NL-24-0384, Request for Alternative RR-PR-04 for Inservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves
| ML24292A210 | |
| Person / Time | |
|---|---|
| Site: | Farley |
| Issue date: | 10/18/2024 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NL-24-0384 | |
| Download: ML24292A210 (1) | |
Text
>. Southern Nuclear October 18, 2024 Docket No.:
50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 NL-24-0384 Joseph M. Farley Nuclear Plant-Unit 2 Request for Alternative RR-PR-04 for lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves Ladies and Gentlemen:
In accordance with 10 CFR 50.55a, "Codes and standards," Southern Nuclear Operating Company (SNC) requests NRC approval of a proposed alternative associated with the lnservice Testing (1ST) Program for Farley Nuclear Plant (Farley). The proposed alternative requests to defer the requirements to perform a Group A quarterly pump tests as required by ISTB-3400, for the 2A, 2B, and 2C charging pumps, and quarterly exercise testing for 2A, 2B, and 2C charging pump mini-flow valves as required by ISTC-3510, until April 14, 2025. This will allow performance of a comprehensive pump test (CPT) for the 2A, 2B, and 2C charging pumps and exercise tests for mini-flow valves during the upcoming spring of 2025 refueling outage.
The next scheduled performance of the Group A test for the 2B charging pump is due November 7, 2024, which is 92 days plus grace from the last test performed on July 15, 2024.
Recent performance of this test for the 2A charging pump caused pressure perturbations on an RCP seal that was recently identified as degraded.
Performance of this testing before the damaged seal can be repaired during the spring 2025 outage could introduce additional damage to the degraded seal and undue stress on the backup RCP seal. Performance of these tests as scheduled would constitute a hardship without a compensating increase in the level of quality and safety.
The proposed alternative in the attached enclosure provides reasonable assurance of pump and valve operational readiness and provides an acceptable level of quality and safety. SNC requests NRC approval of this alternative by November 7, 2024. This request, upon approval, will be applied until April 14, 2025.
This letter contains no NRC commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.
U. S. Nuclear Regulatory Commission NL-24-0384 Page 2 Respectfully submitted, Jamie M. Coleman Regulatory Affairs Director JMC/dsp/cbg
Enclosure:
Request for Alternative RR-PR-04 cc:
Regional Administrator, Region II NRR Project Manager - Farley Nuclear Plant Senior Resident Inspector - Farley Nuclear Plant RTYPE: CFA04.054 2
Joseph M. Farley Nuclear Plant - Unit 2 Request for Alternative RR-PR-04 for lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves Enclosure Request for Alternative RR-PR-04
Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2)
- 1. ASME Code Components Affected Component Number Component Title Code Class Pump Group or Valve Category Q2E21P002A 2A Charging Pump 2
Group A Pump Q2E21P002B 2B Charging Pump 2
Group A Pump Q2E21P002C 2C Charging Pump 2
Group A Pump Q2E21MOV8109A 2A Charging Pump Mini 2
Category B Valve Flow Isolation Q2E21MOV8109B 2B Charging Pump Mini 2
Category B Valve Flow Isolation Q2E21MOV8109C 2C Charging Pump Mini 2
Category B Valve Flow Isolation The chemical and volume control system (CVCS) serves as part of the emergency core cooling system (ECCS) by providing high head safety injection (HHSI) capability. As part of the ECCS, the charging/HHS! pumps provide core cooling and negative reactivity to ensure that the reactor core is protected after any of the following accidents:
Loss of coolant accident (LOCA), coolant leakage greater than the capability of the normal charging system Rod ejection accident Loss of secondary coolant accident, including uncontrolled steam release or feedwater line rupture Steam generator tube rupture (SGTR)
The charging pump mini flow isolation valves perform a safety function in the open position, above a specified Reactor Coolant System (RCS) pressure, to preclude pump damage during normal and other low flow operating conditions.
These valves also perform a safety function in the closed position, below a specified RCS pressure, to:
Prevent total pump flow from exceeding runout conditions.
Ensure that all Charging Pump discharge flow is used for safety injection and seal water purposes.
Prevent loss of containment sump and RCS inventory during high and low safety injection and following switchover to recirculation mode, due to an unanticipated diversion of Charging Pump mini flow and avoid the possible escape of associated contamination and radioactivity to the environment.
