ML093640750

Enclosure 1 to Ipn - 84 - 63, Specific Equipment Deficiencies List

ML093640750
Person / Time
Site:	Indian Point
Issue date:	12/30/2009
From:	New York Power Authority
To:	Office of Nuclear Reactor Regulation
References
Download: ML093640750 (58)

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to IPN -

84 3, SPECIFIC EQUIPMENT DEFICIENCIES-LIST New York Power Authority Indian Point 3 Nuclear Power Plant Docket No.

50-286

Specific Equipment Deficiencies A. Pressure, D/P and Level Transmitters TER Item No.

2 Description FT-946A,B,C,D (RHR Recirc. Flow Transmitters)

Manufacturer and Model No.

Barton 386 3

PT-455,-456,-457,-474 Foxboro (Pressurizer Pressure E11GMMCA Transmitters) 4 PT-402,-403 (Reactor Foxboro Coolant System ElIGH Pressure Transmitters)

-5 FT-924A,-925,-926, Foxboro

-926A,-927,-980, E13DMMCA

-981,-982,-945A,B (High Head SI Flow Trans.)

6 PT-922,-923,-947 Foxboro (SI Pump Suction and E11GM Discharge Pressure Transmitters 7

PT-948A,B,C; Foxboro PT-949A,B,C E11GM (Containment Pressure) 8 PT-1205 (City Water Pressure) PT-406A,B; PT-1260,-1261,-1262 (AFW Pump Suction Pressure PT-1263,-1264,

-1265 (AFW Pump Dis charge Pressure)

PT-1200,-1201,-1202,

-1203 (Main Feedwater Pressure)

Foxboro E11GM Location Containment Containment Containment Containment SI Pump Room Pipe Pene tration Area NRC Category I b Ib Ib Ib Ila Ila Aux. Feed Pump Room Deficiencies Documentation Similarity Aging, Accuracy Test Sequence Similarity Aging, Accuracy, Test Sequence Similarity, Aging AccuraCy Test Sequence Similarity Aging Similarity Aging Similarity Aging Resolution Replaced with Foxboro transmitters qualified to 1971'criteria. (8)

Replaced with Foxboro transmitters qualified to 1971 criteria (8).

Replaced with Foxboro transmitters

.qualified to 1971 criteria. (8)

Replaced with Foxboro transmitters qualified to 1971 criteria. (8)

These Units perform their function in a Mild Environment. (1) Transmitters are qualified for Post Accident Radiation WCAP-8541 applies.(3)

Transmitters qualified. WCAP-8541 and WCAP-9157 and NS-TMA-2319 apply. (3)

Transmitters Qualified for worst case steam environment. In addition, the harsh environment is precluded by a qualified temperature switch. WCAP-8541 and Westinghouse letter NS-TMA-2319 apply. (2)(3)

• Specific Equipment Deficiencies A. Pressure, D/P and Level Transmitters (continued)

TER Item No.

Description 8

PT-419A,B,C Cont'd PT-429A,B,C PT-439A,B,C, PT-449A,B,C (Main Steam Pressure) 9 PT-1163,-1164,-1165,

-1166 (AFW Pressure)

Manufacturer and Model No.

(See Preceeding Page)

Foxboro El1GM Location Aux. Feed Pump Room NRC Category.

Ila Ila Deficiencies Similarity Aging Similarity Aging Resolution See Preceeding Page.

Transmitters qualified. In addition, the harsh environment is precluded by a qualified temperature switch. WCAP-8541 applies. (3) (2) 10 FT-418A,B,FT-428A,B FT-438A,B,FT-448A,B (Main Feedwater Flow)

Foxboro E13DM Aux. Feed Pump Room Similarity Aging Transmitters qualified. In addition, the harsh environment is precluded by a qualified temperature switch. WCAP-8541 applies. (2)(3) 11 LT-417A,B,C,D LT-427A,B,C,D LT-437A,B,C,D LT-447A,B,C,D (Steam Generator Level)

LT-459,-460,-461 (Pressurizer Level) 23 LT-938,-939,-940,-941 (Cntmnt. and Recir. Sump Level) 39 Flow transmitter for the H2 Recombiner Foxboro E13DMMCA GEMS LS1900 Barton 386 Containment Similarity Aging Test.Sequence Containment Documentation Containment Documentation Replaced with Foxboro transmitters qualified to 1971 criteria. (8)

Except LT-459, -460, -461 which will be replaced during cycle 4/5 outage.

Note 13.

Replaced with Foxboro transmitters qualified to 1971 criteria. (8)

Specific Equipment Deficiencies B. Solenoid Valves for Air Operated Valves TER Item No.

Description 12 Solenoid for PCV-1121,

-1123 (City Water Valves)

PCV-1139 (AFW Recirc. Valve)

PCV-1187,-1188,-1189 (AFW Pump Steam Pressure Control) 13 Solenoid for 956A, B,C,D (Pressurizer Sample Isolation) 519,552 (Pressurizer Relief Tank Water Makeup Isolation) 1728,1723 (Sump Pump Discharge Isolation) 1702,1705 (Reactor Coolant Drain Pump Discharge Isolation) 1786,1787 (Reactor Coolant Drain Tank Vent Isolation) 1788,1789 (Drain Tank Gas Analyzer Isolation) 548,549 (Pressurizer Relief Tank Gas-Analyzer Isolation) 956E,F,G,H (Sample Isolation)

Manufacturer and Model No.

ASCO 8300 ASCO 8314 Location Au,. Feed Pump Room NRC Category IIa Pipe Pene tration Area Deficiencies Documentation Aging, Temperature Documentation Aging, Radiation Resolution Solenoids qualified. Harsh environ ment is precluded by a qualified temperature switch. 7154-1IIE applies.

(3)(2)

Solenoids qualified. The only harsh parameter is radiation. Report 7154-212E applies. (4)

Specific Equipment Deficiencies B. Solenoid Valves for Air Operated Valves (continued)

TER Item No.

Description 14 Solenoid for 791, 793,796,798 (Excess Letdown HX Isolation) 201,202 (Letdown Isolation) 15

-Solenoid for LCV-1158 (Condensate Storage Supply to AFW Pumps) 16 SOV-1534 thru 1541 (Radiation Monitor Isolation)

SOV-1271,-1273 (Containment Purge)

SOV-1314,1315,1316, 1317, 1523 thru 1526 (SG Blowdown and Sample Isolation) 17 SOV-1310A,B (Isolates Steam to AFW Pump Turbine)

.18 Solenoid for MS-1-31,

-32,-33,-34 Manufacturer and Model No.

ASCO 8316 ASCO 8317 ASCO 8300 ASCO 8316 Laurence 110114W Location NRC Category.

Pipe Pene tration Area Aux. Feed Pump Room Pipe Pene tration Area Steam and Feed Penetration Area Steam and Feed Penetration Area Deficiencies Documentation Aging Radiation Documentation Aging Radiation Documentation Aging Radiation Documentation Aging Temperature Documentation Resolution Solenoids qualified. The only harsh parameter is radiation. Report 7154-213E applies. (3)(4)

Solenoids qualified. The TER incorrectly states that this valve is located in the Pipe Penetration Area. It is located in the AFW Pump Room. The harsh environ ment is precluded by a qualified tempera ture switch. Report 7154-212E applies.

(2)(3)

Solenoids qualified. The only harsh parameter is radiation Qualification report 7154-111E applies. (3)

Not in Scope of 10CFR5O.49.(3)(5)

To be replaced with qualified units.(9)

Specific Equipment Deficiencies B. Solenoid Valves for Air Operated Valves (continued)

Manufacturer and Model No.

Location NRC Category.

Deficiencies 19 Solenoid for IV-5A&B, 3A&B,-2A&B 20 Solenoid for FCV-1170,

-117!2,PCV-1190 21 Solenoid for Fan Cooler Dampers.31, 32,33,34,35 SOV-1293 thru 1307 41 Solenoids for DWI, DW2,550,1610 (Containment Isolation) 51 Solenoid for PCV-1191,

-1192 (Containment Pressure Relief)

Laurence 629BC85PS ASCO HB-8316 NP-8320 Skinner ASCO NP-8316 ASCO NP-8316 Pipe Pene tration Area Containment Containment Radiation, Aging Spray Documentation Pipe Pene tration Area Pipe Pene tration Area None None These valves are in a mild environment

(< 104 rads) and therefore not within the scope of IOCFR50.49. (10)

Solenoid valves are qualified. AQ521678/TR and F-C4539 apply..7154-110E applies to HB-8316. (6)

Replace with qualified units. Report AQ521678/TR dated March 1978 applies.

Solenoid Valves are qualified units.

Report AQ521678/TR applies. (3)

Report 7154-IIOE Solenoid Valves are qualified units.

Report AQ521678/TR applies. (3)

Report 7154-iiOE TER Item No.

Description Resolution i

Specific Equipment Deficiencies C. Motors TER Item No.

Description 27 Motor for RHR Pump 31 & 32 Manufacturer.

and Model No.

Westinghouse 509UPZ Location RHR Pump Room NRC Category IIa Deficiencies Similarity Aging Resolution Motors are qualified. Qualification report 7154-220E applies. Aging analysis demonstrates 40 year life. (3) 28 Motor for the Aux. Feed Pump 31 & 33 29 Motor for the High Head SI Pump 31,32 &

33 30 Motor for Safety Injection Recircu lation Pump 31 & 32 Westinghouse 509US Westinghouse 509Us Westinghouse 588.5

-Aux. Feed Pump Room SI Pump Room Similarity Similarity Aging Containment Similarity Motors are qualified. Qualification report 7154-221E applies. Harsh environ ment is precluded by qualified tempera ture switch. (2)(3)

Motors are qualified. Qualification report 7154-222E applies. Aging analysis demonstrates 40 year life.. (1)(3)

Motors are qualified. Qualification report 7154-120E applies. Beta Plate-out analysis confirms that radiation test envelopes accident radiation conditions. (3)

Specific Equipment Deficiencies C. Motors (continued)

Description Motor for Contain ment Fan Cooler FCU-31 thru FCU-35 Manufacturer and Model No.

Westinghouse 69F97009 Location Containment NRC

.Category.

