IR 05000280/2019002

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NRC Integrated Inspection Report 05000280/2019002 and 05000281/2019002; 07200055/2019001
ML19217A072
Person / Time
Site: Surry  Dominion icon.png
Issue date: 08/05/2019
From: Bradley Davis
Division Reactor Projects II
To: Stoddard D
Virginia Electric & Power Co (VEPCO)
Reeder D
References
IR 2019001, IR 2019002
Download: ML19217A072 (20)
v • d • e


Text

{{#Wiki_filter:ust 5, 2019

SUBJECT:

SURRY POWER STATION - NRC INTEGRATED INSPECTION REPORT 05000280/2019002 AND 05000281/2019002; 07200055/2019001

Dear Mr. Stoddard:

On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Surry Power Station. On July 3, 2019, the NRC inspectors discussed the results of this inspection with Mr. Fred Mladen and other members of your staff. The results of this inspection are documented in the enclosed report.

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

The inspectors documented a licensee-identified violation which was determined to be of very low safety significance in this report. The NRC is treating this violation as non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy. 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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, /RA/ Bradley J. Davis, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 05000280 and 05000281 07200055 License Nos. DPR-32 and DPR-37 SNM-2501

Enclosure:

As stated

Inspection Report

Docket Numbers: 05000280 and 05000281 07200055 License Numbers: DPR-32 and DPR-37 SNM-2501 Report Numbers: 05000280/2019002 and 05000281/2019002 07200055/2019001 Enterprise Identifier: I-2019-002-0030 I-2019-001-0124 Licensee: Virginia Electric and Power Company Facility: Surry Power Station Location: Surry, VA Inspection Dates: April 1, 2019 to June 30, 2019 Inspectors: L. McKown, Senior Resident Inspector C. Read, Resident Inspector S. Monarque, Project Engineer C. Stancil, Senior Fuel Facility Inspector Approved By: Bradley J. Davis, Chief Reactor Projects Branch 4 Division of Reactor Projects Enclosure

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a integrated inspection at Surry Power 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. A licensee-identified non-cited violation is documented in report section 71153.

List of Findings and Violations No findings or violations of more than minor significance were identified.

Additional Tracking Items Type Issue Number Title Report Status Section LER 05000281/2019-001-00 LER 2019-001-00, Foreign Material 71153 Closed in Breaker Contact Causes Pressurizer Power Operated Relief Valve Block Valve Inoperability.

PLANT STATUS

Unit 1 operated at or near rated thermal power for the entire inspection period.

Unit 2 began the inspection period at rated thermal power. On April 22, 2019, the unit was down powered to 83 percent to repair both high pressure heater drain pumps. The unit was returned to rated thermal power on April 25, 2019, and remained at or near rated thermal power for the remainder of 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 plant status activities described in IMC 2515 Appendix D, Plant Status and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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.

REACTOR SAFETY

71111.01 - Adverse Weather Protection Summer Readiness Sample (IP Section 03.01)

Main article: IP 71111.01
(1) The inspectors evaluated summer readiness prior to the onset of seasonal hot temperatures for plant ventilation systems, vital equipment checks, and temporary equipment installation on May 13, 2019.

71111.04 - Equipment Alignment Partial Walkdown Sample (IP Section 03.01)

Main article: IP 71111.04

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

(1) Unit 1 Turbine Driven Auxiliary Feedwater system on April 18, 2019.
(2) Emergency Service Water Pumps 1-SW-P-1A and -1C protected equipment on April 29, 2019.
    (3)    #2 and #3 Emergency Diesel Generators (EDG) during testing of the #1 EDG on June 24, 2019.
(4) Unit 2 Reactor Trip and Bypass Trip Breaker Partial Alignment on June 25, 2019.
(5) Unit 1 Charging Operating pump trains during overhaul of the 'C' Charging Pump on June 28, 2019.

71111.04S - Equipment Alignment Complete Walkdown Sample (IP Section 03.02)

Main article: IP 71111.04S
(1) The inspectors evaluated system configurations during a complete walkdown of the fire protection system on May 31, 2019.

71111.05Q - Fire Protection Quarterly Inspection (IP Section 03.01)

Main article: IP 71111.05Q

The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Mechanical Equipment Rooms 3 and 4 Smoke Detector Test, 1-SW-263, Appendix R Isolation Valve on May 3, 2019.
(2) Inadequate step in procedures 0-AP-13.00 and 0-FCA-7.00 which failed to isolate Mechanical Equipment Room (MER) 3 from MER 5 following a fire or flood in MER 3 on May 8, 2019.
(3) AAC diesel generator building on March 16, 2019.
(4) Auxiliary Building Elev. 45 ft on May 31, 2019.
(5) Fuel Building on May 31, 2019.
(6) Unit 2 Emergency Switchgear Room on June 12, 2019.

==71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during a Unit 2 down power from 100 percent to 83 percent reactor power to support high pressure heater drain pump maintenance on April 22, 2019.
(2) The inspectors observed and evaluated licensed operator performance in the Control Room when raising Unit 2 power from 83 percent to 100 percent reactor power following high pressure heater drain pump maintenance on April 25, 2019.

Licensed Operator Requalification Training/Examinations (IP Section 03.02)==

Main article: IP 71111.11Q
(1) The inspectors observed and evaluated a scenario in which a toxic gas was released and multiple fission product barriers failed on June 18, 2019.

71111.12 - Maintenance Effectiveness Quality Control (IP Section 02.02)

Main article: IP 71111.12

The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:

(1) Emergency Service Water Pump 1-SW-P-1B Replacement and Testing, Work Order

===38077550701 and 0-MCM-0114-01, April 30 - May 3, 2019. Routine Maintenance Effectiveness Inspection (IP Section 02.01) ===

Main article: IP 38077

The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:

(1) Inspection and Overhaul of Unit 1, 1-SW-268 check valve on April 10, 2019.
(2) Charging pump bearings and seals preventative maintenance effectiveness review on June 17, 2019.
(3) Maintenance Rule structural inspections of the fire pump house and evaluations of cracks in block walls on June 18, 2019.

71111.13 - Maintenance Risk Assessments and Emergent Work Control Risk Assessment and Management Sample (IP Section 03.01)

Main article: IP 71111.13

The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Unit 1 and Unit 2 intake canal level probe testing on April 10, 2019.
(2) Unit 1 and Unit 2 emergent offsite power switching activities planned during emergency service water pump maintenance on April 18, 2019.
(3) Unit 2 downpower to 83%, high pressure heater drain pump replacement, and removal of floor grating for access to EOP components on April 22, 2019.
(4) Unit 1 and 2 emergency service water pump replacement week of April 29, 2019.
(5) Unit 2 reactor coolant pump underfrequency testing on May 31, 2019.
(6) Unit 1 emergent online troubleshooting of high pressure feedwater heater '1B' moisture separator drain tank normal level control valve erratic operation on June 12, 2019.
(7) Unit 1 and Unit 2 transportation of a dry storage cask to ISFSI pad and insertion into a horizontal storage module on June 13, 2019.

