ML20203M160
| ML20203M160 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Summer, Surry, North Anna  |
| Issue date: | 07/20/2020 |
| From: | Mark D. Sartain Dominion Energy Nuclear Connecticut, Dominion Energy Services, Dominion Energy South Carolina, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 20-215 | |
| Download: ML20203M160 (23) | |
Text
Dominion Energy Services, Inc.
5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Energy.com July 20, 2020 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Serial No.:
20-215 NRA/GDM:
R3 Docket Nos.: 50-336 50-338/339 50-280/281 50-395 License Nos.: DPR-65 NPF-4/7 DPR-32/37 NPF-12 VIRGINIA ELECTRIC AND POWER COMPANY {DOMINION ENERGY VIRGINIA)
DOMINION ENERGY NUCLEAR CONNECTICUT, INC. {DENC)
DOMINION ENERGY SOUTH CAROLINA, INC. {DESC)
MILLSTONE POWER STATION UNIT 2 NORTH ANNA AND SURRY POWER STATIONS UNITS 1 AND 2 VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 UPDATED ANCHOR DARLING DOUBLE DISC GATE VALVE INFORMATION AND STATUS
References:
- 1) Letter from Virginia Electric and Power Company and Dominion Nuclear Connecticut, Inc., to the US NRC dated December 18, 2017 (Serial No. 17-343A), for Millstone Power Station Units 2 and 3, North Anna and Surry Power Stations Units 1 and 2, "Anchor Darling Double Disc Gate Valve Information and Status" [ADAMS Accession No. ML17362A043]
- 2) Letter from Virginia Electric and Power Company and Dominion Nuclear Connecticut, Inc., to the US NRC dated December 19, 2018 (Serial No.18-238), "Virginia Electric and Power Company (Dominion Energy Virginia), Dominion Energy Nuclear Connecticut, Inc., Millstone Power Station Unit 2, North Anna and Surry Power Stations Units 1 and 2, Updated Anchor Darling Double Disc Gate Valve Information and Repair Status" [ADAMS Accession No. ML18361A580]
- 3) Letter from South Carolina Gas and Electric to the US NRC dated December 11, 2017 (Serial Number: RC-17-0182), "Virgil C. Summer Nuclear Station (VCSNS), Docket Number 50-395, Operating License No. NPF-12, Anchor Darling Double Disc Gate Valve Information and Status" [ADAMS Accession No. ML17346A561]
Serial No.20-215 Docket Nos. 50-336/338/339/280/281/395 Updated ADDDGV Information and Status Page 2 of 5
- 4) Part 21 Notification from Flowserve Corporation, Part 21 - Wedge Pin Failure in Anchor Darling Motor Operated Double Disc Gate Valves with Threaded Stem to Upper Wedge Connections, dated March 1, 2013, as modified July 11, 2017 [ADAMS Accession No. ML17194A825]
- 5) Boiling Water Reactor Owners Group (BWROG) Topical Report TP 1-112, Revision 4, Recommendations to Resolve Flowserve 10 CFR Part 21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failure, [ADAMS Accession No. ML17243A137]
- 6) BWROG Topical Report TP-16-1-112, Revision 5, Recommendations to Resolve Flowserve 10 CFR Part 21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failure, November 2019 In References 1, 2 and 3, Dominion Energy Virginia, DENC, and South Carolina Electric and Gas (now DESC) (collectively, Dominion Energy), provided a listing of the Anchor Darling double disc gate valve (ADDDGV) population with active safety functions for Millstone Power Station (MPS) Unit 2, North Anna and Surry Power Stations (NAPS and SPS, respectively) Units 1 and 2, and Virgil C. Summer Nuclear Station (VCSNS) Unit 1 that are subject to the Flowserve Part 21 (Reference 4). References 1, 2 and 3 included relevant information for each valve listed pursuant to the recommendations provided in Reference 5.
Subsequent to the submittal of these letters, the NRC hosted several public meetings where the staff expressed concern regarding licensees application of engineering judgement without any specified limitations when determining the maximum allowed values for stem-to-wedge thread coefficients of friction (COF) used in pin shear analyses. As a result, the industry performed two utility surveys that collected the cumulative results of the ADDDGV repairs/inspections performed to date. No additional valves were found with sheared wedge pins.