IIa Deficiencies Similarity Resolution Motors are qualified. Reports '7154-121E dated July 1983 and P801-09-2 dated November 1984 apply. Beta Plate-out analysis confirms that radiation test envelopes accident radiation conditions.

(3) 38 Motor for Hydrogen Recombiner Blower Westinghouse TBDF Containment Similarity Motors are qualified. Qualification report 7154-122E applies. (3)

TER Item No.

31

Specific Equipment Deficiencies D. Temperature Measurement Devices TER Item No.

Description 22 Reactor Coolant System RTD's 37 Hydrogen Recombiner Exhaust Thermocouple 40 Temperature Switches in AFW Pump Room Manufacturer and Model No.

Sostman 11901B Westinghouse A2092 UEC F11OA6CS Location Containment NRC Category Ib Containment Aux. Feed Pump Room Deficiencies Aging Temperature Radiation None Documentation Resolution Narrow range RTD's were replaced with qualified RdF units. WCAP-8587 applies.

Wide range RTD's to be replaced with Qualified Units.(9)

Equipment is qualified. WCAP-7709 applies.

Temperature switches are qualified.

Report 7154-245E applies. (2)(3)

Specific Equipment Deficiencies E. Electro-Pneumatic Transducers TER Item No.

Description 60 Transducer for PCV-1134,-1135,

-1136,-1137 Main Steam Atmosph eric Relief Valves 61 Transducer for FCV-405A,B,C,D PCV-406A,B,C,D AFW Control Valves Manufacturer and Model No.

Fisher 546 Fisher 546 NRC Location Category Steam and Feed HIc Penetration Area Aux. Feed Deficiencies Aging Aging Resolution Transducers qualified. Fisher report 4 Problem 12, Project 72AR28 dated 6/12/73 applies. Aging Report 7205 dated April 1984 applies. (3)

Transducers qualified.

Fisher report 4, Problem 12, Project 72AR28 dated 6/12/73 applies. Aging report 7205 dated April 1984 applies. (3)

Specific Equipment Deficiencies F. Electrical Distribution Devices TER Item No.

Description 24 Kerite Cable 25 Raychem Cable Splice 26 Lewis Cable 32 Terminal Blocks 33 Electrical Penetration 34 Electrical Penetration 35 1 and C panel For H2 Recombiner 44 Rockbestos Cable 45 Rockbestos Cable 59 Conax Connector Manufacturer and Model No.

Kerite Raychem WCSF(N).

Lewis Engineer ing Westinghouse 542247 Westinghouse WX-31774,-31775,

-31776 Westinghouse WX31892 Westinghouse Rockbestos Firewall III Rockbestos Firewall III Conax N11001-33 Location Inside and Out side Containment Inside and Out side Containment Inside and Out side Containment Containment NRC Category Ib Radiation Containment Containment Deficiencies Submergence Radiation Submergence Submergence Radiation Aging, Spray Radiation None None Radiation Pipe Penetration Area Containment Containment None None None Resolution Cable qualified.

Qualification report 170E applies.(3)

Splices qualified. Qualification report 170E applies.(3)

Cable qualified. Qualification report 170E applies.(3)

Terminal blocks qualified. Qualification report 7154-180E applies. (3)

Equipment is qualified. PEN-TR-81-37 and PEN-RLK-3-16-01 apply. (3)

Equipment is qualified.

PEN-TR-81-37 and PEN-RLK-3-16-O1 apply.(3 )

Note (10).

This. equipment is in a mild environment and therefore not within the scope of 10CFR50.49.

Equipment is qualified.

Rockbestos report dated 7/7/77 applies'.(3)

Equipment is qualified.

Rockbestos report dated 7/7/77 and report 170E apply. (3)

Equipment is qualified. Report IPS409 Rev. A applies.(3)

Specific Equipment Deficiencies G. Motor Operated Valves Description HCV-638,-640 RHR Flow Control Valves Manufacturer and Model No.

Limitorque SMB-O0

• Location Containment NRC Category

.IIc Deficiencies Aging Resolution Equipment is qualified. Report 7154-101E contains an Aging Analysis which demonstrates 40 year life. (3)

MOV-880A through H,J, Limitorque K(Filter Dousing Valves);;SMB MOV-856B,C,E,G,H&J (High Head SI Valves) MOV-1802A, B (SI Recirculation Pump Discharge Isolation)

MOV-745A,B; (RHR Isola tion Valves) MOV-889A, B (Recirculation Spray Valves) MOV-746,-747,

-899A,B (RHR HX Isolation Valves) MOV-822A,B (RHR HX Cooling Water Supply Valves) MOV-888A,B (High Head Recirculation Valves)

MOV-222 (Seal Water Isola tion Valve) MOV-769,-784,

-786,-789,-797,FCV-625 (RCP Cooling Water Supply)

MOV-842,-843 (SI Mini-Flow Isolation) MOV-851A,B (SI Discharge Valves) MOV-1810 RWST Discharge Valve)

MOV-887A,B (SI Pump Suction Isolation Valves) MOV-744 RHR Isolation Valve)

MOV-885A,B (Containment Sump Stop Valve) MOV-1835A,B (BIT Discharge Valves)

Inside and Out side Containment Similarity Aging Equipment is qualified. Qualification documented in report 7154-101E. Aging Analyses have been completed which demonstrates 40 year life. (3)(11.)

TER Item No.

1 55

Specific Equipment Deficiencies G. Motor Operated Valves (continued)

Description Manufacturer and Model No.

68 MOV-1852A,B (cont'd)

(BIT Injection Valves)

MOV-894A,B,C,D Accumulator Discharge Isolation.Valves Location NRC Category Deficiencies (See Preceeding Page)

TER Item No.

Resolution

Specific Equipment Deficiencies H. Valve TER Item No.

Limit Switches Description 42 Limit Switches for Valves 1610,550,DW-1, DW-2 (Containment Isolation Valves) 46 Limit Switches for PCV-1121,-1123 (AFW Recirculation Valves) 47 Limit Switches for MS-1-31,-32,-33,-34 (Main Steam Isolation Valves)

Manufacturer and Model No.

NAMCO EA-180 NAMCO EA-170 NAMCO SL3 Location Pipe-Penetration Area AFW' Pump Room Steam & Feed Penetration Area NRC Category Deficiencies None Documentation Documentation Resolution Equipment is qualified. ACME Cleveland Report dated 7/7/77 applies. (3)(2)

Equipment is qualified. Qualification for worst case environment established in report 7154-230E. Harsh environment is precluded by a qualified temperature switch. (2)(3)

Equipment is qualified. Qualification established by report 7154-232E. (3) 48 Limit Switches for NAMCO D2400X PCV-1214,1214A through.

1217,1217A)

(SG BlowdownValves) 956E,G (RCS Sample Iso.

Valves) 201,202 (Letdown Isolation Valves) 791,793, 796,798 (Letdown HX Iso.

Valves) 519,552.(PRZR Re lief Tank.Makeup) 956A,B, C,D (PRZR Sample Iso. Valves) 1723,1728 (Cont. Sump Dis charge) 1786,1787 (RC Drain Tank Vent Valves) 1702,1705 (RC Drain Tank Discharge)

(PCV-1223,1223A through 1226, 1226A (SG Sample Isolation Valves)

Pipe Penetration Area Documentation Equipment is qualified. The only harsh parameter for these switches is radia tion.

Report 7154-233E establishes qualification of these limit switches.

(3)

Specific Equipment Deficiencies H. Valve Limit Switches (continued)

-TER Item No.

Description 48 PCV-1234 through 1241 (cont'd)

(Radiation Monitor Isolation) 956G,H (Accumulator Sample)

PCV-1228 (Inst. Air Isolation) TCV-1104,

-1105 (Service Water)

.548,549 (PRT Gas Analyzer Iso. Valve) 1788,1789 (RCDT Gas Analyzer Iso. Valve) 49 Limit Switches for PCV-1310A,B 50 Limit Switches for IV-2A,-2B,-3A,-3B,

-5A,-5B (H2 Recombiner Isolation) 56 Limit Switches for 856B,G (SI Valves)

PCV-1190 (Ctmnt.

Pressure Relief) 57 Limit Switch for PCV-1191,-1192 (Cntmnt. Pressure Relief) 58 Position Switches for Fan Cooler Dampers (31, 32,33,34,35)

Manufacturer and Model No.

NAMCO D24OOX Micro EXAR7313 Micro EXHAR-3 NAMCO EA-180 NAMCO EA-180 NAMCO EA-740

.Location Pipe Penetration Area NRC Category IB Steam and Feed.

Penetration Area Pipe Penetration Area Containment Pipe Penetration Area Containment Deficiencies Documentation Documentation Documentation Aging Aging Aging Resolution (See Preceeding Page).

Not within scope of rule.(5)

EquipTent is qualified. Report 7154-236E applies. Switches are in a mild environment ( 104 rads.) and therefore not-within the scope of 10 CFR 50.49 (10).

Equipment is qualified. Aging Analysis has been completed and a qualified life established. Report 7154-130E.(3)(12)

Equipment is qualified. Aging analysis has been completed and a qualified life established. Report 7154-130E.(3)

Equipment is qualified. Aging Analysis has been completed and a qualified life established. Report 7154-131E.(3)

Specific Equipment Deficiencies I. Miscellaneous Equipment TER Item No.

Description 36 Igniter Exciter for the H2 Recombiner 43 Relief Valve Acoustic Monitor Manufacturer and Model No.

Westinghouse GLA43737 TEC 500 Location Containment NRC Category Containment Deficiencies None Similairty Aging Temperature Resolution Equipment is qualified.. WCAP-7410L and WCAP-9001 apply.

Unit has been replaced with a qualified TEC system. Report 517-TR-03 Rev. 2 establishes qualification.

Notes for Specific Equipment EQ Deficiencies

1. This equipment performs its function before the environment becomes harsh. A harsh radiation environment can only occur after the safety injection function has been completed and the system is no longer in use. The safety injection pumps take suction from the refueling water storage tank which is not radioactive and no radiation exposure occurs to the equipment. When all of the water has been pumped into the plant the safety injection is no longer used for any break which would cause core damage. Recirculation through the safety injection system would only occur for very small breaks which would not depressurize the reactor coolant system. It is only recirculation through the RHR system after large break LOCA that results in a high radiation area in the pipe penetration area and SI pump room. In addition, test report WCAP-8541, WCAP-8754 and WCAP-7410L establishes qualification of the equipment for the harsh environment so that the equipment would be available for use at any time in the post accident period. Aging analyses and qualification-reports are available for all of the SI System Equipment.

