RA-22-0117, Relief Request for Inservice Testing Program Plan - Fourth Ten-Year Interval
| ML22097A150 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/07/2022 |
| From: | Maza K Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-22-0117 | |
| Download: ML22097A150 (17) | |
Text
Kim Maza Site Vice President Harris Nuclear Plant 5413 Shearon Harris Rd New Hill, NC 27562-9300 984-229-2512 10 CFR 50.55a April 7, 2022 Serial: RA-22-0117 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63
Subject:
Relief Request for Inservice Testing Program Plan - Fourth Ten-Year Interval Ladies and Gentlemen:
Pursuant to 10 CFR 50.55a(z)(1), Duke Energy Progress, LLC (Duke Energy), hereby requests Nuclear Regulatory Commission (NRC) approval of the attached relief request for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The provisions of this relief are applicable to the fourth ten-year inservice testing (IST) program interval at HNP, which commenced on May 2, 2017, and is currently scheduled to end on April 30, 2027, as identified in the Fourth Interval Inservice Testing Program Plan, HNP-IST-004 Revision 0, submitted to the NRC on April 27, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML17117A702).
10 CFR 50.55a(f) requires IST of American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 pumps and valves. 10 CFR 50.55a(f)(4)(ii) requires that IST programs conducted during successive ten-year inspection intervals following the initial ten-year interval comply with the requirements of the latest edition and addenda of the Code, incorporated by reference in paragraph (b) of 10 CFR 50.55a, eighteen months prior to the start of the ten-year interval, subject to the limitations and modifications listed within paragraph (b) of that section.
Therefore, the HNP Inservice Testing Program Plan is based on the requirements of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code), 2004 Edition through 2006 Addenda. Accordingly, the enclosed relief request is sought from the requirements of the 2004 Edition of the ASME OM Code, through the 2006 Addenda, specifically ISTC-3700, Position Verification Testing.
By letter dated December 8, 2020 (ADAMS Accession No. ML20259A512), the NRC issued HNP a license amendment to revise Technical Specification 6.8.4.k, Containment Leakage Rate Testing Program, to reference the guidance in Nuclear Energy Institute (NEI) 94-01, Revision 3-A, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J, and conditions and limitations specified in NEI 94-01, Revision 2-A. The license amendment also allowed the extension of the containment isolation valve leakage test (i.e., Type C tests) from 60 months to 75 months in accordance with NEI 94-01, Revision 3-A for components with established good performance in the 10 CFR 50 Appendix J, Option B performance-based leakage-testing program. However, ISTC-3700 requires valves with remote position indicators be observed at least once every two years to verify that valve operation is accurately indicated, which is in conflict with the allowable Option B performance-based interval for valves eligible for an extended Type C test interval. Therefore, Duke Energy is hereby
U.S. Nuclear Regulatory Commission RA-22-0117 Page 2 submitting a relief request to align the testing frequency with the 10 CFR 50 Appendix J, Option B program, which now specifies an interval limit of 75 months.
Duke Energy requests approval of this relief request, pursuant to 10 CFR 50.55a(z)(1 ), by October 7, 2022, to support the next scheduled refueling outage at HNP.
This letter contains no new regulatory commitments. Please refer any questions regarding this submittal to Lee Grzeck, Acting Manager-Nuclear Fleet Licensing, at 980-373-1530.
Sincerely,
-11 r -?vt,-
Kim E. Maza Site Vice President Harris Nuclear Plant
Enclosure:
Relief Request HNP-IST-004-RR1 for lnservice Testing Program Plan - Fourth Ten-Year Interval : Valve Local Leakage Rate Test (LLRT) History Sample (Last Three Tests) : Position Indication Test History Sample (Last Three Tests) cc:
J. Zeiler, NRC Senior Resident Inspector, HNP C. Smith, NRC Resident Inspector, HNP A. Hon, NRC Project Manager, HNP NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission RA-22-0117 Enclosure RA-22-0117 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63 Relief Request HNP-IST-004-RR1 for Inservice Testing Program Plan - Fourth Ten-Year Interval
U.S. Nuclear Regulatory Commission Page 1 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
- 1. ASME Code Components Affected Active safety-related Target Rock solenoid operated valves that are required by subsection ISTC-3700, "Position Verification Testing," of the 2004 Edition through 2006 Addenda of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants (OM) Code to be observed locally at least once every two years to verify that valve operation is accurately indicated. Where practicable, this local observation should be supplemented by other indications such as use of flowmeters or other suitable instrumentation to verify obturator position. These observations need not be concurrent.