In November 2019, the BWROG Valve Technical Resolution Group (VTRG) issued TR TP16-1-112, Revision 5 (Reference 6) to address the NRC concern regarding stem-to-wedge thread COF and provided simplified recommendations for licensee resolution of the Flowserve Part 21 issue. Analysis of the industry data readily supports a limited amount of wedge-stem thread friction credit in the susceptibility evaluation screen for potential wedge pin failure. Based on engineering evaluation of this data, this revision provides some relaxation of the susceptibility screening and recommended actions to include a periodic test option versus repair for those MOVs considered to be of very low potential risk of wedge pin failure.
Dominion Energy has performed numerous inspections and repairs of its ADDDGVs subject to the Part 21 and has concluded the inspection results are consistent with the
Serial No.20-215 Docket Nos. 50-336/338/339/280/281/395 Updated ADDDGV Information and Status Page 3 of 5 conclusions noted in Reference 6 (e.g., all wedge pins inspected at any of the Dominion Energy plants have been found intact). Consequently, Dominion Energy plans to follow the Reference 6 recommendations going forward for the subject Generic Letter 96-05 ADDDGVs at MPS Unit 2 (with the exception of 2-CS-13.1 B noted in Attachment 1, based on conservative analysis), NAPS and SPS Units 1 and 2, and VCSNS Unit 1. A list of the affected ADDDGVs, their susceptibility determination, COF, and planned actions pursuant to the simplified recommendations of Reference 6 to resolve the Part 21 issue are provided in Attachments 1 through 4, for each site, respectively.
This information updates and supersedes the information previously provided in References 1, 2 and 3 for the Dominion Energy nuclear fleet.
Should you have any questions or require additional information, please contact Mr. Gary D. Miller at (804) 273-2771.
Respectfully, Mark D. Sartain Vice President - Nuclear Engineering and Fleet Support Virginia Electric and Power Company Dominion Energy Nuclear Connecticut, Inc.
Dominion Energy South Carolina, Inc.
Regulatory commitments contained in this correspondence: None Attachments:
- 1. Updated Anchor Darling Double Disc Gate Valve Susceptibility Information -
Millstone Unit 2
- 2. Updated Anchor Darling Double Disc Gate Valve Susceptibility Information - North Anna Units 1 and 2
- 3. Updated Anchor Darling Double Disc Gate Valve Susceptibility Information - Surry Units 1 and 2
- 4. Updated Anchor Darling Double Disc Gate Valve Susceptibility Information - V. C.
Summer Nuclear Station Unit 1
Serial No.20-215 Docket Nos. 50-336/338/339/280/281/395 Updated ADDDGV Information and Status Page 4 of 5 cc:
U.S. Nuclear Regulatory Commission - Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, Pennsylvania 19406 - 2713 U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector Millstone Power Station NRC Senior Resident Inspector North Anna Power Station NRC Senior Resident Inspector Surry Power Station NRC Senior Resident Inspector V. C. Summer Nuclear Station Mr. R. Guzman NRC Senior Project Manager - Millstone U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 C2 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. G. Edward Miller NRC Senior Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 E3 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. Vaughn Thomas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 04 F12 11555 Rockville Pike Rockville, MD 20852-2738
Serial No.20-215 Docket Nos. 50-336/338/339/280/281/395 Updated ADDDGV Information and Status Page 5 of 5 Mr. Marcus Harris Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd., Suite 300 Glen Allen, Virginia 23060
Serial No.20-215 Docket No. 50-336 UPDATED ANCHOR DARLING DOUBLE DISC GATE VALVE INFORMATION Dominion Energy Nuclear Connecticut, Inc.
