SBK-L-15026, NextEra Energy Seabrook, LLCs Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
| ML15068A007 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/27/2015 |
| From: | Dean Curtland NextEra Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| EA-12-051, SBK-L-15026 | |
| Download: ML15068A007 (17) | |
Text
NExTera ENERGY n February 27, 2015 SBK-L-15026 Docket No. 50-443 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Seabrook Station NextEra Energy Seabrook, LLC's Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-05 1)
References:
- 1. NRC Order Number EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, dated March 12, 2012 (ML12056A044)
- 2. NRC Interim Staff Guidance JLD-ISG-2012-03, Compliance with Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, Revision 0, dated August 29, 2012 (ML12221A339)
- 3. NEI 12-02, Industry Guidance for Compliance with NRC Order EA-12-051, To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation,. Revision 1, dated August 2012
- 4. NextEra Energy Seabrook, LLC Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, (Order Number EA-12-051), dated October 26, 2012 (ML12311A012)
- 5. NextEra Energy Seabrook, LLC Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, (Order Number EA-12-05 1), dated February 26, 2013 (ML13063A439)
- 6. NextEra Energy Seabrook, LLC, First Six Month Status Report for the Implementation of Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, dated August 28, 2013 9ADAMS Accession No. ML13247A177).
- 7. Seabrook Station, Unit 1 - Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA 051, Reliable Spent Fuel Pool Instrumentation (TAC No. MF0837), Dated December 4, 2013 (ADAMS Accession No. ML13267A388).
NextEra Energy Seabrook, LLC, P.O. Box 300, Lafayette Road, Seabrook, NH 03874
U.S. Nuclear Regulatory Commission SBK-L-15026/Page 2
- 8. NextEra Energy Seabrook, LLC, Second Six Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, dated February 27, 2014 (ADAMS Accession No. ML14064A189).
- 9. NextEra Energy Seabrook, LLC, Third Six Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation, dated August 24, 2014 (ADAMS Accession No. ML14246A192).
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued an order (Reference 1) to NextEra Energy Seabrook, LLC (NextEra Energy Seabrook). Reference 1 was immediately effective and directs NextEra Energy Seabrook to install reliable spent fuel pool level instrumentation. Specific requirements are outlined in Attachment 2 of Reference 1.
Reference 1 required submission of an initial status report 60 days following issuance of the final interim staff guidance (Reference 2) and an overall integrated plan pursuant to Section IV, Condition C. Reference 2 endorses industry guidance document NEI 12-02, Revision 1 (Reference 3) with clarifications and exceptions identified in Reference 2. Reference 4 provided the NextEra Energy Seabrook initial status report regarding mitigation strategies. Reference 5 provided the NextEra Energy Seabrook overall integrated plan. Reference 6 provided NextEra Energy Seabrook's first six-month status report. In Reference 7, the NRC requested additional information to enable the continued technical review of the NextEra Energy Seabrook Overall Integrated Plan (OIP). Reference 8 provided an update of milestone accomplishments since the last status report, including changes to the compliance method, schedule, or need for relief and the basis, if any. It also provided responses to the Reference 7 request for additional information to the extent possible. Reference 9 provided the third update of milestone accomplishments and also included answers to the request for additional information.
The attachment to this letter provides the fourth six-month status update of milestone accomplishments since the last status report, including changes to the compliance method, schedule, or need for relief and the basis, if any.
This letter contains no new regulatory commitments.
If you have any questions regarding this report, please contact Mr. Michael Ossing, Licensing Manager, at (603) 773-7512.
U.S. Nuclear Regulatory Commission SBK-L-15026/Page 3 I declare under penalty of perjury that the foregoing is true and correct.
Executed on February Z-7
,2015.
