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

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Duke Energy - Anchor Darling Double Disc Gate Valve Information and Status
ML17354A650
Person / Time
Site: Oconee, Mcguire, Catawba, Harris, Brunswick, Robinson, McGuire  Duke Energy icon.png
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)
v • d • e


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,

~~ 0""'~~

Joseph Donahue

\_J 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 Attachment 1 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)

Are multiple Is the susceptibility Does the susceptibility Was an initial stem-Result of Was the diagnostic test Valve Active design Expert evaluation in evaluation rely on thread rotation check Plant Valve Functional susceptibility data reviewed for failure Unit Valve ID System Size Safety basis post- Panel Risk general friction? performed? Valve repair status Name Description evaluation precursors described in (inches) Function accident strokes Ranking conformance with If yes, was the COF greater If yes, include rotation TP16-1-112r4?

required? TP16-1-112r4? than 0.10? criteria (Open, (High, (No), (No),

(susceptible or (repaired or Close, Medium, (Yes/No) (Yes, >0.10), (Yes, 10 deg.), (Yes/ No)

(Yes/No) not susceptible) not repaired)

Both) Low) (Yes, 0.10) (Yes, 5 deg.)

Reactor Recirc Pump BNP 1 1-B32-F031A Reactor Recirc 24x28 Close No Low Susceptible(1) (2) Yes Yes, >0.10 No Yes Not Repaired(4) 1A Discharge Valve Reactor Recirc Pump BNP 1 1-B32-F031B Reactor Recirc 24x28 Close No Low Susceptible(1) (2) Yes Yes, >0.10 No Yes Not Repaired(4) 1B Discharge Valve Reactor Recirc Pump BNP 1 1-B32-F032A Reactor Recirc 4 Close No Low Susceptible(2) Yes No No Yes Not Repaired 1A Disch Bypass Vlv Reactor Recirc Pump BNP 1 1-B32-F032B Reactor Recirc 4 Close No Low Susceptible(2) Yes No No Yes Not Repaired 1B Disch Bypass Vlv HPCI Turbine Steam BNP 1 1-E41-F002 HPCI Supply Inboard 10 Both No Medium Susceptible(2) Yes No No Yes Not Repaired Isolation Valve HPCI Turbine Steam BNP 1 1-E41-F003 HPCI Supply Outboard 10 Both No Medium Susceptible(2) Yes No No Yes Not Repaired Isolation Valve BNP 1 1-E41-F006 HPCI HPCI Injection Valve 14 Both Yes Medium Susceptible(2) Yes No No Yes Not Repaired RCIC Steam Supply BNP 1 1-E51-F008 RCIC Line Outboard 3 Both No Medium Susceptible(1) (2) Yes Yes, >0.10 No Yes Not Repaired Isolation Vlv BNP 1 1-E51-F013 RCIC RCIC Injection Valve 4 Both Yes Medium Susceptible(1) (2) Yes Yes, >0.10 No Yes Not Repaired Reactor Water RWCU Inlet Line BNP 1 1-G31-F001 6 Close No Medium Not Susceptible Yes see footnote (3) No(3) No(3) Repaired Cleanup Inboard Isolation Vlv RWCU Inlet Line Reactor Water BNP 1 1-G31-F004 Outboard Isolation 6 Close No Medium Susceptible(1) (2) Yes Yes, >0.10 No Yes Not Repaired Cleanup Vlv Reactor Recirc Pump BNP 2 2-B32-F031A Reactor Recirc 24x28 Close No Low Susceptible(1) Yes Yes, >0.10 Yes, 5 deg. Yes Not Repaired(4) 2A Discharge Valve Reactor Recirc Pump BNP 2 2-B32-F031B Reactor Recirc 24x28 Close No Low Susceptible(1) Yes Yes, >0.10 Yes, 5 deg. Yes Not Repaired(4) 2B Discharge Valve Reactor Recirc Pump BNP 2 2-B32-F032A Reactor Recirc 4 Close No Low Not Susceptible Yes No Yes, 5 deg. Yes Not Repaired 2A Disch Bypass Vlv Reactor Recirc Pump BNP 2 2-B32-F032B Reactor Recirc 4 Close No Low Susceptible(2) Yes No No Yes Not Repaired 2B Disch Bypass Vlv HPCI Turbine Steam BNP 2 2-E41-F002 HPCI Supply Inboard 10 Both No Medium Susceptible(2) Yes No No Yes Not Repaired Isolation Valve HPCI Turbine Steam BNP 2 2-E41-F003 HPCI Supply Outboard 10 Both No Medium Susceptible(2) Yes No No Yes Not Repaired Isolation Valve 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)

