IR 05000443/2022004

Integrated Inspection Report 05000443/2022004 and Independent Spent Fuel Storage Installation Inspection Report 07200063/2022001

ML23030A482
Person / Time
Site:	Seabrook
Issue date:	01/30/2023
From:	Matt Young NRC/RGN-I/DORS
To:	Coffey B Florida Power & Light Co
References
IR 2022004, ISFSI IR 2022001
Download: ML23030A482 (1)

Text

January 30, 2023

Bob Coffey Executive Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company 700 Universe Blvd.

Mail Stop: EX/JB Juno Beach, FL 33408

SUBJECT: SEABROOK STATION - INTEGRATED INSPECTION REPORT 05000443/2022004 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION INSPECTION REPORT 07200063/2022001

Dear Bob Coffey:

On December 31, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Seabrook Station. On January 17, 2023, the NRC inspectors discussed the results of this inspection with Kyle Barry, Nuclear Operations Site Director and other members of your staff. The results of this inspection are documented in the enclosed report.

One Severity Level IV violation without an associated finding is documented in this report.

We are treating this violation as a non-cited violation consistent with Section 2.3.2 of the Enforcement Policy. Specific follow-up inspection is not warranted for this traditional enforcement violation because it did not involve willfulness, impeding the regulatory process, or actual safety consequences.

No NRC-identified or self-revealing findings were identified during this inspection.

If you contest the violation or the significance or severity of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN:

Document Control Desk, Washington, DC 20555- 0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Resident Inspector at Seabrook Station. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, Matt R. Young, Chief Projects Branch 2 Division of Operating Reactor Safety

Docket Nos. 05000443 and 07200063 License No. NPF-86

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000443 and 07200063

License Number: NPF-86

Report Numbers: 05000443/2022004 and 07200063/2022001

Enterprise Identifier: I-2022-004- 0041

Licensee: NextEra Energy Seabrook, LLC

Facility: Seabrook Station

Location: Seabrook, New Hampshire

Inspection Dates: October 1, 2022 to December 31, 2022

Inspectors: C. Newport, Senior Resident Inspector T. Daun, Resident Inspector N. Eckhoff, Health Physicist O. Masnyk Bailey, Health Physicist P. Ott, Operations Engineer M. Patel, Senior Reactor Inspector S. Veunephachan, Health Physicist

Approved By: Matt R. Young, Chief Projects Branch 2 Division of Operating Reactor Safety

Enclosure

SUMMARY

The N RC continued monitoring the licensees performance by conducting an integrated inspection at Seabrook Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.

List of Findings and Violations

Improper Removal of Quality Control Hold Points from Dry Cask Storage Procedures Cornerstone Severity Cross-Cutting Report Aspect Section Not Applicable Severity Level IV Not Applicable 60855 NCV 05000443/2022004-01 Open/Closed The inspectors identified a Severity Level IV non-cited violation of NextEra's Quality Assurance Manual when the licensee failed to obtain permission from either the Quality Control Level III Inspector or Nuclear Assurance and Assessment (NAA) Manager prior to removing quality control hold points as specified in the dry cask storage operations procedure.

Additional Tracking Items

None.

PLANT STATUS

Seabrook Station began the inspection period operating at 100 percent rated thermal power and remained at or near full power for the inspection period.

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed activities described in IMC 2515, Appendix D, Plant Status, conducted routine reviews using IP 71152, Problem Identification and Resolution, observed r isk significant activities, and completed on -site portions of IPs. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

71111.01 - Adverse Weather Protection

Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated readiness for seasonal extreme weather conditions prior to the onset of seasonal cold temperatures for the following systems on December 13:

• Emergency feedwater, service water, spent fuel storage, and demineralized water

71111.04 - Equipment Alignment

Partial Walkdown Sample (IP Section 03.01) (3 Samples)

The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) B service water cooling tower during A service water cooling tower maintenance on October 12

(2) B emergency diesel generator after monthly operability surveillance on November 28

(3) 'A' coolant charging pump following 'A' valve maintenance on December 17

Complete Walkdown Sample (IP Section 03.02) (1 Sample)

(1) The inspectors evaluated system configurations during a complete walkdown of the service water system on December 20

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:

(1) West main steam and feedwater pipe enclosure (MS-F-1/2/3B-Z) on November 2

(2) Primary auxiliary building (PAB-F-2A/C-Z) on November 10

(3) 'A' switchgear room (CB-F-1A-A) on November 22

(4) B emergency diesel generator (DG-F-3C-A/DG-F-2A-A/DG-F-1B-A) on December 18

(5) Primary auxiliary building (PAB-F-1J-Z) on December 19

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

Requalification Examination Results (IP Section 03.03) (1 Sample)

(1) The inspectors reviewed and evaluated the licensed operator annual requalification results on November 21, 2022 for the annual operating exam completed on June 20, 2022.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)

(1) The inspectors observed and evaluated licensed operator performance of the following activities in the control room:

• Main turbine valve testing on October 21

• A emergency diesel generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> endurance run on November 13

• Control rod operability testing on December 5

Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)

(1) The inspectors observed and evaluated licensed operator requalification training conducted in the plant-reference simulator on December 14

71111.12 - Maintenance Effectiveness

Maintenance Effectiveness (IP Section 03.01) (1 Sample)

The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components remain capable of performing their intended function:

(1) Residual heat removal flow control valve classifications and inservice testing requirements on December 15

Quality Control (IP Section 03.02) (1 Sample)

(1) The inspectors reviewed the licensees quality control program to verify quality control verifications are properly specified in accordance with the Quality Assurance Program and are implemented as specified.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (5 Samples)

The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:

(1) Elevated risk during turbine driven emergency feedwater pump testing on October 5

(2) Elevated risk during 'A' emergency diesel generator run and emergency safeguards actuation system relay testing on October 11

(3) Emergent elevated risk during 'F' inverter rectifier failure on October 18

(4) Elevated risk during supplemental emergency power system bus relay calibrations on November 3

(5) Elevated risk during ocean service water maintenance on November 16

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)

The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:

(1) A centrifugal charging pump elevated vibrations (AR 02437962) on October 3

(2) 120VAC distribution following failed silicone controlled rectifiers in 'F' inverter (AR 02439604) on October 17

(3) B primary component cooling water temperature control valve nitrogen bottle leakage (AR 02442631) on November 30

(4) Control rod H4 misalignment (AR 02443092) on December 5

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)

The inspectors evaluated the following temporary or permanent modifications:

(1) Mechanical penetration area north and south wall structural modifications on December 15

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (4 Samples)

The inspectors evaluated the following post -maintenance testing activities to verify system operability and/or functionality:

(1) A turbine driven emergency feedwater pump steam admission valve MS-V-394 diagnostic testing and maintenance on October 4

(2) 'B' residual heat removal flow instrument following card replacement on October 25

(3) 'C' ocean service water pump and motor replacement on November 18

(4) B containment building spray agastat relay testing on November 29

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance testing activities to verify system operability and/or functionality:

Surveillance Tests (other) (IP Section 03.01) (2 Samples)

(1) 'B' engineered safeguards features actuation system slave relay K608 go-test on October 31

(2) 'A' emergency diesel generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> load test and hot restart on November 14

Inservice Testing (IP Section 03.01) (1 Sample)

(1) A centrifugal charging pump quarterly inservice flow test on October

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Walkdowns and Observations (IP Section 03.01) (4 Samples)

The inspectors evaluated the following radioactive effluent systems during walkdowns:

(1) Wide range gas monitor to plant stack effluent discharge system

(2) Liquid waste test tanks effluent discharge system and sample lines

(3) Steam generator blowdown flash tank effluent discharge system

(4) Turbine building sump effluent discharge system

Sampling and Analysis (IP Section 03.02) (4 Samples)

Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:

(1) Oil and water separator vault 2 effluent sample

(2) Wide range gas monitor particulate sample

(3) Wide range gas monitor noble gas sample

(4) Turbine building sump effluent sample

Dose Calculations (IP Section 03.03) (3 Samples)

The inspectors evaluated the following dose calculations:

(1)22-304 liquid waste test tank 'B' batch release

(2)22-282 liquid waste test tank 'A' batch release

(3)21-211 containment purge batch release

Abnormal Discharges (IP Section 03.04) (1 Sample)

The inspectors evaluated the following abnormal discharges:

(1) There were no abnormal discharges

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

BI01: Reactor Coolant System (RCS) Specific Activity Sample (IP Section 02.10)===

(1) For the period October 1, 2021 through September 30, 2022

BI02: RCS Leak Rate Sample (IP Section 02.11) (1 Sample)

(1) For the period October 1, 2021 through September 30, 2022

OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15) (1 Sample)

(1) For the period October 1, 2021 through September 30, 2022

PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample (IP Section 02.16) (1 Sample)

(1) For the period October 1, 2021 through September 30, 2022

71152A - Annual Follow-up Problem Identification and Resolution Annual Follow-up of Selected Issues (Section 03.03)

The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:

(1) Evaluation of inservice testing associated with misclassified residual heat removal system flow control valves

(2) Corrective actions and extent of condition of review as a result of reactor trip breaker under-voltage trip assembly failures

71152S - Semiannual Trend Problem Identification and Resolution Semiannual Trend Review (Section 03.02)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends that might be indicative of a more significant safety issue.