Sincerely, NextEra Energy Seabrook, LLC Dean Curtland Site Vice President Attachment cc:
D. Dorman, NRC Region I Administrator J.G. Lamb, NRC Project Manager, Project Directorate 1-2 P. Cataldo, NRC Senior Resident Inspector Director, Office of Nuclear Reactor Regulation Ms. Jessica'A. Kratchmann, NRR/JLD/PMB, NRC Mr. Eric E. Bowman, NRR/DPR/PGCB Mr. Perry Plummer Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management 33 Hazen Drive Concord, NH 03305 Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399
Attachment to SBK-L-15026 NextEra Energy Seabrook, LLC's Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
ATTACHMENT
1.0 INTRODUCTION
By letter dated February 26, 2013 (Agency wide Documents Access and Management System (ADAMS) Accession No. ML13063A439), NextEra Energy Seabrook, LLC (NextEra, the licensee) submitted an Overall Integrated Plan (OIP) for the Seabrook Nuclear Plant in response to the March 12, 2012, U.S. Nuclear Regulatory Commission (NRC) Order modifying licenses with regard to requirements for Reliable Spent Fuel Pool (SFP) Instrumentation (Order Number EA-12-051, ADAMS Accession No. ML12056A044). This submittal provides an update of milestone accomplishments since submittal of the Overall Integrated Plan, including any changes to the compliance method, schedule or need for relief/relaxation and the basis.
2.0 MILESTONE ACCOMPLISHMENTS
" Commence Engineering and Design - This milestone is in progress. Seabrook has selected SFP level instrumentation that will be used to meet the criteria delineated in the Overall Integrated Plan. Engineering Change 281849 for installation of the selected SFP level instrumentation is in the approval stage of development.
- Submit First 6 month update - Complete
" Submit Second 6 month update - Complete
- Submit Third 6 month update - Complete 3.0 MILESTONE SCHEDULE STATUS There currently are no changes to the Milestone Schedule provided in the Overall Integrated Plan (Reference 1). Any changes to the following target dates will be reflected in the six month updates.
The current milestones are:
Complete Engineering and Design 1Q 2015 (March)
" Complete Procurement of SFP Instruments 1Q 2015 (March)
- Complete Installation/ Instruments Operational 3Q 2015.(August)
Submit Fifth 6 Month Update 3Q 2015 (August).
" Second Refueling Outage 3Q 2015 (October)
" Training Complete 3Q 2015 (October)
" Required implementation date:
3Q 2015 (Refueling Outage 17)
Page I of 3
4.0 CHANGES TO COMPLIANCE METHOD There currently are no changes to the compliance method documented in the Overall Integrated Plan (Reference 1). Consistent with the requirements of Order EA-12-051 (Reference 2) and the Order guidance documents, the six month reports will delineate any proposed changes to compliance methods.
5.0 NEED FOR RELIEF!RELAXA TIONAND BASIS Seabrook is not requesting relief from the requirements of Order EA-12-051 (Reference 2) or guidance document JLD-ISG-2012-03 (Reference 3) at this time.
Consistent with the requirements of Order EA-12-051 (Reference 2) and the guidance in NEI 12-02 (Reference 4), the six month reports will delineate progress made, any proposed changes in compliance methods, updates to the schedule, and if needed, requests for relief and their bases.
6.0 REOUESTS FOR ADDITIONAL INFORMATION The NRC staff determined that additional information was required to enable the continued technical review of the NextEra Energy Seabrook, LLC (NextEra) Overall Integrated Plan (OIP). Table 1 provides a summary of the status of responses to the Request for Additional Information (RAIs) that were received on December 4, 2013 (Reference 5). Enclosure 1 provides details of the SFP mounting bracket for the level measuring instruments. Enclosure 2 summarizes the design requirements for the Westinghouse supplied level monitoring equipment with reference applicable Westinghouse qualification documentation. Required changes to RAI responses that result from changes in details developed during installation will be provided to the NRC as part of a future six month update.