2. The temperature switch which was installed to isolate the steam supply to the AFW pump turbine (TER Item 40) was placed in NRC category IB by FRC and a Documentation deficiency was assigned. Manufacturer's data for the switch has been obtained and the Authority has determined-that the switch is fully suitable for the conditions which would exist in the AFW pump room at the time the switch is required to function. Report 245E establishes qualification. To preclude the possibility of moisture entering the switch, the units have been sealed with RTV which have been qualified for LOCA exposure. Therefore, the switches are qualified and will function to preclude any harsh environment.

3. Aging evaluations for degradable materials have been completed. Surveillance procedures, maintenance/part replacement/equipment replacement intervals will be determined. The limiting parts in most cases are elastomeric materials. For equipment for which thermal preaging was performed as part of the qualification test program (NUREG-0588 Category 1 IEEE-323-74) the test parameters were used to extrapolate the results to Indian Point Unit No. 3 conditions using the Arrhenius methodology. For equipment for which no preaging was included in the.

qualification testing, the lifetime of degradable non-metallic materials was determined by the Arrhenius methodology using the activation energy data for the materials involved. In either case, the predicted-lifetime will be verified by periodic surveillance and monitoring of the equipment to determine whether degradation which could affect equipment performance (normal and accident) is occurring. Lubricant changeout intervals for motor bearings and Limitorque operators as recommended by the equipment manufacturers, INPO, EPRI and Operating Experience are included in.

the plant maintenance procedures. The Authority is aware that qualification testing performed by the manufacturer, NSSS supplier or utility groups may indicate that some maintenance operations may be required at Intervals'different than are contained in vendor technical manuals. Whenever such data is identified, it will be evaluated and factored into the Indian Point Unit No. 3 program as applicable.

4. The solenoids associated with the containment isolation valves in the pipe penetration area perform their safety function (deenergize to shut the air operated isolation valve) early in the accident. However, since the only harsh parameter is radiation, an analysis was performed to establish the ability of the solenoids to withstand the radiation environment for the I year post-accident period. These analyses demonstrate that all of the materials are suitable for the radiation level to which they would be exposed. Therefore the solenoid valves are considered qualified.

5. These valves are located in the steam and feedline penetration area.

Their function is to isolate a break in the steam line to the AFW pump turbine. The AFW pump room is a sealed room which does not connect to the steam and feedline penetration area so that the valves perform their function in a normal mild environment. The valves are not required to function in the event of a main steam line break in the pipe penetration area.

Their failure in the event of a main steam line break would not preclude supplying auxiliary feed water to the steam generators because the 2 motor operated AFW pumps are not affected and will supply an adequate amount of Feedwater to mitigate the accident.

Therefore it is concluded that these valves are not within the scope of 10CFR50.49 because they are not affected by the accident they are intended to mitigate and have no mitigating function for the accident to which they are exposed.

6. The results of the testing show that the SOVs operated satisfactorily throughout the testing and only showed reduced insulation resistance which did not preclude the units from functioning. The performance of solenoids during the tests indicate successful operation under all operating conditions. The problems identified in the TER are associated with omission of a megger test by the test laboratory not operation.

During the 30 day expsoure to chemical spray, the spray solution penetrated the flexible conduit connected to the solenoid enclosure. As a consequence the coil enclosures of the valves being tested were partially filled with the buffered boric acid spray solution. Even though the solenoid coil was directly in contact with spray solution, the valves cycled properly when energized or de-energized in their normal voltage range (+10%, -15%) for the full 30 day test-duration. However, because of the presence of boric acid solution in the coil enclosure, it was decided that the 500VDC megger test and the dielectric strength test should not be conducted to avoid damage to the coil.

The boric acid solution was baked out of the coil enclosures and the valves were then successfully subjected to the megger and dielectric strength tests.

Since neither megger tests nor dielectric strength tests would be conducted on valves installed at Indian Point Unit No. 3 following an accident, the omission of such testing is of no consequence for the actual applications. The solenoids, however, will be sealed with a~-qualified sealant to preclude entry of any foreigh material through the conduit connection in the solenoid enclosure.

7. Certain cables were assigned to NRC Category Ib and cited with a submergence deficiency. These cables have been subjected to LOCA tests which are significantly more severe than that the Indian Point accident condition; to accelerated water absorption tests (194 0F demineralized water);

Submergence in elevated temperature Hudson River water; and similar cables have been subjected to testing for 8 weeks at 200OF in a solution containing 1800 ppm boric acid, 50 ppm hydrazine, and buffered to a pH of 7-7.5 with trisodium phosphate. The Authority considers that the cables are qualified for post accident submergence as demonstrated in Report 170E.

8. The. transmitters installed utilize amplifier assemblies qualified to IEEE-323-1971 criteria. These assemblies will be replaced with ones qualified to the IEEE-323-1974 criteria which will upgrade the transmitter qualification to the 1974 criteria. This will be completed by the end of the cycle 4/5 refueling outage.

\\

9. This item has been scheduled to be completed during the cycle 4/5 refueling outage.

10.

The only parameter of concern is low levels of radiation 4-i0 3 rads).

11.

MOV-744, MOV-769 and MOV-797 have motor brakes with Class B insulation. WCAP-7410L indicates that the Class B insulated motor brake failed during environmental testing.. Although the testing was more severe than the Indian Point Unit 3 accident conditions, and because it cannot be determined at what point the motor brake failed and the exact cause of the failure, the Authority plans to replace the actuators of MOV-744, MOV-769 and MOV-797 with qualified actuators during the cycle 4/5 outage.

12. Note:

Deleted

13.

As part of the Indian Point Unit 3 TMI action plan program (NUREG-0737) Qualified Barton 764 transmitters were installed to monitor containment water level.

The installed GEMS level switches, however, provide signals to indicating lights in the control room. The Authority considers that the indicating lights provide useful information to the operating personnel.

Therefore, either bistables will be incorporated into the transmitter circuits or the GEM's level switches will be replaced with qualified units to provide signals to the indicating lights in the control room:

to IPN -

84-63 M'ASTER LIST OF ELECTRICAL EQUIPMENT New York Power Authority Indian Point 3 Nuclear Power Plant Docket No. 50-286.

MASTER LIST OF ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY TO BE ENVIRONMENTALLY QUALIFIED INDIAN POINT UNIT NO. 3 System I Safety Injection Plant ID No.

SI Pump 31, 32,33 FT-945A,B FT-924A,-925,-926,

-926A,-927,-980,

-981,932 PT-922,-923,-947 Recjrc. Pump 31, 32 MOV-856B,C,E,G, H,J MOV-1802A,B Limit Switches for 1851A,B MOV-850A, 850C Location SI Pump Room Containment Containment SI Pump Room Containment Containment Containment Pipe Penetr ation Area SI Pump Room Manufacturer and Model No.

Westinghouse 509US Foxboro NE13DH-HIH1 BE Foxboro NE11DM-HIC1 BE Foxboro EliGM Westinghouse 588.5 Limitorque SMB-O0 Limitorque SMB-00 NAMCO D2400X Limitorque SMB-O Description Motor for High Head SI Pump Flow Transmitter (Recirculation Spray.

Flow)

Flow Transmitter (High Head SI Flow)

Pressure Transmitter (SI Pump Suction &

Discharge Pressure Motor for SI Recirc.

Spray Pump High Head SI Valves SI Recirc. & Spray Pump Discharge Valves BIT to Boric Acid Tank (1851A, B)

SI Pump Discharge Expected Or

.Actual Installation Date Original Installation 1984 Original Installation Original Installation Original Installation Original Installation Original Installation 1983 Expected or Actual Environmental Qualification Documentation Date Units qualified.

Report 7154-222E dated July 1983 applies. (a)

Replaced with Foxboro transmitters qualified to 1971 criteria. (f)

Replaced with Foxboro transmitters qualified to 1971 criteria. (f)

Units qualified. WCAP-8541 and NS-TMA-2139 apply. (a)

Units qualified. Report 7154-120E dated July 1983 applies.

Units qualified.

Report 7154-01E dated August 1983 applies.

Units qualified.

Report 7154-101E dated August 1983 applies.

Units Qualified.

Report 7154-233E dated May 1983 applies.

Units Qualified. Repqrt 7154-11OE dated August 1983 applies.

System I, Safety Injection (continued)

Plant ID No..

MOV-889A, B MOV-888A,B MOV-842,843 MOV-851A,B MOV-1810 MOV-887A,B MOV-1835A,B MOV-1852A,B MOV-894A,B,C,D Limit Switches for Values 856B,G Solenoids for PCV-1851A,B Location Containment Pipe Penetration Area SI Pump Room SI Pump Roon SI Pump Room SI Pump Room Pipe Penetration Area SI Pump Room

.Containment Containment Pipe Pene tration Area Manufacturer and Model No.

Limitorque SMB-O Limitorque SMB-O0 Limitorque SMB-00 Limitorque SMB-O0 Limitorque SMB-00 Limitorque SMB-00 Limitorque SMB-O Limitorque SMB-O Limitorque SMB-2 NAMCO EA-180 Description SI Recirculation &

Spray Isolation Valves (Limitorque)

High Head SI Recirc.

Valves (Limitorque)

SI Mini-Flow Valves (Limitorque)

SI Discharge Valves (Limitorque)

RWST Discharge Valve.

(Limitorque)

SI Pump Suction Isolation Valves (Limitorque)

BIT Discharge Valves (Limitorque BIT Injection Valves (Limitorque)

Accumulation Discharge Valves (Limitorque)

Limit Switches for Valves 856B,G ASCO-8314 BIT to Boric Acid Tanks Expected Or Actual Installation Date Original Installation Original Installation Original Original Original Original Installation Installation Installation Installation Original Installation Original Installation Original Installation 1980 Original Installation Units dated Units dated Units dated Units dated Units dated Units dated Units dated Units dated Units dated Units dated Expected or Actual Environmental Qualification Documentation Date qualified.

Report 7154-l01E August 1983 applies.

qualified.

August 1983 qualified.

August 1983 qualified.

August 1983 qualified.