Are multiple Is the susceptibility Does the susceptibility Was an initial stem-Result of Was the diagnostic test Valve Active design Expert evaluation in evaluation rely on thread rotation check Plant Valve Functional susceptibility data reviewed for failure Unit Valve ID System Size Safety basis post- Panel Risk general friction? performed? Valve repair status Name Description evaluation precursors described in (inches) Function accident strokes Ranking conformance with If yes, was the COF greater If yes, include rotation TP16-1-112r4?

required? TP16-1-112r4? than 0.10? criteria (Open, (High, (No), (No),

(susceptible or (repaired or Close, Medium, (Yes/No) (Yes, >0.10), (Yes, 10 deg.), (Yes/ No)

(Yes/No) not susceptible) not repaired)

Both) Low) (Yes, 0.10) (Yes, 5 deg.)

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 Reactor Water RWCU Inlet Line BNP 2 2-G31-F001 6 Close No Medium Susceptible(1) Yes Yes, >0.10 Yes, 5 deg. Yes Not Repaired Cleanup Inboard Isolation Vlv RWCU Inlet Line Reactor Water BNP 2 2-G31-F004 Outboard Isolation 6 Close No Medium Susceptible(1) Yes Yes, >0.10 Yes, 5 deg. Yes Not Repaired Cleanup Vlv (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 TYPE COMMITMENT COMMITTED DATE OR "OUTAGE" ONE-TIME ACTION Programmatic (Yes/No) (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 Outage(Year) 1-B32-F032A 1-B32-F032B B1R22 (2018) Yes No 1-E41-F002 1-E41-F003 1-E41-F006 B1R22 (2018) Yes No 1-E51-F008 1-E51-F013 1-G31-F004 B1R22 (2018) Yes No Unit 2:

MOV Number Outage(Year) 2-B32-F032B 2-E41-F002 2-E41-F003 B2R24 (2019) Yes No 2-E41-F006 B2R24 (2019) 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 Number Outage(Year) 1-E51-F008 B1R23 (2020) Yes No 1-E51-F013 B1R23 (2020) Yes No Unit 2:

MOV Number Outage(Year) 2-E51-F013 B2R24 (2019) Yes No 2-G31-F001 B2R25 (2021) Yes No RA-17-0053 Page 4 of 5 COMMITMENT TYPE COMMITMENT COMMITTED DATE OR "OUTAGE" ONE-TIME ACTION Programmatic (Yes/No) (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 Outage(Year) 1-G31-F004 B1R24 (2022)See Note 1 Yes No Unit 2:

MOV Number Outage(Year) 2-G31-F004 B2R26 (2023)See Note 1 Yes 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 Every outage beginning 1-G31-F004 B1R23 (2020) No Yes Unit 2:

MOV Number Every outage beginning 2-G31-F004 B2R24 (2019) No Yes RA-17-0053 Page 5 of 5 COMMITMENT TYPE COMMITMENT COMMITTED DATE OR "OUTAGE" ONE-TIME ACTION Programmatic (Yes/No) (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 Every other outage beginning 1-B32-F031A B1R22 (2018) No Yes 1-B32-F031B B1R22 (2018) No Yes Unit 2:

MOV Number Every other outage beginning 2-B32-F031A B2R24 (2019) No Yes 2-B32-F031B B2R24 (2019) No Yes RA-17-0053 Attachment 2 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)

Is the susceptibility Does the susceptibility Was an initial stem-Result of Valve Active Are multiple design Expert evaluation in evaluation rely on thread rotation check Was the diagnostic test data Plant Valve Functional susceptibility Valve repair Unit Valve ID System Size Safety basis post-accident Panel Risk general friction? performed? reviewed for failure precursors Name Description evaluation status (inches) Function strokes required? Ranking conformance with If yes, was the COF greater If yes, include rotation described in TP16-1-112r4?

