AEP-NRC-2017-59, Anchor Darling Double Disc Gate Valve Information and Status
| ML17360A155 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/20/2017 |
| From: | Lies Q Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP-NRC-2017-59 | |
| Download: ML17360A155 (7) | |
Text
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/POWER" A unit of American Electric Power Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 lndianaMichiganPower.com December 20, 2017 AEP-NRC-2017-59 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 Renewed Facility Operating License No. DPR-58 and DPR-74 ANCHOR DARLING DOUBLE DISC GATE VALVE INFORMATION AND STATUS
References:
- 1)
Letter from G. A. Krueger, Nuclear Energy Institute (NEI), to J. W. Lubinski, U. S.
Nuclear Regulatory Commission (NRC), Anchor Darling Double Disc Gate Valve Industry Resolution Plan Update (Project 689), dated August 4, 2017.
- 2) Letter from J. E. Pollock, NEI, to B. E. Holian, NRC, NSIAC Concurrence on Anchor Darling Double Disc Gate Valve Industry Response Actions (Project 689),
dated October 26, 2017.
- 3) BWROG Topical Report TP16-1-112, Revision 4, "Recommendations to Resolve Flowserve 1 OCFR Part 21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failures."
In Reference 1, the Nuclear Energy Institute (NEI) provided the U. S. Nuclear Regulatory Commission a resolution plan for the U. S. Nuclear Industry to address the known Anchor Darling Double Disc Gate Valve (ADDDGV) issues. Reference 2 indicated each utility will provide a listing of their Anchor Darling valve population with active safety functions along with relevant valve information, including the results of susceptibility evaluations, repair status, and a repair schedule for each susceptible valve not yet repaired. This letter serves to provide this information for Indiana Michigan Power Company (l&M), the licensee for Donald C. Cook Nuclear Plant Units 1 and 2.
The Enclosure to this letter contains the following information for each ADDDGV.
Plant Name, Unit, and Valve ID System I* "
J
U. S. Nuclear Regulatory Commission Page 2 Valve Functional Description Valve Size Active Safety Function (open, close, both)
Are multiple design basis post-accident strokes required? (yes/no)
Expert Panel Risk Ranking (high, medium, low)
Result of susceptibility evaluation (susceptible or not susceptible)
AEP-NRC-2017-59 Is the susceptibility evaluation in general conformance with TP16-1-112, Revision 4 (Reference 3)?
Does the susceptibility evaluation rely on thread friction? If yes, was the coefficient of friction greater than 0.1 O? For cases where thread-friction was relied upon, information is provided whether the coefficient of friction was above or below 0.10.
Was an initial stem-rotation check performed?
If yes, include rotation criteria (i.e. :s;1Q degrees or ::;;5 degrees).
Was the diagnostic test data reviewed for failure precursors described in TP16-1 -112, Revision 4 (Reference 3)?
The valve's repair status (i.e. repaired or not repaired)
A repair schedule for each susceptible valve There are no new regulatory commitments made in this letter. Should you have any questions or require additional information, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.
Res?~AL Q~
s Site Vice President MPH/mll
Enclosure:
DC Cook Nuclear Power Plant ADDDGV Listing and Long Range Repair/Replacement Plan for Anchor Darling Double Disc Gate Valves c:
R. J. Ancona, MPSC MDEQ - RMD/RPS NRC Resident Inspector C. D. Pederson, NRC Region Ill J. K. Rankin, NRC Washington DC A. J. Williamson - AEP Ft. Wayne, w/o enclosures
ENCLOSURE TO AEP-NRC-2017-59 DC Cook Nuclear Power Plant ADDDGV Listing and Long Range Repair/Replacement Plan for Anchor Darling Double Disc Gate Valves
I Plant Name DC COOK DC COOK DC COOK DC COOK DC COOK DC COOK DC COOK UNIT l
l l
l l
l l
VALVE ID SYSTEM ICM-2SO ECCS ICM-2Sl ECCS ICM-260 ECCS ICM-26S ECCS ICM-30S ECCS ICM-306 ECCS IM0-2SS ECCS DC COOK NUCLEAR POWER PLANT LONG RANGE REPAIR/REPLACEMENT PLAN FOR ANCHOR DARLING DOUBLE DISC GATE VALVES VALVE FUNCTIONAL DESCRIPTION BORON INJECTION TANK TRAIN 'A' OUTLET CONTAINMENT ISOLATION VALVE BORON INJECTION TANK TRAIN '8' OUTLET CONTAINMENT ISOLATION VALVE NORTH SAFETY INJECTION PUMP PP-26N DISCHARGE CONTAINMENT ISOLATION VALVE SOUTH SAFETY INJECTION PUMP PP-26S DISCHARGE CONTAINMENT ISOLATION VALVE RECIRCULATION SUMP TO EAST RHR/CTS PUMPS SUCTION CONTAINMENT ISOLATION VALVE RECIRCULATION SUMP TO WEST RHR/CTS PUMPS SUCTION CONTAINMENT ISOLATION VALVE BORON INJECTION TANK TRAIN 'A' INLET SHUTOFF VALVE VALVE SIZE (Inches) 4 4
4 4
18 18 4
ACTIVE SAFETY FUNCTION (Open, dose, Both)
Open Open Close Close Open Open Open Are multiple design basis post-accident strokes required?