August 1983 qualified.

August 1983 qualified.

August 1983 qualified.

August 1983 qualified.

August 1983 qualified.

August 1983 Report 7154-101E applies.(a)

Report 7154-101E applies. (a)

Report 7154-101E applies. (a)

Report 7154-101E applies..(a)

Report 7154-101E applies. (a)

Report 7154-101E applies. (a)

Report 7154-101E applies.(a)

Report 7154-101E applies. (a)(h)

Report 7154-130E applies.

Units qualified.

Report 7154-212E dated May 1983 applies.

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XIII, Common Equipment.

System II, Auxiliary Coolant Plant ID No.

RHR Pump 31, 32 HCV-638,-640 MOV-745A,B MOV-1869A,B' MOV-746,747, 899A,B MOV-822A,B MOV-7,4 MOV-885A,B FT-638,640 Location RHR Pump Room Containment Containment Containment Containment Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area Containment MOV-769,-784,

-786,-789,-797; FCV-625 Pipe Pene tration Area Manufacturer and Model No.

Westinghouse 509UPZ Limitorque SMB-00 Limitorque SMB-00 Limitorque SMB Limitorque SMB-3 Limitorque SMB-00 Limitorque SMB-1 Limitorque SMB-O Foxboro N-E13DH HJM2-BE Description Motors for RHR Pumps (Westinghouse)

RHR Flow Control Valves (Limitorque)

RHR Isolation Valves (Limitorque)

RHR Isolation Valves (Limitorque)

RHR HX Isolation Valves;(Limitorque)

RHR HX Cooling Water Supply Valves (Limitorque)

RHR Isolation Valve (Limitorque)

Containment Sump Stop Valve RHR Flow Transmitters Limitorque RCP Cooling Water SMB-O0 Isolation (Limitorque)

Expected Or Actual Installation Date Original Installation 1980 Original Installation Original Installation Original Installation Original Installation Original Installation Original Installation 1984 Original Installation Expected or Actual Environmental Qualification Documentation Date Units qualified.

Report 7154-220E dated July 1983 applies.

Units qualified.

Report 7154-101E dated August 1983 applies.

Units qualified.

Report 7154-IOIE dated August 1983 applies.

Units qualified.

Report 7154-101E, dated August 1983 applies.

Units qualified. Report 7154-101E dated August 1983 applies.

Units qualified. Report 7154-101E dated August 1983.applies.

To be replaced with qualified units.

(b)(g)

Units qualified. Report 7154-101E dated August 1983 applies.

Replaced with qualified units.

Report 45592-4 dated 18 May 1983.

Units oualified e~r(ept McV 769 & 797.

Report 7154-101E dated August 1983 applies. (b) (g)

System II, Auxiliary Coolant (continued)

Manufacturer and Model No.

Description Foxboro N-13DH-RHR Recirculation HIM1-BE(A&C)

Flow Transmitters N-13DH-HIM1 BE(B&D)

GEMS LS1900 Recirculation Sump Level Transmitters Expected Or Actual Installation Date 1984 Original Installation Expected or Actual Environmental Qualification Documentation Date Replaced with Foxboro transmitters qualified to 1971 criteria. (f)

Note k.

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XIII, Common Equipment.

Plant ID No.

FT-946A,B, C,D LT-938,-939 Location Containment Containment

System III, Auxiliary Feedwater Plant ID No.

ABFP 31,33 PT-1205 PT-406A,B PT-1260,-1261,

-1262 PT-1263,-1264,

-1265 FT-1200,-1201, 1202-, -1203 PT-1163,-1164, i1165,-1166 Solenoids for PCV-1121, -1123 Solenoid for PCV-1139 Solenoids for PCV-11871-1188,

-1189 Solenoids for LCV-1158 Location AFW Pump Room AFW Pump Room AFW Pump Room AFW Pump Room AFW Pump Room AFW Pump Room AFW Pump Room AFW Pump Room AFW Pump Room AFW Pump Room Manufacturer and Model No.

Westinghouse Foxboro E11GM Foxboro E11GM Foxboro E11GM Foxboro Foxboro E11GM E11GM ASCP 8300 ASCO 8300 ASCO 8300 ASCO 8317 Description Motor for Auxiliary Feed Pumps Pressure Transmitter City Water Pressure Pressure Transmitter AFW Pump Suction Pressure Pressure Transmitter AFW Pump Discharge Pressure Feedwater Flow Transmitter Pressure Transmitter AFW'Pressure City Water Supply to AFW System AFW Recirc. Isolation AFW Pump Steam Pressure Control Condensate Storage Tank Discharge (ASCO)

Expected Or Actual Installation Date Original Installation Original Installation Original Installation Original Installation Original Original Original Original Original Installation Installation Installation Installation Installation Original Installation Units dated Units Aging Units Aging Units Aging Units Aging Units.

Aging Units dated Units dated Units dated Expected or Actual Environmental Qualification Documentation Date qualified. Report 7154-221E July 1983 applies. (c) qualified. WCAP-8541 applies.

March 1984. (c) qualified.

WCAP-8541 applies.

March 1984. (c) qualified. WCAP-8541 applies.

March 1984. (c) qualified. WCAP-8541 applies.

March 1984. (c) qualified. WCAP-8541 applies.

March 1984. (c) qualified. Report 7154-111E June 1983 applies. (c) qualified. Report 7154-111E June 1983 applies. (c) qualified.

Report 7154-111E June 1983 applies. (c)

Units qualified.

Report 7154-212E dated May 1983 applies. (c)

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XIII, Common Equipment.

System III, Auxiliary Feedwater (continued)

Plant ID No.

Limit Switch for PCV-1121, 1123 Limit Switch PCV-1187,1188,

-1189 TC-1112S, 1113S FCV-405A,B,C,D Location AFW Pump Room AFW Pump Room AFW Pump Room AFW Pump Room Manufacturer and Model No.

NAMCO EA-170 Micro BZE-2RN UEC F11OA6CS Fisher 546 Description Position Indicator for Auxiliary Feed water Recirculation Valves AFW Pump Suction Valve Position Indication (Micro)

Temperature Switch In AFW Pump Room E/P Converter for AFW Flow Control Expected Or Actual Installation Date Original Installation Original Installation Original Installation Original Installation Expected or Actual Environmental Qualification Documentation Date Units qualified. Report 7154-233E dated July 1983. (c)

Note C.

Units qualified. Report 7154-245E dated March 1984.(q)

Units qualified. Report 4, Problem 1531 Proj. 72AR28 applies. Aging Analysis Report No. 7205 dated April 1984 applies. (c)

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XIII, Common Equipment.

Note -

Previous submittals included the Solenoid Valves and Limit Switches for PCV-1310A&B, the Isolation Valves for the steam supply to the AFW Pump Turbines. However, the authority has determined that these valves are located in a mild environment for the accident they are intended to mitigate. These valves are located at different elevations in the Steam and Feedline penetration area. Their function is to isolate a break in the steam line to the AFW pump turbine. The AFW pump room is an isolated room which does not connect to the steam and feedline penetration area so that the valves perform their function in a normal mild environment. The valves are not required to function in the event of a main steam line break in the steam and feedline penetration area.

Their failure in the event of a main steam line break would not preclude supplying feedwater to the steam generators because the 2 motor driven AFW pumps are not affected and will supply an adequate amount of feedwater to mitigate the accident. Therefore it is concluded that these valves are not within the Scope of 10CFR50.49 because they are not affected by the accident they are intended to mitigate.

System IV, Reactor Coolant Plant ID No.

PT-455,-456,

-457,-474 LT-459,-460,

-461 PT-402,-403 Solenoids for PCV-956A,B,C,D Solenoids for PCV-519,-552 Solenoids for PCV-1702,-1705 Solenoids for PCV-1786,-1787.

Solenoids for AOV-1788,-1789,

-548,-549,

-956E,F,G,H SOV-1723,1728 MOV-222 Location Containment Containment Containment Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area

-Pipe Pene tration Area Pipe Pene tration Area Manufacturer and Model No.

Foxboro NE11GM NIE-1-BEL Foxboro NE13 DH Description Pressurizer Pressure Transmitters Pressurizer Level Transmitters Foxboro NE11GH-Reactor Coolant System HIM-BE Transmitters ASCO 8314 ASCO 8314 ASCO 8314 ASCO 8314 ASCO 8314 ASCO 8314 Limitorque SMB-O0 Pressurizer Sample Isolation Pressurizer Relief Tank Make-up Isolation R.C. Drain Pump Discharge Valves R.C. Drain Tank.Vent Valves Sampling Isolation, Valves Sump Pump Discharge Valves RCP Seal Water Isolation Expected Or Actual Installation Date 1984 1985 1984 Original Installation Original Installation Original Installation Original lnstallation Original Installation Original Installation Original Installation Expected or Actual Environmental Qualification Documentation Date Replaced with Foxboro transmitters qualified to 1971 criteria. (f)

To be replaced with qualified Foxboro Units. (g)

Replaced with Foxboro transmitters qualified to 1971 criteria. (f)

Units qualified. Report 7154-212E dated May 1983 applies.

Units qualified. Report 7154-212E dated May 1983 applies.

Units qualified.

Report 7154-212E dated May 1983 applies.

Units qualified.

Report 7154-212E dated May 1983 applies.

Units qualified.

Report 7154-212E dated May 1983 applies.

Units qualified. Report 7154-212E dated May 1983 applies.

Units qualified. Report 7154-I01E dated August 1983 applies.

System IV, Reactor Coolant (continued)

Plant ID No.

Location Solenoids for Containment AOV-951,-953,

-955A,B RTD-410A,B, Containment

-411A,B,

-413A,B,-420A,B,

-421A,B,-423A,B,

-430A,B,-431A,B,

-433A,B,-440A,B,

-441A,B,-443A,B No Tag No.

Containment MOV-535,:536 Containment Limit Switches Pipe Pene for PCV-956A, tration Are B,C,D,E,F Limit Switches Pipe Pene for PCV-1702, tration Are

-1705 Limit Switches Pipe Pene for PCV-1786, tration Are

-1787 Manufacturer and Model No.

