LR-N17-0192, Anchor Darling Double Disc Gate Valve Information and Status: Difference between revisions

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: 1) Letter from Greg Krueger (NEI) to John Lubinski (U.S. Nuclear Regulatory Commission), Anchor Darling Double Disc Gate Valve Industry Resolution Plan Update (Project 689), dated August 4, 2017
: 1) Letter from Greg Krueger (NEI) to John Lubinski (U.S. Nuclear Regulatory Commission), Anchor Darling Double Disc Gate Valve Industry Resolution Plan Update (Project 689), dated August 4, 2017
: 2) Letter from Joe Pollock (NEI) to Brian Holian (U.S. Nuclear Regulatory Commission), NSIAC Concurrence on Anchor Darling Double Disc                      i Gate Valve Industry Response Actions (Project 689), dated October                i-26,2017
: 2) Letter from Joe Pollock (NEI) to Brian Holian (U.S. Nuclear Regulatory Commission), NSIAC Concurrence on Anchor Darling Double Disc                      i Gate Valve Industry Response Actions (Project 689), dated October                i-26,2017
: 3) BWROG Topical Report TP-16-1-112, Revision 4, Recommendations to Resolve Flowserve 1OCFR Part 21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failure 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 (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 Salem Generating Station, Units 1and 2.
: 3) BWROG Topical Report TP-16-1-112, Revision 4, Recommendations to Resolve Flowserve 10CFR Part 21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failure 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 (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 Salem Generating Station, Units 1and 2.
The Attachment to this letter contains the following information for each ADDDGV:
The Attachment to this letter contains the following information for each ADDDGV:
* Plant Name, Unit, and Valve ID.
* Plant Name, Unit, and Valve ID.

Latest revision as of 02:14, 10 November 2019

Anchor Darling Double Disc Gate Valve Information and Status
ML17356A023
Person / Time
Site: Salem  PSEG icon.png
Issue date: 12/22/2017
From: Davison P
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N17-0192
Download: ML17356A023 (5)


Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 PSEG Nuclear LLC LR-N17-0192 DEC 22 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311

Subject:

Anchor Darling Double Disc Gate Valve Information and Status

References:

1) Letter from Greg Krueger (NEI) to John Lubinski (U.S. Nuclear Regulatory Commission), Anchor Darling Double Disc Gate Valve Industry Resolution Plan Update (Project 689), dated August 4, 2017
2) Letter from Joe Pollock (NEI) to Brian Holian (U.S. Nuclear Regulatory Commission), NSIAC Concurrence on Anchor Darling Double Disc i Gate Valve Industry Response Actions (Project 689), dated October i-26,2017
3) BWROG Topical Report TP-16-1-112, Revision 4, Recommendations to Resolve Flowserve 10CFR Part 21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failure 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 (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 Salem Generating Station, Units 1and 2.

The Attachment to this letter contains the following information for each ADDDGV:

  • Plant Name, Unit, and Valve ID.
  • System.
  • Valve Functional Description.
  • Valve Size.
  • Active Safety Function (open, close, both).

LR-N17-0192 Page 2

  • Are multiple design basis post-accident strokes are required (yes/no).
  • Expert Panel Risk Ranking (high, medium, low).
  • Result of susceptibility evaluation (susceptible or not susceptible).
  • Is the susceptibility evaluation in general conformance with TP16-1-112R4 (Reference 3)?
  • Does the susceptibility evaluation rely on thread friction? If yes, was the COF greater than 0.1 0? For cases where thread-friction was relied upon, information is provided whether the coefficient of friction was above or below 0.1.
  • Was an initial stem-rotation check performed? If yes, include rotation criteria (i.e.
510 degrees or :55 degrees).
  • Was the diagnostic test data reviewed for failure precursors described in TP16 112R4 (Reference 3)?
  • The valve's repair status (i.e. repaired or not repaired).
  • A repair schedule for each susceptible valve.

There are no regulatory commitments in this letter.

Should you have any questions or require additional information, please contact Mr.

Justin Wearne at 856-339-1351.

Sincerely,

?~}*\)~

Paul J. Davison VP Nuclear Engineering PSEG Nuclear ako : Salem Units 1 and 2 ADDDGV Listing

LR-N17-0192 Page 3 cc: Mr. David Lew, Regional Administrator- NRC Region 1 Ms. Carleen Parker, Project Manager- US NRC Mr. Patrick Finney, USNRC Senior Resident Inspector- Salem Mr. Patrick Mulligan, Manager IV, NJBNE Mr. Lee Marabella, Corporate Commitment Tracking Coordinator Mr. Thomas Cachaza, Salem Commitment Tracking Coordinator

LR-N17-0192 Attachment 1 Salem Units 1 and 2 ADDDGV Listing

LR-N17-0192 Salem Units 1 and 2 ADDDGV Listing Was an initial stem-Does the susceptibility rotation check Active evaluation rely on thread Are multiple Expert Panel Result of performed?