Where local observation is not possible, other indications shall be used for verification of valve operation. The specific valves covered by this relief request are tabulated below.
Valve ID Function Safety Position 1SP-12 Hydrogen Analyzer Cabinet "1A" Supply Iso Vlv (CIV)
CLOSED 1SP-16 REM-3502A Inlet from Containment Atmosphere Iso Vlv (CIV)
CLOSED 1SP-40 Pressurizer Liquid Space Sample Iso Vlv (CIV)
CLOSED 1SP-41 Pressurizer Liquid Space Sample Iso Vlv (CIV)
CLOSED 1SP-42 Hydrogen Analyzer Cabinet "1B" Supply Iso Vlv (CIV)
CLOSED 1SP-59 Pressurizer Steam Space Sample Iso Vlv (CIV)
CLOSED 1SP-60 Pressurizer Steam Space Sample Iso Vlv (CIV)
CLOSED 1SP-62 Hydrogen Analyzer Cabinet "1B" Return Iso Vlv (CIV)
CLOSED 1SP-78 SIS Accumulator "A" Sample Iso Vlv (CIV)
CLOSED 1SP-81 SIS Accumulator "B" Sample Iso Vlv (CIV)
CLOSED 1SP-84 SIS Accumulator "C" Sample Iso Vlv (CIV)
CLOSED 1SP-85 SIS Accumulator Sample Iso Vlv (CIV)
CLOSED 1SP-200 PASS Liquid Return Header Iso Vlv (CIV)
CLOSED 1SP-201 PASS Liquid Return Header Iso Vlv (CIV)
CLOSED 1SP-208 PASS Gas Return Header Iso Vlv (CIV)
CLOSED 1SP-209 PASS Gas Return Header Iso Vlv (CIV)
CLOSED 1SP-915 Hydrogen Analyzer Cabinet "1A" Supply Iso Vlv (CIV)
CLOSED 1SP-916 REM-3502A Inlet from Containment Atmosphere Iso Vlv (CIV)
CLOSED 1SP-917 Hydrogen Analyzer Cabinet "1A" Return Iso Vlv (CIV)
CLOSED 1SP-918 REM-3502A Sample Return to Containment Atmosphere Iso Vlv (CIV)
CLOSED 1SP-919 Hydrogen Analyzer Cabinet "1B" Supply Iso Vlv (CIV)
CLOSED 1SP-939 REM-3502A Sample Return to Containment Atmosphere Iso Vlv (CIV)
CLOSED 1SP-941 Hydrogen Analyzer Cabinet "1A" Return Iso Vlv (CIV)
CLOSED 1SP-943 Hydrogen Analyzer Cabinet "1B" Return Iso Vlv (CIV)
CLOSED 1SP-948 RCS Sample Line Iso Vlv (CIV)
CLOSED 1SP-949 RCS Sample Line Iso Vlv (CIV)
CLOSED Legend: Iso Vlv (CIV) - Isolation Valve (Containment Isolation Valve)
REM - Radioactive Effluent Monitor SIS - Safety Injection System PASS - Post Accident Sampling System
U.S. Nuclear Regulatory Commission Page 2 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
2. Applicable Code Edition and Addenda
ASME OM Code, 2004 Edition through 2006 Addenda.
3. Applicable Code Requirement
Relief is requested from Subsection ISTC of the ASME OM Code, 2004 Edition through 2006 Addenda, Subsection ISTC-3700, "Position Verification Testing", which states:
"Valves with remote position indicators shall be observed locally at least once every two years to verify that valve operation is accurately indicated. Where practicable, this local observation should be supplemented by other indications such as use of flowmeters or other suitable instrumentation to verify obturator position. These observations need not be concurrent. Where local observation is not possible, other indications shall be used for verification of valve operation."
