IV-39-07 IV-39-09 BV-05-05 BV-05-07 IV-201-31 IV-201-07 IV-201-09 IV-201-17 IV-01-02 IV-01-01 IV-33-01 IV-33-02 IV-33-04 IV-83.1-09 IV-83.1-11 110-128 01 01 01 01 01 01 01 01 01 01 01 01 02 02 2

2 2

2 2

2 2

2 2

6 6

6 6

06 06 llll 14 14 14 14 14 14 14 14 19 19 17 17 19 19 18 18 18 18 19 19 12 12 18 18 18'8 6

6 6

6 18 18 06 17 17 17 19 19 19 19 8

19 19 12 N/A N/A N/A N/A N/A N/A 5

5 5

5 73 74 77 N/A N/A N/A N/A 8

6 6

6 78 78 8

9 9

9 2

2 2

2 1

7 7

76 New New New New New New N/A N/A N/A N/A N/A N/A N/A New New New New N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4

N/A 4

N/A 7

N/A 7

N/A 1

1 7,8 7,8 1

1 7,8 7,8 7,8 7,8 1

1 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 1

1 1

1 7,8 1

1 7,8 4

4 5

5 4

5 5

5 5

4 4

5 5

5 5

2 2

2 2

.2 2

2 5

5 5

5 2

2 5

5 5

5 4

4 4

4 5

4 4

2

TABLE 18 (Continued)

VALVE ACTUATORS New/

Corrective Model Plant System Location TER Oeleted Action Schedule Manufacturer No.

ID No.

Code Code No.

Item Code Code Limitorque Limitorgue Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque Limitorque SMB 000 SMB 2

SMB 2

SMB 2

SMB SMB SMB 000 SMB 000 SMB 000 SMB 00 SHB 00 110-127 IV-38-02 IV-38-01 IV-38-13 HOV-IV-31-08 HOV-IV-31-07 HOV-IV-34-01 IV-70-92 IV-70-94 PCV-NC-18 PCV-NC-40 14 14 14 14 14 14 14 9

9 8

8 19 75 N/A 1

4 13 N/A New 7,8 5

19 N/A New 1

4 19 N/A New 1

4 1

N/A New 1

4 1

N/A New 1

4 6

N/A New 7,8 5

13 N/A New 7,8 5

17 N/A New 7,8 5

17 N/A New 7,8 5

17 N/A New 7,8 5

TABLE 19 MOTORS Manufacturer GE GE GE Franklin Fr anklin GE GE GE GE GE Model No.

K X

166A-HC8365174 5K6366XC 166A-HC8365174 5K6366XC 166A-HC8365174 5K6366XC 166A-HC8365174 5K828837C7 HC8365172 5K828837C7 HC8365172 5K828837C7 HC8365172 5K828837C7 HC8365172 5K6338XC 136A 5K6338XC 136A 5K6328CX 136A 5K6328XC 136A 3CT5MJ 3CT5MJ 5K334AK249A CB161088 5K334AK249A CB161088 5K334AK249A CB161088 5K184AL218 5K184AL218 5K8143 16A73 5K8143 16A73 M

Plant ID No.

M81-24 M81-03 M81-04 M81-49 M81-50 M81-51 M81-52 M80-03 M80-04 M80-23 M80-24 122-01 122-02 M70-01 M70-02 M70-03 202-33 202-53 NC08A NCOBB 09 09 09 7

7 11 41 N/A 7,8 1

11-41 N/A 7,8 1

11 41 N/A 7,8 1

3 N/A New 7,8 1

3 N/A New 7,8 1

17 N/A New 7,8 2

17 N/A New 7 8 2

New/

Corrective System Location TER Oeleted Action Schedule Code Code No.

Item Code Code 01 18 44 N/A 7,8 2

01 18 44 N/A 7,8 2

01 18 44 N/A 7,8 2

01 18 44 N/A 7,8 2

01 17 42 N/A 7,8 2

01 17 42 N/A 7,8 2

01 17 42 N/A 7,8 2

01 17 42 N/A 7,8 2

02 18 43 N/A 7,8 2

02 18 43 N/A 7,8 2

02 18 43 N/A 7,8 2

02 18 43 N/A 7,8 2

15 16 91 N/A 7 8 3

15 16 91 N/A 7 8 3

TABLE 20 RADIATION DETECTORS Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code GE GE GE GE GE GE General Gener al 194X927 194X927 194X927 194X927 194X927 194X927 Atomic RD23 Atomic RD23 RE-RN04A3 RE-RN04B4 RE-RN04C RE-RN04D RE-RN04A RE-RN04B 201.7-36A 201.7-37A 06 2