Description ASCO NP-8320A Sampling Isolation 182E Valves RdF Reactor Cool-ant Temperature Sostman TEC -501 Limitorque SMB NAMCO-D2400X NAMCO D2400X NAMCO D2400X a

a a

Relief Valve Acoustic Monitor PORV Block Valves Reactor Coolant &

Pressurizer Sample Valve Position Reactor Coolant Drain Tank Discharge Valve Position R.C. Drain Tank Vent Valve Position Expected Or Actual Installation Date 1984 1983 Original Installation 1982 Original Installation Original Installation Original Installation Original Installation Expected or Actual Environmental Qualification Documentation Date Replaced with qualified units. Report AQ521678/TR dated March 1978.

Units qualified.

Narrow range units replaced with qualified RdF Units.

WCAP-8587 applies.

Wide range units to be replaced with qualified RdF Units.(g)

Units qualified. TEC report 517-TR-03 Rev. 2 applies.

Units qualified.

Report 7154-101E dated August 1983 applies.

Units qualified.

Report 7154-233E dated May 1983 applies.

Units qualified.

Report 7154-233E dated May 1983 appl.ies.

Units qualified.

Report 7154-233E dated May 1983 applies.

System IV, Reactor Coolant (continued)

Plant ID No.

Limit Switches for AOV-951,

-953,-955A,B Limit Switches for AOV-1788,

-1789,-548,-549, 956G,H Location Containment Pipe Pene tration Area Manufacturer and Model No.

Description NAMCO EA-180- Sample Isolation 21302 &

Valve Position EA-180-32302 NAMCO D2400X Sample Isolation Valve Position Expected Or Actual Installation Date 1984 Original Installation Expected or Actual Environmental Qualification Documentation Date Replaced with qualified units.

Report QTR-105 Rev. 1.

Units qualified.- Report 7154-233E dated May 1983 applies.

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XIII, Common Equipment.

System V, Chemical and Volume Control Plant ID oNo.

Location Solenoids for PCV-791,-793,

-796,-798 Solenoids for PCV-201,-202 SOV-1314,1314A thru 1317,1317A Limit Switches for PCV-791,

-793,-796,-798 Limit Switches for PCV-201,

-202 Limit Switches for PCV-1214,1214A thru 1217,1217A Limit Switches for 519 and 552 Limit Switches for Valves 1723 and 1728, Limit Switches for Valves 1786 1787 Limit Switches for Valves for PCV-1234 thru 1241 Pipe Pene tration Area Pipe Pene tration Area Pipe Pdne tration Area Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area Manufacturer and Model No.

ASCO 8316 ASCO 8316 ASCO-8300 NAMCO D2400X NAMCO D2400X NAMCO D2400X NAMCO D240OX NAMCO'D2400X NAMCO D2400X NAMCO D2400X Description Let Down HX Isola tion Valves Let Down Isolation Valves Steam Generator Blowdown Isolation Let Down HX Isola tion Valve Position Indication Let Down Isolation Valve Position/

Indication Steam Generator Blow down Isolation Position PZR Relief Tank Make up Isolation Position Containment Sump Discharge Valves Position Reactor Coolant Drain Tank Vent Position Radiation Monitoring Isolation Valves Position Expected Or Actual Installation Date Original Installation Original Installation Original Installation Original Installation Original Installation Original Installation Original Installation Original Installation Original Installation Original Installation Expected or Actual Environmental Qualification Documentation Date Units qualified. Report 7154-213E dated May 1983 applies.

Units qualified. Report 7154-213E dated May 1983 applies.

Units qualified. Report 7154-111 applies.

Units qualified.

Report 7154-233E dated May 1983 applies.

Units qualified.

Report 7154-233E dated May 1983 applies.

Units qualified. Report 7154-233E dated May 1983 applies.

Units qualified. Report 7154-233E dated May 1983 applies.

Units qualified. Report 7154-233E dated May 1983 applies.

Units qualified.

Report 7154-233E dated May 1983 applies.

Units qualified.

Report 7154-233E dated May 1983 applies.

Cables, splices, terminal blocks, electrical penetrations used in safety related systems are discussed in System XIII, Common Equipment.

System VI, Heating and Ventilation System-(containment)

Plant ID No.

FCU-31,32 33,34,35 SOV-1293, thru 1307 No Tag No.

Solenoids for PCV-1190, FCV-1170,-1172 Solenoids for FCV-1171,-1173 MOV-880A,B,C, D,E,F,G,H,J,K No Tag No.

No Tag-No.

Location Containment Containment Containment Containment Pipe Pene tration Area Containment Containment Pipe Pene tration Area Manufacturer and Model No.

Westinghouse 69F97009 NPX8320 182E NAMCO EA-740 ASCO NP-8316A74E NP-8320A184E ASCO 8300 Description

• Motors for Contain ment Fan Coolers Solenoids valves for Fan Cooler Damper Limit Switches for Fan Cooler Dampers Solenoids for Containment Purge, Pressure Relief Valves Solenoids for

.Containment Purge Valves Limitorque Charcoal Filter SMB-O0 Dousing Valves NAMCO EA180 NAMCO EA80 Limit Switches for Purge Dampers FCV-1170 and 1172 Limit Switches for Purge Dampers FCV-1171 and 1173 Expected Or Actual Installation Date Original Installation 1984 1980 1980 Original Installation Original Installation Original Installation Original Installation Expected or Actual Environmental Qualification Documentation Date Units qualified. Reports 7154-121E dated July 1983 and P801-09-2 dated November 1984 apply. (e)

Replaced with qualified units. Report AQ521678/TR dated March 1978.

Units qualified. Report 7154-131E dated May 1983 applies.

Units qualified. Report 7154-101E dated July 1983 and FC-4539 dated 9/76 apply. AQ521678/TR dated March 1978.

Units qualified. Report 7154-111E dated June 1983 applies.

Units qualified. Report 7154-101E dated August 1983 applies.

Units Qualified. ACME Cleveland Rep ort dated 7/7/77 applies.

Units Qualified. ACME Cleveland Rep-,

• ort dated 7/7/77 applies.

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XIII, Common Equipment.

System VI, Heating and Ventilation System (containment)

Note 2 -

In the May 1983 Submittal, the authority incorrectly identified TE-1203-1, 1203-2, 1203-3, 1204-4, 1203-5 and TC-1117, 1135, 1143 and 1155. These items should not have been listed because:

a) Temperature Detectors Foxboro Model 1502-T (TE-1203-1, -2, -3, -4, -5) Fan cooler outlet temperature. These temperature detectors are used in normal operation to control service'water flow to the fan cooler heat exchangers (the temperature detectors provide a signal to the temperature controllers for valves TCV-1103, 1104 and 1105).

In the event of a safety injection signal, air is removed from the controllers and the valves move to their full open position. Since the temperature detectors have no accident mitigating function and there is no known failure mode of the valves or the temperature detectors which could affect the safety position of the valves, the temperature detectors are exempt from qualification.

b) Temperature Detectors Fenwal EL 2717-11 (TC 1117, 1135, 1143 and 1153), Fan Cooler Charcoal Filter fire detectors. The accident which these fire detectors are intended to mitigate is a fire in the fan cooler charcoal filters. They initiate fire suppression water flow in the event of a high temperature (>3250F) in the fan cooler charcoal filters. The units are hermetically sealed having a stainless steel shell, metallic temperature element, mica insulation, an epoxy/glass lead seal and TAGT insulated lead wires.

The temperature detectors are not used to mitigate a LOCA or MSLB and because of their hermetically sealed design and set point would not be affected by the accident conditions. The detectors are exempt from qualification because they do not have an accident mitigating (LOCA/MSLB) function.

System VII, Main Steam Plant ID No.

PT-419A,B,C PT-429A,B,C PT-439A,B,C PT-449A,B,C FT-419A,B FT-429A,B FT-439A,B FT-449A,B LT-417A,B,C,D LT-427A,B,C,D LT-437A,B,C,D LT-447A,B,C,D Solenoids for MS-1-31,-32,

-33,-34 Limit Switches for MS-1-32,

-32,-33,-34 PCV-1134,-1135,

-1136,-1137 Location AFW Pump Room Containment Containment Steam and Feed Penetration Area Steam and Feed Penetration Area Steam and Feed Penetration Area Manufacturer and Model No.

Foxboro E11GM Description Main Steam Pressure Transmitter Rosemount Main Steam Flow 1151 Transmitters Foxboro N-El3DH HIH1-BEK Laurence 110114W 125434W NAMCO EA750 50100 Steam Generator Level Transmitter Main Steam Isolation Valves Main Steam Isolation Valve Position Indication Fisher 546 Main Steam Atmos pheric Relief Valves Actuation Expected Or Actual Installation Date Original Installation Original Installation 1984 1985 1984 Original Installation Expected or Actual Environmental Qualification Documentation Date Units qualified.- WCAP-8541, and NS-TMA-2319 apply. Aging Report No. 7205N dated May 1984 applies.

Train A transnitters qualified. Report 7201-R4 dated August 1984 applies. (j)

Replaced with Foxboro transmitters qualified to 1971 criteria. (f)'

To be replaced with qualified units.

(g)

Units qualified. Report QTR-110 Rev. 0.

Units qualified.

Report 4 Problem 1531, Project 72AR28 applies.

Aging Report No. 7205 dated April 1984 applies.

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XIII, Common Equipment.

System VIII, Main Feedwater Plant ID No.

FT-418A,B FT-428A,B FT-438A,B FT-448A,B BFD-5-1,5-2, 5-3,5-4 BFD-90-1,90-2, 90-3,90-4 Location AFW Pump Room Steam and Feed Penetration Area Steam and Feed Penetration Area Manufacturer and Model No.

Foxboro E13DM Description Main Feedwater Flow Transmitter Limitorque.

Main Feedwater SMB Isolation Valves Limitorque Low Flow Feedwater SMB Bypass Isolation Valves Expected Or Actual Installation Date Original Installation Original Installation Original Installation Expected or Actual Environmental Qualification Documentation Date Units qualified. WCAP-8541 applies.

Aging Report No.

7205N dated May 1984 applies.

Units qualified. Report 7154-I00E dated August 1983 applies.

Units qualified.

Report 7154-100E dated August 1983 applies.

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XIII, Common Equipment.

System IX, Containment Location Pipe Pene tration Area Manufacturer and Model No.

