RA-17-0053, Duke Energy - Anchor Darling Double Disc Gate Valve Information and Status

Duke Energy - Anchor Darling Double Disc Gate Valve Information and Status

ML17354A650
Person / Time
Site:	Oconee, Mcguire, Catawba, Harris, Brunswick, Robinson, McGuire
Issue date:	12/20/2017
From:	Donahue J Duke Energy Carolinas, Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-17-0053
Download: ML17354A650 (21)

Text

JOSEPH DONAHUE Vice President Nuclear Engineering 526 South Church Street, EC-07H Charlotte, NC 28202 980-373-1758 Joseph.Donahue@duke-energy.com Serial: RA-17-0053 December 20, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325, 50-324 / RENEWED LICENSE NOS. DPR-71 AND DPR-62 CATAWBA NUCLEAR STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-413, 50-414 / RENEWED LICENSE NOS. NPF-35 AND NPF-52 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23 MCGUIRE NUCLEAR STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-369, 50-370 / RENEWED LICENSE NOS. NPF-9 AND NPF-17 OCONEE NUCLEAR STATION, UNIT NOS. 1, 2 AND 3 DOCKET NOS. 50-269, 50-270, AND 50-287 / RENEWED LICENSE NOS. DPR-38, DPR-47, AND DPR-55 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63

SUBJECT:

ANCHOR DARLING DOUBLE DISC GATE VALVE INFORMATION AND STATUS

REFERENCES:

1. Letter from Greg Krueger (NEI) to Mr. John Lubinski, U.S. Nuclear Regulatory Commission, Anchor Darling Double Disc Gate Valve Industry Resolution Plan Update (Project 689), dated August 4, 2017 (ADAMS Accession No. ML17220A363)

2. BWROG Topical Report TP-16-1-112 Rev.4, Recommendations to Resolve Flowserve 10CFR Part21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failures, dated August 2017 (ADAMS Accession No. ML17243A137)

3. Letter from Joe Pollock (NEI) to Mr. Brian Holian, U.S. Nuclear Regulatory Commission, NSIAC Concurrence on Anchor Darling Double Disc Gate Valve Industry Response Actions (Project 689), dated October 26, 2017 (ADAMS Accession No. ML17303A031)

U.S. Nuclear Regulatory Commission RA-17-0053 Page2 Ladies and Gentlemen:

In Reference 1, the Nuclear Energy Institute (NEI) provided the NRC a resolution plan for the U.S. Nuclear Industry to address the known Anchor Darling Double Disk Gate Valve (AD DDGV) issues. Reference 3 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 Duke Energy including Brunswick, Catawba, Harris, McGuire, Oconee, and Robinson nuclear stations (all units) for any active safety function AD DDGV applicable to References 1 and 2. Note, a review has determined that Harris and McGuire stations do not have any active safety function AD DDGV applicable to References 1 and 2. Therefore, no data or commitments are provided for Harris and McGuire stations.

The Attachments to this letter contain the following information for each AD DDGV.

Valve Unit and ID System and Valve Functional Description Valve Size Active Safety Function (open, close, both) and whether multiple design basis post-accident strokes are required (yes/no)

Risk Significance (high, medium, low)

The result of each valve's susceptibility evaluation (i.e. susceptible or not susceptible),

and whether the evaluation is in general conformance with the BWROG guidance (Reference 2).

Whether the susceptibility evaluation relied upon the presence of thread-friction.

o For cases where thread-friction was relied upon, information is provided whether the coefficient of friction was above or below 0.10.

Whether an initial stem-rotation check has been performed and the associated acceptance criteria (i.e. s10 degrees or ss degrees).

Whether existing diagnostic test data has been reviewed for the failure precursors described in Reference 2.

The valve's repair status (i.e. repaired or not repaired).

A committed repair schedule for each susceptible valve (except for four Brunswick valves as detailed in Attachment 1).

Should you have any questions concerning this letter, or require additional information, please contact Art Zaremba, Manager - Nuclear Fleet Licensing, at 980-373-2062.