- 4. Reason For Request Historically, Shearon Harris Nuclear Power Plant, Unit 1 (Shearon Harris) has utilized Local Leak Rate Test (LLRT) procedures, performed on an Appendix J Option A schedule (every refuel), for verifying the remote position indications for the tabulated valves are accurate, as local observation of solenoid movement is prohibited by valve design. Shearon Harris has recently implemented Amendment No. 181 (ADAMS Accession No. ML20259A512) to renewed Facility Operating License No. NPF-63 to adopt Option B of 10 CFR 50 Appendix J consistent with Nuclear Energy Institute (NEI) 94-01, Revision 3-A "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J." Under Option B, and its performance-based Type C test intervals, a Type C valve may have its LLRT interval extended up to 75 months upon completion of two consecutive periodic as-found Type C tests where the results of each test is within a licensee's allowable administrative limits. ISTC-3700 requires the verification of valve operation every two years, which is in conflict with the allowable Option B performance-based interval for valves eligible for an extended Type C test interval. Shearon Harris proposes an alternative to the provisions of ISTC-3700 to allow utilization of the Option B LLRT schedule for scheduling the ISTC-3700 position verification tests for the listed solenoid valves that qualify for testing on a frequency eligible under Option B.
- 5. Proposed Alternative and Basis For Use In accordance with ISTC-3700, where local observation is not possible, other indications shall be used to verify valve position. Shearon Harris performs and utilizes procedure EST-212, "Type C Local Leak Rate Tests," to confirm closed indication when pressurizing these solenoid valves to a differential pressure of greater than or equal to the calculated peak containment internal pressure related to the design basis loss-of-coolant accident (Pa, 41.8 psig) during local leak rate testing. Open indication is confirmed for these solenoid valves by verification of an increase in makeup flow when the valve is taken to the open position. This method satisfies the requirement for position indication verification and
U.S. Nuclear Regulatory Commission Page 3 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency ensures that the indicating lights correspond to valve position. The subject valves are designed such that the position of the valve is not locally observable.
The Shearon Harris Inservice Testing Program ISTC-3700 requirements for these valves are performed in conjunction with local leak rate testing as described above due to solenoid valve design. Shearon Harris has recently implemented Amendment No. 181 to adopt Option B of 10 CFR 50 Appendix J consistent with NEI 94-01, Revision 3-A.
Under Option B, and its performance-based Type C test intervals, a Type C valve may have its LLRT interval extended up to 75 months upon completion of two consecutive periodic as-found Type C tests where the results of each test are within a licensee's allowable administrative limits.
For the subject solenoid valves, as an alternative to the ISTC-3700 two-year frequency requirement, Shearon Harris requests relief from the ISTC-3700 frequency requirements and proposes to perform the alternate method where local leak rate equipment is used to confirm indication is accurate for these solenoid valves where local observation is not possible on the Option B schedule of NEI 94-01, Revision 3-A. The qualification of a valve for an extended Type C test interval under 10 CFR 50 Appendix J Option B, based on successful LLRT, is one general indicator of the structure, system, or components (SSCs) operational readiness.
The operational readiness of these SSCs is also monitored during quarterly inservice testing. Shearon Harris procedure OST-1038, "Sampling, Chemical Addition, and Main Steam Drain Systems ISI [Inservice Inspection] Valve Test Quarterly Interval Mode 1 - 4" or OST-1062 "Sampling, Chemical Addition, And Main Steam Drain Systems ISI Valve Test And Remote Position Indication Test 2 Year Interval Modes 1, 2, 3 And 4" performs a quarterly fail safe (closed) test of the valves in conjunction with stroke time testing to the closed (safety) position of the valve. The quarterly measurement of stroke time and its comparison to the applicable criteria of ISTC-5152, "Stroke Test Acceptance Criteria,"
provides another general indicator of the SSCs operational readiness in addition to the testing performed under 10 CFR 50, Appendix J.
In conclusion, the ability to detect degradation of these SSCs and ensure their operational readiness is performed quarterly during fail safe and stroke time (closed) testing during OST-1038 or OST-1062. A further assessment of the components operational readiness is assessed during Type C testing on an Option B (NEI 94-01, Rev 3-A) schedule, with valves exhibiting acceptable local leakage rate testing performance eligible for testing on an extended test interval of up to 75 months. Performance of the ISTC-3700 indicator check on an Option B schedule provides an acceptable level of quality and safety, for those qualifying for local leakage rate testing on said schedule, in conjunction with quarterly fail safe and stroke time testing.
6. Duration of Proposed Alternative
The proposed alternative is requested for the remainder of the Shearon Harris fourth 10-year inservice testing program interval, which began of May 2, 2017 and will end on April 30, 2027.