71111.15 - Operability Determinations and Functionality Assessments Operability Determination or Functionality Assessment (IP Section 02.02)

Main article: IP 71111.15

The inspectors evaluated the following operability determinations and functionality assessments:

(1) CR1122159, Degraded Rebar and Concrete Associated with 1-SW-P-1B Pump Floor Slab, on April 30, 2019.
(2) CR1122689, High Vibrations on 1-SW-P-1B, 'B' Emergency Service Water Pump, on May 7, 2019.
(3) CR1073491, operability impact of silt deposits in intake canal on ultimate heat sink
(4) CR1124848, Main Control Room Chiller '4A' Failure to Start, first attempted start since 2017 on June 11, 2019.
(5) CR1125718, Delayed Undervoltage Light during Unit 2 Train 'A' Reactor Protection Logic Testing on June 25, 2019.
(6) CR112529, Failure to complete diagnosis of fire due to performance of parallel Time Critical Operator Actions in AP-48.00, Fire Protection - Operations Response, on June 26, 2019.

==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) Temporary Modifications for 1-SW-P-1B Pump Heavy Lifts: Fuel Oil Line Jumper and Flood Protection Restoration.

71111.19 - Post-Maintenance Testing Post Maintenance Test Sample (IP Section 03.01)

Main article: [[=

=IP 71111.18|count=7}}

The inspectors evaluated the following post maintenance tests:

(1) 1-PT-41.1, Component Cooling Water (CC) Pumps Performance Test after replacement of the 1A CC pump seals and motor refurbishment on April 2, 2019.
(2) 2-OSP-TM-001, Turbine Inlet Valve Freedom Test, after cam adjustment of the Unit 2
         #4 Turbine Stop Valve, on April 24, 2019.
(3) Post Maintenance Testing of Unit 1, 1-SW-268 check Valve on April 10, 2019.
(4) 0-OPT-SW-008, Emergency Service Water Pump 1-SW-P-1B Comprehensive Test after replacement of the 1-SW-P-1B pump on May 3 and 6, 2019.
(5) 0-OP-AAC-001, AAC Diesel Generator Operation, on June 13, 2019 following 3-year and 6-year preventative maintenance packages.
(6) 2-PT-8.1, Reactor Protection Logic Test following swapping leads on the Channel 1 Overtemperature Delta Temperature Relay 2-RP-RLY-TC412CXA, on June 26, 2019.
(7) 0-OPT-SW-002, Emergency Service Water Pump 1-SW-P-1B Periodic Test following packing gland failure on June 23, 2019.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: FLEX Testing (IP Section 03.02)

Main article: IP 71111.22
(1) Annual testing of the following FLEX equipment from June 10 through June 24, 2019:
  • 1-FP-P-4, Portable Backup Diesel Fire Pump
  • 0-BDB-P-1, Beyond Design Basis (BDB) High Capacity Pump
  • 0-BDB-P-3B, BDB RCS Pump 3B
  • 0-BDB-GEN-1B, BDB 40kW 120/240VAC Diesel Generator
  • 0-BDB-GEN-1C, BDB 40kW 120/240VAC Diesel Generator

Inservice Testing (IP Section 03.01) (1 Sample)

(1) 1-OPT-CS-002, Containment Spray System Test, on April 15, 2019.

Surveillance Tests (other) (IP Section 03.01) (4 Samples)

(1) 2-OPT-SI-005, Low Head Safety Injection (LHSI) Pump Test, on April 12, 2019.
(2) 2-OPT-EG-001Q, Number 2 Emergency Diesel Generator Quarterly/Monthly Load Test, on April 8, 2019.
(3) 0-NSP-CW-006, Canal Level Probe Removal, Inspection and Cleaning, on April 10, 2019.
(4) 1-OPT-CH-002, Charging Pump Operability and Performance Test for 1-CH-P-1B, on May 16, 2019.

71114.06 - Drill Evaluation Drill/Training Evolution Observation (IP Section 03.02)

Main article: IP 71114.06

The inspectors evaluated:

(1) The inspectors evaluated a licensee emergency planning drill from the control room simulator on June 18, 2019. The drill involved a toxic gas release and the failure of multiple fission product barriers resulting in a General Emergency declaration.

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated a licensee emergency planning drill at the Corporate Emergency Response Center in Glen Allen, VA, on April 11, 2019. The drill involved an earthquake within 200km of Surry which resulted in an Alert declaration due to a hazardous atmosphere at the low level intake structure. The drill also involved aftershocks which resulted in a loss of fuel clad barrier and eventually a large break loss of coolant accident, which ultimately resulted in a General Emergency declaration.

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) ===

Main article: IP 71151
(1) Unit 1 (April 1, 2018 through March 31, 2019)
(2) Unit 2 (April 1, 2018 through March 31, 2019)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (April 1, 2018 through March 31, 2019)
(2) Unit 2 (April 1, 2018 through March 31, 2019)

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)

(1) Unit 1 (April 1, 2018 through March 31, 2019)
(2) Unit 2 (April 1, 2018 through March 31, 2019)

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

Main article: IP 71152

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

(1) Challenges to operator performance including operator work arounds, burdens and challenges; main control room deficiencies and distractions; and night/standing orders on April 4, 2019.
(2) Loss of Configuration Control of Surry Unit 1 Outside Recirculation Spray Pump 01-RS-P-2B Recirculation Isolation Valve 1-RS-6 due to degraded Stem to Disc Interface (CR1114023) on June 24, 2019.

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in scheduling and completion of items added and removed from the equipment reliability top 10 focus items list that might be indicative of a more significant safety issue on June 26, 2019.

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

Main article: IP 71153

The inspectors evaluated the following licensee event report (LER):

(1) LER 05000281/2019-001-00, Foreign Material in Breaker Contact Causes Pressurizer Power Operated Relief Valve Block Valve Inoperability (ADAMS accession ML19098A163). The circumstances surrounding this LER are documented in the Results section. (Closed)

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants

Main article: IP 60855
(1) The inspectors evaluated the licensees independent spent fuel storage installation (ISFSI) cask loadings on June 3, 2019. Specifically, the inspectors observed the following activities:
  • Fuel selection and fuel loading
  • Heavy load movement of dry shielded canister/transfer cask
  • Radiological field surveys The inspectors evaluated the licensee's ISFSI cask movement and installation into the horizontal storage module on June 13, 2019. Specifically, the inspectors observed the following activities:
  • Heavy load movement of transfer cask
  • Radiological field surveys
  • Transportation of the transfer cask to the ISFSI pad The inspectors evaluated the licensee's ISFSI cask movement and installation into the horizontal storage module on June 20, 2019. Specifically, the inspectors observed the following activities:
  • Radiological field surveys
  • Transportation of the transfer cask to the ISFSI pad
  • Installation of the transfer cask into the horizontal storage module The inspectors evaluate the following program changes:
  • Revision of procedure 0-OP-FH-072, NUHOMS 32 PTH Dry Shielded Canister Loading and Unloading, Revisions 28 and

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Surry Technical Specification 6.4.A.7 states, in part, that detailed written procedures with appropriate check-off lists and instructions shall be provided for conditions that include: preventive or corrective maintenance operations which would have an effect on the safety of the reactor. Surry Technical Specification 6.4.D states, in part, that procedures described in section 6.4.A shall be followed. These requirements were implemented, in part, by WO38102324301 and procedure MA-AA-102, Foreign Material Exclusion. Contrary to the above, on November 7, 2018, the licensee failed to follow the written procedures and instructions for breaker preventive maintenance of a unit 2 pressurizer power operated relief valve (PORV) block valve 2-RC-MOV-2536 including foreign material closeout, which resulted in a nylon brush bristle lodged in the valve breaker stationary closed contactor assembly and inoperability of the associated PORV block valve from December 4, 2018, to January 29, 2019. The pressurizer PORV block valves are active reactor coolant system boundary valves which provide the operators with the ability to detect a stuck-open safety or relief valve and to isolate a stuck-open PORV. The licensee reported the operation prohibited by Technical Specifications to the NRC on April 1, 2019, as Licensee Event Report 50-281/2019-001-00, Foreign Material in Breaker Contact Causes Pressurizer Power Operated Relief Valve Block Valve Inoperability.