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60855 - Operation Of An Independent Spent Fuel Storage Installation (ISFSI) Operation Of An ISFSI

(1) The inspectors evaluated NextEra's ISFSI cask loadings during the period of September 19-22, 2022. Specifically, the inspectors observed the following activities:

• Fuel selection and fuel loading

• Heavy load movement of the transfer cask and loaded dry storage canister

• Decontamination of cask

• Drying and backfill evolutions

• Closure welding and non-destructive weld evaluations

• Transfer and transport evolutions

• Radiological field surveys

• Implementation of the quality assurance program

INSPECTION RESULTS

Improper Removal of Quality Control Hold Points from Dry Cask Storage Procedures Cornerstone Severity Cross-Cutting Report Aspect Section Not Severity Level IV Not 60855 Applicable NCV 05000443/2022004 - 01 Applicable Open/Closed The inspectors identified a Severity Level IV non - cited violation of NextEra's Quality Assurance Manual when the licensee failed to obtain permission from either the Quality Control Level III Inspector or NAA Manager prior to removing quality control hold points as specified in the dry cask storage operations p rocedure.

Description : Florida Power & Light Company (now NextEra Energy Company) letter dated October 11, 2006, provided notification of the licensees intent to apply its previously NRC -

approved 10 CFR Part 50, Appendix B, quality assurance program to Seabrook ISFSI activit ies. Specifically, N uclear Assurance Quality Assurance, Revision 56, "Quality Assurance Manual," delineates the quality assurance program for Seabrook Station.

Quality Assurance Manual Section 3.1.1.1 states, in part, that q uality control hold points are inserted in procedures and work control documents and applied as necessary to control the quality materials, structures, components, or systems within the scope of the Quality Assurance Topical Report to predetermined requirements. Section 3.1.1.2.b.7 states that hold point inspections can be waived by any Level II Inspector, but permission must first be obtained from either the Quality Control Level III Inspector or NAA Manager prior to granting the waiver. Contrary to the above, on August 11, 2022, NextEra removed quality control hold points from Procedure FX3000.12, Revision 16, "DSC Sealing Operations," without first obtaining permission from either the Nuclear Assurance Level III Inspector or NAA Manager.

Corrective Actions: Upon identification, NextEra entered this issue into its corrective action program and obtained approvals from the required Quality Control Level III Inspector.

Corrective Action References: AR 02437549

Performance Assessment:

ISFSI and nuclear materials facilities are only subject to traditional enforcement and therefore not subject to the Significance Determination Process as delineated in the Operating Reactor Assessment Program as outlines in IMC 0305.

Enforcement:

Severity: This violation was determined to be a S everity Level IV violation using Section 6.3 of the NRC Enforcement Policy, dated January 14, 2022.

Violation: 10 CFR 72.140(b) states, in part, that each licensee shall establish, maintain, and execute a quality assurance program satisfying each of the applicable criteria of this subpart, and satisfying any specific provision which are applicable to the licensee's activities. Contrary to the above, on August 11, 2022, NextEra did not execute its quality assurance program.

Specifically, the licensee removed quality control hold points from Procedure FX3000.12, Revision 16, "DSC Sealing Operations," without first obtaining permission from either the Quality Control Level III Inspector or NAA Manager.

Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Observation: Annual Review of Residual Heat Removal Valves Found 71152A Misclassified as Passive vice Active in the Inservice Testing Program Inspectors selected residual heat removal valves found misclassified as passive vice active in the inservice testing program for this annual follow-up sample to evaluate the timely disposition of this issue and ensure that corrective actions are commensurate with the safety significance. Inspectors reviewed the corrective action program documents associated with operating experience that Seabrook received from Wolf Creek which incorrectly classified several valves as passive in the inservice testing program. An incorrect classification can impact the required inservice testing.