Sincerely,

~~

\\_J 0""'~~

Joseph Donahue Vice President - Nuclear Engineering JBD

U.S. Nuclear Regulatory Commission RA-17-0053 Page 3 Attachments:

1. Brunswick Nuclear Plant AD DDGV Listing and Commitments

2. Catawba Nuclear Station AD DDGV Listing and Commitments

3. Oconee Nuclear Station AD DDGV Listing and Commitments

4. Robinson Nuclear Plant AD DDGV Listing and Commitments cc:

(all with Attachments unless otherwise noted)

C. Haney, Regional Administrator USNRC Region II G. Smith, USNRC Senior Resident Inspector - BNP J. Zeiler, USNRC Senior Resident Inspector - HNP J. Rotton, USNRC Senior Resident Inspector - RNP J. D. Austin, USNRC Senior Resident Inspector - CNS G. A. Hutto, USNRC Senior Resident Inspector - MNS E. L. Crowe, USNRC Senior Resident Inspector - ONS A. L. Hon, NRR Project Manager - BNP M. C. Barillas, NRR Project Manager - HNP D. J. Galvin, NRR Project Manager - RNP M. Mahoney, NRR Project Manager - CNS & MNS A. L. Klett, NRR Project Manager - ONS RA-17-0053 Brunswick Nuclear Plant AD DDGV Listing and Commitments RA-17-0053 Page 1 of 5 TABLE 1:

BRUNSWICK NUCLEAR PLANT (BNP): ANCHOR DARLING DOUBLE DISC GATE VALVE LISTING (see Reference 3 of the cover letter)

Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)

Active Safety Function Are multiple design basis post-accident strokes required?

Expert Panel Risk Ranking Result of susceptibility evaluation Is the susceptibility evaluation in general conformance with TP16-1-112r4?

Does the susceptibility evaluation rely on thread friction?

If yes, was the COF greater than 0.10?

Was an initial stem-rotation check performed?

If yes, include rotation criteria Was the diagnostic test data reviewed for failure precursors described in TP16-1-112r4?

Valve repair status (Open,

Close, Both)

(Yes/No)

(High,

Medium, Low)

(susceptible or not susceptible)

(Yes/No)

(No),

(Yes, >0.10),

(Yes, 0.10)

(No),

(Yes, 10 deg.),

(Yes, 5 deg.)

(Yes/ No)

(repaired or not repaired)

BNP 1

1-B32-F031A Reactor Recirc Reactor Recirc Pump 1A Discharge Valve 24x28 Close No Low Susceptible(1) (2)

Yes Yes, >0.10 No Yes Not Repaired(4)

BNP 1

1-B32-F031B Reactor Recirc Reactor Recirc Pump 1B Discharge Valve 24x28 Close No Low Susceptible(1) (2)

Yes Yes, >0.10 No Yes Not Repaired(4)

BNP 1

1-B32-F032A Reactor Recirc Reactor Recirc Pump 1A Disch Bypass Vlv 4

Close No Low Susceptible(2)

Yes No No Yes Not Repaired BNP 1

1-B32-F032B Reactor Recirc Reactor Recirc Pump 1B Disch Bypass Vlv 4

Close No Low Susceptible(2)

Yes No No Yes Not Repaired BNP 1

1-E41-F002 HPCI HPCI Turbine Steam Supply Inboard Isolation Valve 10 Both No Medium Susceptible(2)

Yes No No Yes Not Repaired BNP 1

1-E41-F003 HPCI HPCI Turbine Steam Supply Outboard Isolation Valve 10 Both No Medium Susceptible(2)

Yes No No Yes Not Repaired BNP 1

1-E41-F006 HPCI HPCI Injection Valve 14 Both Yes Medium Susceptible(2)

Yes No No Yes Not Repaired BNP 1

1-E51-F008 RCIC RCIC Steam Supply Line Outboard Isolation Vlv 3

Both No Medium Susceptible(1) (2)

Yes Yes, >0.10 No Yes Not Repaired BNP 1

1-E51-F013 RCIC RCIC Injection Valve 4

Both Yes Medium Susceptible(1) (2)

Yes Yes, >0.10 No Yes Not Repaired BNP 1

1-G31-F001 Reactor Water Cleanup RWCU Inlet Line Inboard Isolation Vlv 6

Close No Medium Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired BNP 1

1-G31-F004 Reactor Water Cleanup RWCU Inlet Line Outboard Isolation Vlv 6

Close No Medium Susceptible(1) (2)

Yes Yes, >0.10 No Yes Not Repaired BNP 2

2-B32-F031A Reactor Recirc Reactor Recirc Pump 2A Discharge Valve 24x28 Close No Low Susceptible(1)

Yes Yes, >0.10 Yes, 5 deg.

Yes Not Repaired(4)

BNP 2

2-B32-F031B Reactor Recirc Reactor Recirc Pump 2B Discharge Valve 24x28 Close No Low Susceptible(1)

Yes Yes, >0.10 Yes, 5 deg.

Yes Not Repaired(4)

BNP 2

2-B32-F032A Reactor Recirc Reactor Recirc Pump 2A Disch Bypass Vlv 4

Close No Low Not Susceptible Yes No Yes, 5 deg.