Significance: Green. The failure to prevent foreign material from affecting operation of PORV block valve 2-RC-MOV-2536 was a performance deficiency (PD). The inspectors assessed the significance of the finding using IMC 0609 Attachment 4, Initial Characterization of Findings, Table 2, dated October 7, 2016, and the finding was determined to adversely affect the Barrier Integrity cornerstone under the active components of boundary (valve, seals) area to measure. Specifically, the pressurizer PORV block valve was not available to provide the operators with the ability to detect a stuck-open safety or relief valve and to isolate a stuck-open PORV. An independent bounding risk analysis was performed by a regional senior reactor analyst in accordance with NRC Inspection Manual Chapter 0609 Appendix A. The analysis assumed a non-recoverable failure to operate of the 2-RC-MOV-2536 block valve with no common cause impact for a period of 57 days. The analysis determined that the increase in core damage frequency due to the PD was less than 1E-7/year, a Green finding of very low safety significance.

Corrective Action References: CR1113030

EXIT MEETINGS AND DEBRIEFS

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

  • On July 3, 2019, the inspectors presented the integrated inspection results to Mr. Fred Mladen and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or Procedure Date 60855.1 Miscellaneous Loading for Surry 05/28/2019 Spent Fuel Pool S1-OP-19-03 Fuel Handling Report Procedures 0-OP-FH-072 NUHOMS 32 PTH Dry Shielded Canister Loading and 29 Handling HP-1061.500 NUHOMS Spent Fuel Cask Preparation/Loading and 6 Transport to ISFSI 71111.01 Calculations ME-12152 Loss of Ventilation in the Cable Vault and Tunnel 0 Corrective Action CR1118627 Calculation provides elevated temperature at DBA with loss 03/19/2019 Documents of ventilation. Corrective Action CR1124184 Unit 1 upper cable vault ventilation O.O.S. and high 05/30/2019 Documents temperature Resulting from Inspection Procedures 0-OSP-ZZ-003 Hot Weather Preparation 8 71111.04 Drawings 113E244A Reactor Protection System Reactor Trip Matrices - Surry 20 Power Station - Unit 2 Miscellaneous 1-19-SW-00010 Safety Tagout of 1-SW-P-1B April 30, 2019 Procedures 0-OP-SW-002A Emergency Service Water System Alignment 10 1-OP-CH-002 Charging Pump A Operations 24 1-OP-CH-003 Charging Pump B Operations 26 1-OPT-FW-003 Turbine Driven Auxiliary Feedwater Pump 1-FW-P-2 54 2-PT-8.1 Reactor Protection System Logic (for Normal Operations) 40 71111.04S Corrective Action CR1086466, Documents CR1091946, CR1092279, CR1116987, CR1121992, CR1123110, CR1123469 Drawings 11448-FB-2A Fire Protection - Arrangement, Surry Power Station 22 Inspection Type Designation Description or Title Revision or Procedure Date 11448-FB-3A Yard, Water & Fire Protection Lines, Surry Power Station - 27 Unit 1 11448-FB-47A Flow/Valve Operating Numbers Diagram, Fire Protection & 34 Domestic Water System, Surry Power Station - Unit 1 Miscellaneous Module Nuclear Control Room Operator Development Program 10/06/2017 NCRODP-6-S-6- Surry Power Station: Fire Protection System S SDBD-SPS-FP System Design Basis Document for Fire Protection System 17 Procedures 0-AP-48.00 Fire Protection-Operations Response (with 5 attachments) 37 0-LPT-FP-006 Inspection of Hose Stations and Fire Extinguishers - 8 RCA/North Yard 0-OP-FP-006 Operation of Fire Protection Systems 17 1-OP-52.2A Fire Protection System Alignment 16 CM-AA-FPA-100 Fire Protection/Appendix R (Fire Safe Shutdown) Program 13 71111.05A Drawings 11548-FE-51R Wiring Diagram Internal and External Fire Protection Panel, 4 Surry Power Station, Unit 2 Procedures 0-FCA-7.00 Limiting Mechanical Equipment Room 3 or Fire 13 71111.05Q Drawings 11448-FM-071D Flow/Valve Operating Numbers Diagram Circulating and 15 Service Water System Surry Power Station Unit 1 11548-FM-071A Flow/Valve Operating Numbers Diagram Circulating and 103 Service Water System Surry Power Station Unit 2 Engineering Standing Order Alternative Method to provide Flood Isolation of MER 3 May 2, 2019 Changes SO-19-002 Fire Plans 0-FS-FP-225 Alternate AC Diesel Room - Construction Site Elev. 35 Feet 1 Procedures 0-AP-13.00 Turbine Building or MER 3 Flooding 31 0-EPM-0901-05 Mechanical Equipment Rooms 3 and 4 Smoke Detector Test 6 0-FS-FP-162 Auxiliary Building Elevation 45 Feet - 10 Inches 4 0-FS-FP-163 Fuel Building Elevation 6 Feet - 10 Inches and 15 Feet - 10 1 Inches 0-FS-FP-164 Fuel Building Elevation 27 Feet - 6 Inches and 45 Feet - 10 3 Inches 0-FS-FP-225 Alternate AC Diesel Room 1 Work Orders 38204187733 Mechanical Equipment Room 3 and Mechanical Equipment Room 4 Smoke Detector Test Inspection Type Designation Description or Title Revision or Procedure Date 204187733 Mechanical Equipment Rooms 3 and 4 Smoke Detector Test 0 71111.11Q Corrective Action CR1125393 Last minute EP Inject Message Request Documents Miscellaneous EAL Matrix Surry Power Station Emergency Action Level Matrix 4 Procedures 2-OP-CH-007 Blender Operations 40 2-OP-TM-005 Unit Ramping Operations 36 71111.12 Corrective Action CR1122082, Documents CR1122157, CR1122159, CR1122199, CR1122272, CR1122337 Engineering S-PMTE-2002- Replace the mechanical seals on 1/2-CH-P-1A/B/C 9/11/2002 Evaluations 011 S-PMTE-2005- PM to replace mechanical seals 10/19/2005 0355 Procedures 0-MCM-0109-01 Charging Pump Overhaul 38 0-MCM-0114-01 Emergency Service Water Pump Maintenance 29 0-MCM-0417-52 William Powell Swing Check Valve Inspection and Overhaul 11 Model 2342 VPAP-1001 Quality Control (QC) Inspection Program 20 Work Orders 38077550701 Emergency Service Water Pump 1-SW-P-1B Replacement April 30, and Testing 2019 38103275045 0-NSP-BS-005 1825 Day Freq. PT: Monitoring of Structures 11/26/2018 71111.13 Corrective Action CR1124809 High pressure feedwater heater '1B' moisture separator 06/12/2019 Documents drain tank normal level control valve erratic operation Miscellaneous Radiological Risk Screening Worksheet for NUHOMS cask dated campaign 2/25/2019 EOOS April 10, Schedulers Risk 2019 Evaluation for Surry Power Station Inspection Type Designation Description or Title Revision or Procedure Date EOOS April 18, Schedulers Risk 2019 Evaluation for Surry Power Station Procedures 0-DRP-049 Time Critical Operator Actions 16 Work Orders 38204199267 71111.15 Corrective Action CR1122509, 1-SW-P-1B High Vibrations Documents CR1122600, CR1122662, CR1122689 CR1124848 Main Control Room Chiller '4A' Failure to Start, first 06/11/2019 attempted start since 2017 CR112529 Failure to complete diagnosis of fire due to performance of 06/26/2019 parallel Time Critical Operator Actions CR1125718 Delayed Undervoltage Light during Unit 2 Train A Reactor 06/25/2019 Protection Logic Testing Operability Engineering Logs 1-SW-P-1B ESW Pump high vibrations. May 7, 2019 Evaluations Station Narrative Degradation of 1-SW-P-1B Foundation Rebar and Concrete May 1 and 2, Log Follow-ups Degradation 2019 for CR1122159 Procedures OP-AA-102 Operability Determination 15 71111.18 Calculations CE-2056 Surry Emergency Service Water Pump Heavy Load Rigging 0 

