ML20003F667
| ML20003F667 | |
| Person / Time | |
|---|---|
| Issue date: | 01/03/2020 |
| From: | Douglas Bollock, Kenneth Kolaczyk, Thomas Scarbrough NRC/NRR/DRO/IRIB |
| To: | |
| Bollock D, 415-6609, NRR/DRO | |
| References | |
| Download: ML20003F667 (22) | |
Text
Inspection Procedure 71111.21N Attachment 2 Power-Operated Valve Inspection Public Workshop Douglas Bollock, Kenneth Kolaczyk, Thomas G. Scarbrough, U.S. Nuclear Regulatory Commission January 9, 2020
POV Public Meeting Agenda
- Discuss why we are inspecting POVs
- Review of the POV inspection procedure requirements and guidance
- Overview of EQ inspection lessons learned
- Review questions we have received (FAQ)s
- Mock POV scenario discussion
- Question and answer period 2
Why Are We Inspecting POVs Now?
- Baseline inspection efforts do not examine all POV program attributes described in Generic Letter 96-05
- Operating experience indicates POV/MOV performance gaps still exist:
- Browns Ferry Unit 1, October 23, 2010, Stem Disc Separation
- LaSalle Station Unit 2, February 11, 2017, Wedge Pin and Stem Disc Separation 3
POV Procedure and Guidance 4
IP 71111.21N.02 Objective
- IP 71111.21.02 (July 26, 2019), Design-Basis Capability of Power-Operated Valves under 10 CFR 50.55a Requirements, specifies that the objective is to: assess the reliability, functional capability, and design basis of risk-important POVs as required by 10 CFR 50.55a and applicable 10 CFR Part 50, Appendix A and Appendix B.
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General Guidance Section 02.01 Sample Selection
- As a pre-inspection activity, inspectors will select 30 POVs:
- Multiple systems and different valve types (MOVs, AOVs, HOVs, SOVs, and Squib Valves (as applicable), sizes and manufacturers
- Risk assessment
- Historical performance
- The Inspectors will request the licensee to make available:
- Design-basis capability information including function, safety significance, sizing, margin, and setting assumptions
- See Appendix C to the POV inspection procedure 6
General Guidance Section 02.01 Sample Selection
- Based on POV design-basis capability information, the inspectors will consider the following for selection of a 10 POV sample for detailed inspection review:
- System Risk
- POVs with high incidence of corrective maintenance and/or poor performance
- POVs with low margin
- POVs with questionable assumptions (e.g., low VF, low friction values, not all uncertainties captured)
- POVs in untreated water systems
- POVs in high energy systems
- POVs located in elevated environments (e.g., high temperature, high radiation areas) 7
Inspection Preparation Activities
- Discuss inspection with site POV engineers and obtain information (such as POV capability calculations and assumptions)
- Evaluate POV parameter assumptions for potential issues
- Determine the basis of POV assumptions (such as EPRI, JOG, ComEd) and whether the conditions for each source are correctly applied 8
Typical Sample Gate Valve Data Sheet
- Valve ID SI-123
- Calc Th/Tq Close - 5685 lbs
- Safety Function - Open/Close
- Calc Th/Tq Open - 8250 lbs
- Manufacturer - Westinghouse
- Least Available - 8500 lbs
- Valve Type - Flex Wedge
- Th/Tq Dyn Close - 6200 lbs
- Valve Size - 4
- Th/Tq Dyn Open - 8700 lbs
- Actuator Make - Limitorque
- Meas Close VF - 0.5
- Actuator Size - SMB-000
- Meas Open VF - 0.47
- Risk - Medium
- Meas LSB - 9.5%
- DB Pressure C/O - 105 / 105
- Margin Close - 5%
- Assumed VF C/O - 0.3 / 0.3
- Margin Open - 3.2%
- Assumed LSB - 5%
- Basis - Extrapolated test &
- Assumed SFC - .12 revised calc 9
What Should Licensees Be Concerned With?
- For All Valves
- Assumed friction coefficient is less than bounding values (0.2 stem-to-stem nut friction for gate, globe and 0.6 bearing coefficient for bronze bearings on butterfly valve)
- As left valve settings near structural limits
- Misapplication of EPRI MOV PPM data and methodology
- Using EPRI MOV PPM test data to justify valve factor assumptions in valve capability calculations
- Using static testing as basis for monitoring valve degradation with no engineering analysis or data 10
Inspection Process Flow One month before On-site activities Three months before the inspection, the begin, valves the inspection team leader visits the analyzed and begins, the licensee site to coordinate the program assessed.
receives a data inspection and obtain Two weeks on site, request regarding 30 test data for 8-12 one week office valves review Issues reviewed by Exit meeting held, Report issuance- regional preliminary estimated 45 days management and observations and after exit meeting nationwide finding findings presented review panel 11
EQ Inspection Lessons Learned 12
EQ Inspection Takeaways
- EQ inspection procedure could have benefited from further background guidance
- Inspectors had difficulty interpreting each nuclear power units unique EQ licensing basis
- Communication between inspectors and NRR technical program office not consistent
- The minor, more than minor screening criteria contained in current NRC guidance was not as helpful in assessing specific EQ related issues 13
POV Inspection Enhancements
- Identified singular technical and programmatic points-of-contact within the NRC
- Minor/more-than-minor examples developed
- Enhanced training for inspectors was developed(both technical and inspection implementation focused)
- Enhanced Interactive SharePoint Site developed.
- Tabletop dry runs performed
- Findings review panel established proactively 14
- Q: What has been communicated to stakeholders?
- A: ROP monthly public meetings since May 2019
- POV inspections replacing EQ inspections beginning in January 2020
- NRC incorporated lessons learned from EQ inspection implementation 15
- Q: What is publicly available in regards to POV material?
- A: Publicly available now:
- Inspection Procedure IP71111.21N.02 (ML19067A240)
- MOV technical training (ADAMS Package: ML19235A1212020)
- EQ lessons learned (ML19183A063) 16
- Q: What is publicly available in regards to POV material?
- A: Public availability forthcoming:
- POV Inspection implementation training
- Minor/More-than-minor examples specific to POVs (as an appendix to the IP) 17
- Q: What are the NRC resources uses per POV inspection?
- A: 3 NRC inspectors, 2 weeks onsite
- 210 hrs (+/- 32 hrs)
- No use of contract inspectors planned 18
- Q: Will there be other public workshops?
- A: The NRC staff has now held two public workshops on POV inspections.
- Staff is open to more as needed and will consider any input received today.
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Scenario Discussions
- Scenario one:
- Service water/emergency service water isolation valve testing
- Scenario two:
- Block valve design assumptions 20
Q & A Session 21
For additional information, contact Doug Bollock Douglas.Bollock@nrc.gov Ken Kolaczyk Kenneth.Kolaczyk@nrc.gov Tom Scarbrough Thomas.Scarbrough@nrc.gov Mike Farnan Michael.Farnan@nrc.gov 22