Yes Not Repaired BNP 2

2-B32-F032B Reactor Recirc Reactor Recirc Pump 2B Disch Bypass Vlv 4

Close No Low Susceptible(2)

Yes No No Yes Not Repaired BNP 2

2-E41-F002 HPCI HPCI Turbine Steam Supply Inboard Isolation Valve 10 Both No Medium Susceptible(2)

Yes No No Yes Not Repaired BNP 2

2-E41-F003 HPCI HPCI Turbine Steam Supply Outboard Isolation Valve 10 Both No Medium Susceptible(2)

Yes No No Yes Not Repaired BNP 2

2-E41-F006 HPCI HPCI Injection Valve 14 Both Yes Medium Susceptible(2)

Yes No No Yes Not Repaired RA-17-0053 Page 2 of 5 TABLE 1:

BRUNSWICK NUCLEAR PLANT (BNP): ANCHOR DARLING DOUBLE DISC GATE VALVE LISTING (see Reference 3 of the cover letter)

Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)

Active Safety Function Are multiple design basis post-accident strokes required?

Expert Panel Risk Ranking Result of susceptibility evaluation Is the susceptibility evaluation in general conformance with TP16-1-112r4?

Does the susceptibility evaluation rely on thread friction?

If yes, was the COF greater than 0.10?

Was an initial stem-rotation check performed?

If yes, include rotation criteria Was the diagnostic test data reviewed for failure precursors described in TP16-1-112r4?

Valve repair status (Open,

Close, Both)

(Yes/No)

(High,

Medium, Low)

(susceptible or not susceptible)

(Yes/No)

(No),

(Yes, >0.10),

(Yes, 0.10)

(No),

(Yes, 10 deg.),

(Yes, 5 deg.)

(Yes/ No)

(repaired or not repaired)

BNP 2

2-E51-F013 RCIC RCIC Injection Valve 4

Both Yes Medium Susceptible(1)

Yes Yes, >0.10 Yes, 5 deg.

Yes Not Repaired BNP 2

2-G31-F001 Reactor Water Cleanup RWCU Inlet Line Inboard Isolation Vlv 6

Close No Medium Susceptible(1)

Yes Yes, >0.10 Yes, 5 deg.

Yes Not Repaired BNP 2

2-G31-F004 Reactor Water Cleanup RWCU Inlet Line Outboard Isolation Vlv 6

Close No Medium Susceptible(1)

Yes Yes, >0.10 Yes, 5 deg.

Yes Not Repaired (A) Applied Wedge Pin Torque must bound anticipated design basis operating torque requirements and current maximum total torque (1) As a conservative action, Duke is considering MOVs Susceptible if their wedge-pin analysis relies on the presence of thread friction >0.10. See commitment table.

(2) This valve is Susceptible because a stem-rotation check has not been performed. See commitment table.

(3) Not applicable for repaired valves (i.e. a wedge-pin analysis, initial stem rotation check, and diagnostic review are not required for repaired valves).

(4) Repair is not planned, an Engineering evaluation found that the safety function is not adversely affected by the Part 21 condition. Ongoing stem rotation checks and diagnostic testing will be performed at an increased frequency to provide additional confidence. See commitment table.

Additional information:

These valves have a safety function to close only, so the potential for separation of the stem to upper wedge connection on the BNP RCR discharge valves does not pose a nuclear safety concern. These valves do not have a disc retainer so if the wedge pin were to fracture there is a very low probability the loose parts from the fractured pin could prevent the valve from performing its safety function. Going forward these valves will be diagnostically tested every 4 years.

RA-17-0053 Page 3 of 5 TABLE 2:

BRUNSWICK NUCLEAR PLANT (BNP): ANCHOR DARLING DOUBLE DISC GATE VALVE COMMITMENTS The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRCs information and are not regulatory commitments.)

COMMITMENT COMMITTED DATE OR "OUTAGE" COMMITMENT TYPE ONE-TIME ACTION (Yes/No)

Programmatic (Yes/No)

Perform stem rotation checks in accordance with TP16-1-112r4 (Reference 2) with contingency repairs on the following AD DDGV MOVs:

Unit 1:

MOV Number 1-B32-F032A 1-B32-F032B 1-E41-F002 1-E41-F003 1-E41-F006 1-E51-F008 1-E51-F013 1-G31-F004 Unit 2:

MOV Number 2-B32-F032B 2-E41-F002 2-E41-F003 2-E41-F006 Outage(Year)

B1R22 (2018)

B1R22 (2018)

B1R22 (2018)

Outage(Year)

B2R24 (2019)

B2R24 (2019)

Yes Yes Yes Yes Yes No No No No No Repair the following Anchor Darling double disc gate valves to resolve Flowserves Part 21 dated 2/25/2013 including the updated Part 21 issued 7/11/2017.

