CP-201200879, Relief Request No. V-1 for Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 2004 Edition, Through 2006 Addenda; Third Interval Start Date: August 3, 2013)

Relief Request No. V-1 for Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 2004 Edition, Through 2006 Addenda; Third Interval Start Date: August 3, 2013)

ML12263A351
Person / Time
Site:	Comanche Peak
Issue date:	09/06/2012
From:	Flores R, Madden F Luminant Generation Co, Luminant Power
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-201200879, TXX-12116
Download: ML12263A351 (14)

Text

Rafael Flores Luminant Power u

Luminant Senior Vice President

& Chief Nuclear Officer Rafael.Flores@Luminant.com P 0 Box 1002 6322 North FM 56 Glen Rose, TX 76043 T 254 897 5550 C 817 559 0403 F 254 897 6652 CP-201200879 Ref. # 10CFR50.55a(a)(3)(i)

TXX-12116 September 6, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NOS. 50-445 AND 50-446 RELIEF REQUEST NO. V-1 FOR UNIT 1 AND UNIT 2 INSERVICE TESTING PLAN FOR PUMPS AND VALVES (ASME OM CODE 2004 EDITION, THROUGH 2006 ADDENDA; THIRD INTERVAL START DATE: AUGUST 3,2013)

REFERENCES:

1. Letter logged TXX-98153 dated June .24, 1998 from C. Lance Terry to the NRC submitting Relief Request No. V-8, Revision 2, for the Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1989 Edition, No Addenda; Unit I Interval Start Date: August 13, 1990, First Interval; Unit 2 Interval Start Date:

August 3, 1993, First Interval).

2. NRC Letter dated August 14, 1998, from John N. Hannon to C. Lance Terry concerning Approval of Risk-Informed Inservice Testing (RI-IST) Program for Comanche Peak Steam Electric Station, Units 1 and 2 (TAC Nos. M94165, M94166, MA19722 and MA1973)

Dear Sir or Madam:

Luminant Generation Company LLC (Luminant Power) requests relief from ASME OM Code 2004 Edition, through 2006 Addenda, for the testing of the motor-operated valves at Comanche Peak Nuclear Power Plant (CPNPP) pursuant to 10CFR50.55a(a)(3)(i) for the third interval of the CPNPP Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves.

Luminant Power had previously submitted this relief request via Reference 1 and it had been approved by the NRC via Reference 2.

This communication contains no new commitment regarding Comanche Peak Units 1 and 2.

Should you have any questions, please contact Mr. Jack Hicks at (254) 897-6725.

A member of the STARS Alliance Callaway

• Comanche Peak

• Diablo Canyon Palo Verde

• San Onofre - South Texas Project

• Wolf Creek

U. S. Nuclear Regulatory Commission TXX-12116 Page 2 of 2 09/06/2012 Sincerely, Luminant Generation Company LLC Rafael Flores By: Z A .

Director, Oversight & Regulatory Affairs Attachment- Relief Request V-1 (Third Interval Start Date: August 3, 2013) c- E. E. Collins, Region IV Luis Ponce B. K. Singal, NRR Texas Department of Licensing and Regulation Resident Inspectors, Comanche Peak P. 0. Box 12157 Jack Ballard, ANII, Comanche Peak Austin, Texas 78711-2332

Attachment to TXX-12116 Page 1 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

1. ASME Code Component(s) Affected See attached table.

2. Applicable Code Edition and Addenda

The applicable code edition is the ASME OM Code, 2004 Edition through 2006 Addenda.

3. Applicable Code Requirements ISTC-5120, Motor-Operated Valves, ISTC-5121(a) states: "Active valves shall have their stroke times measured when exercised in accordance with ISTC-3500."

ISTC-3700, Position Verification Testing, states in part: "Valves with remote position indicators shall be observed locally at least once every 2 years to verify that valve operation is accurately indicated."

ISTC-3510, Exercising Test Frequency, states: "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months, except as provided by ISTC-3520, ISTC-3540, ISTC-3550, ISTC-3560, ISTC-5221, and ISTC-5222. Power-operated relief valves shall be exercise tested once per fuel cycle."

4. Reason for Request 10CFR50.55a(a)(3)(i)

NUREG-1482, Rev. 1, Section 4.2.5 states in part: As an alternative to MOV stroke-time testing, ASME developed Code Case OMN-1 Revision 0, "Alternative Rules for Preservice and lnservice Testing of Certain E16ctric Motor-Operated Valve Assemblies in LWR Power Plants" which provides periodic exercising and diagnostic testing for use in assessing the operational readiness of MOVs.