Page 2 of 3
Table 1 Open RAIs Status RAI Levels Complete, Reference 11 RAI Arrangement Complete, Reference I I RAI-3 a, b, c - Mounting Complete, Table 2 RAI Mounting Complete, Table 2 RAI Mounting Complete, Reference 11 RAI-6 a, b, c - Qualification Complete, Table 2 RAI Qualification Complete, Table 2 RAI Independence Complete, Table 2 RAI Power Supply Complete, Table 2 RAI Accuracy Complete, Table 2 RAI-1 I - Testing and Calibration Complete, Table 2 RAI Display Complete, Table 2
RAI-13
Complete, Reference 11
RAI-14
Complete. Reference 11 RAI Testing and Calibration Complete, Table 2 References
- 1. NextEra Energy Seabrook, LLC's Overall Integrated Plan in Response to March 12, 2012 Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), dated February 26, 2013 (ADAMS Accession No. ML13063A439)
- 2. NRC Order EA-12-051, "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," dated March 12, 2012 (ADAMS Accession No ML12056A044).
- 3. NRC JLD-ISG-2012-03, Compliance with Order EA-12-051, Reliable Spent Fuel Pool Instrumentation, Revision 0, August 29, 2012.
- 4. NEI 12-02, Industry Guidance for Compliance with NRC Order EA-12-051, "To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," Revision 1, August 2012.
- 5. Seabrook Station, Unit 1 - Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA 051, Reliable Spent Fuel Pool Instrumentation (TAC No. MF0837), Dated December 4, 2013 (ADAMS Accession No. ML13267A388).
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ENCLOSURE-2 T
Parameter Westinghouse Reference A
io Test or
,Topic Smay DcmnNubrAdditonal Comment
- al is Licensee Evaluation Summary Document Number Analysls Results Design SFPIS WNA-DS-02957-GEN Contains technical N/A The design and implementation requirements as defined in Table 2 references 1, 2 and 3 Specification Requirements SFPIS requirements are bounded by the design Westinghouse Design Specification for the SFPIS (WNA-derived from based on NRC order, DS-02957-GEN).
References 1, 2, NEI guidance.
& 3 2
Test Strategy Per WNA-PT-00188-GEN Strategy for performing N/A The SFPIS qualification test strategy as described in WNA-PT-00188-GEN envelopes Requirements.
the testing and the Seabrook specific environmental and seismic design requirements. Refer to verification of the Seabrook Specification S-S-E-0227, Spent Fuel Pool Instrumentation System.
SFPIS and pool-side bracket.
3 Environmental 500 F to 1400 EQ-QR-269 and WNA-Results are summarized Test passed For Seabrook specific temperature and humidity requirements the electronic enclosures qualification F,
TR-03149-GEN for all in EQ-QR-269 and conditions that will be located in the Containment Enclosure Building and Control Building for electronics 0 to 95% RH conditions.
WNA-TR-03149-GEN.
described.
Essential Switchgear Rooms are enveloped by the Westinghouse qualification for enclosure with Radiation Aging normal and BDBE conditions.
Display TID u sI E03 Ry verification As described in Westinghouse Report WNA-TR-03149-GEN, radiation is not normal (outside summarized in Section considered to be an aging mechanism for equipment that is only subjected to TID < 1E4 SFP area) 5 of WNA-TR-03149-rads. TID to equipment located in the Containment Enclosure Building and Control TID < 1 E03 R y GEN.
Building Essential Switchgear Rooms will be less than 1 E3 rads for normal and BDBE abnormal conditions. Refer to Seabrook Specification S-S-E-0227, Spent Fuel Pool (outside SFP Instrumentation System.
area)
Westinghouse has provided an interim position regarding the radiation aging qualification and the open item from Steris (ref. Response to Table 2, NRC Question 7). NextEra Energy is tracking closure of the open item and will provide additional update if Westinghouse's position changes.
Page 1 of 8
ENCLOSURE -2 arameter Westinghouse Reference A
Test or oi Additional Comment Aayi ieseEauto Summary Document Number Analysis
.Results 4
Environmental Testing for Level Sensor components in SFP area -
Saturated Steam &
Radiation 50 OF to 212 0 F and 100%
humidity EQ-QR-269 Thermal aging test results summarized in EQ-QR-269 Section 5.2.