TP16-1-112r4? than 0.10? criteria (Open, (High, (No), (No),

(susceptible or (repaired or Close, Medium, (Yes/No) (Yes, >0.10), (Yes, 10 deg.), (Yes/ No)

(Yes/No) not susceptible) not repaired)

Both) Low) (Yes, 0.10) (Yes, 5 deg.)

S/G BLWDN CONT.

CNS 1 1BB008A BB 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired ISOL. INSIDE VLV.

S/G BLWDN CONT.

CNS 1 1BB010B BB ISOL. OUTSIDE 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired VLV.

S/G BLWDN CONT.

CNS 1 1BB019A BB 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired ISOL. INSIDE VLV..

S/G BLWDN CONT.

CNS 1 1BB021B BB ISOL. OUTSIDE 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired VLV.

S/G BLWDN CONT.

CNS 1 1BB056A BB 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired ISOL. INSIDE VLV.

S/G BLWDN CONT.

CNS 1 1BB057B BB ISOL. OUTSIDE 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired VLV.

S/G BLWDN CONT.

CNS 1 1BB060A BB 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired ISOL. INSIDE VLV.

S/G BLWDN CONT.

CNS 1 1BB061B BB ISOL. OUTSIDE 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired VLV.

TURBINE DRIVEN CNS 1 1CA038A CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP TO S/G ISOL.

MOTOR DRIVEN CNS 1 1CA042B CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP B TO S/G ISOL.

MOTOR DRIVEN CNS 1 1CA046B CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP B TO S/G ISOL.

TURBINE DRIVEN CNS 1 1CA050A CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP TO S/G ISOL.

TURBINE DRIVEN CNS 1 1CA054B CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP TO S/G ISOL.

MOTOR DRIVEN CNS 1 1CA058A CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP A TO S/G ISOL.

MOTOR DRIVEN CNS 1 1CA062A CA AUX FEEDWATER 4.00 Close No Low Susceptible(2) Yes Yes, 0.10 No Yes Not Repaired PMP A TO S/G ISOL.

TURBINE DRIVEN CNS 1 1CA066B CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP TO S/G ISOL.

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)

Is the susceptibility Does the susceptibility Was an initial stem-Result of Valve Active Are multiple design Expert evaluation in evaluation rely on thread rotation check Was the diagnostic test data Plant Valve Functional susceptibility Valve repair Unit Valve ID System Size Safety basis post-accident Panel Risk general friction? performed? reviewed for failure precursors Name Description evaluation status (inches) Function strokes required? Ranking conformance with If yes, was the COF greater If yes, include rotation described in TP16-1-112r4?

TP16-1-112r4? than 0.10? criteria (Open, (High, (No), (No),

(susceptible or (repaired or Close, Medium, (Yes/No) (Yes, >0.10), (Yes, 10 deg.), (Yes/ No)

(Yes/No) not susceptible) not repaired)

Both) Low) (Yes, 0.10) (Yes, 5 deg.)

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 S/G BLWDN CONT.

CNS 2 2BB008A BB 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired ISOL. INSIDE VLV.

S/G BLWDN CONT.

CNS 2 2BB010B BB ISOL. OUTSIDE 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired VLV.

S/G BLWDN CONT.

CNS 2 2BB019A BB 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired ISOL. INSIDE VLV.

S/G BLWDN CONT.

CNS 2 2BB021B BB ISOL. OUTSIDE 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired VLV.

S/G BLWDN CONT.

CNS 2 2BB056A BB 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired ISOL. INSIDE VLV.

