current air-operated valve regulatory activities steven unikewicz us nuclear regulatory commission...

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Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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Page 1: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

Current Air-Operated Valve Regulatory Activities

Steven UnikewiczUS Nuclear Regulatory CommissionOffice of Nuclear Reactor Regulation

January 2006

Page 2: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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Topics

• Current Regulations / Guidance

• NRC Reg Guide 1.192

• Risk Informed IST

• 10 CFR 50.69

• Recent Events/Current Topics

• Other AOV related Regulatory Activities

Page 3: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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Current Regulations / Guidance

• ASME OM Code of record: 10 CFR 50.55a(b)(2)– 2001 Edition through the 2003 Addenda– 2004 Edition endorsement expected Jan/Feb 2006– Scope defined in ISTA 1100

• Use of ASME Code defined in 10 CFR 50.55a(f)– ASME Code Class components or equivalent

• NUREG 1482 Guidelines for Inservice Testing– Revision 1 incorporates guidance to date and ASME 2000A Edition– Revision 0 still valid for 1995 and earlier Editions

Page 4: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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NRC Reg Guide 1.192

• ASME OM Code Case Acceptability issued March 2003

• Conditions placed on certain Code Cases

• Licensees may use approved OM Code Cases provided all conditions listed in Code Case and Reg Guide are met

• Risk Informed IST Code Cases- Code Case OMN-3- Code Case OMN-12

Page 5: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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OMN 3Requirements for Safety Significance Categorization of

Components using Risk Insights for Inservice Testing

• RI component Code Cases use OMN 3 to catagorize HSS and LSS components

• Four (4) conditions proposed on use of OMN 3– Condition 1: Program must include non-ASME

components categorized as HSSC that may not be in current IST program

– Condition 2: Decision Criteria must be consistent with Reg Guide 1.174

Page 6: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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OMN 3

• - Condition 3: Defense in Depth and Safety Margin evaluations must be consistent with Reg Guide 1.175

• - Condition 4: Implementation of Inservice Testing Program and Performance Monitoring must be consistent with Reg Guide 1.175 and OMNs 1, 4, 7 and 12

Page 7: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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OMN 12Alternative Requirements for IST using Risk Insights for

Pneumatically and Hydraulically Operated Valves

• New AOV/HOV test strategy coupled with risk-informed categorization

• Used in conjunction with Code Case OMN-3

• NRC conditions ensure technical philosophy consistent with Code Case OMN-1 (MOV Code Case)

Page 8: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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OMN 12Alternative Requirements for IST using Risk Insights for

Pneumatically and Hydraulically Operated Valves

• Eight (8) NRC Conditions on use of OMN-12– (1) Include a mix of static and dynamic testing which

may be altered when justified by evaluation of test data

– (2) Evaluate adequacy of diagnostic test interval which shall not exceed 5 years or 3 RO

– (3) Evaluate potential increase in CDF and risk of interval extension to ensure small and consistent with NRC Regulatory Guide 1.174 and 1.175 criteria

– (4) Degradation rate and capability margin evaluated to ensure AOV/HOV capable of performing design basis functions until next test

Page 9: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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OMN 12Alternative Requirements for IST using Risk Insights for

Pneumatically and Hydraulically Operated Valves

- (5) Capable of performing design basis function until next test

- (6) Setpoints based on direct dynamic test information, test based methodology, or grouping with dynamically tested valves

- (7) Initial and periodic diagnostic testing to verify setpoints

- (8) Evaluate operability of AOV/HOV if valve does not satisfy acceptance criteria

Page 10: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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Reg Guide 1.175 Risk Informed IST

• Same as current IST Program Scope except: Must include Non-ASME Code AOVs / HOVs categorized as high safety significant (HSS)

• AOVs / HOVs that are not within the scope of the Code but AOV / HOV program identified

- Non ASME Code low safety significant (LSS) AOVs / HOVs

- Non-ASME Code LSS Dampers

• Consider comprehensive activities for related Non-ASME Code HSS Components (eg. Dampers)- March 27, 2000 SONGS SE (Adams ML003695622)

Page 11: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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10 CFR 50.69• NRC prepared 10 CFR 50.69 to risk-inform regulations for treatment of

structures, systems, and components (SSCs), including MOVs.

• 10 CFR 50.69 categorizes SSCs based on safety significance, and specifies treatment that is intended to provide appropriate confidence in design capability.

• To provide reasonable confidence that low-risk safety‑related SSCs can perform their design‑basis functions, proposed 10 CFR 50.69 replaces special treatment requirements with high-level requirements for

• (1) design control; • (2) procurement; • (3) maintenance, inspection, testing, and surveillance; and • (4) corrective action.

Page 12: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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Recent Events/Current Topics

• It is expected that Sites have fully implemented their AOV JOG Programs- RIS 2000-003 Performance of Safety-Related POV’s Under Design Basis Conditions

• Recent Inspections have identified lack of Design Basis information at various sites - Air Accumulator Sizing

- Underestimation of Thrust

Page 13: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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Recent Events/Current Topics

• Failures of valve plugs and loosening of valve parts due to vibration

• Extended Power Uprates– Replacement of manual valves with AOVs– Follow JOG or QME or prototype testing– Stating manufacture’s experience is not enough

• Testing – mix of Static / Dynamic techniques

Page 14: Current Air-Operated Valve Regulatory Activities Steven Unikewicz US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation January 2006

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Other AOV related Regulatory Activities

• Continued participation with ASME OM 19, Sub-group on Air Operated Valves – next meeting July 19, 2006 after the ASME/NRC Pump and Valve Symposium

• Continued participation with ASME OM Code, Sub-section ISTE, Risk Informed Inservice Testing

• Ninth ASME/NRC Pump and Valve Symposium, July 17 thru 19, 2006, at L’Enfant Plaza Hotel in Washington, DC see www.asmeconferences.org/nrcasme9 for more details