Millstone Power Station Unit 2
Serial No.20-215 Docket No. 50-336 Page 1 of 2 Millstone Power Station Unit 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions (Open,
- Close, Both)
(High,
- Medium, Low)
(Susceptible or not Susceptible)
MPS 2
2-CS-4.1A Containment Spray A Containment Spray Header Isolation Valve 8
Both High Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements MPS 2
2-CS-4.1B Containment Spray B Containment Spray Header Isolation Valve 8
Both High Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements MPS 2
2-CS-13.1A Containment Spray RWST Outlet Header A Isolation Valve 18 Close Medium Not Susceptible (COF < 0.1) 0.078 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements MPS 2
2-CS-13.1B Containment Spray RWST Outlet Header B Isolation Valve 18 Close Medium Not Susceptible (COF = 0.101)1 0.101 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements MPS 2
2-CS-16.1A Containment Spray Containment Sump Outlet Header A Isolation Valve 24 Both High Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements 1 (ETE-MP-2020-1063, Revision 0, documents COF = 0.101 is acceptable)
Serial No.20-215 Docket No. 50-336 Page 2 of 2 Millstone Power Station Unit 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions (Open,
- Close, Both)
(High,
- Medium, Low)
(Susceptible or not Susceptible)
MPS 2
2-CS-16.1B Containment Spray Containment Sump Outlet Header B Isolation Valve 24 Both High Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements
Serial No.20-215 Docket Nos. 50-338/339 UPDATED ANCHOR DARLING DOUBLE DISC GATE VALVE INFORMATION Virginia Electric and Power Company (Dominion Energy Virginia)
North Anna Power Station Units 1 and 2
Serial No.20-215 Docket Nos. 50-338/339 Page 1 of 3 North Anna Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions (Open, Close, Both)
(High, Medium, Low)
(Susceptible or Not Susceptible)
NAPS 1
1-RH-MOV-1720A Residual Heat Removal Residual Heat Removal to B RCS Loop 10x8x10 Open Medium Susceptible 0.138 Internal valve repair within 2 years; OR perform diagnostic testing every 2 years until internal valve repair within 2 RFO (4 years)
NAPS 1
1-RH-MOV-1720B Residual Heat Removal Residual Heat Removal to C RCS Loop 10x8x10 Open Medium Susceptible 0.163 Internal valve repair within 2 years; OR perform diagnostic testing every 2 years until internal valve repair within 2 RFO (4 years)
NAPS 1
1-SI-MOV-1890A Safety Injection Low Head Safety Injection Hot Leg Injection Valve 10x8x10 Both Low Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements NAPS 1
1-SI-MOV-1890B Safety Injection Low Head Safety Injection Hot Leg Injection Valve 10x8x10 Both Low Not Susceptible (COF < 0.2) 0.142 Perform compensatory diagnostic testing and stem rotation checks (i.e., tests 1 & 2 every 2 years; tests 3 & 4 every 4 years; test 5 and after may be performed at the established GL 96-05 periodic test interval)
NAPS 1
1-SI-MOV-1890C Safety Injection Low Head Safety Injection Cold Leg Injection Valve 10x8x10 Both Low Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements
Serial No.20-215 Docket Nos. 50-338/339 Page 2 of 3 North Anna Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions (Open, Close, Both)
(High, Medium, Low)
(Susceptible or Not Susceptible)
NAPS 1
1-SI-MOV-1890D Safety Injection Low Head Safety Injection Cold Leg Injection Valve 10x8x10 Both Low Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements NAPS 2
2-RH-MOV-2720A Residual Heat Removal Residual Heat Removal to B RCS Loop 10x8x10 Open Medium Susceptible 0.159 Internal valve repair within 2 years; OR perform diagnostic testing every 2 years until internal valve repair within 2 RFO (4 years)
NAPS 2
2-RH-MOV-2720B Residual Heat Removal Residual Heat Removal to C RCS Loop 10x8x10 Open Medium Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements NAPS 2
2-SI-MOV-2890A Safety Injection Low Head Safety Injection Hot Leg Injection Valve 10x8x10 Both Low Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements NAPS 2
2-SI-MOV-2890B Safety Injection Low Head Safety Injection Hot Leg Injection Valve 10x8x10 Both Low Not Susceptible (COF < 0.2) 0.132 Perform compensatory diagnostic testing and stem rotation checks (i.e., tests 1 & 2 every 2 years; tests 3 & 4 every 4 years; test 5 and after may be performed at the established GL 96-05 periodic test interval)
Serial No.20-215 Docket Nos. 50-338/339 Page 3 of 3 North Anna Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions (Open, Close, Both)
(High, Medium, Low)
(Susceptible or Not Susceptible)
NAPS 2
2-SI-MOV-2890C Safety Injection Low Head Safety Injection Cold Leg Injection Valve 10x8x10 Both Low Not Susceptible (COF < 0.2) 0.135 Perform compensatory diagnostic testing and stem rotation checks (i.e., tests 1 & 2 every 2 years; tests 3 & 4 every 4 years; test 5 and after may be performed at the established GL 96-05 periodic test interval)