Steam test results summarized in EQ-QR-269 Section 5.7.
Passed The temperature and humidity values of 212'F and 100% envelop the service environment requirements for the SFPIS components that will be located in the SFP area. Refer to Seabrook Specification S-S-E-0227, Spent Fuel Pool Instrumentation System.
1E03 R y WNA-TR-03149-GEN and Thermal Aging &
Passed The normal operating dose in the SFP area per is < I.E03 R y. Refer to Seabrook normal (SFP EQ-QR-269 radiation aging Specification S-S-E-0227, Spent Fuel Pool Instrumentation System.
area) verification are summarized in Sections 4.1 and 5 (entire system) of WNA-TR-03149-GEN IE07Ry BDBE (SFP area)
EQ-QR-269 Radiation aging program was conducted in accordance with procedures EQ-TP-326 and EQ-TP-354.
Radiation aging results are summarized in EQ-QR-269 Section 5.3.
Passed The BDBE radiation value to which the Westinghouse equipment was qualified is 1.E+9 R y for the probe stainless steel cable and weight and 1 E+7R y for the equipment on the Operating deck above the pool (Ref. Section 5.1.2 of WNA-TR-03149-GEN).
With SFP water level at Level 3 the only components of SFPI that are exposed to the SFP are the stainless steel probe and the stainless steel anchor. Since stainless steel is inherently resistant to degradation from radiation the probe and anchor, environmental testing of these components was not required. Equipment located above the SFP (Coaxial cable, coupler and connector) were aged to lE+l 1 R y to assure qualification to 1 E+7 R y. Westinghouse completed its aging qualification of the SFPIS to 10 years.
Westinghouse has provided an interim position regarding the radiation aging qualification and the open item from Steris (ref. Response to Table 2, NRC Question 7).
NextEra Energy is tracking closure of the open item and will provide additional update if Westinghouse's position changes.
U ______________
Page 2 of 8
ENCLOSURE -2 Parameter Westinghouse Refeec Test or Topic Additional Comment Licensee Evaluation Summary Document Number Analysis Results Environmental 500 F to 1400 WNA-TR-03149-GEN and Testing summarized in Passed Temperature is < 140'F and humidity is < 95% RH for abnormal conditions in the WNA-TR-03149-GEN, Testing for F,
EQ-QR-269 Section 3.3.
Containment Enclosure Building and Control Building Essential Switchgear Rooms.
Level Sensor elens 0 to 95% RH Radiation Aging As described in Westinghouse Report WNA-TR-03149-GEN, radiation is not Hou s
verification considered to be an aging mechanism for equipment that is only subjected to TID 1E4 Housing -
summarized in WNA-rads. TID to equipment located in the Containment Enclosure Building and Control outside SFP TID < 1E03 R y TR-03149-GEN, Building Essential Switchgear Rooms will be less than 1E3 rads for normal and BDBE normal (outside Section 5.
conditions. Refer to Seabrook Specification S-S-E-0227, Spent Fuel Pool SFP area)
Thermal aging test Instrumentation System TID < I E03 R y results summarized in abnormal EQ-QR-269 Section (outside SFP 5.2.
area)
Steam test results summarized in EQ-QR-269 Section 5.7 6
Thermal &
1E03 R y EQ-QR-269 and WNA-Thermal aging test Passed See response to Item 4 above.
Radiation normal (SFP TR-03149-GEN results summarized in Aging -
area)
EQ-QR-269 Section Aging Tests - Westinghouse completed aging qualification of SFPIS to 10 years.
organic 5.2.
Westinghouse has provided an interim position regarding the radiation aging componentsi E07 R Radiation aging results qualification and the open item from Steris (ref, Response to Table 2, NRC Question SFP area BDBE (SFP are summarized in EQ-7). NextEra Energy is tracking closure of the open item and will provide additional area)
QR-269 Section 5.3 update if Westinghouse's position changes.