N/A New 7,8,10 3

06 2

N/A New 7,8,10 3

06 2

N/A New 7,8,10 3

06 2

N/A New 7,8,10 3

06 11 N/A New 7,8,10 3

06 ll N/A New 7,8,10 3

11 13 86 N/A 7,8 1

11 13 86 N/A 7,8 1

TABLE 21 PRESSURE SWITCHES Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code Mercoid Mercoid Vibraswitch Vibraswitch Vibraswitch Mercoid Mercoid Mercoid Mercoid Mercoid Mercoid Static 0-Ring Barksdale Barksdale Barksdale Barksdale Barksdale Barksdale DA23-156 DAW-43-103 366 366 366 CP4122 CP4122 CP4122 CP4122 CP4122 Cp4122 SNNKK3SlC1A 82S-H12SS 82S-HI2SS 82S-H12SS 82S-H12SS 82S-H12SS 82S-H12SS PS-R068A PS-R0688 PS-70-108 PS-70-109 PS-70-110 VCS68-11A VCS68-118 VCS68-12A VCS68-128 VCS68-13A VCS68-138 122-14 NR-108A NR-1088 NR-108C NR-1080 NR-108E NR-108F 8

8 9

9 0

14 14 14 14 14 14 15 18 18 18 18 18 18 17 17llll 11 17 17 17 17 17 17 16 15 15 14 14 14 14 N/A New N/A New N/A New N/A New N/A New 37 N/A 37 N/A 37 N/A 37 N/A 37 N/A 37 N/A 85 N/A N/A New N/A New N/A New N/A New N/A New N/A New 7,8 7,8 1

1 1

7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8 7,8

TABLE 22 PENETRATIONS/CONNECTORS New/

Corrective Model Plant System Location TER Oeleted Action Schedule Manufacturer No.

ID No.

Code Code No.

Item Code Code D.G. O'rien 19,5, 28 PIN 816 N/A 4 PIN 85 O.G. O'rien Cl OC0001G14/

N/A C10C0001G21 D.G. O'rien C10C0001G14/

N/A C10C0001G21 17 17 17 19 52 N/A 7 8 4

92 N/A 7,8 4

93 N/A 7 8 4

TABLE 23 ELECTRIC HEATERS Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Oeleted Action Schedule Code Code No.

Item Code Code Thermon TFK Thermon TFK Honeywell R7283B1081 202-73 202-73 202-76 7

03 N/A New 7,8 3

7 03 N/A New 7,8 3

7 03 N/A New 7,8 3

TABLE 24 H2-02 MONITORS Manufacturer Beckman Beckman Model No.

H2-02 H2-02 Plant ID No.

No.

11 No.

11 New/

Corrective System Location TER Deleted Action Schedule Code Code No.

Item Code Code 12 03 N/A New 7,8 3

12 03 N/A New 7,8 3

Manufacturer Model No.

Plant ID No.

TABLE 25 DELETED EQUIPMENT System Location Code Code New/

Corrective TER Deleted Action Schedule No.

Item Code Code Mercoid Mercoid GE/MAC GE/MAC GE/MAC GE/MAC Mercoid Mercoid Rosemount Rosemount ASCO ASCO Omega 0mega GE GE/MAC GE Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount Rosemount OA5432 DA5432 551 551 551 551 SD 8136 SD 8136 1151DP 11510P HVA904058A HVA904058A HWANSA2231 OH114T834 HWANSA2231 DH114T834 IC7700 551 194X92792 194X92792 194X92792 194X92792 1151DP 1151DP 1151DP 1151OP 1151DP 1151DP 1151DP 1151DP 1151OP 1151OP PS-40-08 PS-40-07 PT-80-75 PT-80-69 PT-80-47 PT-80-54 PS-80-61 PS-80-60 FT-ID-33A FT-ID-33B SV-NC-16A SV-NC-16B TE-70-269A TE-70-276A PB-1671 PT-ID-45 RE-RN05A RE-RN05B RE-RN05C RE-RN05D OPT-01-26A DPT-01-26B OPT-01-26C DPT-01-26D DPT-01-26E DPT-01-26F OPT-01-26G OPT-01-26H LT 58-05 LT 58-06 01 01 02 02 02 02 02 02 05 05 08 08 09 09 13 18 19 19 19 19 5

5 5

5 5

5 5

5 01 01 12 12 18 18 18 18 12 12 16 16 17 17 17 17 11 15 2

2 2

2 16 16 16 16 16 16 16 16 18 18 34 34 23 24 24 24 33 33 40 40 13 13 88 88 72 26 51 51 51 51 31 31 31 31 31 31 31 31 36 36 Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted Deleted N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Deleted Deleted Deleted Deleted Deleted N/A N/A N/A N/A N/A N/A N/A N/A N/A Deleted N/A Deleted N/A Deleted N/A Deleted

• N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 0

TABLE 26 QUALIFIED EQUIPMENT Manufacturer Model No.

Plant ID No.

New/

Corrective System Location TER Deleted Action Schedule Code 'ode No.

Item Code Code ELECTRICAL TERMINALS OZ Gedney XL N/A 17 01 61 N/A N/A N/A Kerite FR2/FR Rockbestos 16TSP Rockbestos Control N/A N/A CABLE 17 17 17 7

97 06 95 N/A 06 96 N/A N/A N/A N/A N/A r

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