S/G BLWDN CONT.

CNS 2 2BB057B BB ISOL. OUTSIDE 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired VLV.

S/G BLWDN CONT.

CNS 2 2BB060A BB 4.00 Close No Low Susceptible(2) Yes Yes, 0.10 No Yes Not Repaired ISOL. INSIDE VLV.

S/G BLWDN CONT.

CNS 2 2BB061B BB ISOL. OUTSIDE 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired VLV.

TURBINE DRIVEN CNS 2 2CA038A CA AUX FEEDWATER 4.00 Close No Low Susceptible(2) Yes Yes, 0.10 No Yes Not Repaired PMP TO S/G ISOL.

MOTOR DRIVEN CNS 2 2CA042B CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP B TO S/G ISOL.

MOTOR DRIVEN CNS 2 2CA046B CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP B TO S/G ISOL TURBINE DRIVEN CNS 2 2CA050A CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP TO S/G ISOL.

TURBINE DRIVEN CNS 2 2CA054B CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP TO S/G ISOL.

MOTOR DRIVEN CNS 2 2CA058A CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP A TO S/G ISOL.

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)

Is the susceptibility Does the susceptibility Was an initial stem-Result of Valve Active Are multiple design Expert evaluation in evaluation rely on thread rotation check Was the diagnostic test data Plant Valve Functional susceptibility Valve repair Unit Valve ID System Size Safety basis post-accident Panel Risk general friction? performed? reviewed for failure precursors Name Description evaluation status (inches) Function strokes required? Ranking conformance with If yes, was the COF greater If yes, include rotation described in TP16-1-112r4?

TP16-1-112r4? than 0.10? criteria (Open, (High, (No), (No),

(susceptible or (repaired or Close, Medium, (Yes/No) (Yes, >0.10), (Yes, 10 deg.), (Yes/ No)

(Yes/No) not susceptible) not repaired)

Both) Low) (Yes, 0.10) (Yes, 5 deg.)

MOTOR DRIVEN CNS 2 2CA062A CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP A TO S/G ISOL.

TURBINE DRIVEN CNS 2 2CA066B CA AUX FEEDWATER 4.00 Close No Low Not Susceptible Yes see footnote (3) No(3) No(3) Repaired PMP TO S/G ISOL.

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.)

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

(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 Outage 1CA062A, 1SV025B, 1SV027A C1R24 (Fall 2018) Yes No Unit 2:

MOV Number Outage 2BB060A, 2CA038A, 2SV025B, 2SV027A C2R22 (Spring 2018) Yes No RA-17-0053 Attachment 3 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)

Is the susceptibility Does the susceptibility Was an initial stem-Result of Valve Active Are multiple design Expert evaluation in evaluation rely on thread rotation check Was the diagnostic test data Plant Valve Functional susceptibility Valve repair Unit Valve ID System Size Safety basis post-accident Panel Risk general friction? performed? reviewed for failure precursors Name Description evaluation status (inches) Function strokes required? Ranking conformance with If yes, was the COF greater If yes, include rotation described in TP16-1-112r4?

TP16-1-112r4? than 0.10? criteria (Open, (High, (No), (No),

(susceptible or (repaired or Close, Medium, (Yes/No) (Yes, >0.10), (Yes, 10 deg.), (Yes/ No)

(Yes/No) not susceptible) not repaired)

Both) Low) (Yes, 0.10) (Yes, 5 deg.)

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 (3) (3) (3)

ONS 1 1FDW-104 FDW SG Shell Drain Block Valve 4.00 Close No Low Not Susceptible Yes see footnote No No Repaired Spent Fuel Pool to RC Make Up System Block ONS 1 1SF-97 SF 3.00 Both No High Not Susceptible Yes see footnote (3) No(3) No(3) Repaired Inside Containment Isolation 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 Spent Fuel Pool to RC Make Up System Block ONS 2 2SF-97 SF 3.00 Both No High Not Susceptible Yes see footnote (3) No(3) No(3) Repaired Inside Containment Isolation 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 (3) (3) (3)