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Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2)
2. Applicable Code Edition and Addenda
American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) 2004 Edition with Addenda through OMb-2006.
3. Applicable Code Requirement
ISTB-3400, Frequency of lnservice Tests, states "An inservice test shall be run on each pump as specified in Table ISTB-3400-1 ". Table ISTB-3400-1, lnservice Test Frequency, specifies that for Group A pumps, a 'Comprehensive [Pump] Test' (CPT) be performed biennially and a 'Group A Test' be performed quarterly.
ISTC-3510, Exercising Test Frequency, states "Active Category A, Category B, and Category C check valves shall be exercised nominally every 3 months."
4. Reason for Request
Pursuant to 10 CFR 50.55a, Codes and standards, paragraph (z)(2), an alternative is proposed to the quarterly pump and valve test requirements of the ASME OM-2004 Code with Addenda through OMb-2006. The basis of the request is that compliance with the specified requirements results in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Increased inleakage into the Unit 2 Reactor Coolant Drain Tank (RCDT) was identified on September 4, 2024. The increased inleakage is due to degradation of the 2B Reactor Coolant Pump (RCP) #2 seal causing increased seal leakoff which drains into the RCDT.
On September 19, 2024, during performance of the quarterly Group A test for the 2A charging pump and Category B valve test for the 2A charging pump mini flow isolation valve, perturbations were experienced that caused a decrease in the 2B RCP #1 seal leakoff flow rate and an increase in the #2 seal leakoff flow rate. Performance of the Group A pump test causes perturbations to the #1 and #2 seals based on the required changes to seal injection flow, charging flow, Volume Control Tank (VCT) pressure, and pressure perturbations on the #1 seal return flow path during the test. The Category B valve tests are performed in conjunction with the pump test and require charging pump alignments to be swapped. The Category B valve tests cause pressure perturbations to the #1 RCP seal leak-off line and the potential to degrade the #1 RCP seal. The
- 1 seal does not have a fully functional backup in the event of failure due to the degradation of the #2 seal. Continued performance of the Group A pump tests and Category B valve tests causes undue stress to the #1 and #2 RCP seals and could cause further degradation.
The potential damage or degradation of the #1 seal, combined with the known degradation of the
- 2 seal, challenges plant safety and reliability due to the potential for a small break loss of coolant E-3
Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2) accident through the seal package. Damage or degradation of the #1 seal (due to the perturbations caused by the Group A pump test and Category B valve tests) could cause seal leakoff flow rates to exceed abnormal operating procedure limits and require a shutdown of Unit 2 in order to prevent the potential small break loss of coolant accident. The abnormal operating procedure directs preparing for an orderly shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> if the #1 seal leakoff is greater than 6 gpm and combined seal leak off is less than 8 gpm. The procedures direct manually tripping the reactor then securing the affected RCP if combined #1 and #2 seal leakoff are greater than 8 gpm.
Repairs to address the 2B RCP seal leakage are scheduled for the upcoming refueling outage in the spring of 2025. As a contingency, the repair scope is included on the forced outage worklist and would be performed if a forced outage of sufficient duration and scope were necessary prior to the planned refueling outage. Repair of the 2B RCP seal requires the pump and motor to be decoupled which would require shutdown of the Unit 2 reactor and reduce plant reliability.
The next performance of the Group A test for the 2B charging pump and the Category B test for the charging pump mini flow isolation valves is due November 7, 2024, which is 92 days plus grace from the last test performed on July 15, 2024. Southern Nuclear Operating Company is requesting NRC approval of this relief request by November 7, 2024, prior to the expiration of the testing frequency window.
5. Proposed Alternative and Basis for Use
The proposed alternative requests to defer the requirements to perform Group A quarterly pump tests as required by ISTB-3400 for the 2A, 2B, and 2C charging pumps and quarterly exercise testing for the 2A, 2B, and 2C charging pump mini flow isolation valves as required by ISTC-3510 until April 14, 2025. This will allow performance of a comprehensive pump test (CPT) for the 2A, 2B, and 2C charging pumps and the performance of a Category B valve test for the 2A, 2B, and 2C charging pump mini flow isolation valves during the upcoming spring of 2025 refueling outage.