Unit 1 MOV Number 1-E51-F008 1-E51-F013 Unit 2:

MOV Number 2-E51-F013 2-G31-F001 Outage(Year)

B1R23 (2020)

B1R23 (2020)

Outage(Year)

B2R24 (2019)

B2R25 (2021)

Yes Yes Yes Yes No No No No RA-17-0053 Page 4 of 5 COMMITMENT COMMITTED DATE OR "OUTAGE" COMMITMENT TYPE ONE-TIME ACTION (Yes/No)

Programmatic (Yes/No)

Repair / replace the following Anchor Darling double disc gate valves with a flex-wedge valve to resolve Flowserves Part 21 dated 2/25/2013 including the updated Part 21 issued 7/11/2017.

Unit 1 MOV Number 1-G31-F004 Unit 2:

MOV Number 2-G31-F004 Outage(Year)

B1R24 (2022)See Note 1 Outage(Year)

B2R26 (2023)See Note 1 Yes Yes No No Note 1:

Replacement is currently scheduled per the stations long range plan by the date/outage shown.

Per BWR owners group recommendation (TP16-1-112r4, Reference 2), 1-G31-F004 should be repaired by 2020 and the 2-G31-F004 should be repaired by 2021. As a part of the BNP station long range plan, these valves are currently scheduled to be replaced with a flex-wedge design. The risk of a consequential wedge pin fracture /

stem disc separation occurring between the BWROG recommended repair date and the BNP long range plan replacement date is considered low for the following reasons:

(1) These valves are limit seated valves so the risk of breaking the pin during normal operation is low.

(2) The safety function of these valves is to close. Closing of the valves drives the stem into the wedge. These valves do not have a safety function to open.

(3) These valves do have disc retainer, there is at least one occurrence in the industry where the wedge pin broke and the disc retainer became foreign material and prevented the associated valve from fully closing. The G31-F001 is the inboard RWCU suction isolation valve and the G31-F004 is the outboard RWCU suction isolation valve. These valves are primary containment isolation valves (PCIV). If one were to fail to fully close due to a the disc retainer the other PCIV would close and the PCIV function would remain intact.

Perform diagnostic testing and stem rotation checks with contingency repairs each refueling outage on the following AD DDGV MOVs until they are repaired/replaced (i.e. method (c) in TP16-1-112r4, Reference 2):

Unit 1 MOV Number 1-G31-F004 Unit 2:

MOV Number 2-G31-F004 Every outage beginning B1R23 (2020)

Every outage beginning B2R24 (2019)

No No Yes Yes RA-17-0053 Page 5 of 5 COMMITMENT COMMITTED DATE OR "OUTAGE" COMMITMENT TYPE ONE-TIME ACTION (Yes/No)

Programmatic (Yes/No)

Perform diagnostic testing and stem rotation checks with contingency repairs every other refueling outage on the following AD DDGV MOVs (i.e. method (c) in TP16-1-112r4, Reference 2):

Unit 1 MOV Number 1-B32-F031A 1-B32-F031B Unit 2:

MOV Number 2-B32-F031A 2-B32-F031B Every other outage beginning B1R22 (2018)

B1R22 (2018)

Every other outage beginning B2R24 (2019)

B2R24 (2019)

No No No No Yes Yes Yes Yes RA-17-0053 Catawba Nuclear Station AD DDGV Listing and Commitments RA-17-0053 Page 1 of 4 TABLE 1:

CATAWBA NUCLEAR STATION (CNS): ANCHOR DARLING DOUBLE DISC GATE VALVE LISTING (see Reference 3 of the cover letter)

Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)

Active Safety Function Are multiple design basis post-accident strokes required?

Expert Panel Risk Ranking Result of susceptibility evaluation Is the susceptibility evaluation in general conformance with TP16-1-112r4?

Does the susceptibility evaluation rely on thread friction?

If yes, was the COF greater than 0.10?

Was an initial stem-rotation check performed?

If yes, include rotation criteria Was the diagnostic test data reviewed for failure precursors described in TP16-1-112r4?

Valve repair status (Open,

Close, Both)

(Yes/No)

(High,

Medium, Low)

(susceptible or not susceptible)

(Yes/No)

(No),

(Yes, >0.10),

(Yes, 0.10)

(No),

(Yes, 10 deg.),

(Yes, 5 deg.)

(Yes/ No)

(repaired or not repaired)

CNS 1

1BB008A BB S/G BLWDN CONT.

ISOL. INSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1BB010B BB S/G BLWDN CONT.