Foxboro E11GM Solenoid Valves ASCO NP8316 for PCV-1191,

-1192 Limit Switches for PCV-1190,

-1191,-1192 LT-940,-941 Solenoids for DWI,DW2,550, 1610 Limit Switches

.for DW1,DW2, 550,1610 PT-1421,1422 LT-1253,1254 Containment and Pipe Penetration Area Containment Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area Containment NAMCO EA-180 Gems LS1900 ASCO NP8316 NAMCO EA-180 Barton 763 Barton 764 Description Containment Pressure Transmitters Actuates Containment Pressure Relief Valves Containment Pressure Relief Valve Position Indicatidn Containment Sump Level.

Actuates Contain ment Isolation Valves Containment Isolation Valve Position Indication Containment Pressure Transmitter Containment Level Transmitters Expected Or Actual Installation Date Original Installation 1980 1980 Original Installation 1980 1980 Expected or Actual Environmental.

Qualification Documentation Date Units qualified. 'WCAP-8541 applies.

AgingMarch 1984.

Units qualified. Report 7154-110E and ASCO report AQ521678/rR apply.

Units qualified. Report 7154-130E applies.

Note K.

Units qualified. ASCO report AQ521678/

TR applies.

Units qualified. Report 7154-130E applies.

Units qualified. Barton report R3-763-6 applies.

Units qualified. Barton report R3-764 9-0 applies.

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XIII, Common Equipment.

Plant ID No.

PT-948A,B,C PT-949A,B,C

System X, Instrument Air Plant ID No.

Location Solenoid for PCV-1228 Limit Switch for PCV-1228 Pipe Pene tration Area Pipe Pene tration Area Manufacturer and Model No.

ASCO 8300 NAMCO D2400X Description Instrument Air Isolation Instrument Air Isolation Valve Position Indication Expected Or Actual Installation Date Original Installation Original Installation Expected or Actual Environmental Qualification Documentation Date Unit Qualified. Report 7154-111E applies.

Unit qualified. Report 7154-233E dated May 1983 applies.

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XIII, Common Equipment.

System XI, H2 Recombination Plant ID No.

Location No Tag No.

No Tag No.

Containment Containment Containment Containment No Tag No.

31FS-2A &

32FS-2B Manufacturer and Model No.

Westinghouse Westinghouse Westinghouse Foxboro N-EI3DM HIHI-BE Description Igniter Exciter for H2 Recombiner Thermocouple for H2 Recombiner Exhaust Temperature H2 Recombiner Blower Motor Transmitter for H2 Recombiner Flow Expected Or Actual Installation Date Original Installation Original Installation Original Installation 1984 Expected or Actual Environmental Qualification Documentation Date Qualified. WCAP-7709L applies.

Qualified. WCAP-7709L applies.

Motor qualified.

Report 7154-122E dated July 1983 applies.

Replaced with Foxboro transmitters qualified to 1971 criteria. (f)

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XV Common Equipment.

System XII, Sampling Plant ID No.

SOV-1534,

-1535,-1536,

-1537,-1538,

-1539,-1540,

-1541 Location Pipe Pene tration Area Manufacturer and Model No.

ASCO 8300 Description Containment Building Air Sample Isolation Expected Or Actual Installation Date Original Installation Expected or Actual Environmental Qualification Documentation Date Units qualified. Report 7154-111E dated June 1983 applies.

SOV-1523,1523A thru i526,1526A Limit Switches for PCV-1223, 1223A thru 1226, 1226A No Tag No.

M-1 through M-10 No Tag NO.

No Tag No.

Solenoid for 958 Pipe Pene tration Area Pipe Pene tration Area Pipe Pene tration Area None Pipe Pene tration Area 990A,B; Pipe Pene 994A tration Area ASCO 8300 NAMCO D2400X NAMCO D2400X ASCO 8262 Thomas 727CH33 Millipore CN0949 ASCO NP8320 Limitorque SMB-O00/-O0 Solenoids for Steam Generator Sample Isolation Position Indication for Steam Generator Sample Isolation Valves PositionIndication for Containment Building Air Sampling Sampling System Isolation Sample Pump Motor Sample Pump Motor RHR Sample SI Recirculation Sample Original Installation Original Installation Original Installation 1980 1980 1980 1980 1980 Units qualified.

Report 7154-111E dated June 1983 applies.

Units qualified. Report 7154-233E dated May 1983 applies.

Units qualified. Report 7154-233E dated May 1983 applies.

Units Qualified.

Report 1001 dated

• June 1984 applies.

Units qualified.

Report 7154-1051 dated July 1984 applies.

Units qualified.

Report 7154-1051 dated July 1984 applies.

Unit Qualified. Report AQ521678/TR applies.

Units Qualified. Report 7154-101E August 1983 applies.

System XII, Sampling (continued)

Manufacturer and Model No.

Thomas 707CN50 Dayton 2Z830 Dayton 4X426A General Atomic RD-25 General Atomic Description Sample Pump Motor Sample*Pump Motor Capacitor High Range Radiation Monitor Wide Range Gas Monitor Expected Or Actual Installation Date 1980 1980 1980 1983

.1983 Expected or Actual Environmental Qualification Documentation Date Units qualified.

Report 7154-1051 dated July 1984 applies.

Units qualified..- Report 7154-1051 dated July 1984 applies.

Units qualified. -Report 7154-1051 dated July 1984 applies.

Units qualified. Report E-254-960 May 1, 1981 applies.

Unit qualified. Report E255-968 applies.

Cables, splices, terminal blocks, electrical penetrations used in safety-related systems are discussed in System XV, Common Equipment.

Plant ID No.

No Tag No.

No Tag No.

No Tag No.

Location R25,R26 PAB PAB Containment:

Fan House

System XIII, Common Equipment Location Containment Containment Inside & Out side Cntmt.

Inside & Out side Cntmt.

Inside & Out

• outside Cntmt.

Inside & Out side Cntmt.

Containment Manufacturer and Model No.

Westinghouse 542247 Westinghouse WX31774,31775, 31776,31892 Rockbestos Firewall III Kerite Raychem WCSF(N)

Lewis Conax N11001 Description Terminal Block Electrical Pene trations Rockbestos Cable Kerite Cable Raychem Cable Splice Lewis Cable Connector Expected Or Actual Installation Date Original Installation Original Installation 1980 Original Installation Original Installation Original Installation 1980 Expected or Actual Environmental Qualification Documentation Date Units qualified. Report 7154-180E dated January 1983 applies. (j)

Units qualified. PENTR-81-37 and PENRLK 3-16-01 apply.

Cable qualified. Report 170E applies.

Cable qualified.

Report 170E applies.

Splices qualified.

Report 170E applies.

Cable qualified. Report 170E applies.

Connector qualified. Conax Report IPS-409 applies.

Plant ID No.

N/A N/A

Note's for Master List of Electrical Equipment Important to Safety a) This equipment performs its function before the environment becomes harsh.

A harsh radiation environment can only occur after the safety injection function has been completed and the system is no longer in use.

The safety injection pumps take suction from the refueling water storage tank which is not radioactive and no radiation exposure occurs to the equipment.

When all of the water has been pumped into the plant the safety injection is no longer used for any break which would cause core damage.

Recirculation through the safety injection system would only occur for very small breaks which would not -depressurize the reactor coolant system.

It is only recirculation through the RHR system after large break LOCA that results in a high radiation area in the pipe penetration area and SI pump room.

In addition, test report WCAP-8541, WCAP-8754 and WCAP-7410L establishes qualification of the equipment for the harsh environment so that the equipment would be available for use at any time in the post accident period.

Aging analyses and qualification reports are available for all of the SI System Equipment.

b) MOV-744, MOV-769 and MOV-797 have motor brakes with Class B insulation. WCAP-7410L indicates that the Class B insulated motor brake failed during environmental testing.

Although the testing was more severe than the Indian Point Unit 3 accident conditions, because it cannot be determined at what point the motor brake failed and the exact cause of the failure, the Authority plans to replace the actuators of MOV-744, MOV-769 and MOV-797 with qualified actuators.

c) As noted in the FRC TER for equipment located in the Auxiliary Feed Pump Room:

"At present, qualification is not established for the redundant temperature switches (see equipment item 40).

Once the Licensee has demonstrated a reliable steam line isolation feature initiated by the qualified temperature switches, the safety-related components located in the auxiliary pump room will be excluded from the scope of their review.

The Licensee should ensure that the critical components will not be elevated to temperatures that will affect their operability."

The Authority agrees with the FRC evaluation.

The temperature switch (TER item 40) has been qualified in Report 245E. Since the temperature switch will. preclude a harsh steam environment the equipment is satisfactory.

An evaluation of the effects of a break in the 4" steam supply line to the AFW turbine driven pump has been made and it has been determined that the total duration of the transient is less than one minute.

The safety-related equipment located in the AFW pump room has b

'een evaluated for a much more conservative transient (1350F for I hour) and it has been concluded that the equipment is qualified and satisfactory for the environment. WCAP-8541 demonstrates that the transmitters are qualified and perform reliably well above the maximum accident temperature.

To ensure continued qualification the seals will be replaced as required by the aging analysis.

d) -Note Deleted.

e) The stator insulation on one fan cooler motor has been upgraded from Class F to Class H.

f)

The transmitters installed utilize amplifier assemblies qualified to IEEE-323 1971 criteria.

These assemblies will be replaced with ones qualified to the. IEEE-323-1974 criteria which Will upgrade the transmitter qualification to the 1974 criteria. This will be completed by the end of the cycle 4/5 refueling outage.

g) This item has been scheduled to be completed during the cycle 4/5 refueling outage.

h) Regarding the accumulator discharge valves, FRC, (in TER-C5257-206) stated the following:

"FRC Evaluation" The accumulator discharge valves (MOV-894A,B,C,D) are normally-open motor-operated gate valves. These valves are checked-open by the safety injection signal at the start of the accident. Accumulators are installed to reflood the core following a design basis accident during the initial blowdown while the safety injection pumps are being started and attaining rated capacity. Accumulator injection begins within seconds of the start of the accident, and the dead-band for starting the active safety injection equipment is generally approximately 30 seconds. Once the accumulators have discharged, the discharge valves are shut as a backup to the check valves, which prevent back-flooding of the accumulators. Since there are two check valves in each accumulator discharge line, the proper operation of these valves following the injection phase of an accident is of little consequence even if the valves are not promptly shut.