NUREG-1482, Revision 1, Section 4.2.5 recommends that the licensees implement ASME Code Case OMN-1 Revision 0 as accepted by the NRC (with certain conditions) in the regulations or Regulatory Guide (RG) 1.192, as an alternative to the stroke-time testing provisions in the ASME Code for MOVs. RG 1.192 allows licensees to implement ASME Code Case OMN-1, Revision 0, (in accordance with the provisions in the RG) as an alternative to the Code provisions for MOV stroke time testing in the ASME OM Code 1995 Edition through 2000 Addenda.

The Code of Record for Comanche Peak Nuclear Power Plant (CPNPP) Third 10-Year IST Interval is ASME OM Code 2004 Edition with Addenda through 2006 Addenda.

Note: OMN-1 Revision 0, was previously approved for use at CPNPP by the NRC, Refer to NRC Letter dated August 14, 1998 from Mr. John N. Hannon to Mr. C. Lance Terry, Technical Assignment Control (TAC) Nos. M94165, M94166, MA1972, and MA1973.

Attachment to TXX-12116 Page 2 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

5. Proposed Alternative and Basis for Use Pursuant to the guidelines provided in NUREG-1482, Rev. 1, Section 4.2.5, and the conditions stated in RG 1.192, CPNPP proposes to implement Code Case OMN-1 Revision 1, in lieu of the stroke-time provisions specified in ISTC-5120 for MOVs as well as the position verification testing in ISTC-3700.

There are no significant differences between the versions of Code Case OMN-1 that is in the 1999 Addenda of the OM Code currently approved for use in RG 1.192, Revision 0 and the Revision 1 of the Code Case (OMN-1-1) in 2009 Edition of the OM Code.

The use of Code Case OMN-1 Revision 1 by a licensee permits licensees to replace stroke time and position verification testing of MOVs with a program of exercising MOVs every refueling cycle and diagnostically testing on longer intervals.

The proposed alternative is considered to be acceptable because Code Case OMN-1 Revision 1 provides a superior method than the stroke-timing method required by the OM code for assessing the operational readiness of MOVs.

Using the provisions of this relief request as an alternative to the MOV stroke time testing requirements of ISTC-5120 and position indication verification of ISTC-3700 provide an acceptable level of quality for determination of valve operational readiness. Code Case OMN-1 Revision 1 should be considered acceptable for use with ASME OM Code 2004 Edition through 2006 Addenda as the Code of Record.

There are recognized weaknesses in the stroke-time testing requirements for MOVs in the OM Code and the use of Code Case OMN-1 Revision 1 by a licensee resolves the weaknesses. Code Case OMN-1 Revision I permits licensees to replace stroke time and position verification testing of MOVs with a program of exercising MOVs every refueling cycle and diagnostically testing on longer intervals.

Luminant Power believes that the proposed alternative to be acceptable because Code Case OMN-1 Revision 1 provides a superior method than the stoke-timing method required by the OM Code for assessing the operational readiness of MOVs. The NRC staff has recommended that licensees implement Code Case OMN-1 as an alternative to the MOV stroke-time and position verification testing provisions in the ASME Code. The NRC has also found that there are no significant differences between the version of Code Case OMN-1 that is in the 1999 Addenda of the OM Code currently approved for use in RG 1.192 and the version of Code Case OMN-1 in the 2004 Edition of the OM Code. [Reference ADAMS Accession No. ML102150077.]

However, Luminant Power intends to maintain the following exceptions which were addressed in the original submission of the relief request for OMN-1 Revision 0 to the requirements in ASME Code Case OMN-1 as described below:

1) Paragraph 3.3.1, items (a) & (b) - The initial inservice test frequency for each MOV shall be determined based upon the MOV's risk significance category (i.e. High or Low) and magnitude of margin. See Figure 1 for initial inservice test frequency details. The inservice test frequency may change when sufficient test data has been collected and

Attachment to TXX-12116 Page 3 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013) analyzed to determine a more appropriate test frequency. No test frequency shall exceed 10 years.

2) Paragraph 6.4.3 - In order to maintain consistency and compatibility with the Joint Owners Group (JOG) MOV Periodic Verification Program, "Functional Margin" will be redefined to agree with the definition of "Margin" as detailed in Topical Report MPR-1807 (Reference 2). The terms "Functional Margin" and "Margin" shall be synonymous within the CPNPP MOV Periodic verification program.

