ML18192A240

2018-7-19 ROP Public Meeting Handout - Draft IP7111122

ML18192A240
Person / Time
Issue date:	07/12/2018
From:	Aron Lewin NRC/NRR/DIRS/IRIB
To:
Lewin A, NRR/DIRS, 415-2259
References
IP7111122
Download: ML18192A240 (18)

Text

DRAFT NRC INSPECTION MANUAL IRIB INSPECTION PROCEDURE 71111 ATTACHMENT 22 SURVEILLANCE TESTING Effective Date: January 1, 2019 PROGRAM APPLICABILITY: IMC 2515 Appendix A INSPECTABLE AREA: Surveillance Testing CORNERSTONES: Mitigating Systems Barrier Integrity INSPECTION BASES: See IMC 0308 Attachment 2 Inspection activities in this area focus on evaluating the licensees surveillance testing (including inservice testing) activities and their effectiveness in demonstrating that safety systems are capable of performing their intended safety function consistent with their design and licensing bases. Failure to identify and resolve performance degradation of structures, systems and components, could result in long periods of unknown equipment unavailability. This inspectable area verifies aspects of the associated cornerstones not measured by performance indicators.

EFFECTIVE DATE: July 1, 2015 LEVEL OF EFFORT: Review 14 to 22 surveillance tests per year regardless of the number of reactor units at the site.

Reviews of surveillance tests associated with a modification of the surveillance frequency in accordance with the Risk Management Technical Specification Initiative 5b Surveillance Frequency Control Program are expected to utilize a greater amount of resource hours.

If any reviews in this area are conducted, it is expected that the total level of effort will be closer to the minimum sample size.

See IMC 2515 and IMC 2515 Appendix A for further guidance on deviating from this sample size and on sample selection.

Issue Date: 1 71111.22

DRAFT SAMPLE REQUIREMENTS Sample Requirements Minimum Baseline Completion Budgeted Range Sample Requirements Sample Type Section Frequency Sample Size Samples Hours Surveillance Tests 10 (size may be (other) lower depending 03.01 Annual on applicability of sample types)

Inservice Testing 03.01 Annual 3 Containment Annual (if 14 to 22 tests 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> per Isolation Valve 03.01 1 applicable) per site site Testing Ice Condenser Annual (if 03.01 1 Testing applicable)

RCS Leakage Annual (if 03.01 1 Detection Testing applicable)

FLEX Testing 03.02 Annual 1 71111.22-01 INSPECTION OBJECTIVE 01.01 This inspection will focus on verifying Verify that surveillance testing (including inservice testing) activities provide objective evidence that risk- or safety-significant structures, systems, and components (SSCs) remain capable of performing their intended safety functions and maintain their operational readiness consistent with their design and licensing bases (i.e., will operate within safety limits and limiting conditions for operation will be met.)

01.02 Verify that testing activities provide objective evidence that FLEX SSCs remain capable of performing their intended functions and maintain their operational readiness consistent with their licensing bases.

71111.22-02 GENERAL INSPECTION GUIDANCE Issue Date: 2 71111.22

DRAFT Once or twice a year, inspectors should consider conducting a vertical slice review of work activities on safety-significant systems to assess whether different aspects of the licensees processes work effectively together, e.g., Maintenance, Operations, Risk Management, Scheduling, etc. For a given evolution, a vertical slice review could involve performing (in conjunction with IP 71111.22, as applicable) an associated sample in IP 71111.04, Equipment Alignment, IP 71111.12, Maintenance Effectiveness, IP 71111.13, Maintenance Risk Assessments and Emergent Work Control, IP 71111.18, Plant Modifications, IP 71111.19, Post-Maintenance Testing, and IP 71152, Problem Identification & Resolution.

The following table outlines additional inspection guidance for selecting risk- or safety-significant systems.