U.S. Nuclear Regulatory Commission Page 4 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
7. Precedents
A similar request was approved for Fermi, Unit 2 (ADAMS Accession No. ML17354B002),
which requested ISTC-3700 requirements be aligned with 10 CFR 50 Appendix J, Option B for valves eligible for testing on an Option B schedule.
- 8. References None.
U.S. Nuclear Regulatory Commission RA-22-0117 Enclosure ATTACHMENT 1 Valve Local Leak Rate Test (LLRT) History Sample (Last Three Tests)
U.S. Nuclear Regulatory Commission Page 1 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
- Valve Local Leak Rate Test (LLRT) History Sample (Last Three Tests)
Valve Number Admin.
Limit (sccm)
As-Found LLRT Date As-Found Measured Value (sccm)
Sat or Unsat As-Left LLRT Date As-Left Measured Value (sccm)
Sat or Unsat 1SP-12 500 04/26/2021 10/15/2019 04/08/2018 31 24 56 Sat.
Sat.
Sat.
04/26/2021 10/15/2019 04/27/2018 31 24 133 Sat.
Sat.
Sat.
1SP-16 300 04/25/2021 10/16/2019 04/23/2018 109 1230 1593 Sat.
Unsat.
Unsat.
04/25/2021 10/28/2019 04/23/2018 109 40 1593 Sat.
Sat.
Unsat.*
1SP-40 300 04/28/2021 10/15/2019 04/23/2018 3332 24 36 Unsat.
Sat.
Sat.
05/09/2021 10/15/2019 04/23/2018 3723 24 36 Unsat.**
Sat.
Sat.
1SP-41 300 04/28/2021 10/15/2019 04/23/2018 4058 24 24 Unsat.
Sat.
Sat.
05/09/2021 10/28/2019 04/23/2018 3833 24 24 Unsat.**
Sat.
Sat.
1SP-42 300 10/28/2019 04/18/2018 10/22/2016 49 32 24 Sat.
Sat.
Sat.
10/28/2019 04/18/2018 10/22/2016 49 32 24 Sat.
Sat.
Sat.
1SP-59 300 04/27/2021 10/30/2019 04/09/2018 62 24 24 Sat.
Sat.
Sat.
05/07/2021 10/30/2019 04/09/2018 60 24 24 Sat.
Sat.
Sat.
(*) 1SP-16 leakage of 1593 sccm ( 300 sccm) accepted under evaluation EC #412101.
(**) 1SP-40 and 1SP-41 elevated leakage rates accepted under evaluation EC #419545.
U.S. Nuclear Regulatory Commission Page 2 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
- Valve Local Leak Rate Test (LLRT) History Sample (Last Three Tests)
Valve Number Admin.
Limit (sccm)
As-Found LLRT Date As-Found Measured Value (sccm)
Sat or Unsat As-Left LLRT Date As-Left Measured Value (sccm)
Sat or Unsat 1SP-60 300 05/07/2021 10/30/2019 04/09/2018 104 24 169 Sat.
Sat.
Sat.
05/07/2021 10/30/2019 04/09/2018 104 24 169 Sat.
Sat.
Sat.
1SP-62 300 04/27/2021 10/28/2019 04/18/2018 34 165 54 Sat.
Sat.
Sat.
04/27/2021 10/28/2019 04/18/2018 34 165 54 Sat.
Sat.
Sat.
1SP-78 500 04/28/2021 10/29/2019 04/28/2018 24 48 28 Sat.
Sat.
Sat.
04/28/2021 10/29/2019 04/28/2018 24 48 28 Sat.
Sat.
Sat.
1SP-81 500 04/28/2021 10/29/2019 04/28/2018 56 52 24 Sat.
Sat.
Sat.
04/28/2021 10/29/2019 04/28/2018 56 52 24 Sat.
Sat.
Sat.
1SP-84 300 04/26/2021 10/29/2019 04/28/2018 88 69 152 Sat.
Sat.
Sat.
04/28/2021 10/29/2019 04/28/2018 710 69 152 Unsat.*
Sat.
Sat.
(*) 1SP-84 leakage of 710 sccm ( 300 sccm) accepted under evaluation EC #419545.
U.S. Nuclear Regulatory Commission Page 3 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
- Valve Local Leak Rate Test (LLRT) History Sample (Last Three Tests)
Valve Number Admin.