                                              & Load Drop Evaluation for 01-SW-P-1A, 01-SW-P-1B, &

01-SW-P-1C Engineering S1-17-155 Emergency Service Water Pump Fuel Oil Line Jumper 3 Changes SU-19-00112 Emergency Service Water Pump House Flood Protection 0 Restoration Following Postulated Load Drop of 1-SW-P-1B Engineering ETE-SU-2019- Emergency Service Water Pump NUREG-0612 Heavy Load 0 Evaluations 0008 Requirements ETE-SU-2019- Repair Disposition for 1-SW-P-1B Pump Pit Plate 0 1007 71111.19 Corrective Action CR1121088 Interlock switch for 2-MS-TV-4 found out of adjustment. April 17, Documents 2019 Inspection Type Designation Description or Title Revision or Procedure Date CR1122502, Pushbutton start needs reset, throttle linkage repair, 1-SW- CR1122504, P-1B packing leakage, fuel filter leak, loose base plate bolts CR1122558, CR1122559, CR1122572, CR1122744 Drawings 11448-FM-072D Flow/Valve Operating Numbers Diagram Component 32 and 37 Cooling Water System, Sheets 1 and 2 respectively Procedures 0-MCM-0107-01 Component Cooling Pump Maintenance 13 0-MCM-0417-52 William Powell Swing Check Valve Inspection and Overhaul 11 Model 2342 0-OP-AAC-001 AAC Diesel Generator Operation 30 0-OPT-SW-002 Emergency Service Water Pump 1-SW-P-1B 68 0-OPT-SW-008 Emergency Service Water Pump 1-SW-P-1B 27 Comprehensive Test 1-PT-18.8 Charging Pump Service Water Performance 38 1-PT-41.1 Component Cooling Water Pumps Performance Test 35 2-OSP-TM-001 Turbine Inlet Valve Freedom Test 46 2-PT-8.1 Reactor Protection System Logic (for Normal Operations) 40 Work Orders 38103680975 38103680975 Unit 2 Turbine Stop Valve Interlock Verification 0 38103711862 and 38103401882 204192362 204199804 06/26/2019 71111.22 Corrective Action CR1120556, Documents CR1120552 Corrective Action CR1120807 Non-ISI elevated vibes Point 9 Documents CR1120821 1-CS-115 externally leaking by Resulting from CR1120834 1-CS-PP-1B Pump seal drain boric acid accumulation. Inspection Engineering SU-13-01025 Implementation of the Beyond Design Basis Diverse and 06/16/2014 Changes Flexible Coping Strategies (FLEX) Program Inspection Type Designation Description or Title Revision or Procedure Date Engineering ETE-CPR-2014- Site Acceptance Testing (SAT) and Periodic Performance 2 Evaluations 1002 Verification Testing Acceptance Criteria for BDB FLEX Strategy Pumps - North Anna 1&2 and Surry 1&2 Procedures 0-MPM-1960-01 Semi-Annual or Annual Test of BDB Flex Equipment 15 0-NSP-CW-006 Canal Level Probe Removal, Inspection and Cleaning 6 0-OP-BDB-003 BDB 120/240 VAC Generator Operator Aid 1 0-OP-BDB-007 BDB High Capacity Pump Operating Aid 0 1-FSG-1 Long Term RCS Inventory Control 4 1-FSG-8 Alternate RCS Boration 4 1-OPT-CH-002 Charging Pump Operability and Performance Test for 1-CH- 59 P-1B 1-OPT-CS-002 Containment Spray System Test 18 2-OPT-EG-001 Number 2 Emergency Diesel Generator Monthly Start 77 Exercise Test 2-OPT-SI-005 LHSI Pump Test 34 71114.06 Corrective Action CR1125343 SJUN19FS Obj 4 (Notifications) Met with Problem Documents CR1125452 SJUN19FS Obj 20 (Exercise Conduct) Met with Problem Procedures EPIP-1.01 Emergency Manager Controlling Procedure 60 EPIP-3.06 Corporate Emergency Response Center Activation 0 EPIP-3.10 CERC Technical Support Controlling Procedure 0 EPIP-4.36 CERC Accident Assessment Controlling Procedure 0 71151 Miscellaneous 1Q/2019 Performance Indicators - Surry 1 and 2 - Reactor 06/25/2019 Coolant System Leakage 1Q/2019 Performance Indicators - Surry 1 and 2 - Safety 06/25/2019 System Functional Failures Unit 2 Control Room Narrative Log, 04/01/2018 - 3/31/2019 1Q/2019 Performance Indicators - Surry 1 and 2 - Reactor 06/25/2019 Coolant System Activity Unit 1 Control Room Narrative Log, 04/01/2018 - 3/31/2019 NEI 99-02 Regulatory Assessment Performance Indicator Guideline 7 71152 Corrective Action CA7489560 Documents CR015505, CR020890, Inspection Type Designation Description or Title Revision or Procedure Date CR021127, CR572210, CR1044721, CR1116262, and CA018234 CR1114023 Corrective Action CR1121189 Evaluate OPS aggregate impact based on NRC April 18, Documents observations and recommendations. 2019 Resulting from CR1121192 Self assessments for OP-AA-1700 (OAI) not performed from April 18, Inspection 2011 to 2017. 2019 Miscellaneous Equipment Reliability Top 10 Focus Items 04/23/2019 Equipment Reliability Top 10 Focus Items 01/22/2019 OAI Units 1 and 2 Operations Aggregate Impact March 1 and April 1, 2019 RO Logs Units 1 and 2 RO Abnormal Status Reports April 4, 2019 SPS Units 1 and TS 3.1 Reactor Coolant System Amendment Technical 250 and 251 Specifications SPS Units 1 and 4.2.7 Leakage 50 UFSAR Procedures 0-OP-BR-001 Boron Recovery Tank Transfer to the Surry Radwaste 11 Facility 1-OP-ZZ-002 Maintenance of Plant Operations 36 OP-AA-1700 Operations Aggregate Impact 8 Self-Assessments PIR1074492 Informal Self-Assessment on Surry Power Station's February Operations Aggregate Impact 2017 Work Orders 38052036702 Valve 01-CC-573 Replacement 38078187402 Valve 2-CC-322 Replacement 38103686836 Valve 01-BR-145 Bonnet Overhaul 204193252 Actuator / Valve Overhaul 17|= =IP 71111.18|count=7}}