The licensee determined that four valves associated with the residual heat removal system had been misclassified as passive when they had an active safety function.

The licensee created actions in the corrective action program to revise procedures associated with the inservice testing of the four valves. The procedure updates have been completed and the four valves have all been stroke timed to establish reference times and limiting values as required by the inservice testing program. The procedures also establish appropriate testing intervals for future valve trending.

Inspectors noted that corrective actions were timely and appropriate. No findings or violations were identified during the review.

Observation: Annual Review of Corrective Actions and Extent of Condition of 71152A Review as a Result of Reactor Trip Breaker Under-Voltage Trip Assembly Failures The inspectors reviewed NextEra's evaluation and corrective actions associated with various failures of reactor trip and bypass breakers attributed to issues with the under-voltage trip assembly. Specifically, inspectors focused on the corrective action program evaluation associated with AR 02409702. The annual follow-up sample was selected due to an adverse trend of reactor trip breaker failures within the corrective action program and to evaluate any potential impact on the breaker's ability to close/trip.

The inspectors reviewed the evaluation, extent of condition review, procedures, manufacturers failure analysis, relevant issue reports and interviewed the licensee subject matter expert on the topic.

Based on the documents reviewed and discussions with personnel, inspectors did not identify any findings or violations of more than minor significance.

Minor Violation 71152S Minor Violation: The inspectors evaluated a sample of issues and events that occurred over the third and fourth quarters of 2022. The evaluation revealed a trend associated with transient combustible material not being adequately controlled or evaluated.

Seabrook Station, Unit 1 Facility Operating License Condition 2.F requires, in part, for NextEra to implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, the Fire Protection Program Report, and the Fire Protection and Safe Shutdown Capability report, as supplemented. FP2.2, Control of Combustible Materials, Revision 24, provides the programmatic requirements for combustible materials within safety-related areas. Inspectors determined that Seabrook not maintaining provisions of the fire protection program as required over this period was a performance deficiency and was reasonably within their ability to foresee and correct. Five examples associated with this performance deficiency include:

• August 4, 2022: AR 02433626 (NRC-identified) documented a can of flammable aerosol left behind following smoke detector testing. Once identified by the inspectors, the materials were immediately removed from the location.

• August 10, 2022: AR 02434022 (NRC-identified) documented cardboard barrels not stored in accordance with the requirements of the approved permanent storage area permit. Once identified by the inspectors, the barrels were appropriately covered with fire retardant cloth as required by the storage permit.

• September 12, 2022: AR 02436563 (NRC-identified) documented a repeat condition of cardboard barrels not stored in accordance with the requirements of the approved permanent storage area permit. The station took action to immediately cover the barrels again and then obtained specialty covers fitting the barrels to help prevent future issues.

• October 17, 2022: AR 02439603 documented the on-shift fire brigade leader identified combustibles in a high risk area without a fire loading evaluation. The station implemented an appropriate fire patrol until the fire loading evaluation is completed for the area.

• December 27, 2022: AR 02444657 documented the on-shift fire brigade leader identified combustibles improperly stored in a high risk area. The combustibles were removed from the area.

AR 2445019 was initiated to further evaluate how non-compliant transient combustible materials in the plant are addressed. The inspectors determined that, in most cases, the issues were appropriately evaluated by Seabrook staff for potential trends at a low threshold and resolved within the scope of the corrective action program.

Screening: The inspectors determined the performance deficiency was minor. Specifically, the initiating events cornerstone objective was not adversely affected since the fire protection strategies for the area/zone remained sufficient even with the error.

Enforcement:

This failure to comply with provisions of the approved fire protection program constitutes a minor violation that is not subject to enforcement action in accordance with the NRCs Enforcement Policy.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

• On November 10, 2022, the inspectors presented the 71124.06/71151 debrief inspection results to Brian Booth, Site Vice President and other members of the licensee staff.

• On January 17, 2023, the inspectors presented the integrated inspection results to Kyle Barry, Nuclear Operations Site Director and other members of the licensee staff.