ISOL. OUTSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1BB019A BB S/G BLWDN CONT.

ISOL. INSIDE VLV..

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1BB021B BB S/G BLWDN CONT.

ISOL. OUTSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1BB056A BB S/G BLWDN CONT.

ISOL. INSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1BB057B BB S/G BLWDN CONT.

ISOL. OUTSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1BB060A BB S/G BLWDN CONT.

ISOL. INSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1BB061B BB S/G BLWDN CONT.

ISOL. OUTSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1CA038A CA TURBINE DRIVEN AUX FEEDWATER PMP TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1CA042B CA MOTOR DRIVEN AUX FEEDWATER PMP B TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1CA046B CA MOTOR DRIVEN AUX FEEDWATER PMP B TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1CA050A CA TURBINE DRIVEN AUX FEEDWATER PMP TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1CA054B CA TURBINE DRIVEN AUX FEEDWATER PMP TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1CA058A CA MOTOR DRIVEN AUX FEEDWATER PMP A TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1CA062A CA MOTOR DRIVEN AUX FEEDWATER PMP A TO S/G ISOL.

4.00 Close No Low Susceptible(2)

Yes Yes, 0.10 No Yes Not Repaired CNS 1

1CA066B CA TURBINE DRIVEN AUX FEEDWATER PMP TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1SV025B SV S/G PORV BLOCK 6.00 Close No Low Susceptible(2)

Yes No No Yes Not Repaired RA-17-0053 Page 2 of 4 TABLE 1:

CATAWBA NUCLEAR STATION (CNS): ANCHOR DARLING DOUBLE DISC GATE VALVE LISTING (see Reference 3 of the cover letter)

Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)

Active Safety Function Are multiple design basis post-accident strokes required?

Expert Panel Risk Ranking Result of susceptibility evaluation Is the susceptibility evaluation in general conformance with TP16-1-112r4?

Does the susceptibility evaluation rely on thread friction?

If yes, was the COF greater than 0.10?

Was an initial stem-rotation check performed?

If yes, include rotation criteria Was the diagnostic test data reviewed for failure precursors described in TP16-1-112r4?

Valve repair status (Open,

Close, Both)

(Yes/No)

(High,

Medium, Low)

(susceptible or not susceptible)

(Yes/No)

(No),

(Yes, >0.10),

(Yes, 0.10)

(No),

(Yes, 10 deg.),

(Yes, 5 deg.)

(Yes/ No)

(repaired or not repaired)

CNS 1

1SV026B SV S/G PORV BLOCK 6.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 1

1SV027A SV S/G PORV BLOCK 6.00 Close No Low Susceptible(2)

Yes No No Yes Not Repaired CNS 1

1SV028A SV S/G PORV BLOCK 6.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2BB008A BB S/G BLWDN CONT.

ISOL. INSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2BB010B BB S/G BLWDN CONT.

ISOL. OUTSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2BB019A BB S/G BLWDN CONT.

ISOL. INSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2BB021B BB S/G BLWDN CONT.

ISOL. OUTSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2BB056A BB S/G BLWDN CONT.

ISOL. INSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2BB057B BB S/G BLWDN CONT.

ISOL. OUTSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2BB060A BB S/G BLWDN CONT.

ISOL. INSIDE VLV.

4.00 Close No Low Susceptible(2)

Yes Yes, 0.10 No Yes Not Repaired CNS 2

2BB061B BB S/G BLWDN CONT.

ISOL. OUTSIDE VLV.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2CA038A CA TURBINE DRIVEN AUX FEEDWATER PMP TO S/G ISOL.

4.00 Close No Low Susceptible(2)

Yes Yes, 0.10 No Yes Not Repaired CNS 2

2CA042B CA MOTOR DRIVEN AUX FEEDWATER PMP B TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2CA046B CA MOTOR DRIVEN AUX FEEDWATER PMP B TO S/G ISOL 4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2CA050A CA TURBINE DRIVEN AUX FEEDWATER PMP TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2CA054B CA TURBINE DRIVEN AUX FEEDWATER PMP TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2CA058A CA MOTOR DRIVEN AUX FEEDWATER PMP A TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired RA-17-0053 Page 3 of 4 TABLE 1:

CATAWBA NUCLEAR STATION (CNS): ANCHOR DARLING DOUBLE DISC GATE VALVE LISTING (see Reference 3 of the cover letter)

Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)

Active Safety Function Are multiple design basis post-accident strokes required?

Expert Panel Risk Ranking Result of susceptibility evaluation Is the susceptibility evaluation in general conformance with TP16-1-112r4?

Does the susceptibility evaluation rely on thread friction?