FRC

Conclusion:

The accumulator discharge valves (Item 7) do not require environmental qualification beyond their short-term function."

The Authority has reviewed the applicable test reports (WCAP-7410L and Limitorque B0003) and has determined that the testing envelopes the Indian Point Unit 3 accident conditions and that the valves are qualified for their required operating time plus I hour.

i) The test reports applicable to the Westinghouse terminal blocks installed at Indian Point Unit No. 3 are F-C4911-1 and F-C4911-2.

Insulation resistance measurements were made during the test at 500VDC, 1OOVDC and 50VDC. The lowest resi tance measurement at 500VDC was 6.5 x i05 ohms which corresponds to a leakage current of 0.77 milliamps. The lowest resistance at 1OOVDC was 6 x 100 ohms which corresponds to a leakage current of 0.17 milliamps. The lowest resistance at 50VDC was 3.5 x 105 ohms which corresponds to a leakage current of 0.14 milliamps. The leakage currents would not adversely affect Indian Point Unit No. 3 instrument circuits.

j) The transmitter qualified in Report 7201-R4 dated August 1984 was partially encapsulated in RTV to ensure that no steam entered the electronics housing. Four of the installed transmitters were encapsulated in 1984.

The remaining four units will be encapsulated during the cycle 4/5 refueling outage or replaced with qualified units.

k) As part of the Indian Point Unit 3 TMI action plan program (NUREG-0737) Qualified Barton 764 transmitters were installed to monitor containment water level.

The installed GEMS level switches, however, provide signals to indicating lights in the control room. The Authority considers that the indicating lights provide useful information to the operating personnel.

Therefore, either bistables will be incorporated into the transmitter circuits or the GEM's level switches will be replaced with qualified units to provide signals to the'indicating lights in the control room.

to IPN -

84 -63 ENVIRONMENTAL PARAMETERS New York Power Authority Indian Point 3 Nuclear Power Plant Docket No. 50-286

Environmental Parameters Accident Conditions Inside Containment

a. LOCA - Figures III-i( and 111-2 are the accident temperature and pressure profiles developed for the Indian Point Unit No. 3 FSAR.

NUREG-0588 Appendix A and Regulatory Guide 1.89, revision 1, Appendix C state that topical report WCAP-8312A is an acceptable method for calculating the mass energy releases to the containment assuming a LOCA.

This WCAP was followed in the Indian Point Unit No. 3 analysis that resulted in the peak. pressure in figure 111-2. Themodel for heat transfer to the containment heat sinks used in the analysis is in agreement with Appendix B.1 of NUREG-0588.

The references and assumptions are found in WCAP-8312A (non-proprietary) or WCAP-8264.(Proprietary) for the mass and energy release analysis, and in WCAP-7155 for the containment pressure transient analysis.

However, the NRC SER oi Evi,,onmLjetaal Qudlification of Safety Related Electrical Equipiment fur Indian Point Unit No. 3, dated May 21, 1981, stated:

"The staff has concluded that the minimum temperature profile for equipment qualification purposes should include a margin to account for

.higher than average temperatures in the upper regions of the containment that can exist due to stratification especially following a postulated MSLB. Use of the steam saturation temperature corresponding to the total building pressure (partial pressure of steam plus partial pressure of air) versus time will provide an acceptable margin for either a postulated LOCA, or MSLB, whichever is controlling as to potential adverse environment effects on equipment.

The licensee's specified temperature (service condition) of 258F (the NYPA submittal actually used 2710F) does not satisfy the above requirements. Furthermore the Licensee's specified pressure is low as compared to the plants of similar design. The Licensee is requested to verify that the pressure profile in the FSAR was calculated based on the code requirements defined in the NUREG-0588. If by using these codes the peak containment pressure is still 40 psig, then a saturation temperature corresponding to the pressure profile should be used."

NYPA in response to the May 21, 1981 NRC SER stated:

"The correct peak pressure is 40.6 psig. The temperature reported is the saturation temperature at the steam partial pressure of 36.9 psig.

According to the SER the peak temperature reported should be the saturation temperature corresponding to the total containment pressure to account for margin. The saturation temperature at 55.3 psia (40.6 psg 287OF.

sig is0F

The curve for saturation temperature corresponding to the pressure profile is shown in-Figure III-l A.

The Franklin Research Center (FRC) TER-C5257-456 considered that the NYPA response cited above was satisfactory and the SER dated December 30, 1932 concurred with the FRC TER evaluation.

In order to establish a temperature and pressure profile to be used in LOCA simulation testing it is necessary to ensure that the parameters used meet both the NRC requirements and the requirements of IEEE-323-74. Figures 111-3 and 111-4 are temperature and pressure pro files which envelop these ru luirujants.

Pressure The pressure profile is based on the accident pressure profile

.Contained in Figure 111-2. A 10 psig pressure margin has been applied to the accident profile for the first 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of the test. IEEE-323-74 recommends a 10% margin on pressure. The IEEE recommendation would add a 4 psig margin to the 40.6 psig peak pressure. Using a different computer code the NRC calculated a peak pressure of 44 psig for the Indian Point Unit No. 3 containment. Adding a 10% margin, 4.4 psig, to the NRC calculated pressure would result in a test pressure of 48.4 psig. The 50 psig pressure shown on Figure III-4envelopes all of the calculated pressures but does not exceed the 10 psig maximum pressuremargn identified in paragraph 6.3.1.5 of IEEE-323-74. The recommended test vessel pressure conservatively simulates the actual accident conditions.

At approximately 7,000 seconds after the incident the containment sump temperatures is less than 170OF, and the containment ambient temperature and vapor temperature is less than 150 0 F. At this point there is no source of pressurization, and while high humidity conditions exist, containment pressure is essentially atmospheric. This profile is the same as submitted to NRC and accepted by FRC and NRC.

T _ _AT_.

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Temperature The temperature profile, Figure 111-3, for the first three hours of the test profile is based on the profile contained in Figure Ill-1 A. No additional margin is required on top of this temperature profile because the temperature is always 290F higher than the accident temperature profile. Figure.III-I B.

IEEE-323-74 recommends a 15°F margin. To comply with the NRC requirements (cited previously) to use a temperature corresponding to saturation at the accident pressure (40.6 psig) a 290F temperature margin has been applied in the profile shown in Figure 111-3.

The test temperature therefore envelopes both the IEEE recommendations and the NRC requirements.

The tust temperature (1490F) between 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> and 30 days is determined for the equipownt involved using the Arrhenius method to represent a 1 year post accident period dt 100°F and 100% relative humidity.

The analysis assumes a.1.

year plus 10' Madrgin as recoiigended by IEEE-323-74 (401 days).

Chemical Spray The spray solution to be used in the test should consist of a solution of boric acid (2000ppm boron) buffered with sodium hydroxide'to achieve a pH of 10 at room temperature (200C).

No margin is recommended by IEEE-323-74 (section 6.3.1.5) for chemical spray., Table A-l of IEEE-323-74 identifies some generic parameters for chemical spray which are intended to envelop the parameters for all plants and notes that the values given may vary from plant to plant. Therefore the spray composition used in LOCA simulation testing is the same as is used in the Indian Point Unit No. 3 plant. The spray duration is shown on Figure 111-3.

Time The total test duration is 30 days. A 10% margin has been applied to all of the dwell times as recommended in IEEE-323-74, and has been included in figures 111-3 and 111-4. In addition a 10% margin in the conservative direction has been applied to the rise-times indicated on the test profiles (figures 111-3 and 111-4).

4 SPRAY I

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10 sec 300 260 260 240 220 200 60 0 F/hr Drop -.

17 min 60 min 77 cin TIME 94 min 167 in 277 =in 10 Ihrs 30 day; 220/

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-4 15 PSIG 77 mn 94 zini 167 in 277 =in 0 PSIG 10 krs 30 56" PSIG

b. Discussion of MSLB Inside Containment:

Specific analyses of a main steam line break (MSLB) inside of containment have-not been performed for Indian Point Unit No. 3 Environmental qualification of electrical equipment has been based on the NRC position contained in paragraph 4.2 of the DOR Guidelines which states:

"4.2 Service conditions for a PWR Main Steam Line Break (MSLB) Inside Conta i nment Equipment required to function in a steam line break environment must be qualified for the high temperature and pressure that could result. In some cases the environmental stress on exposed equipment may be higher than that resulting from a LOCA, in others it may be no more severe than for a LOCA due to the automatic operation of a containment spriy system.

1. Temperature and d

i',;uru Steam Conditions - Equipment qualified for a LOCA enviruuimrlt is considered qualified for a MSLB accident environmeunt in plants with automatic spray systems not subject to disabliny '.irauJl! cumponent failures. This position is based on the "Best Estimate" calculation of a typical plant peak temperature and pressure and a thenmal analysis of typical components inside containment.I The final acceptability of this approach. i.e., use of the "Best Estimate', is pending completion of Task Action Plan A-21, Main Steamline Break Inside Containment.

lSee NUREG-0458, -Short Term Safety Assessment of the Environmental Qualification of Safety-Related Electrical Equipment of SEP Operating Reactors, for a more detailed discussion of the best estimate calculation."

In TER-C5257-456, FRC stated:

"Accident Conditions:

For PWR plants, the DOR Guidelines state that the environmental service conditions inside containment for the most severe LOCA be established by the Licensee based onthe FSAR analysis. In addition, for plants equipped automatic containment spray systems not subject to single component failure or delayed initiation, the Guidelines state that equipment qualified for the most severe LOCA environment is also qualified for the postulated MSLB. The Design of the Indian Point No. 3 nuclear power plant satisfies these criteria. The environmental conditions resulting from a feedline break are less severe than those from a LOCA".

The NRC in SER dated December 30, 1982 concurred with the FRC conclusions...

In order to verify the conservatism of the LOCA profile for MSLB accident conditions, a comparison was made to calculations performed on a Westinghouse PWR plant of similar power rating and similar containment volume. The plant selected was North Anna Unit 2 which has a power rating of 890 Mwe compared to the 965 MWe rating of Indian Point Unit No. 3. The North Anna Unit 2 profiles for MSLB are shown in figures 111-5 and 111-6.

The following points are noted.