Limit (sccm)
As-Found LLRT Date As-Found Measured Value (sccm)
Sat or Unsat As-Left LLRT Date As-Left Measured Value (sccm)
Sat or Unsat 1SP-85 300 04/26/2021 10/29/2019 04/28/2018 355 188 106 Unsat.
Sat.
Sat.
04/28/2021 10/29/2019 04/28/2018 596 188 106 Unsat.*
Sat.
Sat.
1SP-200 300 05/07/2021 11/04/2019 04/23/2018 83 34 74 Sat.
Sat.
Sat.
05/08/2021 11/05/2019 04/24/2018 83 82 75 Sat.
Sat.
Sat.
1SP-201 300 04/26/2021 11/04/2019 04/23/2018 862 4022 4508 Unsat.
Unsat.
Unsat.
05/08/2021 11/05/2019 04/24/2018 5059 4296 4092 Unsat.**
Unsat.**
Unsat.**
1SP-208 300 05/07/2021 10/16/2019 04/22/2018 35 91 41 Sat.
Sat.
Sat.
05/07/2021 10/16/2019 04/22/2018 35 91 41 Sat.
Sat.
Sat.
1SP-209 300 05/07/2021 10/16/2019 04/22/2018 58 79 28 Sat.
Sat.
Sat.
05/07/2021 10/16/2019 04/22/2018 58 79 28 Sat.
Sat.
Sat.
(*) 1SP-85 leakage of 596 sccm ( 300 sccm) accepted under evaluation EC #419545.
(**) 1SP-201 elevated leak rates accepted under EC #412101 (2018), EC #416496 (2019), and EC #419545 (2021).
U.S. Nuclear Regulatory Commission Page 4 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
- Valve Local Leak Rate Test (LLRT) History Sample (Last Three Tests)
Valve Number Admin.
Limit (sccm)
As-Found LLRT Date As-Found Measured Value (sccm)
Sat or Unsat As-Left LLRT Date As-Left Measured Value (sccm)
Sat or Unsat 1SP-915 300 04/26/2021 10/15/2019 04/18/2018 66 24 762 Sat.
Sat.
Unsat.
04/26/2021 10/15/2019 05/01/2018 66 24 25 Sat.
Sat.
Sat.
1SP-916 300 04/25/2021 10/16/2019 04/23/2018 94 24 24 Sat.
Sat.
Sat.
04/25/2021 10/28/2019 04/23/2018 94 34 24 Sat.
Sat.
Sat.
1SP-917 300 10/14/2019 04/11/2018 10/10/2016 148 92 153 Sat.
Sat.
Sat.
10/14/2019 04/28/2018 10/10/2016 148 63 153 Sat.
Sat.
Sat.
1SP-918 300 04/25/2021 10/14/2019 04/08/2018 96 42 42 Sat.
Sat.
Sat.
04/25/2021 10/29/2019 04/28/2018 96 39 48 Sat.
Sat.
Sat.
1SP-919 300 10/28/2019 04/18/2018 10/22/2016 32 24 24 Sat.
Sat.
Sat.
10/28/2019 04/18/2018 10/22/2016 32 24 24 Sat.
Sat.
Sat.
U.S. Nuclear Regulatory Commission Page 5 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
- Valve Local Leak Rate Test (LLRT) History Sample (Last Three Tests)
Valve Number Admin.
Limit (sccm)
As-Found LLRT Date As-Found Measured Value (sccm)
Sat or Unsat As-Left LLRT Date As-Left Measured Value (sccm)
Sat or Unsat 1SP-939 300 04/25/2021 10/14/2019 04/08/2018 101 199 40 Sat.
Sat.
Sat.
04/25/2021 10/29/2019 04/28/2018 101 36 49 Sat.
Sat.
Sat.
1SP-941 300 10/14/2019 04/11/2018 10/10/2016 78 24 48 Sat.
Sat.
Sat.
10/14/2019 04/28/2018 10/10/2016 78 24 48 Sat.
Sat.
Sat.
1SP-943 300 04/27/2021 10/28/2019 04/18/2018 68 253 73 Sat.
Sat.
Sat.
04/27/2021 10/28/2019 04/18/2018 68 253 73 Sat.
Sat.
Sat.
1SP-948 300 04/28/2021 10/29/2019 04/22/2018 27 24 24 Sat.
Sat.
Sat.
05/06/2021 10/29/2019 05/02/2018 61 24 24 Sat.
Sat.
Sat.