ONS 3 3FDW-104 FDW SG Shell Drain Block Valve 4.00 Close No Low Not Susceptible Yes see footnote No No Repaired Spent Fuel Pool to RC Make Up System Block ONS 3 3SF-97 SF 3.00 Both No High Not Susceptible Yes see footnote (3) No(3) No(3) Repaired Inside Containment Isolation (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 Attachment 4 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)

Is the susceptibility Does the susceptibility Was an initial stem-Result of Valve Active Are multiple design Expert evaluation in evaluation rely on thread rotation check Was the diagnostic test data Plant Valve Functional susceptibility Valve repair Unit Valve ID System Size Safety basis post-accident Panel Risk general friction? performed? reviewed for failure precursors Name Description evaluation status (inches) Function strokes required? Ranking conformance with If yes, was the COF greater If yes, include rotation described in TP16-1-112r4?

TP16-1-112r4? than 0.10? criteria (Open, (High, (No), (No),

(susceptible or (repaired or Close, Medium, (Yes/No) (Yes, >0.10), (Yes, 10 deg.), (Yes/ No)

(Yes/No) not susceptible) not repaired)

Both) Low) (Yes, 0.10) (Yes, 5 deg.)

SDAFW PUMP FW RNP 2 AFW-V2-14A AFW 4 Both Yes Medium Susceptible(2) Yes No No Yes Not Repaired DISCH TO SG SDAFW PUMP FW RNP 2 AFW-V2-14B AFW 4 Both Yes Medium Susceptible(2) Yes No No Yes Not Repaired DISCH TO SG SDAFW PUMP FW RNP 2 AFW-V2-14C AFW 4 Both Yes Medium Susceptible(2) Yes No No Yes Not Repaired DISCH TO SG AFW HEADER RNP 2 AFW-V2-16A AFW 4 Both Yes Medium Susceptible(2) Yes No No Yes Not Repaired DISCH TO SG AFW HEADER RNP 2 AFW-V2-16B AFW 4 Both Yes Medium Susceptible(2) Yes No No Yes Not Repaired DISCH TO SG AFW HEADER RNP 2 AFW-V2-16C AFW 4 Both Yes Medium Susceptible(2) Yes No No Yes Not Repaired DISCH TO SG COOLING WATER RNP 2 CC-716B CC INLET 6 Close No Low Not Susceptible Yes see footnote 3 No(3) Yes Repaired(4)

BEARING COOLING RNP 2 CC-730 CC 6 Close No Low Susceptible(2) Yes No No Yes Not Repaired WATER OUTLET RCP SEAL WATER RNP 2 CVC-381 CVC RETURN 3 Close No Low Not Susceptible Yes see footnote 3 Yes, 10 deg. No(3) Repaired(4)

SG STM SUPPLY TO RNP 2 MS-V1-8A MS STM DRIVEN AFW 2 Both Yes Medium Not Susceptible Yes see footnote 3 No(3) No(3) Repaired PUMP SG STM SUPPLY TO RNP 2 MS-V1-8B MS STM DRIVEN AFW 2 Both Yes Medium Not Susceptible Yes see footnote 3 No(3) No(3) Repaired PUMP SG STM SUPPLY TO RNP 2 MS-V1-8C MS STM DRIVEN AFW 2 Both Yes Medium Not Susceptible Yes see footnote 3 No(3) No(3) Repaired PUMP RHR PUMP RNP 2 RHR-752A RHR 14 Close No Low Susceptible(1) Yes Yes, >0.10 Yes, 10 deg. Yes Not Repaired SUCTION RHR PUMP RNP 2 RHR-752B RHR 14 Close No Low Susceptible(1) Yes Yes, >0.10 Yes, 10 deg. Yes Not Repaired SUCTION CV SUMP RECIRC RNP 2 SI-860A SI 14 Both Yes High Susceptible(1) Yes Yes, >0.10 Yes, 10 deg. Yes Not Repaired SUCTION CV SUMP RECIRC RNP 2 SI-860B SI 14 Both Yes High Susceptible(1) Yes Yes, >0.10 Yes, 10 deg. Yes Not Repaired SUCTION CV SUMP RECIRC RNP 2 SI-861A SI 14 Both Yes High Susceptible(1) Yes Yes, >0.10 Yes, 10 deg. Yes Not Repaired SUCTION CV SUMP RECIRC RNP 2 SI-861B SI 14 Both Yes High Susceptible(1) Yes Yes, >0.10 Yes, 10 deg. Yes Not Repaired SUCTION RHR LOOP RWST RNP 2 SI-862A SI 14 Close No High Susceptible(1) Yes Yes, >0.10 Yes, 10 deg. Yes Not Repaired ISOL 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)