"Margin", as defined in Reference 2, is dependent upon "Required Thrust." At CPNPP "Required Thrust" for rising stem MOVs has been determined from stem thrust measurements taken during extensive baseline testing performed in response to GL 89-10 under both static and dynamic test conditions. Valve factors have been determined by statistical means for each group of rising stem MOVs; these factors will be reviewed/verified as new data is obtained from CPNPP testing and results are received from the JOG Periodic Verification Program."

6. Duration of Proposed Alternative This proposed alternative will be utilized for the third ten-year interval of the CPNPP Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (August 3, 2013 through August 2, 2023).

7. References

1) NRC Letter dated August 14, 1998 from Mr. John N. Hannon to Mr. C. Lance Terry, Technical Assignment Control (TAC) NOS. M94165, M94166, MA1972, and MA1973.

2) Joint BWR, Westinghouse and Combustion Engineering Owners' Group Program on Periodic Verification on Motor-Operated Valves (MOV) Periodic Verification, Topical Report MPR-1807, Revision 2, July 1997

8. Precedents

1) NRC Letter to Mr. Edward D. Halpin from Mr. Michael T. Markley dated September 2, 2010.

Subject:

"South Texas Project, Units I and 2 -Relief Request Nos., VRR-01, PRR-01, PRR-02, AND PRR-03 for the Third 10-year Inservice Testing Program Interval (TAC NOS. ME3515, ME3516, ME3517, ME3518, ME3519, ME3520, ME3521, AND ME3522)." [ADAMS Accession No. ML102150077]

Attachment to TXX-12116 Page 4 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

System Valve Number Category Code Description Class Auxiliary Feedwater HV-2480 B 3 Aux feedwater Pump Emergency Supply Flowpath HV-2481 B 3 Aux feedwater Pump Emergency Supply Flowpath HV-2482 B 3 Aux feedwater Pump Emergency Supply Flowpath HV-2484 B 3 Condensate System to Condensate Storage Tank Isolation to Preclude Tank Overpressurization HV-2485 B 3 Condensate System to Condensate Storage Tank Isolation to Preclude Tank Overpressurization HV-2491A B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2491B B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2492A B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2492B B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2493A B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2493B B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2494A B 2 Containment Isolation & AFW to Faulted SG Flow Isolation HV-2494B B 2 Containment Isolation & AFW to Faulted SG Flow Isolation Component Cooling Water HV-4512 B 3 Train A to Train B Crosstie Isolation HV-4513 B 3 Train A to Train B Crosstie Isolation

Attachment to TXX-12116 Page 5 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

System Valve Number Category Code Description I_ _Class

__ I HV-4514 B 3 Train A to Train B Crosstie Isolation HV-4515 B 3 Train A to Train B Crosstie Isolation HV-4524 B 3 Non-Safety Loop Flowpath Isolation HV-4525 B 3 Non-Safety Loop Flowpath Isolation HV-4526 B 3 Non-Safety Loop Flowpath Isolation HV-4527 B 3 Non-Safety Loop Flowpath Isolation HV-4572 B 3 -RHRHeat Exchanger Cooling Flowpath HV-4573 B 3 RHR Heat Exchanger Cooling Flowpath HV-4574 B 3 Containment Spray Heat Exchanger Cooling Flowpath HV-4575 B 3 Containment Spray Heat Exchanger Cooling Flowpath HV-4696 A 2 Containment Isolation & RCP Thermal Barrier Rupture Isolation HV-4699 B 2 Passive Pipe Break Isolation (Inside Containment)

HV-4700 A 2 Containment Isolation & Passive Pipe Break Isolation (Inside Containment)

HV-4701 A 2 Containment Isolation HV-4708 A 2 Containment Isolation HV-4709 A 2 Containment Isolation & RCP Thermal Barrier Rupture Isolation

.1. I. I I

Attachment to TXX-12116 Page 6 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