If yes, was the COF greater than 0.10?

Was an initial stem-rotation check performed?

If yes, include rotation criteria Was the diagnostic test data reviewed for failure precursors described in TP16-1-112r4?

Valve repair status (Open,

Close, Both)

(Yes/No)

(High,

Medium, Low)

(susceptible or not susceptible)

(Yes/No)

(No),

(Yes, >0.10),

(Yes, 0.10)

(No),

(Yes, 10 deg.),

(Yes, 5 deg.)

(Yes/ No)

(repaired or not repaired)

CNS 2

2CA062A CA MOTOR DRIVEN AUX FEEDWATER PMP A TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2CA066B CA TURBINE DRIVEN AUX FEEDWATER PMP TO S/G ISOL.

4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2SV025B SV S/G PORV BLOCK 6.00 Close No Low Susceptible(2)

Yes No No Yes Not Repaired CNS 2

2SV026B SV S/G PORV BLOCK 6.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired CNS 2

2SV027A SV S/G PORV BLOCK 6.00 Close No Low Susceptible(2)

Yes No No Yes Not Repaired CNS 2

2SV028A SV S/G PORV BLOCK 6.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired (A) Applied Wedge Pin Torque must bound anticipated design basis operating torque requirements and current maximum total torque (1) footnote 1 is not used in Attachment 2.

(2) This valve is susceptible because a stem-rotation check has not been performed. These MOVs will be repaired per the commitment table.

(3) Not applicable for repaired valves (i.e. a wedge-pin analysis, initial stem rotation check, and diagnostic review are not required for repaired valves).

RA-17-0053 Page 4 of 4 TABLE 2:

CATAWBA NUCLEAR STATION (CNS): ANCHOR DARLING DOUBLE DISC GATE VALVE COMMITMENTS The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRCs information and are not regulatory commitments.)

CATAWBA NUCLEAR STATION COMMITMENT COMMITTED DATE OR "OUTAGE" COMMITMENT TYPE ONE-TIME ACTION (Yes/No)

Programmatic (Yes/No)

Repair the following Anchor Darling double disc gate valves to resolve Flowserves Part 21 dated 2/25/2013 including the updated Part 21 issued 7/11/2017.

Unit 1:

MOV Numbers 1CA062A, 1SV025B, 1SV027A Unit 2:

MOV Number 2BB060A, 2CA038A, 2SV025B, 2SV027A Outage C1R24 (Fall 2018)

Outage C2R22 (Spring 2018)

Yes Yes No No RA-17-0053 Oconee Nuclear Station AD DDGV Listing and Commitments RA-17-0053 Page 1 of 1 TABLE 1:

OCONEE NUCLEAR STATION (ONS): ANCHOR DARLING DOUBLE DISC GATE VALVE LISTING (see Reference 3 of the cover letter)

Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)

Active Safety Function Are multiple design basis post-accident strokes required?

Expert Panel Risk Ranking Result of susceptibility evaluation Is the susceptibility evaluation in general conformance with TP16-1-112r4?

Does the susceptibility evaluation rely on thread friction?

If yes, was the COF greater than 0.10?

Was an initial stem-rotation check performed?

If yes, include rotation criteria Was the diagnostic test data reviewed for failure precursors described in TP16-1-112r4?

Valve repair status (Open,

Close, Both)

(Yes/No)

(High,

Medium, Low)

(susceptible or not susceptible)

(Yes/No)

(No),

(Yes, >0.10),

(Yes, 0.10)

(No),

(Yes, 10 deg.),

(Yes, 5 deg.)

(Yes/ No)

(repaired or not repaired)

ONS 1

1FDW-103 FDW SG Shell Drain Block Valve 4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired ONS 1

1FDW-104 FDW SG Shell Drain Block Valve 4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired ONS 1

1SF-97 SF Spent Fuel Pool to RC Make Up System Block Inside Containment Isolation 3.00 Both No High Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired ONS 2

2FDW-103 FDW SG Shell Drain Block Valve 4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired ONS 2

2SF-97 SF Spent Fuel Pool to RC Make Up System Block Inside Containment Isolation 3.00 Both No High Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired ONS 3

3FDW-103 FDW SG Shell Drain Block Valve 4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired ONS 3

3FDW-104 FDW SG Shell Drain Block Valve 4.00 Close No Low Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired ONS 3

3SF-97 SF Spent Fuel Pool to RC Make Up System Block Inside Containment Isolation 3.00 Both No High Not Susceptible Yes see footnote (3)

No(3)

No(3)

Repaired (1) footnote 1 is not used in Attachment 3.