Safety friction? Valve repair status Valve design basis post Risk Ranking susceptibility If yes, include Was diagnostic test Plant Valve ID Function Is the susceptibility If yes, was the COF (repaired or Unit System Valve Functional Description Size accident strokes (High, evaluation rotation criteria data reviewed for Comments Name Functional Location (MOV) (Open, evaluation in general greater than 0.10? not repaired)

(inches) required? Medium, (susceptible or not (No), failure precursors Close, conformance with TP16*1* (No),

(Yes/No) Low) suceptlble) 112R4?(A) (Yes, >0.10), (Yes, S10 deg.), described in TP 16 Both)

(Yes/No) (Yes, :50.10) (Yes, ss deg.) 112 R4?

(Yes/No)

Y (using thread friction) 2 Safety Injection 14" Both Yes Medium No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem S2SJ -21SJ44-MTRY CONT SUMP SUCT VALVE Note 2 Repair scoped into 2R23 Y (using thread friction) 2 Safety Injection 14" Both Yes Medium No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem S2SJ -22SJ44-MTRY CONT SUMP SUCT VALVE Note 2 Repair scoped into 2R23 Y (using thread friction) 1 Safety Injection 14" Both Yes Medium No Yes COF > 0.10 Yes,< 5 deg. Yes Repaired Salem S1SJ -11SJ44-MTRY CONT SUMP SUCT VALVE Note 2 No Further action required. Note 1 Y (using thread friction) 1 Safety Injection 14" Both Yes Medium No Yes COF > 0.10 Yes,< 5 deg. Yes Repaired Salem S1SJ -12SJ44-MTRY CONT SUMP SUCT VALVE Note 2 No Further action required. Note 1 Y (using thread friction) 1 Safety Injection 4" Both Yes Low No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem 51SJ -1SJ12-MTRY BIT OUTLET MOV Note 2 1R26 or 1R27 Y (using thread friction) 1 Safety Injection 4" Both Yes Low No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem 51SJ -1SJ13-MTRY BIT OUTLET MOV Note 2 1R26 or 1R27 Y (using thread friction) 1 Safety Injection 4" Both Yes Low No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem 51SJ -1SJ4-MTRY BIT INLET MOV Note 2 1R26 or 1R27 Y (using thread friction) 1 Safety Injection 4" Both Yes Low No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem 51SJ -1SJ5-MTRY BIT INLET MOV Note 2 1R26 or 1R27 Y (using thread friction) Medium Risk must be repaired in 1 Safety Injection 8" Open No Medium No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem S1SJ -11SJ45-MTRY RHR TO 51 PMPS STOP MOV Note 2 1R26 Y (using thread friction) 1 Safety Injection 8" Open No Medium No Yes COF > 0.10 Yes,< 5 deg. Yes Repaired Salem 51SJ -12SJ45-MTRY RHR TO CHG Sl PMPS STOP MOV Note 2 No Further action required. Note 1 Y (using thread friction) 1 Containment Spray 8" Both Yes Low No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem S1CS -11CS36-MTRY RHR CS STOP VALVE Note 2 1R26 or 1R27 Y (using thread friction) 1 Containment Spray 8" Both Yes Low No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem 51CS -12CS36-MTRY RHR CS STOP VALVE Note 2 1R26 or 1R27 Y (using thread friction) 1 Safety Injection 4" Both Yes Low No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem S1SJ -11SJ40-MTRY SJ HDR STOP VALVE Note 2 Due for Diagnostic testing in 1R26 Y (using thread friction) 1 Safety Injection 4" Both Yes Low No Yes COF > 0.10 Yes,< 5 deg. Yes Repaired Salem 51SJ -12SJ40-MTRY SJ HDR STOP VALVE Note 2 No Further action required. Note 1 Y (using thread friction) 2 Safety Injection 4" Both Yes Low No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem 52SJ -21SJ40-MTRY SJ HDR STOP VALVE Note 2 Repair scoped into 2R23 Y (using thread friction) 2 Safety Injection 4" Both Yes Low No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem 52SJ -22SJ40-MTRY SJ HDR STOP VALVE Note 2 Repair scoped into 2R23 Salem 1 S1RHR-11RH4-MTRY Residual Heat Removal RHR PUMP SUCT MOV 14" Close No Medium No Y (Pin Shear only) No- Note3 Yes,< 5 deg. Yes Not Repaired Salem 1 S1RHR-12RH4-MTRY Residual Heat Removal RHR PUMP SUCT MOV 14" Close No Medium No Y (Pin Shear only) No- Note 3 Yes,< 5 deg. Yes Not Repaired Internal inspection performed Apr-2 14" Close No Medium No Y (Pin Shear only) No- Note 3 Yes,< 5 deg. Yes Not Repaired 2017. No issue identified during Salem S2RHR-21RH4-MTRY Residual Heat Removal RHR PUMP SUCT MOV internal inspection.