The Group A quarterly pump tests and quarterly Category B valve tests will resume as scheduled following the spring of 2025 refueling outage and repair of the 2B RCP seal.
Previous trends for the 2A, 2B, and 2C charging pumps and the charging pump mini flow isolation valves are in Attachment 1 (Tables 1 - 15) and show the operational readiness of the pumps and valves to perform their intended safety function. The last two years of data from the quarterly Group A testing and the last 10 years of data from the CPT for the 2A, 2B, and 2C Charging Pumps indicate there is no current pump degradation. All recorded values for pump vibration, flow, and differential pressure during the review period were within ASME OM Code and design limits.
The last two years of recorded stroke times for the charging pump mini flow isolation valves have been within ASME OM Code and design limits. Therefore it is unlikely that the upcoming quarterly pump and valve tests would produce a failing value for any test parameter. Additionally, no E-4
Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2) significant maintenance has been performed or is planned for the 2A, 2B, or 2C charging pumps or charging pump mini flow valves that would alter the pump and valve test parameters.
Repairs to the 2B RCP seal are planned for the upcoming spring of 2025 refueling outage because repair of the seal requires the pump and motor to be decoupled which would require shutdown of the Unit 2 reactor. In the current conditions, performing the Group A quarterly test for the 2A, 2B, and 2C charging pumps and the Category B valve test for the 2A, 2B, and 2C charging pump mini flow isolation valves would constitute a hardship without a compensating increase in the level of quality and safety. The proposed alternative to ISTB-3400, Frequency of lnservice Tests, and ISTC-3510, Exercising Test Frequency, provides reasonable assurance of pump and valve operational readiness and provides an acceptable level of quality and safety.
Relief is requested pursuant to 10 CFR 50.55a(z)(2) based on the determination that compliance with the ASME OM Code required quarterly charging pump and valve test requirements cannot be achieved without considerable plant safety and reliability risks prior to significant repairs to address the 2B RCP seal degradation. Performance of the Group A quarterly charging pump test and Category B valve test has shown to cause perturbations to the #1 and #2 RCP seals that could challenge the ability of the RCP seal package to prevent loss of coolant which challenges plant safety and reliability.
6. Duration of Proposed Alternative
This request, upon approval, will be applied until April 14, 2025. This date provides an adequate window of opportunity to perform the Comprehensive Pump Tests (CPTs) and valve exercise tests during the spring 2025 refueling outage, after repairs have been made to the RCP seal. The performance of the quarterly Group A inservice tests and quarterly valve exercise tests for the components included in this request will resume at the normal frequency following the spring 2025 refueling outage.
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Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2)
- 7. Precedent The NRC authorized Ginna Nuclear Power Plant Alternative Request PR-03 to defer performance of the Comprehensive Pump Test (CPT) and Pump Periodic Verification Test (PPVT) of the 'B' Auxiliary Feedwater Pump due to degradation of a condensate heater check valve causing partial flow blockage until the scheduled fall 2024 refueling outage.
V. Sreenivas (NRC) to David P. Rhoades (Constellation Energy Generation, LLC), "R. E.
Ginna Nuclear Power Plant-Alternative Associated with lnservice Testing of 'B' Auxiliary Feedwater Pump - PR-03 (EPID L-2024-LLR-0006)," dated July 16, 2024 (ML24170A385)
The NRC authorized Monticello Nuclear Generating Plant Alternative Request PR-08 to defer the quarterly testing of certain components in the HPCI system due to a degraded component in a connected system until the scheduled spring 2023 refueling outage.
V. Sreenivas (NRC) to C. P. Domingos (Northern States Power Company), "Monticello Nuclear Generating Plant - Authorization and Safety Evaluation for Alternative Request PR-08 (EPID L-2022-LLR-0088)," dated April 25, 2023 (ML23107A285)
The NRC authorized Millstone Power Station Alternative Request P-06 to defer quarterly Group A testing of the spare charging pump due to system unavailability accrued during the test and due to test alignment requirements that caused temperature and flow transients on the RCP seals.