Thermal Aging &
radiation aging verification summarized in Sections 4.1 and 5 of WNA-TR-03149-GEN.
Page 3 of 8
ENCLOSUREN-2 Parameter Westinghouse Reference Test or L
Topic Summary Document Number Additional Comment Analysis Licensee Evaluation Results 7
Basis for Dose Normal LTR-SFPIS-13-35 and Westinghouse Basis for Passed for NextEra has determined the Westinghouse basis is acceptable.
Requirement Conditions:
WNA-DS-02957-GEN Radiation Dose all The normal operating dose in the SFP area is
<1 E+3 R y, which is bounding for 1E03 R y TID Requirement conditions Seabrook. Refer to Section 5.1.1 of WNA-TR-03149-GEN and Seabrook specification (above pool)
S-S-l -E--0227, Spent Fuel Pool Instrumentation System.
1E09 R y TID Equipment located above the SFP (Coaxial cable, coupler and connector) were aged to (1' above fuel I E+ 1I R y to assure qualification to 1E+7 R y. The as tested test BDBE condition (TID rack) of 1 E+ 1 R y) above bounds the Seabrook requirement of 1.06E+7 R y.
BDBE Conditions:
1E07 R y TID (above pool)
<lE09 R y TID (1' above fuel rack) 8 Seismic Per Spectra in EQ-QR-269 EQ-QR-269 Passed The TRS that was used by Westinghouse for seismic qualification of the SFPIS, Qualification WNA-DS-summarizes the results including the poolside mounting brackets, envelops the Seabrook RSS.
02957-GEN of seismic testing that was performed by Westinghouse.
WNA-TR-03149-GEN WNA-TR-03149-GEN Passed provides high level summary of the pool-side bracket analysis and equipment seismic test program.
Page 4 of 8
ENCLOSURE -2 Parameter Westinghouse Reference Test or Topic S
ary Docum e Numer Additional Comment Test Licensee Evaluation Summary Document Number Analysis Results EQ-TP-353 (procedure)
Seismic Pull test for Passed straight and 90 degree coaxial connectors was performed in accordance with Westinghouse procedure EQ-TP-353.
9 Sloshing N/A LTR-SEE-II-13-47 and Calculation to Passed Adequate sloshing forces (inclusive of vertical and horizontal impact forces, WNA-TR-03149-GEN.
demonstrate that probe hydrodynamic forces) were considered by Westinghouse in the calculation for sloshing will not be sloshed out forces. The calculated forces were also considered by Westinghouse in the design the of the SFP.
bracket, including anchorage requirements, to ensure the probe will not be degraded or Sloshing is also sloshed out of the SFP during a seismic event.
addressed in Section 7.2 of WNA-TR-03149-GEN.
10 Spent Fuel Acceptance WNA-TP-04613-GEN and Test plan and procedure Passed The monitoring requirements from Westinghouse procedures WNA-TP-04613-GEN Pool Criteria for WNA-TP-00 1 89-GEN used to demonstrate and WNA-TP-00 1 89-GEN assure SFPIS performance in accordance with requirements Instrumenta-Performance that SFPIS meet its of Table 2 reference 1, 2 and 3.
tion System during EQ operational and Functionality testing accuracy requirements Test Procedure during Equipment Qualification Testing.
11 Boron Build-Per requirement WN-TR-03149-GEN, Boron build up Passed Boron buildup testing and justification provided in WNA-TP-00 I 89-GEN "Integrated Up in WNA-DS-LTR-CDME-1 3-78A and demonstrated through Functional Test Plan" assure SFPIS performance in accordance with the requirements 02957-GEN LTR-SFPIS-13-026 Integrated Functional of Table 2 reference 1, 2 and 3 Test (IFT).