Cornerstone Inspection Objective Risk Priority Example Mitigating Systems Identify any Focus in areas with Integrated mitigating system, potential for common safeguards testing credited by the mode failures.

licensee as operable Emergency diesel when assessing risk, Select surveillance start/load testing which is adversely tests which cross impacted by technical disciplines Battery performance surveillance testing (electrical, testing related failures such mechanical, I&C) as failure to Reactor protection, adequately test, IST of pumps and RCS leakage failure to meet test valves that perform detection, and safety criteria or, failure to important functions in injection realign equipment mitigating systems.1 instrumentation after the surveillance. testing Safety bus loss of voltage and degraded voltage relay testing Pumps that provide injection water flow and valves that change position to provide injection water flow to the reactor coolant system.

Issue Date: 3 71111.22

DRAFT Cornerstone Inspection Objective Risk Priority Example Barrier Integrity Identify any Containment containment integrity isolation valve supporting system, testing, credited by the ventilation/filtration licensee as operable system testing when assessing risk, which is adversely impacted by surveillance test failures such as failure to adequately test, failure to meet test criteria or failure to realign equipment after the test.

1. For additional guidance on IST inspection refer to IP 73756, In-service Testing of Pumps and Valves and NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants.

Consider selection of the IST activity based on the component or system performance history (known deficiencies), or if the component or system had recently undergone corrective or preventive maintenance.

Include observation of surveillance testing activities of at least one containment isolation valve(s) each refueling cycle as part of the inspection sample. Also, for ice condenser containment design sites, select one or two ice condenser system surveillances to observe during each refueling outage as part of the inspection sample.

In addition, if the Reactor Coolant System (RCS) is being monitored by the licensee due to performance degradation (i.e., increasing leakage), include RCS leakage detection surveillance testing as part of the inspection sample (See Section 02.02b.14).

During plant outages, sample selection must should focus on infrequent surveillance tests, and particularly large-scale actuation tests and full-flow ESF pump testing, as well as inspections of normally inaccessible SSCs (e.g., containment sump inspections, RWST or CST internal inspections).

As part of the sample, consider reviewing surveillance tests in which there was a modification of the surveillance frequency in accordance with the Risk Management Technical Specification Initiative 5b Surveillance Frequency Control Program.

After Fukushima, the NRC ordered every U.S. commercial reactor to have mitigation strategies for dealing with the long-term loss of normal safety systems following the occurrence of a beyond-design-basis external event (NRC Order EA-12-049, ML12054A735). Given the defense-in-depth Issue Date: 4 71111.22

DRAFT nature FLEX, it is possible that FLEX SSCs may not be considered risk- or safety-significant at a site. However, FLEX increases defense-in-depth for beyond-design-basis scenarios to address loss of power and loss of the ultimate heat sink occurring simultaneously at all units on a site. As a result, as a minimum, one inspection sample a year is associated with FLEX testing.

Implementation guidance for FLEX is found in Nuclear Energy Institute (NEI) 12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, and endorsed via Japan Lessons Learned Project Directorate Interim Staff Guidance (JLD-ISG) 2012-01, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events. Various revisions are in effect. NEI 12-06, Revision 0 (ML12242A378) is endorsed via JLD-ISG 2012-01, Revision 0 (ML12229A174).

NEI 12-06, Revision 2 (ML15348A015) is endorsed via JLD-ISG 2012-01, Revision 1 (ML15357A163). NEI 12-06, Revision 4 (ML16354B421) is endorsed via JLD-ISG 2012-01, Revision 2 (ML17005A188). It should be noted that not all revisions of NEI 12-06 are endorsed.

Verification of activities under this procedure should focus on performance-based field observations of complete surveillance / testing evolutions, followed by verification of the bases and of the proper demonstration of performance that supports operability / functionality determinations.

71111.22-03 INSPECTION SAMPLES REQUIREMENTS 03.01 Surveillance Testing Verify by witnessing surveillance tests and/or reviewing the test data, that surveillance testing activities and results provide objective evidence that the affected SSCs remain capable of performing their intended safety functions (under conditions as close as practical to design bases conditions or as required by Technical Specifications) and maintain their operational readiness consistent with the facilitys current licensing basis.

IMC 2515 emphasizes observing plant activities over reviewing procedures and records.

Specific Guidance Significant surveillance test attributes for consideration include the following:

1. Effect of testing on plant operations has been adequately addressed by licensee (control room and/or engineering) personnel.