(Yes/No)
No No No No No No No Expert Pane l Risk Ranking (High, Medium, Low)
HIGH HIGH MEDIUM MEDIUM HIGH HIGH HIGH Result of susceptibility evaluation (susceptible or not susceptlble)1*1 Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Is the susceptibilfty evaluation in general conformance with TP16-l-112R47111 (Yes/No)
Yes Yes Yes Yes Yes Yes Yes Does the susceptibility evaluation rely on thread friction 7 If yes, was the COF greater than.10?
(No),
(Yes, >.10),
(Y
- 10) es s.
No No No No Yes, s.10 Yes, s.10 No Was an initial stem-rotation check performed? tf yes, include rotation criteria.
(No),
(Yes<lO Deg.),
(Vess S Deg.)
No No No Yes, :s; 10 deg.
No Yes, s 5 deg.
No Was the diagnostic test data reviewed for failure precursors described in TP16-l-112R47 (Yes/No)
Yes Yes Yes Yes Yes Yes Yes Valve repair status (repaired or not repaired)
Not repaired Not Repaired Not repaired Not repaired Not repaired Not repaired Not Repaired
I Plant Name DC COOK DC COOK DC ODOK DC COOK DC COOK DC COOK DC COOK UNIT 1
1 1
1 1
1 1
VALVE ID SYSTEM IM0-2S6 ECCS IM0-310 RHR IM0-314 RHR IM0-320 RHR IM0-324 RHR IM0-340 RHR IM0-350 RHR DC COOK NUCLEAR POWER PLANT LONG RANGE REPAIR/REPLACEMENT PLAN FOR ANCHOR DARLING DOUBLE DISC GATE VALVES VALVE FUNCTIONAL DESCRIPTION BORON INJECTION TANK TRAIN 'B' INLET SHUTOFF VALVE EAST RESIDUAL HEAT REMOVAL PUMP PP-3SE SUCTION SHUTOFF VALVE EAST RHR HX 1-HE-17E DISCHARGE CROSSTIE SHUTOFF VALVE WEST RESIDUAL HEAT REMOVAL PUMP PP-3SW SUCTION SHUTOFF VALVE WEST RHR HX I
- HE-17W DISCHARGE CROSSTIE SHUTOFF VALVE EAST RESIDUAL HEAT REMOVAL HEAT EXCHANGER TO CHARGING PUMPS SUCTION SHUTOFF VALVE WEST RHR HEAT EXCHANGER OUTLET TO SAFETY INJECTION PUMP SUCTION SHUTOFF VALVE VALVE SIZE (inches) 4 14 6
14 6
8 8
ACTIVE SAFETY FUNCTION (Open, Close, Both)
Open dose Close Close Close Open Open Are multiple design basis post-accident strokes required?
(Yes/No)
No No No No No No No E>cpert Panel Risk Ranking (High, Medium, Low)
HIGH HIGH LOW HIGH LOW HIGH HIGH Result of susceptibility evaluation (susceptible or not susceptible)fAI Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Is the susceptibllfty evaluation In general conformance with TP16-l-112R4?111 (Yes/No)
Yes Yes Yes Yes Yes Yes Yes Does the susceptibility evaluation rely on thread friction? If yes, was the COF greater than.10?
(No),
(Yes, >.10),
(Y
- 10) es s.
No No No No No Yes, s.10 Yes, s.10 Was an Initial stem-rotation check performed? If yes, include rotation criteria.
(No),
(Yes<!O Deg.),
(Yes< 5 Deg.)
No No Yes, s 10 deg.
Yes, s 5 deg.
No No Yes, S S deg.
Was the diagnostic test data reviewed for failure precursors described in TP16*1*112R4?
(Yes/No)
Yes Yes Yes Yes Yes Yes Yes Valve repair status (repaired or not repaired)
Not repaired Not repaired Not repaired Not repaired Not repaired Not repaired Not repaired
Plant Name DC COOK DC COOK DC COOK DC COOK DC COOK DC COOK DC COOK UNIT l
2 2
2 2
2 2
VALVE ID SYSTEM IM0-390 ECCS ICM-2SO ECCS ICM-2Sl ECCS ICM-305 ECCS ICM-306 ECCS IM0-25S ECCS IM0-2S6 ECCS DC COOK NUCLEAR POWER PLANT LONG RANGE REPAIR/REPLACEMENT PLAN FOR ANCHOR DARLING DOUBLE DISC GATE VALVES VALVE FUNCTIONAL DESCRIPTION REFUELING WATER STORAGE TANK TK-33 TO RESIDUAL HEAT REMOVAL PUMPS SUCTION SHUTOFF VALVE BORON INJECTION TAN K TRAIN 'A' OUTLET CONTAINMENT ISOLATION VALVE BORON INJECTION TANK TRAIN 'B' OUTLET CONTAINMENT ISOLATION VALVE RECIRCULATION SUMP TO EAST RHR/CTS PUMPS SUCTION CONTAINMENT ISOLATION VALVE REd RCULATION SUMP TO WEST RHR/CTS PUMPS SUCTION CONTAINMENT ISOLATION VALVE BORON INJECTION TANK TRAIN 'A' INLET SHUTOFF VALVE BORON INJECTION TANK TRAIN 'B' INLET SHUTOFF VALVE VALVE SIZE (inches) 10 4
4 18 18 4
4 ACTIVE SAFffi FUNCTION (Open, dose, Both) dose Open Open Open Open Open Open Are multiple design basis post-accident strokes required?