(2) footnote 2 is not used in Attachment 3.

(3) A wedge-pin analysis, stem rotation check, and diagnostic review are not required for repaired valves.

No commitments are being made for Oconee Nuclear Station.

RA-17-0053 Robinson Nuclear Plant AD DDGV Listing and Commitments RA-17-0053 Page 1 of 4 TABLE 1:

ROBINSON NUCLEAR PLANT (RNP): ANCHOR DARLING DOUBLE DISC GATE VALVE LISTING (see Reference 3 of the cover letter)

Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)

Active Safety Function Are multiple design basis post-accident strokes required?

Expert Panel Risk Ranking Result of susceptibility evaluation Is the susceptibility evaluation in general conformance with TP16-1-112r4?

Does the susceptibility evaluation rely on thread friction?

If yes, was the COF greater than 0.10?

Was an initial stem-rotation check performed?

If yes, include rotation criteria Was the diagnostic test data reviewed for failure precursors described in TP16-1-112r4?

Valve repair status (Open,

Close, Both)

(Yes/No)

(High,

Medium, Low)

(susceptible or not susceptible)

(Yes/No)

(No),

(Yes, >0.10),

(Yes, 0.10)

(No),

(Yes, 10 deg.),

(Yes, 5 deg.)

(Yes/ No)

(repaired or not repaired)

RNP 2

AFW-V2-14A AFW SDAFW PUMP FW DISCH TO SG 4

Both Yes Medium Susceptible(2)

Yes No No Yes Not Repaired RNP 2

AFW-V2-14B AFW SDAFW PUMP FW DISCH TO SG 4

Both Yes Medium Susceptible(2)

Yes No No Yes Not Repaired RNP 2

AFW-V2-14C AFW SDAFW PUMP FW DISCH TO SG 4

Both Yes Medium Susceptible(2)

Yes No No Yes Not Repaired RNP 2

AFW-V2-16A AFW AFW HEADER DISCH TO SG 4

Both Yes Medium Susceptible(2)

Yes No No Yes Not Repaired RNP 2

AFW-V2-16B AFW AFW HEADER DISCH TO SG 4

Both Yes Medium Susceptible(2)

Yes No No Yes Not Repaired RNP 2

AFW-V2-16C AFW AFW HEADER DISCH TO SG 4

Both Yes Medium Susceptible(2)

Yes No No Yes Not Repaired RNP 2

CC-716B CC COOLING WATER INLET 6

Close No Low Not Susceptible Yes see footnote 3 No(3)

Yes Repaired(4)

RNP 2

CC-730 CC BEARING COOLING WATER OUTLET 6

Close No Low Susceptible(2)

Yes No No Yes Not Repaired RNP 2

CVC-381 CVC RCP SEAL WATER RETURN 3

Close No Low Not Susceptible Yes see footnote 3 Yes, 10 deg.

No(3)

Repaired(4)

RNP 2

MS-V1-8A MS SG STM SUPPLY TO STM DRIVEN AFW PUMP 2

Both Yes Medium Not Susceptible Yes see footnote 3 No(3)

No(3)

Repaired RNP 2

MS-V1-8B MS SG STM SUPPLY TO STM DRIVEN AFW PUMP 2

Both Yes Medium Not Susceptible Yes see footnote 3 No(3)

No(3)

Repaired RNP 2

MS-V1-8C MS SG STM SUPPLY TO STM DRIVEN AFW PUMP 2

Both Yes Medium Not Susceptible Yes see footnote 3 No(3)

No(3)

Repaired RNP 2

RHR-752A RHR RHR PUMP SUCTION 14 Close No Low Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RNP 2

RHR-752B RHR RHR PUMP SUCTION 14 Close No Low Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RNP 2

SI-860A SI CV SUMP RECIRC SUCTION 14 Both Yes High Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RNP 2

SI-860B SI CV SUMP RECIRC SUCTION 14 Both Yes High Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RNP 2

SI-861A SI CV SUMP RECIRC SUCTION 14 Both Yes High Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RNP 2

SI-861B SI CV SUMP RECIRC SUCTION 14 Both Yes High Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RNP 2

SI-862A SI RHR LOOP RWST ISOL 14 Close No High Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RA-17-0053 Page 2 of 4 TABLE 1:

ROBINSON NUCLEAR PLANT (RNP): ANCHOR DARLING DOUBLE DISC GATE VALVE LISTING (see Reference 3 of the cover letter)

Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)

Active Safety Function Are multiple design basis post-accident strokes required?

Expert Panel Risk Ranking Result of susceptibility evaluation Is the susceptibility evaluation in general conformance with TP16-1-112r4?

Does the susceptibility evaluation rely on thread friction?