System Valve Number Category Code Description Class Chemical & Volume Control LCV-0112B B 2 ECCS Flowpath Boundary & Isolation of VCT Cover Gas from Charging Pumps' Suction Header (upon low VCT level) & Boron Dilution Flowpath Isolation LCV-0112C B 2 ECCS Flowpath Boundary & Isolation of VCT Cover Gas from Charging Pumps' Suction Header (upon low VCT level) & Boron Dilution Flowpath Isolation LCV-0112D B 2 ECCS Injection Flowpath & Boration Flowpath/ECCS Recirculation Flowpath Boundary LCV-0112E B 2 ECCS Injection Flowpath & Boration Flowpath/ECCS Recirculation Flowpath Boundary 8100 A 2 Containment Isolation 8104 B 2 Boration Flowpath 8105 A 2 Boration Flowpath/ECCS Flowpath Boundary & Containment Isolation 8106 B 2 Boration Flowpath/ECCS Flowpath Boundary 8109 B 2 ECCS Flowpath Boundary 8110 B 2 ECCS Flowpath Boundary 8111 B 2 ECCS Flowpath Boundary 8112 A 2 Containment Isolation 8351A B 2 Containment Isolation 8351B B 2 Containment Isolation 8351B B 2 Containment Isolation

Attachment to TXX-12116 Page 7 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

System Valve Number Category Code Description Class 8351C B 2 Containment Isolation 8351D B 2 Containment Isolation 8511A B 2 High Head Safety Injection Pump Miniflow Path/ECCS Recirculation Flowpath Boundary 8511B B 2 High Head Safety Injection Pump Miniflow Path/ECCS Recirculation Flowpath Boundary 8512A B 2 ECCS Recirculation Flowpath Boundary 8512B B 2 ECCS Recirculation Flowpath Boundary Containment Spray LV-4754 B 3 Chemical Additive Flowpath/Chemical Additive Tank Isolation LV-4755 B 3 Chemical Additive Flowpath/Chemical Additive Tank Isolation HV-4758 B 2 Sump Recirculation Flowpath Boundary HV-4759 B 2 Sump Recirculation Flowpath Boundary FV-4772-1 B 2 Pump Miniflow Flowpath/Containment Spray Flowpath Boundary FV-4772-2 B 2 Pump Miniflow Flowpath/Containment Spray Flowpath Boundary FV-4773-1 B 2 Pump Miniflow Flowpath/Containment Spray Flowpath Boundary FV-4773-2 B 2 Pump Miniflow Flowpath/Containment Spray Flowpath Boundary HV-4776 A 2 Containment Spray Flowpath/Containment Isolation HV-4777 A 2 Containment Spray Flowpath/Containment Isolation

Attachment to TXX-12116 Page 8 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

System Valve Number Category Code Description Class HV-4782 B 2 Sump Recirculation Flowpath/Containment Isolation HV-4783 B 2 Sump Recirculation Flowpath/Containment Isolation Reactor Coolant 8000A B 1 Post Accident Vent Path/Vent Path Isolation & Reactor Coolant Pressure Boundary 8000B B 1 Post Accident Vent Path/Vent Path Isolation & Reactor Coolant Pressure Boundary Residual Heat Removal FCV-0610 B 2 Pump Miniflow Path/ECCS & RHR Flowpath Boundary FCV-0611 B 2 Pump Miniflow Path/ECCS & RHR Flowpath Boundary 8701A A 1 RHR Flowpath/Containment Isolation & Reactor Coolant Pressure Boundary 8701B A 1 RHR Flowpath/Containment Isolation & Reactor Coolant Pressure Boundary 8702A A 1 RHR Flowpath/Reactor Coolant Pressure Boundary 8702B A 1 RHR Flowpath/Reactor Coolant Pressure Boundary 8716A B 2 ECCS Injection Flowpath/ECCS Recirculation Flowpath Boundary 8716B B 2 ECCS Injection Flowpath/ECCS Recirculation Flowpath Boundary Safety Injection 8801A B 2 ECCS to Cold Legs Flowpath & Boration Flowpath/ Containment Isolation &

Passive Pipe Break Isolation 8801B B 2 ECCS to Cold Legs Flowpath & Boration Flowpath/ Containment Isolation &

Passive Pipe Break Isolation

Attachment to TXX-12116 Page 9 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

System Valve Number Category Code Description I_ I_ [Class I I 8802A B 2 ECCS to Hot Legs Flowpath/ECCS to Cold Legs Flowpath Boundary &

Containment Isolation & Passive Pipe Break Isolation 8802B B 2 ECCS to Hot Legs Flowpath/ECCS to Cold Legs Flowpath Boundary &