J. G. Danna (NRC) to D. G. Stoddard (Dominion Energy Nuclear Connecticut, Inc.),
"MILLSTONE POWER STATION, UNIT NO 3 -ALTERNATIVE REQUEST P-06 FOR 'C' CHARGING PUMP TEST FREQUENCY (EPID L-2018-LLR-0078)," dated October 4, 2018 (ML18275A012)
G. T Bischof (Dominion Energy Nuclear Connecticut, Inc.) to U.S. Nuclear Regulatory Commission, "MILLSTONE POWER STATION UNIT 3 PROPOSED ALTERNATIVE REQUEST P-06 FOR 'C' CHARGING PUMP TEST FREQUENCY," dated May 29, 2018 (ML18156A131)
- 8. References None.
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Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2)
Table 1 - 2A Charging Pump Quarterly Group A Test - Differential Pressure Trends Date Flow (gpm)*
dP (psid) dP Acceptance Criteria (psid)**
12/7/2022 131.2 2674.5 2404.4 to 2681 3/7/2023 132.4 2667.7 2404.4 to 2681 6/6/2023 131.1 2668.5 2404.4 to 2681 9/5/2023 132.0 2664.8 2404.4 to 2681 12/5/2023 132.0 2666 2404.4 to 2681 3/13/2024 132.5 2633 2404.4 to 2681 6/11/2024 131.0 2673 2404.4 to 2681 9/19/2024 132.2 2665 2404.4 to 2681
- Flow is adjusted to the reference point of 130 gpm +2%/-1% (128.7 gpm to 132.6 gpm)
- Upper limit bounded by design limit Table 2 - 2A Charging Pump Biennial CPT - Differential Pressure Trends Date Flow (gpm)*
dP (psid) dP Acceptance Criteria (psid) 4/24/2013 608 1420.5 1348 to 1491 11/9/2014 613 1451 1348 to 1491 4/27/2016 612 1415 1348 to 1491 11/1/2017 611 1371.5 1348 to 1491 4/23/2019 613 1421.5 1348 to 1491 10/31/2020 613.5 1354 1348 to 1491 4/15/2022 618 1435 1348 to 1491 10/20/2023 609 1367 1348 to 1491
- Flow is adjusted to the reference point of 610 gpm +2%/-1 % (603.9 to 622.2 gpm)
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Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2)
Table 3 - 2A Charging Pump Quarterly Group A Test - Vibration Data Pump Inboard Pump Inboard Pump Outboard Pump Pump Date Outboard Outboard Horizontal (IPS*)
Vertical (IPS)
Horizontal (IPS)
Vertical (IPS)
Axial (IPS) 12/7/2022 0.181 0.078 0.115 0.110 0.048 3/7/2023 0.195 0.093 0.113 0.101 0.051 6/6/2023 0.177 0.081 0.114 0.117 0.051 9/5/2023 0.186 0.085 0.100 0.098 0.054 12/5/2023 0.205 0.098 0.120 0.109 0.054 3/13/2024 0.180 0.096 0.114 0.111 0.053 6/11/2024 0.196 0.096 0.121 0.102 0.058 9/19/2024 0.189 0.089 0.115 0.115 0.057 Acceptance
- 0.325
- 0.203
- 0.310
- 50.215
- 50.125 Criteria
- Inches per second Table 4 - 2A Charging Pump Biennial CPT - Vibration Data Pump Inboard Pump Inboard Pump Outboard Pump Pump Date Outboard Outboard Horizontal (IPS)
Vertical (IPS)
Horizontal (IPS)
Vertical (IPS)
Axial (IPS) 4/24/2013 0.156 0.067 0.157 0.078 0.041 11/9/2014 0.299 0.132 0.139 0.096 0.043 4/27/2016 0.120 0.068 0.158 0.082 0.049 11/1/2017 0.138 0.070 0.158 0.089 0.034 4/23/2019 0.140 0.083 0.152 0.061 0.032 10/31/2020 0.106 0.064 0.157 0.075 0.030 4/15/2022 0.171 0.083 0.146 0.058 0.029 10/20/2023 0.181 0.095 0.174 0.060 0.042 Acceptance
- 0.325
- 0.325
- 0.325
- 0.237
- 0.187 Criteria E-8
Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2)
Table 5 - 2B Charging Pump Quarterly Group A Test - Differential Pressure Trends Date Flow (gpm)*
dP (psid) dP Acceptance Criteria (psid)**
11/30/2022 132.3 2667.9 2399 to 2681 2/28/2023 132.4 2666.2 2399 to 2681 4/13/2023 131.9 2665 2399 to 2681 7/10/2023 132.0 2660 2399 to 2681 1/16/2024 131.9 2674 2399 to 2681 4/15/2024 132.1 2671 2399 to 2681 7/15/2024 132.0 2663 2399 to 2681
- Flow is adjusted to the reference point of 130 gpm +2%/-1% (128.7 gpm to 132.6 gpm)
- Upper limit bounded by design limit Table 6 - 2B Charging Pump Biennial CPT - Differential Pressure Trends Date Flow (gpm)*
dP (psid) dP Acceptance Criteria (psid) 4/24/2013 613 1271 1217 to 1346 11/9/2014 612 1325.5 1217 to 1346 4/27/2016 610.9 1299.3 1217 to 1346 11/1/2017 607 1226.5 1217 to 1346 4/23/2019 611 1261.5 1217 to 1346 10/31/2020 611.7 1254.5 1217 to 1346 4/15/2022 615 1227 1217 to 1346 10/20/2023 604 1218 1217 to 1346
- Flow is adjusted to the reference point of 610 gpm +2%/-1 % (603.9 to 622.2 gpm)
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Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2)
Table 7 - 2B Charging Pump Quarterly Group A Test - Vibration Data Pump Inboard Pump Inboard Pump Outboard Pump Pump Date Outboard Outboard Horizontal (IPS)
Vertical (IPS)
Horizontal (IPS)
Vertical (IPS)
Axial (IPS) 11/30/2022 0.117 0.085 0.235 0.067 0.045 2/28/2023 0.135 0.078 0.253 0.071 0.043 4/13/2023 0.125 0.139 0.251 0.112 0.065 7/10/2023 0.108 0.089 0.246 0.069 0.041 1/16/2024 0.098 0.093 0.226 0.078 0.047 4/15/2024 0.119 0.100 0.243 0.071 0.044 7/15/2024 0.093 0.065 0.241 0.074 0.053 Acceptance
- 0.325
- 0.167
- 0.325
- 0.240
Vertical (IPS)
Horizontal (IPS)
Vertical (IPS)
Axial (IPS) 4/24/2013 0.101 0.075 0.242 0.116 0.070 11/9/2014 0.107 0.089 0.236 0.099 0.052 4/27/2016 0.118 0.083 0.249 0.078 0.046 11/1/2017 0.107 0.064 0.227 0.069 0.039 4/23/2019 0.122 0.072 0.224 0.073 0.040 10/31/2020 0.119 0.073 0.258 0.083 0.036 4/15/2022 0.140 0.084 0.224 0.056 0.035 10/20/2023 0.113 0.075 0.292 0.196 0.072 Acceptance
- 0.300
- 0.205
- 0.325
- 50.312
- 0.195 Criteria E-10
Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2)
Table 9 - 2C Charging Pump Quarterly Group A Test - Differential Pressure Trends Date Flow (gpm)*
dP (psid) dP Acceptance Criteria (psid)**
10/25/2022 131.6 2706 2503.5 to 2720 1/24/2023 132.4 2704 2503.5 to 2720 4/27/2023 130.2 2705 2503.5 to 2720 7/25/2023 132.0 2701 2503.5 to 2720 1/30/2024 130.7 2703.4 2503.5 to 2720 4/30/2024 131.5 2702 2503.5 to 2720 7/31/2024 131.8 2700 2503.5 to 2720
- Flow is adjusted to the reference point of 130 gpm +2%/-1% (128.7 gpm to 132.6 gpm)
- Upper limit bounded by design limit Table 10 - 2C Charging Pump Biennial CPT-Differential Pressure Trends Date Flow (gpm)*
dP (psid) dP Acceptance Criteria (psid) 4/24/2013 622 1287.5 1219 to 1349 11/9/2014 612 1376.1 1283 to 1420**