(Yes/No)
No No No No No No No Expert Panel Risk Ranking (High, Medium, Low)
HIGH HIGH HIGH HIGH HIGH HIGH HIGH Result of susceptibility evaluation (susceptible or not susceptible)(*)
Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Is the susceptibility evaluation in general conformance with TP16-l-112R4?!81 (Yes/No)
Yes Yes Yes Yes Yes Yes Yes Does the susceptibility evaluatlon rely on thread friction? If yes, was the COF greater than.10?
(No),
(Yes, >.10),
(Yes s.10)
No No No Yes, s.10 Yes, s.10 No No Was an initial stem-rotation check performed? If yes, include rotation criteria.
(No),
(YesSlO Deg.),
(Vess S Deg.)
Yes, s 5 deg.
Ye s, s 5 deg.
No No No No No Was the diagnostic test data reviewed for failure precursors described in TP16-l-112R4?
(Yes/ No)
Yes Yes Yes Yes Yes Yes Yes Valve repair status (repaired or not repaired)
Not repaired Not repaired Not repaired Not repaired Not repa ired Not repaired Not re paired
Plant Name DC COOK DC COOK DC COOK DC COOK DC COOK DC COOK DC COOK UNIT 2
2 2
2 2
2 2
(A)
(B)
VALVE ID IM0-310 IM0-314 IM0-320 IM0-324 IM0-340 IM0*3SO IM0 -390 DC COOK NUCLEAR POWER PLANT LONG RANGE REPAIR/REPLACEMENT PLAN FOR ANCHOR DARLING DOUBLE DISC GATE VALVES SYSTEM RHR RHR RHR RHR RHR RHR E=
VALVE FUNCTIONAL DESCRIPTION EAST RESIDUAL HEAT REMOVAL PUMP PP-3SE SUCTION SHUTOFF VALVE EAST RHR HX 2*HE*
17E DISCHARGE CROSSTIE SHUTOFF VALVE WEST RESIDUAL HEAT REMOVAL PUMP PP*3SW SUCTION SHUTOFF VALVE WEST RHR HX 2*
HE-17W DISCHARGE CROSSTIE SHUTOFF VALVE EAST RESIDUAL HEAT REMOVAL HEAT EXCHANGER TO CHARGING PUMPS SUCTION SHUTOFF VALVE WEST RHR HEAT EXCHANGER OUTLET TO SAFETY INJECTION PUMP SUCTION SHUTOFF VALVE REFUELING WATER STORAGE TANK TK-33 TO RESIDUAL HEAT REMOVAL PUMPS SUCTION SHUTOFF VALVE VALVE SIZE (Inches) 14 6
14 6
8 8
10 ACTIVE SAFETY FUNCTION (Open, Oose, Both)
Close Close dose Close Open Open dose Are multiple design basis post-accident strokes required?
(Yes/No)
No No No No No No No Since no valves were determined to be susceptible. no repair schedule has been provided.
Expert Panel Risk Ranking (High, Medium, Low)
HIGH LOW HIGH LOW HIGH HIGH HIGH Applied Wedge Pin Torque bounds anticipated design basis operating 1orquc requirements and current maximum total torque.
Result of susceptibility evaluation (susceptible or not susceptible)1*1 Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Not Susceptible Is the susceptibility evaluation in general conformance with TP16-l-112R47181 (Yes/No}
Yes Yes Yes Yes Yes Yes Yes Does the susceptibility evaluation rely on thread friction? If yes, was the COF greater than.10?
(No},
(Yes, >.10),
(Yes<.10)
No No No No Yes, s.10 Yes, s.10 No Was an initial stem-rotation check performed? If yes, include rotation criteria.
(No),
(Yes<lO Deg.),
(Yes< S Deg.)
No No No No No Yes, < 10 deg.
No Was the diagnostic test data reviewed for failure precursors described in TP16+112R47 (Yes/No)
Yes Yes Yes Yes Yes Yes Yes Valve repair status (repaired or not repaired)
Not repaired Not repaired Not repaired Not repaired Not repaired Not repaired Not repaired