The inspectors evaluated the following post maintenance tests:

(1) 1-PT-41.1, Component Cooling Water (CC) Pumps Performance Test after replacement of the 1A CC pump seals and motor refurbishment on April 2, 2019.
(2) 2-OSP-TM-001, Turbine Inlet Valve Freedom Test, after cam adjustment of the Unit 2
         #4 Turbine Stop Valve, on April 24, 2019.
(3) Post Maintenance Testing of Unit 1, 1-SW-268 check Valve on April 10, 2019.
(4) 0-OPT-SW-008, Emergency Service Water Pump 1-SW-P-1B Comprehensive Test after replacement of the 1-SW-P-1B pump on May 3 and 6, 2019.
(5) 0-OP-AAC-001, AAC Diesel Generator Operation, on June 13, 2019 following 3-year and 6-year preventative maintenance packages.
(6) 2-PT-8.1, Reactor Protection Logic Test following swapping leads on the Channel 1 Overtemperature Delta Temperature Relay 2-RP-RLY-TC412CXA, on June 26, 2019.
(7) 0-OPT-SW-002, Emergency Service Water Pump 1-SW-P-1B Periodic Test following packing gland failure on June 23, 2019.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: FLEX Testing (IP Section 03.02)

Main article: IP 71111.22
(1) Annual testing of the following FLEX equipment from June 10 through June 24, 2019:
  • 1-FP-P-4, Portable Backup Diesel Fire Pump
  • 0-BDB-P-1, Beyond Design Basis (BDB) High Capacity Pump
  • 0-BDB-P-3B, BDB RCS Pump 3B
  • 0-BDB-GEN-1B, BDB 40kW 120/240VAC Diesel Generator
  • 0-BDB-GEN-1C, BDB 40kW 120/240VAC Diesel Generator

Inservice Testing (IP Section 03.01) (1 Sample)

(1) 1-OPT-CS-002, Containment Spray System Test, on April 15, 2019.

Surveillance Tests (other) (IP Section 03.01) (4 Samples)

(1) 2-OPT-SI-005, Low Head Safety Injection (LHSI) Pump Test, on April 12, 2019.
(2) 2-OPT-EG-001Q, Number 2 Emergency Diesel Generator Quarterly/Monthly Load Test, on April 8, 2019.
(3) 0-NSP-CW-006, Canal Level Probe Removal, Inspection and Cleaning, on April 10, 2019.
(4) 1-OPT-CH-002, Charging Pump Operability and Performance Test for 1-CH-P-1B, on May 16, 2019.

71114.06 - Drill Evaluation Drill/Training Evolution Observation (IP Section 03.02)

Main article: IP 71114.06

The inspectors evaluated:

(1) The inspectors evaluated a licensee emergency planning drill from the control room simulator on June 18, 2019. The drill involved a toxic gas release and the failure of multiple fission product barriers resulting in a General Emergency declaration.

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated a licensee emergency planning drill at the Corporate Emergency Response Center in Glen Allen, VA, on April 11, 2019. The drill involved an earthquake within 200km of Surry which resulted in an Alert declaration due to a hazardous atmosphere at the low level intake structure. The drill also involved aftershocks which resulted in a loss of fuel clad barrier and eventually a large break loss of coolant accident, which ultimately resulted in a General Emergency declaration.

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) ===

Main article: IP 71151
(1) Unit 1 (April 1, 2018 through March 31, 2019)
(2) Unit 2 (April 1, 2018 through March 31, 2019)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (April 1, 2018 through March 31, 2019)
(2) Unit 2 (April 1, 2018 through March 31, 2019)

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)

(1) Unit 1 (April 1, 2018 through March 31, 2019)
(2) Unit 2 (April 1, 2018 through March 31, 2019)

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

Main article: IP 71152

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

(1) Challenges to operator performance including operator work arounds, burdens and challenges; main control room deficiencies and distractions; and night/standing orders on April 4, 2019.
(2) Loss of Configuration Control of Surry Unit 1 Outside Recirculation Spray Pump 01-RS-P-2B Recirculation Isolation Valve 1-RS-6 due to degraded Stem to Disc Interface (CR1114023) on June 24, 2019.

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in scheduling and completion of items added and removed from the equipment reliability top 10 focus items list that might be indicative of a more significant safety issue on June 26, 2019.

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

Main article: IP 71153

The inspectors evaluated the following licensee event report (LER):

(1) LER 05000281/2019-001-00, Foreign Material in Breaker Contact Causes Pressurizer Power Operated Relief Valve Block Valve Inoperability (ADAMS accession ML19098A163). The circumstances surrounding this LER are documented in the Results section. (Closed)

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants

Main article: IP 60855
(1) The inspectors evaluated the licensees independent spent fuel storage installation (ISFSI) cask loadings on June 3, 2019. Specifically, the inspectors observed the following activities:
  • Fuel selection and fuel loading
  • Heavy load movement of dry shielded canister/transfer cask
  • Radiological field surveys The inspectors evaluated the licensee's ISFSI cask movement and installation into the horizontal storage module on June 13, 2019. Specifically, the inspectors observed the following activities:
  • Heavy load movement of transfer cask
  • Radiological field surveys
  • Transportation of the transfer cask to the ISFSI pad The inspectors evaluated the licensee's ISFSI cask movement and installation into the horizontal storage module on June 20, 2019. Specifically, the inspectors observed the following activities:
  • Radiological field surveys
  • Transportation of the transfer cask to the ISFSI pad
  • Installation of the transfer cask into the horizontal storage module The inspectors evaluate the following program changes:
  • Revision of procedure 0-OP-FH-072, NUHOMS 32 PTH Dry Shielded Canister Loading and Unloading, Revisions 28 and

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Surry Technical Specification 6.4.A.7 states, in part, that detailed written procedures with appropriate check-off lists and instructions shall be provided for conditions that include: preventive or corrective maintenance operations which would have an effect on the safety of the reactor. Surry Technical Specification 6.4.D states, in part, that procedures described in section 6.4.A shall be followed. These requirements were implemented, in part, by WO38102324301 and procedure MA-AA-102, Foreign Material Exclusion. Contrary to the above, on November 7, 2018, the licensee failed to follow the written procedures and instructions for breaker preventive maintenance of a unit 2 pressurizer power operated relief valve (PORV) block valve 2-RC-MOV-2536 including foreign material closeout, which resulted in a nylon brush bristle lodged in the valve breaker stationary closed contactor assembly and inoperability of the associated PORV block valve from December 4, 2018, to January 29, 2019. The pressurizer PORV block valves are active reactor coolant system boundary valves which provide the operators with the ability to detect a stuck-open safety or relief valve and to isolate a stuck-open PORV. The licensee reported the operation prohibited by Technical Specifications to the NRC on April 1, 2019, as Licensee Event Report 50-281/2019-001-00, Foreign Material in Breaker Contact Causes Pressurizer Power Operated Relief Valve Block Valve Inoperability.