2. Preconditioning of SSCs prior to or post-testing. Unacceptable preconditioning is defined as the alteration; variation; manipulation; or adjustment of the physical condition of a SSC before or during TS surveillance or ASME Code testing such that that it will alter one or more of SSCs operational parameters, which results in acceptable test results. Such changes could mask the actual as-found condition of Issue Date: 5 71111.22

DRAFT the SSC and possibly result in an inability to verify the operability of the SSC. In addition, preconditioning could make it difficult to determine whether the SSC would perform its intended function during an design basis event in which the SSC might be needed (See Part 9900, Technical Guidance, Maintenance - Preconditioning of Structures, Systems, and Components Before Determining Operability, for additional guidance).

3. Acceptance criteria are clearly derived from the supporting technical bases (design bases, setpoint calculations, UFSAR, Technical Specification Bases, etc.) and demonstrate operational readiness consistent with the facilitys current licensing basis.

4. Measuring and test equipment (M&TE) specified in procedures are part of the measuring and test equipment program, their calibration status is within acceptable limits, and their range and accuracy are consistent with the application as supported by design bases documents. Plant equipment calibration is correct, accurate, properly documented and the calibration frequency is in accordance with TS, UFSAR, licensee procedures and commitments.

5. Test is performed in sequence and in accordance with written procedure.

6. Jumpers installed or leads lifted during testing are properly controlled.

7. Electrical connections are properly torqued, secure, and maintain their intended design function.

8. For cases where the licensee relies on multiple surveillance tests to satisfy a surveillance requirement, the affected surveillance test procedures collectively accomplish the entire scope of the surveillance requirement.

9. Setpoints, required test accuracy, test frequency, and allowable setpoint drift for selected safety-related instrumentation and control surveillance tests (i.e., RPS, NIs, etc.) conform to applicable setpoint calculations. Reference setpoint data has been accurately incorporated into the applicable test procedure(s).

10. Annunciator and other alarms are demonstrated to be functional and setpoints are consistent with design bases documents. Alarm response procedure entry points and actions are consistent with plant design/licensing bases documents.

11. Testing methods, acceptance criteria, and required corrective actions for IST activities meet with the applicable version of the ASME Code,Section XI. In concert with Technical Specification requirements, IST programs are intended to ensure the operational readiness of certain safety related pumps and valves.

Inspectors must review reference values or changes to reference values for consistency with the design bases and verify that the current acceptance criteria Issue Date: 6 71111.22

DRAFT match the most recent reference test data. For pump testing, the inspectors must should verify that the licensee established system operating conditions that reflect limiting operational conditions and are sufficiently repeatable to allow performance trending. Inspectors should also review sufficient test performance history to verify that the licensee identified and is addressing any adverse trends.

12. For local leak rate testing, isolation valves inside and outside containment are each tested with pressure exerted in a direction consistent with expected accident conditions. The inspectors must should verify that the licensee updates the total containment leak rate data with the new measured value, and confirm that the overall leak rate is still within acceptable limits. The inspectors must should verify that the licensee schedules the isolation valve(s) for maintenance if administrative limits are exceeded. The inspectors must should also verify that the containment penetration(s) is declared inoperable if acceptance criteria are exceeded.

13. Test frequency was adequate to demonstrate operability (meets Technical Specification requirements), and reliability. Appendix A, Risk Management Technical Specifications Initiative 5b Surveillance Frequency Control Program, provides additional information for reviews associated with the application of the Risk Management Technical Specification Initiative 5b Surveillance Frequency Control Program.

14. If an adverse trend in RCS leakage is being monitored by the licensee, the inspectors should verify that the licensee has programs and processes in place to (1) monitor plant-specific instrumentation that could indicate potential RCS leakage, (2) meet existing requirements related to degraded or inoperable leakage detection instruments, (3) use an inventory balance check when there is unidentified leakage (4) take appropriate corrective action for adverse trends in unidentified leak rates, and (5) pay particular attention to changes in unidentified leakage. [C1]

15. Unavailability of the tested equipment is appropriately considered in the licensees Mitigating System Performance Index data.