Salem 2 S2RHR-22RH4-MTRY Residual Heat Removal RHR PUMP SUCT MOV 14" Close No Medium No Y (Pin Shear only) No- Note3 Yes,< 5 deg. Yes Not Repaired Y (using thread friction) 1 Residual Heat Removal 8" Close No Low No Yes COF > 0.10 Yes,< 5 deg. Yes Not Repaired Salem 51RHR-11RH19-MTRY RHR HX DISCH CROSS CONN MOV Note 2 1R26 or 1R27 Y (using thread friction) 1 Residual Heat Removal 8" Close No Low No Yes COF > 0.10 Yes,< 5 deg. Yes Repaired Salem 51RHR-12RH19-MTRY RHR HX DISCH CROSS CONN MOV Note 2 No Further action required. Note 1 Salem 1 51CC -1CC117-MTRY Component Cooling RCP CC INLET MOV 6" Close No Low No Y (Pin Shear only) No- Note 3 Yes,< 5 deg. Yes Not Repaired Salem 1 S1CC -1CC118-MTRY Component Cooling RCP CC INLET MOV 6" Close No Low No Y (Pin Shear only) No- Note3 Yes,< 5 deg. Yes Not Repaired Salem 1 S1CC -1CC136-MTRY Component Cooling RCP BRG MOV 6" Close No Low No Y (Pin Shear only) No- Note 3 Yes,< 5 deg. Yes Not Repaired Salem 1 51CC -1CC187-MTRY Component Cooling RCP MOT BRG CC MOV 6" Close No Low No Y (Pin Shear only) No- Note 3 Yes,< 5 deg. Yes Not Repaired Salem 1 51SJ -1SJ135-MTRY Safety Injection SJ DISCH TO COLD LEGS VLV 4" Close No Low No Y (Pin shear only) No- Note 3 Yes,< 5 deg. Yes Not Repaired Salem 2 52CC -2CC117-MTRY Component Cooling RCP CC INLET MOV 6" Close No Low No Y (Pin Shear only) No- Note 3 Yes,< 5 deg. Yes Not Repaired Salem 2 S2CC -2CC118-MTRY Component Cooling RCP CC INLET MOV 6" Close No Low No Y (Pin Shear only) No- Note 3 Yes,< 5 deg. Yes Not Repaired Salem 2 52CC -2CC136-MTRY Component Cooling RCP BRG MOV 6" Close No Low No Y (Pin Shear only) No- Note3 Yes,< 5 deg. Yes Not Repaired Salem 2 52CC -2CC187-MTRY Component Cooling RCP MOT BRG CC MOV 6" Close No Low No Y (Pin Shear only) No- Note 3 Yes,< 5 deg. Yes Not Repaired Salem 2 52SJ -2SJ135-MTRY Safety Injection SJ DISCH TO COLD LEGS VLV 4" Close No Low No Y (Pin Shear only) No- Note 3 Yes,< 5 deg. Yes Not Repaired (A) Applied Wedge Pin Torque must bound anticipated design basis operating torque requirements and current maximum total torque.

NOTES:

1. The Repair method for the MOV's includes replacing the stem with a new stem with a Integral collar, torquelng the stem/wedge connection to 120 percent of the maximum anticipated design basis operating torque (assuming a 0.20 COF), and pinning the connection with new lnconel718 pins.
2. For all MOVs which required thread friction to validate the current operational capability, PSEG plans to repair all18 valves lAW the schedule above (within the next two refuel outages at each unit)
3. For the remaining 14 MOVs which screened out as acceptable based on PIN shear capability alone, PSEG plans to monitor using normally scheduled diagnostic testing and stem rotation checks per the MOV program requirements lAW NRC GL 96-05.