Significance: Green. The failure to prevent foreign material from affecting operation of PORV block valve 2-RC-MOV-2536 was a performance deficiency (PD). The inspectors assessed the significance of the finding using IMC 0609 Attachment 4, Initial Characterization of Findings, Table 2, dated October 7, 2016, and the finding was determined to adversely affect the Barrier Integrity cornerstone under the active components of boundary (valve, seals) area to measure. Specifically, the pressurizer PORV block valve was not available to provide the operators with the ability to detect a stuck-open safety or relief valve and to isolate a stuck-open PORV. An independent bounding risk analysis was performed by a regional senior reactor analyst in accordance with NRC Inspection Manual Chapter 0609 Appendix A. The analysis assumed a non-recoverable failure to operate of the 2-RC-MOV-2536 block valve with no common cause impact for a period of 57 days. The analysis determined that the increase in core damage frequency due to the PD was less than 1E-7/year, a Green finding of very low safety significance.

Corrective Action References: CR1113030

EXIT MEETINGS AND DEBRIEFS

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

  • On July 3, 2019, the inspectors presented the integrated inspection results to Mr. Fred Mladen and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or Procedure Date 60855.1 Miscellaneous Loading for Surry 05/28/2019 Spent Fuel Pool S1-OP-19-03 Fuel Handling Report Procedures 0-OP-FH-072 NUHOMS 32 PTH Dry Shielded Canister Loading and 29 Handling HP-1061.500 NUHOMS Spent Fuel Cask Preparation/Loading and 6 Transport to ISFSI 71111.01 Calculations ME-12152 Loss of Ventilation in the Cable Vault and Tunnel 0 Corrective Action CR1118627 Calculation provides elevated temperature at DBA with loss 03/19/2019 Documents of ventilation. Corrective Action CR1124184 Unit 1 upper cable vault ventilation O.O.S. and high 05/30/2019 Documents temperature Resulting from Inspection Procedures 0-OSP-ZZ-003 Hot Weather Preparation 8 71111.04 Drawings 113E244A Reactor Protection System Reactor Trip Matrices - Surry 20 Power Station - Unit 2 Miscellaneous 1-19-SW-00010 Safety Tagout of 1-SW-P-1B April 30, 2019 Procedures 0-OP-SW-002A Emergency Service Water System Alignment 10 1-OP-CH-002 Charging Pump A Operations 24 1-OP-CH-003 Charging Pump B Operations 26 1-OPT-FW-003 Turbine Driven Auxiliary Feedwater Pump 1-FW-P-2 54 2-PT-8.1 Reactor Protection System Logic (for Normal Operations) 40 71111.04S Corrective Action CR1086466, Documents CR1091946, CR1092279, CR1116987, CR1121992, CR1123110, CR1123469 Drawings 11448-FB-2A Fire Protection - Arrangement, Surry Power Station 22 Inspection Type Designation Description or Title Revision or Procedure Date 11448-FB-3A Yard, Water & Fire Protection Lines, Surry Power Station - 27 Unit 1 11448-FB-47A Flow/Valve Operating Numbers Diagram, Fire Protection & 34 Domestic Water System, Surry Power Station - Unit 1 Miscellaneous Module Nuclear Control Room Operator Development Program 10/06/2017 NCRODP-6-S-6- Surry Power Station: Fire Protection System S SDBD-SPS-FP System Design Basis Document for Fire Protection System 17 Procedures 0-AP-48.00 Fire Protection-Operations Response (with 5 attachments) 37 0-LPT-FP-006 Inspection of Hose Stations and Fire Extinguishers - 8 RCA/North Yard 0-OP-FP-006 Operation of Fire Protection Systems 17 1-OP-52.2A Fire Protection System Alignment 16 CM-AA-FPA-100 Fire Protection/Appendix R (Fire Safe Shutdown) Program 13 71111.05A Drawings 11548-FE-51R Wiring Diagram Internal and External Fire Protection Panel, 4 Surry Power Station, Unit 2 Procedures 0-FCA-7.00 Limiting Mechanical Equipment Room 3 or Fire 13 71111.05Q Drawings 11448-FM-071D Flow/Valve Operating Numbers Diagram Circulating and 15 Service Water System Surry Power Station Unit 1 11548-FM-071A Flow/Valve Operating Numbers Diagram Circulating and 103 Service Water System Surry Power Station Unit 2 Engineering Standing Order Alternative Method to provide Flood Isolation of MER 3 May 2, 2019 Changes SO-19-002 Fire Plans 0-FS-FP-225 Alternate AC Diesel Room - Construction Site Elev. 35 Feet 1 Procedures 0-AP-13.00 Turbine Building or MER 3 Flooding 31 0-EPM-0901-05 Mechanical Equipment Rooms 3 and 4 Smoke Detector Test 6 0-FS-FP-162 Auxiliary Building Elevation 45 Feet - 10 Inches 4 0-FS-FP-163 Fuel Building Elevation 6 Feet - 10 Inches and 15 Feet - 10 1 Inches 0-FS-FP-164 Fuel Building Elevation 27 Feet - 6 Inches and 45 Feet - 10 3 Inches 0-FS-FP-225 Alternate AC Diesel Room 1 Work Orders 38204187733 Mechanical Equipment Room 3 and Mechanical Equipment Room 4 Smoke Detector Test Inspection Type Designation Description or Title Revision or Procedure Date 204187733 Mechanical Equipment Rooms 3 and 4 Smoke Detector Test 0 71111.11Q Corrective Action CR1125393 Last minute EP Inject Message Request Documents Miscellaneous EAL Matrix Surry Power Station Emergency Action Level Matrix 4 Procedures 2-OP-CH-007 Blender Operations 40 2-OP-TM-005 Unit Ramping Operations 36 71111.12 Corrective Action CR1122082, Documents CR1122157, CR1122159, CR1122199, CR1122272, CR1122337 Engineering S-PMTE-2002- Replace the mechanical seals on 1/2-CH-P-1A/B/C 9/11/2002 Evaluations 011 S-PMTE-2005- PM to replace mechanical seals 10/19/2005 0355 Procedures 0-MCM-0109-01 Charging Pump Overhaul 38 0-MCM-0114-01 Emergency Service Water Pump Maintenance 29 0-MCM-0417-52 William Powell Swing Check Valve Inspection and Overhaul 11 Model 2342 VPAP-1001 Quality Control (QC) Inspection Program 20 Work Orders 38077550701 Emergency Service Water Pump 1-SW-P-1B Replacement April 30, and Testing 2019 38103275045 0-NSP-BS-005 1825 Day Freq. PT: Monitoring of Structures 11/26/2018 71111.13 Corrective Action CR1124809 High pressure feedwater heater '1B' moisture separator 06/12/2019 Documents drain tank normal level control valve erratic operation Miscellaneous Radiological Risk Screening Worksheet for NUHOMS cask dated campaign 2/25/2019 EOOS April 10, Schedulers Risk 2019 Evaluation for Surry Power Station Inspection Type Designation Description or Title Revision or Procedure Date EOOS April 18, Schedulers Risk 2019 Evaluation for Surry Power Station Procedures 0-DRP-049 Time Critical Operator Actions 16 Work Orders 38204199267 71111.15 Corrective Action CR1122509, 1-SW-P-1B High Vibrations Documents CR1122600, CR1122662, CR1122689 CR1124848 Main Control Room Chiller '4A' Failure to Start, first 06/11/2019 attempted start since 2017 CR112529 Failure to complete diagnosis of fire due to performance of 06/26/2019 parallel Time Critical Operator Actions CR1125718 Delayed Undervoltage Light during Unit 2 Train A Reactor 06/25/2019 Protection Logic Testing Operability Engineering Logs 1-SW-P-1B ESW Pump high vibrations. May 7, 2019 Evaluations Station Narrative Degradation of 1-SW-P-1B Foundation Rebar and Concrete May 1 and 2, Log Follow-ups Degradation 2019 for CR1122159 Procedures OP-AA-102 Operability Determination 15 71111.18 Calculations CE-2056 Surry Emergency Service Water Pump Heavy Load Rigging 0 