If yes, was the COF greater than 0.10?

Was an initial stem-rotation check performed?

If yes, include rotation criteria Was the diagnostic test data reviewed for failure precursors described in TP16-1-112r4?

Valve repair status (Open,

Close, Both)

(Yes/No)

(High,

Medium, Low)

(susceptible or not susceptible)

(Yes/No)

(No),

(Yes, >0.10),

(Yes, 0.10)

(No),

(Yes, 10 deg.),

(Yes, 5 deg.)

(Yes/ No)

(repaired or not repaired)

RNP 2

SI-862B SI RHR LOOP RWST ISOL 14 Close No High Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RNP 2

SI-864A SI RWST DISCHARGE 16 Close No High Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RNP 2

SI-864B SI RWST DISCHARGE 16 Close No High Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RNP 2

SI-869 SI LOOPS "B" AND "C" HOT LEG INJECTION SHUTOFF 3

Both Yes Low Susceptible(1)

Yes Yes, >0.10 Yes, 10 deg.

Yes Not Repaired RNP 2

SI-878A SI SI PUMP DISCH HDR CROSS-CONN 4

Close No Medium Susceptible(2)

Yes Yes, 0.10 No No(5)

Not Repaired RNP 2

SI-878B SI SI PUMP DISCH HDR CROSS-CONN 4

Close No Medium Susceptible(1) (2)

Yes Yes, >0.10 No No(5)

Not Repaired (A) Applied Wedge Pin Torque must bound anticipated design basis operating torque requirements and current maximum total torque (1) As a conservative action, Duke is considering MOVs Susceptible if their wedge-pin analysis relies on the presence of thread friction >0.10. See commitment table.

(2) These valves are Susceptible because a stem-rotation check has not been performed. A wedge pin analysis has been performed. See commitment table.

(3) Not applicable for repaired valves (i.e. a wedge-pin analysis, initial stem rotation check, and diagnostic review are not required for repaired valves).

(4) The stem/wedge connection was torqued in 2013 to a known value (which is greater than the operating loads). The stem has an integral backseat. The pin and thread friction are not relied upon.

(5) There is no test data to trend. These valves were not Program Valves prior to now.

RA-17-0053 Page 3 of 4 TABLE 2:

ROBINSON NUCLEAR PLANT (RNP): ANCHOR DARLING DOUBLE DISC GATE VALVE COMMITMENTS The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRCs information and are not regulatory commitments.)

COMMITMENT COMMITTED DATE OR "OUTAGE" COMMITMENT TYPE ONE-TIME ACTION (Yes/No)

Programmatic (Yes/No)

Perform stem rotation checks in accordance with TP16-1-112r4 (Reference 2) with contingency repairs on the following AD DDGV MOVs:

Unit 2:

MOV Number RHR-752A RHR-752B SI-860B SI-861A SI-861B SI-878A SI-878B CC-730 MOV Number AFW-V2-14A AFW-V2-14B AFW-V2-14C AFW-V2-16A AFW-V2-16B AFW-V2-16C Outage(Year)

R2R31 (2018)

R2R31 (2018)

R2R31 (2018)

R2R31 (2018)

R2R31 (2018) 12/31/2018 12/31/2018 Yes Yes Yes Yes Yes Yes Yes No No No No No No No Repair the following Anchor Darling double disc gate valves to resolve Flowserves Part 21 dated 2/25/2013 including the updated Part 21 issued 7/11/2017.

Unit 2:

MOV Number RHR-752A RHR-752B SI-860A SI-860B SI-861A SI-861B SI-862A SI-862B SI-864A SI-864B SI-878A SI-878B Outage(Year)

R2R33 (2022)

R2R33 (2022)

R2R31 (2018)

R2R32 (2020)

R2R32 (2020)

R2R32 (2020)

R2R31 (2018)

R2R31 (2018)

R2R31 (2018)

R2R31 (2018)

R2R32 (2020)

R2R32 (2020)

Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes Yes No No No No No No No No No No No No RA-17-0053 Page 4 of 4 COMMITMENT COMMITTED DATE OR "OUTAGE" COMMITMENT TYPE ONE-TIME ACTION (Yes/No)

Programmatic (Yes/No)

Replace the following Anchor Darling double disc gate valves with a different valve design to resolve Flowserves Part 21 dated 2/25/2013 including the updated Part 21 issued 7/11/2017.

Unit 2:

MOV Number AFW-V2-14A AFW-V2-14B AFW-V2-14C SI-869 Outage(Year)

R2R31 (2018)

R2R31 (2018)

R2R31 (2018)

R2R31 (2018)

Yes Yes Yes Yes No No No No