Containment Isolation & Passive Pipe Break Isolation 8804A B 2 ECCS Recirculation Flowpath/Passive Pipe Break Isolation 8804B B 2 ECCS Recirculation Flowpath/Passive Pipe Break Isolation 8806 B 2 ECCS Flowpath Boundary (during Recirculation) 8807A B 2 ECCS Recirculation Flowpath/Passive Pipe Break Isolation 8807B B 2 ECCS Recirculation Flowpath/Passive Pipe Break Isolation 8808A B 2 ECCS from Accumulators to Cold Legs Flowpath 8808B B 2 ECCS from Accumulators to Cold Legs Flowpath 8808C B 2 ECCS from Accumulators to Cold Legs Flowpath 8808D B 2 ECCS from Accumulators to Cold Legs Flowpath 8809A A 2 ECCS to Cold Legs Flowpath/ECCS to Hot Legs Flowpath Boundary & Passive Pipe Break Isolation & Containment Isolation 8809B A 2 ECCS to Cold Legs Flowpath/ECCS to Hot Legs Flowpath Boundary & Passive Pipe Break Isolation & Containment Isolation 8811A B 2 ECCS Recirculation Flowpath/Containment Isolation & Passive Pipe Break Isolation

Attachment to TXX-12116 Page 10 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

System Valve Number Category Code Description Class 8811B B 2 ECCS Recirculation Flowpath/Containment Isolation & Passive Pipe Break Isolation 8812A B 2 ECCS Recirculation Flowpath Boundary & Shutdown Cooling Flowpath Boundary (during Safety Grade Cold Shutdown) 8812B B 2 ECCS Recirculation Flowpath Boundary & Shutdown Cooling Flowpath Boundary (during Safety Grade Cold Shutdown) 8813 B 2 ECCS Recirculation Flowpath Boundary 8814A B 2 ECCS Recirculation Flowpath Boundary 8814B B 2 ECCS Recirculation Flowpath Boundary 8821A B 2 ECCS to Cold Legs Flowpath/ECCS to Hot Legs Flowpath Boundary & Passive Pipe Break Isolation 8821B B 2 ECCS to Cold Legs Flowpath/ECCS to Hot Legs Flowpath Boundary & Passive Pipe Break Isolation Safety Injection 8835 B 2 ECCS to Cold Legs Flowpath/ECCS to Hot Legs Flowpath Boundary &

Containment Isolation & Passive Pipe Break Isolation 8840 A 2 ECCS to Hot Legs Flowpath/ECCS to Cold Legs Flowpath Boundary &

Containment Isolation & Passive Pipe Break Isolation 8923A B 2 Passive Pipe Break Isolation 8923B B 2 Passive Pipe Break Isolation 8924 B 2 Passive Pipe Break Isolation

Attachment to TXX-12116 Page 11 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE IiNSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

System Valve Number Category Code Description Class Service Water HV-4286 B 3 Service Water Flowpath/Throttling during Pump Start HV-4287 B 3 Service Water Flowpath/Throttling during Pump Start HV-4393 B 3 Service Water Flowpath HV-4394 B 3 Service Water Flowpath HV-4395 B 3 AFW Pump Emergency Supply Flowpath HV-4396 B 3 AFW Pump Emergency Supply Flowpath Containment Isolation HV-6082 A 2 Containment Isolation HV-6083 A 2 Containment Isolation HV-6084 A 2 Containment Isolation HV-4075B A 2 Containment Isolation HV-4075C A 2 Containment Isolation HV-5540 A 2 Containment Isolation HV-5541 A 2 Containment Isolation HV-5542 A 2 Containment Isolation Containment Isolation HV-5543 A 2 Containment Isolation HV-5562 A 2 Containment Isolation HV-5563 A 2 Containment Isolation

Attachment to TXX-12116 Page 12 of 12 COMANCHE PEAK NUCLEAR POWER PLANT UNITS 1 AND 2 ASME OM CODE INSERVICE TESTING PROGRAM RELIEF REQUEST V-1 (THIRD INTERVAL START DATE: AUGUST 3,2013)

LEGEND: Category A = Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their required safety function(s).

Category B = Valves for which seat leakage in the closed position is inconsequential for fulfillment of their required safety function(s).

Class = Code Class Figure 1 Inservice Test Frequency R MARGIN I Low Medium High S High 1 cycle 2 cycles 3 cycles K Low 2 cycles 4 cycles 6 cycles*

• Not to exceed 10 years Notes:

1. Criteria for MOV Margin Categories Low Margin: <10%

Medium Margin: >10% and <15%

High Margin: >15%

2. Criteria for Risk Categories High Risk: Risk-Informed IST Program Low Risk: Risk-Informed IST Program