16. After completion of testing, equipment is returned to the positions/status required for the SSCs to perform its intended safety function.

17. Test equipment is removed after testing.

18. Test data is complete, verified, and meets procedure requirements.

19. For test results that do not meet the acceptance criteria, the results of licensee engineering evaluations and apparent/root cause analyses provide and acceptable bases for returning affected SSCs to an operable status.

Issue Date: 7 71111.22

DRAFT

20. Performance trends for the last several completed tests are appropriately documented and addressed. If testing indicates unacceptable setpoint drift or otherwise demonstrates degradation, the inspector must assess the adequacy of the licensees corrective actions. These may include component replacement and/or increased frequency of testing, for example.

03.02 FLEX Testing Verify by witnessing tests and/or reviewing the test data, that testing activities and results provide objective evidence that FLEX SSCs remain capable of performing their intended functions (under conditions as close as practical to licensing conditions) and maintain their operational readiness consistent with the facilitys current licensing basis.

Specific Guidance Section 11.5 of NEI 12-06 contains guidance on FLEX maintenance and testing.

03.03 Identification and Resolution of Problems. Verify that the licensee is identifying surveillance testing problems at an appropriate threshold and entering them in the corrective action program.

Specific Guidance Select a sample of significant surveillance testing problems documented in the corrective action program, and verify thatin order to determine if the licensee has identified and implemented appropriate corrective actions. Examples of significant surveillance testing problems and appropriate inspector follow-up include:

a. Licensee actions to addressed M&TE that fails calibration. Inspectors must assess the adequacy of the licensees corrective actions, considering the following: the licensee tracks which surveillance tests used each piece of M&TE, compares the failed M&TE calibration information to each surveillance test that used that M&TE, and then assesses the impact to the operability of the affected system. Inspectors should also consider performing a 71111.15, Operability Determinations and Functionality Assessments, sample to more thoroughly assess the potential effects on operability.

b. Licensee actions to address degraded system performance identified during in-service testing. When degraded performance is revealed, inspectors must review the condition reporting data base to verify that the licensee is implementing appropriate corrective actions, such as testing with increased frequency in accordance with ASME Code, Surveillance Frequency Control Program, or other applicable requirements.

Issue Date: 8 71111.22

DRAFT See Inspection Procedure 71152, Identification and Resolution of Problems, for additional guidance.

71111.22-04 RESOURCE ESTIMATE The annual resource expenditure for this inspection procedure is estimated to be 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> to review surveillance testing activities at a site regardless of the number of reactor units at that site. See IMC 2515 Appendix A for guidance on deviating from this resource estimate.

71111.22-05 COMPLETION STATUS Inspection of the minimum sample size will constitute completion of this procedure in the Reactor Programs Systems (RPS). That minimum sample size will consist of 14 surveillance testing activities in a year regardless of the number of reactor units at the site.

71111.22-0604 REFERENCES Inspection Manual Chapter 2515, Light-Water Reactor Inspection Program - Operations Phase Inspection Manual Chapter 2515, Appendix A, Risk-Informed Baseline Inspection Program Inspection Procedure 73756, Inservice Testing of Pumps and Valves Inspection Procedure 61720, Containment Local Leak Rate Testing Inspection Procedure 71111.04, Equipment Alignment Inspection Procedure 71111.12, Maintenance Effectiveness Inspection Procedure 71111.13, Maintenance Risk Assessments and Emergent Work Control Inspection Procedure 71111.15, Operability Determinations and Functionality Assessments Inspection Procedure 71111.18, Plant Modifications Inspection Procedure 71111.19, Post-Maintenance Testing Inspection Procedure 71152, Identification and Resolution of ProblemsBulletin 88-04, "Potential Safety-Related Pump Loss," May 5, 1988.

Code of Federal Regulations, Title 10, Part 50, Section 50.55a, "Codes and Standards."

Generic Letter 89-04, "Guidance on Developing Acceptable Inservice Testing Programs," April 3, 1989.

Issue Date: 9 71111.22

DRAFT Information Notice 97-90, Use of Nonconservative Acceptance Criteria in Safety-Related Pump Surveillance Tests, December 30, 1997 10 CFR 50, Appendix J, including Option B.

NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components Inspection Manual Part 9900, Technical guidance, Maintenance - Preconditioning of Structures, Systems, and Components Before Determining Operability Regulatory Guide, 1.45, Reactor Coolant Pressure Boundary Leakage Detection Systems Regulatory Issue Summary 06-17, NRC Staff Position on the Requirements of 10 CFR 50.36, Technical Specifications, Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels Information Notice 2010-25, Inadequate Electrical Connections NEI 12-06, Revision 0, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, (ML12242A378)

NEI 12-06, Revision 2, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, (ML15348A015)

NEI 12-06, Revision 4, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, (ML16354B421)

JLD-ISG 2012-01, Revision 0, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, (ML12229A174)

JLD-ISG 2012-01, Revision 1, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, (ML15357A163)

JLD-ISG 2012-01, Revision 2, Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, (ML17005A188)

END Issue Date: 10 71111.22

DRAFT APPENDIX A RISK MANAGEMENT TECHNICAL SPECIFICATIONS INITIATIVE 5b SURVEILLANCE FREQUENCY CONTROL PROGRAM (SFCP) 71111.22A-01 OBJECTIVE The objective of this Appendix is to support the review of licensees implementation of the risk management technical specification (RMTS) Initiative 5b, described in the RMTS Guidelines Document NEI 04-10, Risk Informed Method for Control of Surveillance Frequencies.

71111.22A-02 INSPECTION REQUIREMENTS AND GUIDANCE 02.01 Surveillance Frequency Changes

a. Confirm that the surveillance frequency change was evaluated for prohibitive commitments, and either no such commitments existed or they were revised prior to implementation of the Surveillance Test Interval (STI) change.

b. Confirm that the qualitative evaluation included, as a minimum, the items identified in NEI 04-10, step 7.

c. If the affected component or system is modeled in the PRA, or was added to the PRA model to support application of the SFCP, then confirm that a full scope evaluation using the licensee's PRA model was completed and satisfied the acceptance criteria of <1 E-6 CDF and <1 E-7 LERF.

d. If the affected component or system is not modeled in the PRA, then confirm acceptable qualitative or bounding analyses were completed and satisfied the acceptance criteria of

<1 E-7 CDF and <1 E-8 LERF.

e. Confirm the cumulative impact of all STI changes meets the acceptance criteria of <1 E-5 CDF and <1 E-6 LERF.

f. Confirm appropriate sensitivity studies were completed and acceptable to justify the surveillance frequency change.

g. Confirm an acceptable procedural implementation and monitoring strategy was completed for the affected systems and components.

02.02 SFCP Process and Oversight

a. SFCP Process:

1. Review IDP meeting minutes for the selected Surveillance frequency.

Issue Date: AppA-2 71111.22

DRAFT

2. Verify that the required training/qualification of personnel involved with the approval of the selected Surveillance Frequency change was conducted. The required training should cover the areas listed in Section 4 of NEI 04-10 and should be commensurate with their respective responsibilities.

3. Review any risk management actions that were implemented. Review NEI 04-10, Appendix A for SFCP documentation requirements.

b. SFCP Oversight:

1. Review plant on-site review committee meeting minutes for the selected Surveillance frequency.

2. If applicable, verify that any issue affecting the system or component for which the surveillance frequency applies is properly captured in the Corrective Actions Program.

71111.22A-03 REFERENCES IP 71111.13, Maintenance Risk Assessments and Emergent Work Control.

RG 1.174, An Approach for Using Probabilistic Risk Assessment in Risk Informed Decisions on Plant Specific Changes to the Licensing Basis.

RG 1.177, An Approach for Plant-Specific, Risk-Informed Decision-making: Technical Specifications.

RG 1.200, An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk Informed Activities.

EPRI 1009474, Dec 2004 RMTS Guidelines.

Licensee Safety Evaluation Report (SER) for the license amendments adopting RITS 5b.

NEI 04-10 Revision 01, Risk-Informed Technical Specifications Initiative 5b, Risk Informed Method for Control of Surveillance Frequencies, Industry Guidance Document (ML062570416).