NAPS 2
2-SI-MOV-2890D Safety Injection Low Head Safety Injection Cold Leg Injection Valve 10x8x10 Both Low Not Susceptible (COF < 0.2) 0.133 Perform compensatory diagnostic testing and stem rotation checks (i.e., tests 1 & 2 every 2 years; tests 3 & 4 every 4 years; test 5 and after may be performed at the established GL 96-05 periodic test interval)
Serial No.20-215 Docket Nos. 50-280/281 UPDATED ANCHOR DARLING DOUBLE DISC GATE VALVE INFORMATION Virginia Electric and Power Company (Dominion Energy Virginia)
Surry Power Station Units 1 and 2
Serial No.20-215 Docket Nos. 50-280/281 Page 1 of 8 Surry Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions2 (Open, Close, Both)
(High,
- Medium, Low)
(Susceptible or not Susceptible)
SPS 1
01-CH-MOV-1289A Charging Main Charging Header Isolation 3
Open Low Not Susceptible (COF < 0.1) 0.095 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 1
01-CH-MOV-1289B Charging Main Charging Header Isolation 3
Open Low Not Susceptible (COF < 0.1) 0.095 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 1
01-CH-MOV-1370 Charging Residual Heat Removal Outlet Isolation to Accumulator Discharge Line 3
Both Low Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 1
01-CH-MOV-1373 Charging Residual Heat Removal Outlet Isolation to Accumulator Discharge Line 3
Both Low Not Susceptible (COF < 0.2) 0.118 Perform compensatory diagnostic testing and stem rotation checks (i.e., tests 1 & 2 every 2 years; tests 3 & 4 every 4 years; test 5 and after may be performed at the established GL 96-05 periodic test interval) 2 Diagnostic testing with stem rotation checks have been completed every refueling outage since spring 2018. Therefore, the first and second required diagnostic tests and stem rotation checks for the unrepaired valves are considered complete.
Serial No.20-215 Docket Nos. 50-280/281 Page 2 of 8 Surry Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions2 (Open, Close, Both)
(High,
- Medium, Low)
(Susceptible or not Susceptible)
SPS 1
01-RH-MOV-1720A Residual Heat Removal Low Head Safety Injection Pump Cold Leg Discharge Stop Valve 10x8x10 Both Medium Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 1
01-RH-MOV-1720B Residual Heat Removal Low Head Safety Injection Pump Cold Leg Discharge Stop Valve 10x8x10 Both Medium Not Susceptible (COF < 0.1) 0.013 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 1
01-SI-MOV-1864A Safety Injection High Head Safety Injection to Reactor Coolant System (RCS)
Cold Legs 10 Open Low Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 1
01-SI-MOV-1864B Safety Injection High Head Safety Injection to RCS Cold Legs 10 Open Low Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements
Serial No.20-215 Docket Nos. 50-280/281 Page 3 of 8 Surry Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions2 (Open, Close, Both)
(High,
- Medium, Low)
(Susceptible or not Susceptible)
SPS 1
01-SI-MOV-1867C Safety Injection High Head Safety Injection from Charging Header to RCS Hot Legs 3
Both High Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 1
01-SI-MOV-1867D Safety Injection Low Head Safety Injection Pump Hot Leg Discharge Stop Valve 3
Both High Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 1
01-SI-MOV-1869A Safety Injection Low Head Safety Injection Pump Hot Leg Discharge Stop Valve 3
Both Low Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 1
01-SI-MOV-1890A Safety Injection Low Head Safety Injection Pump Hot Leg Discharge Stop Valve 10x8x10 Both Low Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements
Serial No.20-215 Docket Nos. 50-280/281 Page 4 of 8 Surry Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions2 (Open, Close, Both)
(High,
- Medium, Low)
(Susceptible or not Susceptible)
SPS 1
01-SI-MOV-1890B Safety Injection Charging Pump Supply from RWST 10x8x10 Both Low Not Susceptible (COF < 0.1) 0.043 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 1
01-SI-MOV-1890C Safety Injection Charging Pump Supply from RWST 10x8x10 Both Low Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 2
02-CH-MOV-2115B Charging Main Charging Header Isolation 8
Both High Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 2
02-CH-MOV-2115D Charging Main Charging Header Isolation 8
Both High Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 2
02-CH-MOV-2289A Charging Residual Heat Removal Outlet Isolation to Accumulator Discharge Line 3
Close Low Not Susceptible (Valve DIA < 6 inches) 0.201 Perform compensatory diagnostic testing and stem rotation checks (i.e., tests 1 & 2 every 2 years; tests 3 & 4 every 4 years; test 5 and after may be performed at the established GL 96-05 periodic test interval)