                                              & Load Drop Evaluation for 01-SW-P-1A, 01-SW-P-1B, &

01-SW-P-1C Engineering S1-17-155 Emergency Service Water Pump Fuel Oil Line Jumper 3 Changes SU-19-00112 Emergency Service Water Pump House Flood Protection 0 Restoration Following Postulated Load Drop of 1-SW-P-1B Engineering ETE-SU-2019- Emergency Service Water Pump NUREG-0612 Heavy Load 0 Evaluations 0008 Requirements ETE-SU-2019- Repair Disposition for 1-SW-P-1B Pump Pit Plate 0 1007 71111.19 Corrective Action CR1121088 Interlock switch for 2-MS-TV-4 found out of adjustment. April 17, Documents 2019 Inspection Type Designation Description or Title Revision or Procedure Date CR1122502, Pushbutton start needs reset, throttle linkage repair, 1-SW- CR1122504, P-1B packing leakage, fuel filter leak, loose base plate bolts CR1122558, CR1122559, CR1122572, CR1122744 Drawings 11448-FM-072D Flow/Valve Operating Numbers Diagram Component 32 and 37 Cooling Water System, Sheets 1 and 2 respectively Procedures 0-MCM-0107-01 Component Cooling Pump Maintenance 13 0-MCM-0417-52 William Powell Swing Check Valve Inspection and Overhaul 11 Model 2342 0-OP-AAC-001 AAC Diesel Generator Operation 30 0-OPT-SW-002 Emergency Service Water Pump 1-SW-P-1B 68 0-OPT-SW-008 Emergency Service Water Pump 1-SW-P-1B 27 Comprehensive Test 1-PT-18.8 Charging Pump Service Water Performance 38 1-PT-41.1 Component Cooling Water Pumps Performance Test 35 2-OSP-TM-001 Turbine Inlet Valve Freedom Test 46 2-PT-8.1 Reactor Protection System Logic (for Normal Operations) 40 Work Orders 38103680975 38103680975 Unit 2 Turbine Stop Valve Interlock Verification 0 38103711862 and 38103401882 204192362 204199804 06/26/2019 71111.22 Corrective Action CR1120556, Documents CR1120552 Corrective Action CR1120807 Non-ISI elevated vibes Point 9 Documents CR1120821 1-CS-115 externally leaking by Resulting from CR1120834 1-CS-PP-1B Pump seal drain boric acid accumulation. Inspection Engineering SU-13-01025 Implementation of the Beyond Design Basis Diverse and 06/16/2014 Changes Flexible Coping Strategies (FLEX) Program Inspection Type Designation Description or Title Revision or Procedure Date Engineering ETE-CPR-2014- Site Acceptance Testing (SAT) and Periodic Performance 2 Evaluations 1002 Verification Testing Acceptance Criteria for BDB FLEX Strategy Pumps - North Anna 1&2 and Surry 1&2 Procedures 0-MPM-1960-01 Semi-Annual or Annual Test of BDB Flex Equipment 15 0-NSP-CW-006 Canal Level Probe Removal, Inspection and Cleaning 6 0-OP-BDB-003 BDB 120/240 VAC Generator Operator Aid 1 0-OP-BDB-007 BDB High Capacity Pump Operating Aid 0 1-FSG-1 Long Term RCS Inventory Control 4 1-FSG-8 Alternate RCS Boration 4 1-OPT-CH-002 Charging Pump Operability and Performance Test for 1-CH- 59 P-1B 1-OPT-CS-002 Containment Spray System Test 18 2-OPT-EG-001 Number 2 Emergency Diesel Generator Monthly Start 77 Exercise Test 2-OPT-SI-005 LHSI Pump Test 34 71114.06 Corrective Action CR1125343 SJUN19FS Obj 4 (Notifications) Met with Problem Documents CR1125452 SJUN19FS Obj 20 (Exercise Conduct) Met with Problem Procedures EPIP-1.01 Emergency Manager Controlling Procedure 60 EPIP-3.06 Corporate Emergency Response Center Activation 0 EPIP-3.10 CERC Technical Support Controlling Procedure 0 EPIP-4.36 CERC Accident Assessment Controlling Procedure 0 71151 Miscellaneous 1Q/2019 Performance Indicators - Surry 1 and 2 - Reactor 06/25/2019 Coolant System Leakage 1Q/2019 Performance Indicators - Surry 1 and 2 - Safety 06/25/2019 System Functional Failures Unit 2 Control Room Narrative Log, 04/01/2018 - 3/31/2019 1Q/2019 Performance Indicators - Surry 1 and 2 - Reactor 06/25/2019 Coolant System Activity Unit 1 Control Room Narrative Log, 04/01/2018 - 3/31/2019 NEI 99-02 Regulatory Assessment Performance Indicator Guideline 7 71152 Corrective Action CA7489560 Documents CR015505, CR020890, Inspection Type Designation Description or Title Revision or Procedure Date CR021127, CR572210, CR1044721, CR1116262, and CA018234 CR1114023 Corrective Action CR1121189 Evaluate OPS aggregate impact based on NRC April 18, Documents observations and recommendations. 2019 Resulting from CR1121192 Self assessments for OP-AA-1700 (OAI) not performed from April 18, Inspection 2011 to 2017. 2019 Miscellaneous Equipment Reliability Top 10 Focus Items 04/23/2019 Equipment Reliability Top 10 Focus Items 01/22/2019 OAI Units 1 and 2 Operations Aggregate Impact March 1 and April 1, 2019 RO Logs Units 1 and 2 RO Abnormal Status Reports April 4, 2019 SPS Units 1 and TS 3.1 Reactor Coolant System Amendment Technical 250 and 251 Specifications SPS Units 1 and 4.2.7 Leakage 50 UFSAR Procedures 0-OP-BR-001 Boron Recovery Tank Transfer to the Surry Radwaste 11 Facility 1-OP-ZZ-002 Maintenance of Plant Operations 36 OP-AA-1700 Operations Aggregate Impact 8 Self-Assessments PIR1074492 Informal Self-Assessment on Surry Power Station's February Operations Aggregate Impact 2017 Work Orders 38052036702 Valve 01-CC-573 Replacement 38078187402 Valve 2-CC-322 Replacement 38103686836 Valve 01-BR-145 Bonnet Overhaul 204193252 Actuator / Valve Overhaul

17]]

[[IP sample::=

=IP 71111.18|count=7}}

The inspectors evaluated the following post maintenance tests:

(1) 1-PT-41.1, Component Cooling Water (CC) Pumps Performance Test after replacement of the 1A CC pump seals and motor refurbishment on April 2, 2019.
(2) 2-OSP-TM-001, Turbine Inlet Valve Freedom Test, after cam adjustment of the Unit 2
         #4 Turbine Stop Valve, on April 24, 2019.
(3) Post Maintenance Testing of Unit 1, 1-SW-268 check Valve on April 10, 2019.
(4) 0-OPT-SW-008, Emergency Service Water Pump 1-SW-P-1B Comprehensive Test after replacement of the 1-SW-P-1B pump on May 3 and 6, 2019.
(5) 0-OP-AAC-001, AAC Diesel Generator Operation, on June 13, 2019 following 3-year and 6-year preventative maintenance packages.
(6) 2-PT-8.1, Reactor Protection Logic Test following swapping leads on the Channel 1 Overtemperature Delta Temperature Relay 2-RP-RLY-TC412CXA, on June 26, 2019.
(7) 0-OPT-SW-002, Emergency Service Water Pump 1-SW-P-1B Periodic Test following packing gland failure on June 23, 2019.