THIRD PARTY REVIEWS

Inspectors reviewed Institute of Nuclear Power Operations reports that were issued during the inspection period.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 02438441

Documents 02438556

2443158

Procedures OP-AA-102-1002 Seasonal Readiness Revision 39

Work Orders 40804059

71111.04 Corrective Action 02442254

Documents 02442256

2442265

Drawings 1-SW-B20792 Service Water System Nuclear Overview Revision 6

1-SW-B20794 Service Water System Nuclear Detail Revision 41

1-SW-B20795 Service Water System Nuclear Detail Revision 50

1-SW-B20796 Service Water System Nuclear Detail Revision 6

1-SWA-B20372 Air Handling System for Service Water Pumphouse and Revision 7

Service Water Cooling Tower

Procedures OS1016.05 Service Water Cooling Tower Operations Revision 39

OX1426.19 Aligning DG 1B Control for Auto Start Revision 7

Work Orders 40789104

71111.05 Corrective Action 02439603

Documents 02440827

71111.12 Corrective Action 02437549

Documents

Resulting from

Inspection

Work Orders 40669738

40744923

40754508

40762252

40762253

40800098

40813751

71111.13 Corrective Action 02439604

Inspection Type Designation Description or Title Revision or

Procedure Date

Documents

Work Orders 40808642

40808989

40808997

240311

71111.15 Corrective Action 02437962

Documents 02439604

2442631

2443092

Drawings FP33851 Overall UPS Schematic Revision 5

FP33949 Loss of 120VAC Vital Instrument Bus PP1E or PP1F Revision 13

Miscellaneous 9763-006-106-2 Purchase Order Specification for Uninterruptible Power

Supplies

Calc-9763-3-ED-Uninterruptible Power Supplies (UPS) Load, Class IE

00-34-F

DBD-ED-04 Design Basis Document 120VAC Vital and Non-vital Revision 6

Instrument Power Systems

Procedures OS1247.02 Loss of 120VAC Vital Instrument Bus PP1E or PP1F Revision 17

OX1410.02 Quarterly Rod Operability Surveillance Revision 9

Work Orders 40847479

40849644

40854902

71111.18 Corrective Action 02276197

Documents

Miscellaneous 170443-CA-15 Repair Design for the Mechanical Penetration North and Revision 2

South Walls

170443-CA-15, Evaluation of Mechanical Penetration Area Structure Revision 0

App H

Engineering Mechanical Penetration Area North and South Wall Structural Revision 1

Change 294652 Modifications

Field Change Structural Modification of the Mechanical Penetration Area Revision 1

Request 294652

Work Orders 40751508

Inspection Type Designation Description or Title Revision or

Procedure Date

71111.19 Corrective Action 02358763

Documents 02438768

2442647

Drawings 1-NHY-310900 Containment Spray Pump 1-P-9B Protection Schematic Revision 2

Procedures LS0563.11 Testing of Agastat 125 VDC (7000 Series) TDPU Timing Revision 11

Relays

OX1406.02 Containment Spray Pump and Valve Quarterly Operability 18 Revision 24

Month Position Indication and Comprehensive Pump Testing

OX1436.02 Turbine Driven Emergency Feedwater Pump Quarterly and Revision 35

Monthly Valve Alignment

OX1456.81 Operability Testing of IST Valves Revision 42

Work Orders 40727715

40735009

40773795

40777647

40787202

40799660

40813351

40824251

40832087

40832392

71111.22 Corrective Action 02437962

Documents

Procedures OX1426.05 DG 1B Monthly Operability Surveillance Revision 55

OX1426.22 Emergency Diesel Generator 1A 24 Hour Load Test and Hot Revision 33

Restart

OX1456.01 Charging Pump A & B Quarterly Flow and Valve Stroke Revision 28

Position Test and 18 Month Remote Position Indication

Verification

OX1456.46 Train B ESFAS Slave Relay K608 Go-Test Revision 09

Work Orders 40810278

40810564

40810596

Inspection Type Designation Description or Title Revision or

Procedure Date

40810622

40847479

71152A Corrective Action 00018073

Documents 02409702

2406026

2409702

2409185

2376637

200735

01811285

2410481

2420425

Procedures LS0557.26 Corrective Maintenance of Westinghouse DS-416 Reactor Revision 2

Trip Breakers

LS0557.30 Post Outage Inspection of Reactor Trip Breakers Revision 1

OX1413.01 A Train RHR Quarterly Flow and Valve Stroke Test and 18 Revision 31

Month Valve Stroke Observation

OX1413.03 A Train RHR Quarterly Flow and Valve Stroke Test and 18 Revision 24

Month Valve Stroke Observation

OX1456.81 Operability Testing of IST Valves Revision 44

Work Orders 40726023

40726026

40726041

205262

260517

40776756

40776756

40782369

40782369

15