NEI 04-10 Revision 1, Risk-Informed Technical Specifications Initiative 5b, Risk Informed Method for Control of Surveillance Frequencies, Industry Guidance Document (ML071360456).

NUMARC 93-01,NEI - Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants, Revision 3.

GDC in 10 CFR Part 50, Appendix A.

1 NEI 04-10, Revision 0, is referenced in the Limerick Generating Station technical specification surveillance frequency control program. All other licensees reference NEI 04-10, Revision 1.

Issue Date: A-3 71111.22

DRAFT NEI 00-04, Revision 0, 10 CFR 50.69 SSC Categorization Guideline (ML052900163).

END Issue Date: AppA-2 71111.22

DRAFT Attachment 1 - Revision History for IP 71111.22 Commitment Accession Description of Change Description of Comment and Tracking Number Training Feedback Number Issue Date Required and Resolution Change Notice Completion Accession Date Number (Pre-Decisional, Non-Public)

N/A 01/17/2002 Revised to incorporate minor changes to the NO N/A CN 02-001 inspection requirements. In addition, inspection resource estimates and inspection level of effort are revised to provide a band for more inspection flexibility.

C1 05/11/2004 Revised to include RCS leak detection system YES 9/24/2003

Reference:

CN 04-013 surveillance as part of the surveillance testing Davis-Besse samples. Revision also includes surveillance Lessons testing attributes for reviewing annunciator/alarm Learned Task setpoints and alarm response procedure actions.

Force Item 3.2.1(3)

N/A 01/05/2006 Reduced the estimated resources required to NO N/A CN 06-001 complete this inspection activity based on inspection hours charged to this IP during last several ROP cycles. Completed historical CN search.

Issue Date: Att1-1 71111.22

DRAFT Commitment Accession Description of Change Description of Comment and Tracking Number Training Feedback Number Issue Date Required and Resolution Change Notice Completion Accession Date Number (Pre-Decisional, Non-Public)

N/A 02/27/07 IP 71111.22 address feedback form 71111.22-912 NO N/A CN-07-007 to clarify Section 02.02 to more clearly describe what is to be accomplished when conducting the leakage detection surveillance inspection.

Issue Date: Att1-2 71111.22

DRAFT Commitment Accession Description of Change Description of Comment and Tracking Number Training Feedback Number Issue Date Required and Resolution Change Notice Completion Accession Date Number (Pre-Decisional, Non-Public)

N/A ML092780504 Revised IP to make changes recommended by NO N/A 12/24/09 2009 ROP Realignment process. (Ref.

CN-09-032 ML092090312.)

• Did not make changes recommended by FF71111.19-1334; see FF for details.

• Incorporated FF2515-1309 by adding reference to IMC 2515 in Section 2.02 to emphasize observation of plant activities.

• Incorporated FF2515-1325 by removing quarterly sample requirements in Level Of Effort section and Section 2.01. Quarterly samples are not required by IMC 2515.

• In Section 04, reduced the resource estimate by 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

N/A ML11213A004 Revised to incorporate feedback associated with NO ML112840035 11/08/11 Feedback Form No. 71111.22-1550.

CN 11-031 Issue Date: Att1-3 71111.22

DRAFT Commitment Accession Description of Change Description of Comment and Tracking Number Training Feedback Number Issue Date Required and Resolution Change Notice Completion Accession Date Number (Pre-Decisional, Non-Public)

N/A ML12086A064 Revised to reflect NRC approval of Risk YES ML12086A084 04/12/2012 Management Technical Specification Initiative 5b To be CN 12-005 Surveillance Frequency Control Program. conducted by NRR after IP issuance.

N/A ML15040A283 Revised to incorporate feedback associated with NO ML15127A419 06/15/15 the ROP Enhancement Project.

CN 15-011 N/A Revisions are made to: None (1) Address recommendations from the working group established to update the ROP for regulatory actions taken following the Fukushima Dai-ichi accident (ML17164A285). IP revised to allow for oversight of FLEX testing, and as a minimum, require one inspection sample per year.

(2) Conform to new IP format requirements found in IMC 0040 (ML18003A122).

Issue Date: Att1-2 71111.22