ML20202C257

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Forwards List of Category B & C Valves Included in Formal Inservice Insp (ISI) Program.All Valves Tested Satisfactorily Except as Noted.Util Will Continue to Perform ISI Per ASME Requirements Until Exemption Request Granted
ML20202C257
Person / Time
Site: Crane Constellation icon.png
Issue date: 07/07/1986
From: Standerfer F
GENERAL PUBLIC UTILITIES CORP.
To: Travers W
Office of Nuclear Reactor Regulation
References
0447A, 4410-86-L-0115, 4410-86-L-115, 447A, NUDOCS 8607110187
Download: ML20202C257 (4)


Text

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GPU Nuclear Corporation Nuclear

, ors: 48o Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84-2386 Writer's Direct Dial Number:

(717) 948-8461 4410-86-L-Oll5 Document ID 0447A July 7, 1986 TMI-2 Cleanup Project Directorate Attn:

Dr. W. D. Travers Director US Nuclear Regulatory Commission c/o Three Mile Island Nuclear Station Middletown, PA 17057

Dear Dr. Travers:

Three Mile Island Nuclear Station, Unit 2 (TMI-2)

Operating License No. DPR-73 Dccket No. 50-320 Inservice Inspection Program Pursuant to the NRC Letter dated June 4, 1986, GPU Nuclear has initiated a formal Inservice Inspection (ISI) Program at TMI-2. As discussed with your staff, the attached list of category B and C valves have been included in the program. All of the valves listed in the attachment have been tested satisfactorily except as noted. GPU Nuclear will continue to perform the ISI program on a quarterly basis, per the requirements of ASME Boiler and Pressure Vessel Code,Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components", until such time as the GPU Nuclear request for exemption from ISI requirements (reference GPU Nuclear letter 4410-86-L-0075 dated May 15, 1986) is granted.

Sincerely, L

. R. Standerfer Vice President / Director, TMI-2 FRS/CJD/eml y

Attachment 8607110187 860707 lkg PDR ADOCK 0500 0

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l GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation

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ATTACHMENT 4410-86-L-Oll5 ISI PROGRAM f

f VALVE CATEGORY VALVE FUNCTION i

AH-EP-5182 8 and C Controls NR-V-144B AH-EP-5205 B and C Controls NR-V-144A AH-EP-5210 B and C Controls Damper 04092C AH-EP-5216 A and B B and C Controls Damper D4096A and AH-V-32A l

l AH-EP-5217 A and B B and C Controls Damper D40968 and AH-V-32B I

AH-EP-5222 A B

Controls Damper D4088B AH-EP-5222 B B and C Controls NR-V-85B l

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AH-EP-5227 A B

Controls NR-V-85A i

AH-EP-5227 B B and C Controls Damper D4088A AH-EP-5235 A and B B and C Controls AH-V-28A and Damper D4074A AH-EP-5237 A and B B and C Controls AH-V-288 and Damper D4074B i

AH-EP-5245 B

Controls Damper D4076 AH-EP-5246 A and B B

Controls Damper D4073, ID 4075A, ID 40758, and ED 4075 l

AH-EP-5265 B and C Controls Damper D4091A t

i AH-EP-5266 B and C Controls Damper D4091B AH-EP-5356 A B

Controls NR-V-ll6A AH-EP-5356 B B and C Controls Damper D5356 AH-EP-5358 A B

Controls NR-V-1168 AH-EP-5358 B B and C Controls Damper D5358 i

AH-V-14 A and B C

Control Building Liquid Cooler Pump Discharge

  • AH-V-28 A and B B

Cable Room Fan Coil Unit Water (See Note 1)

Inlet AH-V-29 A and B B

Cable Room Fan Coil Unit Water L

Outlet l

AH-V-32 A and B B

Control Room Fan Coil Unit Water Inlet i

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ATTACHMENT 4410-86-L-Oll5 ISI PROGRAM VALVE CATEGORY VALVE FUNCTION AH-V-33 A and B B

Control Room Fan Coil Unit Water Outlet AH-V-124 A and B B

Control Room Recirculation Instrument Air AH-V-125 A and B B

Control Room Recirculation Instrument Air DH-V-5 A and B B

Borated Water Storage Tank (BWST) to Decay Heat Removal Pumps DH-V-102 A and B B

Discharge from Decay Heat Removal i

Pumps to RV DH-V-119 C

BWST Vacuum Breaker Valve DH-V-128 A and B B

Discharge from Decay Heat Removal Cooler to RV DV-V-227 C

BWST Vacuum Breaker Valve NR-V-1 A, B, C and D C

NR-P-1 A, B, C and D Discharge Valves NR-V-2 A, B, C and D B

NR-P-2 A, B, C and D Discharge Valves NR-V-33 A C

River Water to Emergency Diesel Generator Cooling NR-V-34 B C

River Water to Emergency Diesel Generator Cooling

  • NR-V-39 A and B B

Diesel Generator Cooler Outlet (See Note 2)

NR-V-82 A and B C

Control Building Rive Water Booster Pump Discharge I

NR-V-85 A and B B

Control Building Mechanical Room Fan Coil Inlet NR-V-88 A and B B

Control Building Mechanical Room Fan Coil Outlet NR-V-ll6 A and B B

River Water Pump House Fan Coil Inlet NR-V-ll7 A and B B

River Water Pump House Fan Coil Outlet 1

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ATTACHMENT 4410-86-L-0115 i

ISI PROGRAM VALVE CATEGORY VALVE FUNCTION 4

NR-V-144 A and B B

Inlet to Liquid Chiller Condenser -

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Control Building l

i NR-V-145 A and B B

Outlet from Liquid Chiller Conden-t ser - Control Building

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  • NR-V-181 A and B Lube Water to NR-P-1 A, B, C and D 1

(See Note 3)

Check Valves NR-V-234 A, B, C and D C

Nuclear River Pump Lube Water i

l Supply

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  • SW-V-1 A and B C

Screen Wash Pump A and B Discharge j

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(See Note 4) l

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SW-V-20 B

Lube Water to Screen Wash Pumps f

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i SW-V-35 C

Domestic Water Supply to Screen i

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Wash Pumps l

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NOTES:

1.

AH-V-28 A and B cannot be tested at this time due to cooler AH-C-17A being out of service. These valves will be tested once the cooler is l

repaired.

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2.

NR-V-39A has been tested. NR-V-39B will be tested during the July i

j Monthly Surveillance for Emergency Diesel Genrator 18.

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3.

NR-V-181 A and B have replaced NR-V-186 A, B, C and D, which were f

referenced in the GPU Nuclear submittal 4410-86-L-0075 dated May 15, 1986. Valves NR-V-186 A, B, C and D have been removed from the Nuclear l

l Service River Water System.

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i 4.

SW-V-1A cannot be tested because screen wash pump 1A (SW-P-1A) is no 1

longer installed. SW-V-18 cannot be tested because the valve internals i

have been removed. The safety function of this check valve is to open j

upon SW-P-1B startup to permit flow to the screens. Since the valve internals are removed, (i.e., valve is always in the open position), it i

still performs this function.

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