Page 5 of 8
ENCLOSURE -2 Parameter Westinghouse Reference Test or Topic Additional Comment Licensee Evaluation Summary Document Number Analysis Results 12 Pool-side N/A CN-PEUS-14-16 Analysis included Passed See response to NRC Question. 4. Seabrook seismic requirements to withstand a SSE Bracket seismic forces and are bounded by the Westinghouse analysis for the poolside mounting bracket.
Seismic hydrodynamic forces, Equipment anchorage will be designed by Seabrook to meet the calculated Analysis as appropriate.
Westinghouse loads (tension and shear loads, and hydrodynamic load) with appropriated safety margin.
13 Additional N/A WNA-DS-02957-GEN Weights provided to N/A Equipment anchorage will be designed by Seabrook to meet the calculated Brackets licensees for their own Westinghouse loads (tension and shear loads, and hydrodynamic load) with (Sensor evaluation.
appropriated safety margin.
Electronics and Electronics Enclosure) 14 Shock &
WNA-DS-WNA-TR-03149-GEN WNA-TR-03149-GEN, N/A Westinghouse SFP measurement channels will be permanently installed and fixed to Vibration 02957-GEN Section 7 provides rigid, structural walls or floors of Seismic Category I structures.
justification for shock and vibration.
Page 6 of 8
ENCLOSURE -2 Parameter Westinghouse Reference Additional Test or Summary Document Number Analysis Results 15 Westinghouse Integrated WNA-TP-04752-GEN, The Integrated passed SFPIS functional testing and post modification testing in accordance with Engineering Factory Functional Test WNA-TR-03357-WEP, Functional Test Change 281849 assure SFPIS performance in accordance with the requirements of Acceptance Requirements WNA-TR-03351-GPRYI demonstrated Table 2 references 1, 2 and 3.
Test, including from WNA-DS-functionality of the full dead zone 02957-GEN.
system, which included verification.
12" dead-zone calibration of each at top of probe channel.
Dead-zone tests are 4" dead-zone at bottom of probe described in WNA-TP-04752-GEN, Section 9.6.2.
16 Channel
+/- 3 inches per WNA-CN-00301-GEN Channel accuracy from Passed Seabrook has reviewed WNA-DS-02957-GEN and WNA-CN-00301-GEN and found Accuracy WNA-DS-measurement to that channel accuracy requirements are met.
02957-GEN display.
17 Power 3 day battery WNA-CN-00300-GEN N/A Passed Seabrook has reviewed WNA-CN-00300-GEN and concluded that the SFPIS battery Consumption life (minimum) has a capacity that is > 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> which meets the Order requirements. The SFPIS power SFPIS power loading does not challenge the plant electrical distribution system or Emergency Diesel consumption Generator loading.
18 Technical N/A WNA-GO-00127-GEN Information and N/A Seabrook will utilize WNA-GO-00 127-GEN as input for procedure preparation and Manual instructions for system maintenance.
Operation, Installation, use, etc. are included here.
Page 7 of 8
ENCLOSURE -2 Parameter Westinghouse Reference Te.t.or Topic S
ary Docum e Numer Additional Comment Analysis Licensee Evaluation Summary Document Number A
1nalysis Results 19 Calibration Routine WNA-TP-04709-GEN Includes preventative N/A Seabrook will utilize WNA-TP-04709-GEN as input for development of plant Testing/calibrati maintenance actions procedures for calibration and preventive maintenance of the SFPIS.
on verification such as those for Boron and Calibration buildup and cable probe method inspection.
20 Failure Modes N/A WNA-AR-00377-GEN Addresses mitigations N/A Seabrook will utilize WNA-AR-00377-GEN as input for procedure preparation and and Effects for the potential failure system troubleshooting if required.
Analysis modes of the system.
(FMEA) 21 EMI/ RFI RG 1.180, Rev.
WNA-TR-03149-GEN and N/A Passed to Refer to the response to Table 2, NRC Question 7. NextEra has reviewed the test report Qualification 1 test conditions EQ-QR-269 perfor-and concluded that the results comply with the requirements performance criterion B.
Testing mance criterion B Page 8 of 8