4/27/2016 612.4 1310.6 1283 to 1420 11/1/2017 612 1316.4 1283 to 1420 4/23/2019 616 1341.5 1283 to 1420 10/31/2020 612.5 1310 1283 to 1420 4/15/2022 614 1357 1283 to 1420 10/20/2023 604 1284 1283 to 1420
- Flow is adjusted to the reference point of 610 gpm +2%/-1 % (603.9 to 622.2 gpm)
- Acceptance criteria updated following pump replacement E-11
Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2)
Table 11 - 2C Charging Pump Quarterly Group A Test - Vibration Data Pump Inboard Pump Inboard Pump Outboard Pump Pump Date Outboard Outboard Horizontal (IPS)
Vertical (IPS)
Horizontal (IPS)
Vertical (IPS)
Axial (IPS) 10/25/2022 0.081 0.082 0.127 0.073 0.042 1/24/2023 0.068 0.06 0.131 0.087 0.036 4/27/2023 0.087 0.065 0.151 0.067 0.036 7/25/2023 0.062 0.082 0.135 0.080 0.033 1/30/2024 0.084 0.086 0.137 0.092 0.039 4/30/2024 0.085 0.086 0.150 0.084 0.046 7/31/2024 0.084 0.094 0.151 0.079 0.034 Acceptance
- 50.120
- 0.165
- 0.325
- 0.325
- 0.165 Criteria Table 12 - 2C Charging Pump Biennial CPT-Vibration Data Pump Inboard Pump Inboard Pump Outboard Pump Pump Date Outboard Outboard Horizontal (IPS)
Vertical (IPS)
Horizontal (IPS)
Vertical (IPS)
Axial (IPS) 4/24/2013 0.112 0.069 0.074 0.052 0.049 11/9/2014 0.124 0.078 0.13 0.054 0.033 4/27/2016 0.220 0.119 0.115 0.055 0.027 11/1/2017 0.096 0.078 0.127 0.042 0.026 4/23/2019 0.096 0.078 0.127 0.042 0.026 10/31/2020 0.040 0.042 0.109 0.062 0.027 4/15/2022 0.028 0.034 0.095 0.053 0.024 10/20/2023 0.034 0.043 0.117 0.067 0.027 Acceptance
- 0.282
- 0.200
- 0.267
- 0.155
- 0.202 Criteria E-12
Enclosure to NL-24-0384 Request for Alternative RR-PR-04 lnservice Testing of the 2A, 2B, and 2C Charging Pumps and Mini-Flow Isolation Valves in Accordance with 10 CFR 50.55a{z)(2)
Table 13 - Q2E21MOV8109A Stroke Time Data Date Stroke Time Open Stroke Time Closed Stroke Time Acceptance (seconds)
(seconds)
Criteria (seconds) 12/7/2022 7.34 7.82 5.57 to 9.29 3/7/2023 7.45 7.97 5.57 to 9.29 6/6/2023 7.26 7.75 5.57 to 9.29 9/5/2023 7.26 7.82 5.57 to 9.29 10/20/2023 7.22 7.87 5.57 to 9.29 12/5/2023 7.15 7.69 5.57 to 9.29 3/13/2024 7.34 8.27 5.57 to 9.29 6/11/2024 7.25 7.81 5.57 to 9.29 9/19/2024 7.25 7.88 5.57 to 9.29 Table 14-Q2E21MOV8109B Stroke Time Data Date Stroke Time Open Stroke Time Closed Stroke Time Acceptance (seconds)
(seconds)
Criteria (seconds) 11/30/2022 7.32 7.77 5.4 to 9.0 2/28/2023 7.02 7.51 5.4 to 9.0 4/13/2023 7.02 7.70 5.4 to 9.0 7/10/2023 7.16 7.67 5.4 to 9.0 10/20/2023 7.03 7.78 5.4 to 9.0 1/16/2024 7.45 7.57 5.4 to 9.0 4/15/2024 7.07 7.71 5.4 to 9.0 7/15/2024 6.94 7.56 5.4 to 9.0 Table 15 - Q2E21MOV8109C Stroke Time Data Date Stroke Time Open Stroke Time Closed Stroke Time Acceptance (seconds)
(seconds)
Criteria (seconds) 10/25/2022 6.58 7.15 4.97 to 8.28 1/24/2023 6.75 7.00 4.97 to 8.28 4/27/2023 6.77 7.14 4.97 to 8.28 7/25/2023 6.91 7.34 4.97 to 8.28 10/20/2023 6.96 7.15 4.97 to 8.28 1/30/2024 6.89 7.14 4.97 to 8.28 4/30/2024 6.84 7.13 4.97 to 8.28 7/31/2024 7.07 7.26 4.97 to 8.28 E-13