• The North Anna plant: is a 3 loop-des'ign whereas the Indian Point Unit No. 3 plant is a 4 loop design. The Main steam lines and steam generator volume for Indian Point-Unit-No. 3 are. 30% less than the North Anna Plant which would result in lower temperatures and pressures than shown on figures 111-5 and 111-6. The North Anna Containment Volume is slightly smaller than Indian Point Unit No. 3.

e The peak temperature shown on figures 111-5 and 111-6 are the result of stratification in the upper third of the containment.

o. The North Anna temperature profile shown on figure 111-5 exceeds the LOCA temperature for Indian Point Unit No. 3 by 140OF for less than 80 seconds. Transient heat transfer calculations are used to determine the temperature of equipment subjected to MSLB condition.

I It has been concluded that if the temperature resulting from a main steam line break (MSLB) were to exceed the Indian Point Unit No. 3 design profile even in some local aru as, this would be of no consequence due to the short duration and may therefore be ignored for qualification. This evaluation confirms the DOR Guidel-ines approach cited previously. Since the LOCA test profiles contained in Figures 111-3 and 111-4 are more severe than the effects of a conservative MSLB profile, the LOCA test envelopes the MSLB parameters.

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Radiation Service Conditions In the August 24, 1981 submittal from NYPA to NRC the following information on radiation doses (40 year plus accident) was provided.

"The integrated beta and gamma radiation doses calculated at the center of the Indian Point Unit 3 containment building for periods of 30 days and 1 year following a design basis LOCA are summarized as follows; Ganna -Dose Beta Dose (rd)

(rd) 30 days 1.8 x 10 7 1.4 x i I year 3.0 x 10 2.0 x 108 This data is based on Elie dLiu-,.: information documented in NUREG-0588 Appendix ' 0 and the DOR Lu d~L Ii Appendix Us. A conservative 30-day danvit dose was derived by u-u l L1iLc nu,,ogrums given in the DOR Guidelines.

This method wato utvd by d'umitii a containnent volume of 2.6 x 106 ft and a reactor puwer rxaiii of 3025 MW for Indian Point Unit 3. The 30-day beta dose w.s obtained from the information given in Appendix D of NUREG-0588.

The 1-year beta and gamma doses were predicted by extrapolating the 30-day doses to one year. In order to perform this extrapolation, the information tabulated In Table 0-5 and Table D-6 of NUREG-0588 was plotted.in order to establish the shape of the curves representing beta and gamma doses with respect to time. These curves were then conservatively extrapolated to I year. The shape of the individual curves were then used to extrapolate the plant-specific 30-day doses for beta and gamnia radiation to 1 year.

A factor of 2.7 reduction in total gama dose may be used for equip ment outside the.crane wall."

The information noted above was reviewed by both the Franklin Research Center (FRC) and the NRC staff. FRC in TER-C5257-456 and NRC in SER dated December 30, 1982 concluded that the radiation values used for evaluation of equipment installed at Indian Point Unit NIo.3. were satisfactory and met the requirements of the DOR Guidelines. The radiation dose information cited above was used for evaluation of test parameters.

It is noted that the radiation dose data transmitted to NRC in the August 24, 1981 submittal is very conservative and based on extrapolation of the data provided in NUREG-0588 Appendix 0. Since the issuance of NUREG-0588. NRC has performed additional analyses which are contained in Appendix D to Regulatory Guide 1.89, Revision 1. An evaluation of the Indian Point Unit No. 3 radiation doses based on the information contained in Regulatory Guide 1.89 Revision i confirms the conservatism of the previous Qualification Test Radiation Parameters.

Table 7-1

SUMMARY

TABLE OF ESTIMATES FOR TOTAL AIRBORNE GAMMA DOSE CONTRIBUTORS IN CONTAINMENT TO A POINT IN THE CONTAINMENT CENTER INDIAN POINT UNIT NUMBER 3 Airborne Iodine Dose (R)

Airborne Noble Gas Dose (R)

Plateout Iodine Dose (R)

Total Dose (R)

CR) 0.00 0.03 0.06 0.09 0.12 0.15 0.18 0.21 0.25 0.38 0.50 0.75 1.00 2.00 5.00 8.00 24.0 60.0 96.0

92.

298.

394.

560.

720.

888.

1060 1220 1390 1560 1730 1900 2060 2230 2950 3670 4390 5110 5830 6550 7270 8000 8710 lime (Hr) 3.55E+4 6.3E+4 8.03E+4 9.22E+4 1.02E+5 1.08E+5

1.

14E+5 1.20E+5 1.37E+5 1.49E+5 1.74E+5 1.96E+5 2.66E+5 4.06E+5 4.89E+5 7.44E+5 9.66E+5 1.07E+6 1.24E+6 1.36E+6 1.43E+6 1.52E+6 1.57E+6 1.59E+6 1.60E+6 1.61E+6

1.

62E+6

1. 62E+6 1.62E+6 1.62E+6 1.62E+6 1.62E+6 1.62E+6 1.62E+6

.1.62E+6 1.62E+6 1.62E+6 1.62E+6 1.62E+6 1.62E+6 1.62E+6 4.92E+4 1.02E+5 1.46E+5 1.84E+5 2.21E+5 2.56E+5 2.88E+5 3.31Et5 4.56E+5 5.61E+5 7.60E+5 8.28E+5 1.50E+6 2.62E+6 3.22E+6 4.62E+6 5.27E+6 5.57E+6 6.12E+6 6.46E+6 6.50E+6 6.67E+6 6.74E+6 6.77E+6 6.77E+6 6.78E+6 6.79E+6 6.80E+6 6.80E+6 6.80E+6 6-80E+6 6.80E+6 6.81E+6 6.82E+6 6.82E+6

.6.82E+6 6.82E+6 6.82E+6 6.82E+6 6.82E+6 6.82E+6 1.24E+3 2.93E+3 5.32E+3 8.11E+3

1. 12E+

1.45E+4 1.27E+4 2.24 E+4 3.72E+4 5.09E+4 7.82E+4 1.03E+5 1.92E+5 3.98E+5 5.51E+5 1.07E+6 1.55E+6 1.76E+6 2.10E+6 2.35E+6 2.51E+6

.2.68E+6 2.77E+6 2.82E+6 2.85E+6 2.86E+6 2.87E+6 2.88E+6 2.88E+6 2.89E+6 2.89E+6 2.89E+6 2.89E+6 2.89E+6 2.89E+6 2.89E+6 2.89E+6 2.89E+6 2.89E+6 2.89E+6 2.89E+6 9.1OE+4 1.69E+5 231E+5 2.85E+5 3.34E+5 3.79E+5, 4.21E+5 4.73E+5 6.32E+5 7.60E+5 1.01E+6 1.23E+6 1.96E+6 3.43E+6 4.26E+6 6.43E+6 7.82E+6 8.41E+6 9.44E+6 1.01E+7 1.04E+7 1.09E+7 1.11E+7 1.12E+7 1.13E+7 1.13E+7 1.13E+7 1.13E+7 1.13E+7

1. 13E+7 1.13E+7

1.

13E+7 1.14E+7 1.14E+7 1.14E+7 1.14E+7 1.14E+7 1.14E+7 1.14E+7 1.14E+7 1.14E+7 Total 1.14E+7

Table 72

SUMMARY

CONTRIBUTORS TABLE OF ESTIMATES FOR TOTAL AIRBORNE'BETA DOSE IN CONTAINMENT TO A POINT IN-THE CONTAINMENT CENTER INDIAN POINT UNIT NUMBER 3 Time Airborne Iodine (Hr)

Dose (rads)*

• Airborne Noble

-Gas Dose (rads)*

'.-Iotal Dose (rads)*

0.00 0.03 0.06 0.09 0.12 0.15 0.18 0.21 0.25 0.38 0.50 0.75 1.00 2.00 5.00 8.,00 I

24.0 60.0 96.0 192.

298.

394.

560.

720.

888.

1060 1220 1390 1560 1730 1900 2060 2230 2950 3670 4390 5110 5830 6550 7270 8000 8710 1.68E+5 1.93E+5 2.45E+5 2.82E+5 3.09E+5 3.31E+5 2.48E+5 3.68E+5 4.18E+5 4.54E+5 5.25E+5 5.90E+5 7.89E+5 1.16E+6 1.38E+6 3.72E+6 2.86E+6 3.22E+6 3.78E+6 4.15E+6 4.42E+6 4.67E+6 4.81E+6 4.89E+6 4.93E+6 4.96E+6 4.98E+6 4.98 E+6 4.98E+6 4.98E+6 4.98 E+6 4.99E+6 4.99E+6 4.99E+6 4.99E+6 4.99E+6 4.99E+6 4.99E+6 4.99E+6 4.99E+6 4.99E+6

4. 03E+5 7.27E+5 9.95E+5 1.20E+6 1.40E+6 1.58E+6 1.73E+6

1. 92E+6 2.43E+6 2.84E 6 3.61E+6 4.29E+6 6.65E+6 1.22E+7 1.62E+7 3.OOE+7 4.54E+7 5.51E+7 7.38E+7 8.63E+7 9.22E+7' 9.88E+7 1.02E+8 1.05E+8 1.06E+8 1.07E+8 1.08E+8 1.09E+8 1.12E+8 1.12E+8 1.13E+8 1.14E+8 1.19E+8 1.24E+8 1.29E+8 1.35E+8 1.39E+8 1.43E+8 1.49E+8 1.53E+8 1.59E+8 5.12E+5 9.22E+5 1.24E+6 1.49E+6 1.69E+6 1.91E+6 2.07E+6 2.28E+6 2.85E+6 3.30E+6 4.12E+6 4.87E+6 7.45E+6 1.13E+7 1.75E+7 3.22E+7 4.82E+7 5.84E+7

.7.74E+7 9.07E+7 9.66E+7 1.03E+8 1.07E+8 1.09E+8 1.1OE+8 1.12E+8 1.13E+8 1.15E+8 1.16E+8 1.17E+8 1.18E+8 1.19E+8 1.24E+8 1.29E+8 1.35E+8 1.39E+8 1.45E+8 1.49E+8 1.54E+8 1.59E+8

1.

64E+8 Total 1.64E+8 to IPN.

84.63 STEAMLINE BREAK ANALYSES New York Power Authority Indian Point 3 Nuclear Power Plant Docket No. 50-286