L-17-280, Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues
| ML17243A134 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/29/2017 |
| From: | Bologna R FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-17-280 | |
| Download: ML17243A134 (4) | |
Text
FENOC' Beaver Valley Power Station P.O. Box4 Shippingporl, PA 15077 FirstEnergy Nuclear Operating Company Richard D. Bologna 724-682-5234 Site Vice President Fax: 724-643-8069 August 29, 2017 L-17-280 10 CFR Part 21 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit Nos. 1 and 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues
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.
- 2) BWROG Topical Report TP-16-1-112, Rev.4, Recommendations to Resolve Flowserve 10 CFR Part 21 Notification Affecting Anchor Darling Double Disc Gate Valve Wedge Pin Failures (Revision 4)," dated August 2017.
In Reference 1, the Nuclear Energy Institute (NEI) provided the NRC a near-term plan for the U.S. Nuclear Industry to address the known Anchor Darling Double Disk Gate Valve (ADDDGV) issues. The NEI letter states that each affected utility will communicate to the NRC by August 31, 2017 a list of "High Significance" Valves and an associated repair schedule.* FirstEnergy Nuclear Operating Company (FE NOC) hereby provides this information for the Beaver Valley Power Station (BVPS), Unit 1. BVPS Unit 2 is not affected by this issue.
Attachment 1 contains commitments regarding the repair and resolution of the susceptible High Significance Motor Operated Valves (MOV). At the FENOC BVPS site, High Significance MOVs were determined using the NRC approved Generic Letter (GL) 96-05 Risk Ranking Methodology and includes High, Medium and Low Risk GL 96-05 MOVs.
FENOC is an active participant in the Boiling Water Reactors Owners Group (BWROG) committee that is developing corrective actions and maintenance activities to ensure proper functioning of the Anchor Darling valves, and will comply with the Reference 2 recommended actions to address applicable GL 96-05 MOVs affected by the ADDDGV Part 21. The require*ments for each category of valves are in accordance with the BWROG simplified recommendations and schedule for Part 21 applicable MOVs. These include the following aspects:
Beaver Valley Power Station, Unit Nos. 1 and 2
- L-17-280 Page2
- Screening evaluation method for susceptible MOVs
- Wedge Pin Analysis
- Stem Rotation Check Methods
- Diagnostic Test I Evaluation Methods
- Valve Repair Methods
- Repair Schedule A brief explanation of the specific valve repair and test/inspection commitment scope as contained in Attachment 1 are as follows:
Category A - This group includes Susceptible High and Medium Risk GL 96-05 MOVs which have multiple open/close active safety function strokes. This group of valves will be repaired by the next refueling outage. For BVPS, there are no MOVs that meet this criteria.
Category B - This group includes Susceptible High or Medium Risk GL 96-05 MOVs which only stroke once, open or closed, to perform their safety function. This group of valves will either be repaired at the next refueling outage OR pass diagnostic tests and stem rotation checks during the next refueling outage with final repair within two refueling outages (as applicable). For BVPS, there is only one MOV at Unit 1 that meets this criteria.
- Plant Valve ID Beaver Valley Power Station, Unit 1 MOV-1 Sl-890C - Low Head Safety Injection to Reactor Coolant System Cold Legs This MOV functions as the Low Head Safety Injection to Reactor Coolant System (RCS) cold legs, which has an active safety function to close only. Diagnostic testing and stem rotation checks are planned for the next refueling outage 1R25, which is scheduled for the Spring of 2018. Permanent repairs will be performed within two (2) Refueling Outages [1 R26], which occurs in the Fall of 2019. This plan is in accordance with BWROG recommended actions.
Category C - This group includes Susceptible Low Risk GL 96-05 MOV. This group of valves will either be repaired at the next refueling outage OR pass diagnostic tests and stem rotation checks every refueling outage with final repair within three refueling outages (as applicable).
For BVPS, there are two MOVs at Unit 1 that meets this criteria.
Plant Valve ID Beaver Valley Power Station, Unit 1 MOV-1 Sl-890A Low Head Safety Injection to RCS Hot Legs Beaver Valley Power Station, Unit 1 MOV-1Sl-890B Low Head Safety Injection to RCS Hot Legs These MOVs function as the Low Head Safety Injection to RCS Hot Legs, which have an active safety function to open only. Diagnostic testing and stem rotation checks are planned for the next two (2) refueling outages: 1R25 (Spring) and 1R26 (Fall). Permanent repairs will be performed within three (3) Refueling Outages [1 R27], which is scheduled for the Spring of 2021.
This plan is in accordance with BWROG recommended. actions.
Beaver Valley Power Station, Unit Nos. 1 and 2 L-17-280 Page 3 Also in Reference 1, NEI states that susceptibility reviews and repair plans for safety related valves against the revised BWROG guidance (Reference 2) be communicated to the NRC by December 31, 2017. FENOC will provide this information including repair schedule commitments in a separate letter in accordance with the NEI Plan.
Commitments regarding the BVPS Unit No. 1 repairs and any other commitments that FENOC identifies by evaluating the revised BWROG guidance will be provided in the December 2017 response.
Should the NRC staff require additional information regarding this report, please do not hesitate to contact Stephen Hovanec, Manager Technical Services, at 724-682-7607. :
SUMMARY
OF REGULATORY COMMITMENTS cc: Mr. D. H. Dorman, NRG Region I Administrator Mr. J. A. Krafty, NRG Senior Resident Inspector Mrs. 8. Venkataraman, NRR Project Manager
Attachment 1 L-17-280
SUMMARY
OF REGULATORY COMMITMENTS The following table identifies commitments made in this submittal. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRC's information and are not regulatory commitments.)
COMMITTED DATE COMMITMENT "OUTAGE" MOV-1 Sl-890C - Low Head Safety Injection to 'Reactor Coolant System Cold Legs Refueling Outage (Year)
Perform diagnostic testing and stem rotation checks with 1R25 2018 contingent repairs every outage until repairs complete within two refueling outages (Category B)
Repair - MOV-1Sl-890C - Low Head Safety Injection to Refueling Reactor Coolant System Cold Legs Outage (Year) 1R26 2019 MOV-1 Sl-890A & 8908 - Low Head Safety Injection to Reactor Coolant System Hot Legs Refueling Outage (Year)
Perform diagnostic testing .and stem rotation checks with 1R25 2018 contingent repairs every outage until repairs complete 1R26 2019 within three refueling outages (Category C)
Repair- MOV-1Sl-890A & B - Low Head Safety Injection Refueling to Reactor Coolant System Hot Legs Outage (Year) 1R27 2021