Serial No.20-215 Docket Nos. 50-280/281 Page 5 of 8 Surry Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions2 (Open, Close, Both)
(High,
- Medium, Low)
(Susceptible or not Susceptible)
SPS 2
02-CH-MOV-2289B Charging Residual Heat Removal Outlet Isolation to Accumulator Discharge Line 3
Close Low Not Susceptible (Valve DIA < 6 inches) 0.201 Perform compensatory diagnostic testing and stem rotation checks (i.e., tests 1 & 2 every 2 years; tests 3 & 4 every 4 years; test 5 and after may be performed at the established GL 96-05 periodic test interval)
SPS 2
02-CH-MOV-2370 Charging High Head Safety Injection from Charging Header to RCS Cold Legs 3
Open Low Not Susceptible (COF < 0.1) 0.077 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 2
02-CH-MOV-2373 Charging Low Head Safety Injection Pump Cold Leg Discharge Stop Valve 3
Open Low Not Susceptible (COF < 0.2) 0.102 Perform compensatory diagnostic testing and stem rotation checks (i.e., tests 1 & 2 every 2 years; tests 3 & 4 every 4 years; test 5 and after may be performed at the established GL 96-05 periodic test interval)
SPS 2
02-RH-MOV-2720A Residual Heat Removal Low Head Safety Injection Pump Cold Leg Discharge Stop Valve 10x8x10 Open Medium Not Susceptible (COF < 0.1) 0.098 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements
Serial No.20-215 Docket Nos. 50-280/281 Page 6 of 8 Surry Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions2 (Open, Close, Both)
(High,
- Medium, Low)
(Susceptible or not Susceptible)
SPS 2
02-RH-MOV-2720B Residual Heat Removal High Head Safety Injection to RCS Cold Legs 10x8x10 Open Medium Not Susceptible (COF < 0.1) 0.093 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 2
02-SI-MOV-2842 Safety Injection High Head Safety Injection to RCS Cold Legs 4
Both High Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 2
02-SI-MOV-2864A Safety Injection Low Head Safety Injection Pump Hot Leg Discharge Stop Valve 10 Both Low Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 2
02-SI-MOV-2864B Safety Injection Low Head Safety Injection Pump Hot Leg Discharge Stop Valve 10 Both Low Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements
Serial No.20-215 Docket Nos. 50-280/281 Page 7 of 8 Surry Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions2 (Open, Close, Both)
(High,
- Medium, Low)
(Susceptible or not Susceptible)
SPS 2
02-SI-MOV-2867C Safety Injection Low Head Safety Injection Pump Cold Leg Discharge Stop Valve 3
Both High Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 2
02-SI-MOV-2867D Safety Injection Main Charging Header Isolation 3
Both High Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 2
02-SI-MOV-2890A Safety Injection Main Charging Header Isolation 10x8x10 Both Low Not Susceptible (COF < 0.1)
N/A3 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements SPS 2
02-SI-MOV-2890B Safety Injection Residual Heat Removal Outlet Isolation to Accumulator Discharge Line 10x8x10 Both Low Not Susceptible (COF < 0.1) 0.058 Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements 3 02-SI-MOV-2890A was the only valve at Surry that is not repaired that did not require wedge thread friction for the pin shear analysis.
Serial No.20-215 Docket Nos. 50-280/281 Page 8 of 8 Surry Power Station Units 1 and 2 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions2 (Open, Close, Both)
(High,
- Medium, Low)
(Susceptible or not Susceptible)
SPS 2
02-SI-MOV-2890C Safety Injection Residual Heat Removal Outlet Isolation to Accumulator Discharge Line 10x8x10 Both Low Not Susceptible; (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements
Serial No.20-215 Docket No. 50-395 UPDATED ANCHOR DARLING DOUBLE DISC GATE VALVE INFORMATION Dominion Energy South Carolina V. C. Summer Nuclear Station Unit 1
Serial No.20-215 Docket No. 50-395 Page 1 of 1 V. C. Summer Nuclear Station Unit 1 Anchor Darling Double Disc Gate Valves Subject to the Flowserve Part 21 Plant Name Unit Valve ID System Valve Functional Description Valve Size (inches)
Active Safety Function Expert Panel Risk Ranking Result of Susceptibility Evaluation (TP16-1-112 R5)
Required Coefficient of Friction Planned Corrective Actions (Open, Close, Both)
(High, Medium, Low)
(Susceptible or not Susceptible)
VCS 1
XVG03004A-SP Reactor Building (RB)
Spray RB Spray Sump Isolation Valve A (IRC) 12 Both Low Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements VCS 1
XVG03004B-SP Reactor Building Spray RB Spray Sump Isolation Valve B (IRC) 12 Both Low Not Susceptible (Repaired)
N/A Perform stem rotation checks in conjunction with established GL 96-05 periodic diagnostic testing requirements