Is the susceptibility Does the susceptibility Was an initial stem-Result of Valve Active Are multiple design Expert evaluation in evaluation rely on thread rotation check Was the diagnostic test data Plant Valve Functional susceptibility Valve repair Unit Valve ID System Size Safety basis post-accident Panel Risk general friction? performed? reviewed for failure precursors Name Description evaluation status (inches) Function strokes required? Ranking conformance with If yes, was the COF greater If yes, include rotation described in TP16-1-112r4?

TP16-1-112r4? than 0.10? criteria (Open, (High, (No), (No),

(susceptible or (repaired or Close, Medium, (Yes/No) (Yes, >0.10), (Yes, 10 deg.), (Yes/ No)

(Yes/No) not susceptible) not repaired)

Both) Low) (Yes, 0.10) (Yes, 5 deg.)

RHR LOOP RWST RNP 2 SI-862B SI 14 Close No High Susceptible(1) Yes Yes, >0.10 Yes, 10 deg. Yes Not Repaired ISOL 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 LOOPS "B" AND "C" HOT LEG RNP 2 SI-869 SI 3 Both Yes Low Susceptible(1) Yes Yes, >0.10 Yes, 10 deg. Yes Not Repaired INJECTION SHUTOFF SI PUMP DISCH RNP 2 SI-878A SI 4 Close No Medium Susceptible(2) Yes Yes, 0.10 No No(5) Not Repaired HDR CROSS-CONN SI PUMP DISCH RNP 2 SI-878B SI 4 Close No Medium Susceptible(1) (2) Yes Yes, >0.10 No No(5) Not Repaired HDR CROSS-CONN (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 TYPE COMMITMENT COMMITTED DATE OR "OUTAGE" ONE-TIME ACTION Programmatic (Yes/No) (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 Outage(Year)

RHR-752A RHR-752B R2R31 (2018) Yes No SI-860B R2R31 (2018) Yes No SI-861A SI-861B R2R31 (2018) Yes No SI-878A SI-878B R2R31 (2018) Yes No CC-730 R2R31 (2018) Yes No MOV Number AFW-V2-14A AFW-V2-14B AFW-V2-14C 12/31/2018 Yes No AFW-V2-16A AFW-V2-16B AFW-V2-16C 12/31/2018 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 2:

MOV Number Outage(Year)

RHR-752A R2R33 (2022) Yes No RHR-752B R2R33 (2022) Yes No SI-860A R2R31 (2018) Yes No SI-860B R2R32 (2020) Yes No SI-861A R2R32 (2020) Yes No SI-861B R2R32 (2020) Yes No SI-862A R2R31 (2018) Yes No SI-862B R2R31 (2018) Yes No SI-864A R2R31 (2018) Yes No SI-864B R2R31 (2018) Yes No SI-878A R2R32 (2020) Yes No SI-878B R2R32 (2020) Yes No RA-17-0053 Page 4 of 4 COMMITMENT TYPE COMMITMENT COMMITTED DATE OR "OUTAGE" ONE-TIME ACTION Programmatic (Yes/No) (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 Outage(Year)

AFW-V2-14A R2R31 (2018) Yes No AFW-V2-14B R2R31 (2018) Yes No AFW-V2-14C R2R31 (2018) Yes No SI-869 R2R31 (2018) Yes No

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