1SP-949 300 05/06/2021 10/29/2019 04/22/2018 24 24 24 Sat.
Sat.
Sat.
05/06/2021 10/29/2019 05/02/2018 24 24 24 Sat.
Sat.
Sat.
U.S. Nuclear Regulatory Commission RA-22-0117 Enclosure ATTACHMENT 2 Position Indication Test History Sample (Last Three Tests)
U.S. Nuclear Regulatory Commission Page 1 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
- Position Indication Test History Sample (Last Three Tests)
Valve Number Test Date Status Procedure Number 1SP-12 04/26/2021 PASS EST-212 10/15/2019 PASS EST-212 04/27/2018 PASS EST-212 1SP-16 04/25/2021 PASS EST-212 10/28/2019 PASS EST-212 04/23/2018 PASS EST-212 1SP-40 05/09/2021 PASS EST-212 10/15/2019 PASS EST-212 04/23/2018 PASS EST-212 1SP-41 05/09/2021 PASS EST-212 10/28/2019 PASS EST-212 04/23/2018 PASS EST-212 1SP-42 03/19/2022 PASS WO #20523117 10/28/2019 PASS EST-212 04/18/2018 PASS EST-212 1SP-59 05/07/2021 PASS EST-212 10/30/2019 PASS EST-212 04/09/2018 PASS EST-212 1SP-60 05/07/2021 PASS EST-212 10/30/2019 PASS EST-212 04/09/2018 PASS EST-212 1SP-62 04/27/2021 PASS EST-212 10/28/2019 PASS EST-212 04/18/2018 PASS EST-212 1SP-78 04/28/2021 PASS EST-212 10/29/2019 PASS EST-212 04/28/2018 PASS EST-212
U.S. Nuclear Regulatory Commission Page 2 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
- Position Indication Test History Sample (Last Three Tests)
Valve Number Test Date Status Procedure Number 1SP-81 04/28/2021 PASS EST-212 10/29/2019 PASS EST-212 04/28/2018 PASS EST-212 1SP-84 04/28/2021 PASS EST-212 10/29/2019 PASS EST-212 04/28/2018 PASS EST-212 1SP-85 04/28/2021 PASS EST-212 10/29/2019 PASS EST-212 04/28/2018 PASS EST-212 1SP-200 05/08/2021 PASS EST-212 11/05/2019 PASS EST-212 04/24/2018 PASS EST-212 1SP-201 05/08/2021 PASS EST-212 11/05/2019 PASS EST-212 04/24/2018 PASS EST-212 1SP-208 05/07/2021 PASS EST-212 10/16/2019 PASS EST-212 04/22/2018 PASS EST-212 1SP-209 05/07/2021 PASS EST-212 10/16/2019 PASS EST-212 04/22/2018 PASS EST-212 1SP-915 04/26/2021 PASS EST-212 10/15/2019 PASS EST-212 05/01/2018 PASS EST-212 1SP-916 04/25/2021 PASS EST-212 10/28/2019 PASS EST-212 04/23/2018 PASS EST-212
U.S. Nuclear Regulatory Commission Page 3 RA-22-0117 Enclosure 10 CFR 50.55a Relief Request HNP-IST-004-RR1 Relief to Perform Position Indication Testing at Appendix J Option B Frequency
- Position Indication Test History Sample (Last Three Tests)
Valve Number Test Date Status Procedure Number 1SP-917 03/19/2022 PASS WO #2053117 10/14/2019 PASS EST-212 04/28/2018 PASS EST-212 1SP-918 04/25/2021 PASS EST-212 10/29/2019 PASS EST-212 04/28/2018 PASS EST-212 1SP-919 03/19/2022 PASS WO #2053117 10/28/2019 PASS EST-212 04/18/2018 PASS EST-212 1SP-939 04/25/2021 PASS EST-212 10/29/2019 PASS EST-212 04/28/2018 PASS EST-212 1SP-941 03/19/2022 PASS WO #2053117 10/14/2019 PASS EST-212 04/28/2018 PASS EST-212 1SP-943 04/27/2021 PASS EST-212 10/28/2019 PASS EST-212 04/18/2018 PASS EST-212 1SP-948 05/06/2021 PASS EST-212 10/29/2019 PASS EST-212 05/02/2018 PASS EST-212 1SP-949 05/06/2021 PASS EST-212 10/29/2019 PASS EST-212 04/22/2018 PASS EST-212