71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: FLEX Testing (IP Section 03.02)

Main article: IP 71111.22
(1) Annual testing of the following FLEX equipment from June 10 through June 24, 2019:
  • 1-FP-P-4, Portable Backup Diesel Fire Pump
  • 0-BDB-P-1, Beyond Design Basis (BDB) High Capacity Pump
  • 0-BDB-P-3B, BDB RCS Pump 3B
  • 0-BDB-GEN-1B, BDB 40kW 120/240VAC Diesel Generator
  • 0-BDB-GEN-1C, BDB 40kW 120/240VAC Diesel Generator

Inservice Testing (IP Section 03.01) (1 Sample)

(1) 1-OPT-CS-002, Containment Spray System Test, on April 15, 2019.

Surveillance Tests (other) (IP Section 03.01) (4 Samples)

(1) 2-OPT-SI-005, Low Head Safety Injection (LHSI) Pump Test, on April 12, 2019.
(2) 2-OPT-EG-001Q, Number 2 Emergency Diesel Generator Quarterly/Monthly Load Test, on April 8, 2019.
(3) 0-NSP-CW-006, Canal Level Probe Removal, Inspection and Cleaning, on April 10, 2019.
(4) 1-OPT-CH-002, Charging Pump Operability and Performance Test for 1-CH-P-1B, on May 16, 2019.

71114.06 - Drill Evaluation Drill/Training Evolution Observation (IP Section 03.02)

Main article: IP 71114.06

The inspectors evaluated:

(1) The inspectors evaluated a licensee emergency planning drill from the control room simulator on June 18, 2019. The drill involved a toxic gas release and the failure of multiple fission product barriers resulting in a General Emergency declaration.

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated a licensee emergency planning drill at the Corporate Emergency Response Center in Glen Allen, VA, on April 11, 2019. The drill involved an earthquake within 200km of Surry which resulted in an Alert declaration due to a hazardous atmosphere at the low level intake structure. The drill also involved aftershocks which resulted in a loss of fuel clad barrier and eventually a large break loss of coolant accident, which ultimately resulted in a General Emergency declaration.

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) ===

Main article: IP 71151
(1) Unit 1 (April 1, 2018 through March 31, 2019)
(2) Unit 2 (April 1, 2018 through March 31, 2019)

BI02: RCS Leak Rate Sample (IP Section 02.11) (2 Samples)

(1) Unit 1 (April 1, 2018 through March 31, 2019)
(2) Unit 2 (April 1, 2018 through March 31, 2019)

MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)

(1) Unit 1 (April 1, 2018 through March 31, 2019)
(2) Unit 2 (April 1, 2018 through March 31, 2019)

71152 - Problem Identification and Resolution Annual Follow-up of Selected Issues (IP Section 02.03)

Main article: IP 71152

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

(1) Challenges to operator performance including operator work arounds, burdens and challenges; main control room deficiencies and distractions; and night/standing orders on April 4, 2019.
(2) Loss of Configuration Control of Surry Unit 1 Outside Recirculation Spray Pump 01-RS-P-2B Recirculation Isolation Valve 1-RS-6 due to degraded Stem to Disc Interface (CR1114023) on June 24, 2019.

Semiannual Trend Review (IP Section 02.02) (1 Sample)

(1) The inspectors reviewed the licensees corrective action program for potential adverse trends in scheduling and completion of items added and removed from the equipment reliability top 10 focus items list that might be indicative of a more significant safety issue on June 26, 2019.

71153 - Followup of Events and Notices of Enforcement Discretion Event Report (IP Section 03.02)

Main article: IP 71153

The inspectors evaluated the following licensee event report (LER):

(1) LER 05000281/2019-001-00, Foreign Material in Breaker Contact Causes Pressurizer Power Operated Relief Valve Block Valve Inoperability (ADAMS accession ML19098A163). The circumstances surrounding this LER are documented in the Results section. (Closed)

OTHER ACTIVITIES

- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL

60855.1 - Operation of an Independent Spent Fuel Storage Installation at Operating Plants Operation of an Independent Spent Fuel Storage Installation at Operating Plants

Main article: IP 60855
(1) The inspectors evaluated the licensees independent spent fuel storage installation (ISFSI) cask loadings on June 3, 2019. Specifically, the inspectors observed the following activities:
  • Fuel selection and fuel loading
  • Heavy load movement of dry shielded canister/transfer cask
  • Radiological field surveys The inspectors evaluated the licensee's ISFSI cask movement and installation into the horizontal storage module on June 13, 2019. Specifically, the inspectors observed the following activities:
  • Heavy load movement of transfer cask
  • Radiological field surveys
  • Transportation of the transfer cask to the ISFSI pad The inspectors evaluated the licensee's ISFSI cask movement and installation into the horizontal storage module on June 20, 2019. Specifically, the inspectors observed the following activities:
  • Radiological field surveys
  • Transportation of the transfer cask to the ISFSI pad
  • Installation of the transfer cask into the horizontal storage module The inspectors evaluate the following program changes:
  • Revision of procedure 0-OP-FH-072, NUHOMS 32 PTH Dry Shielded Canister Loading and Unloading, Revisions 28 and

INSPECTION RESULTS

Licensee-Identified Non-Cited Violation 71153 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.

Violation: Surry Technical Specification 6.4.A.7 states, in part, that detailed written procedures with appropriate check-off lists and instructions shall be provided for conditions that include: preventive or corrective maintenance operations which would have an effect on the safety of the reactor. Surry Technical Specification 6.4.D states, in part, that procedures described in section 6.4.A shall be followed. These requirements were implemented, in part, by WO38102324301 and procedure MA-AA-102, Foreign Material Exclusion. Contrary to the above, on November 7, 2018, the licensee failed to follow the written procedures and instructions for breaker preventive maintenance of a unit 2 pressurizer power operated relief valve (PORV) block valve 2-RC-MOV-2536 including foreign material closeout, which resulted in a nylon brush bristle lodged in the valve breaker stationary closed contactor assembly and inoperability of the associated PORV block valve from December 4, 2018, to January 29, 2019. The pressurizer PORV block valves are active reactor coolant system boundary valves which provide the operators with the ability to detect a stuck-open safety or relief valve and to isolate a stuck-open PORV. The licensee reported the operation prohibited by Technical Specifications to the NRC on April 1, 2019, as Licensee Event Report 50-281/2019-001-00, Foreign Material in Breaker Contact Causes Pressurizer Power Operated Relief Valve Block Valve Inoperability.

Significance: Green. The failure to prevent foreign material from affecting operation of PORV block valve 2-RC-MOV-2536 was a performance deficiency (PD). The inspectors assessed the significance of the finding using IMC 0609 Attachment 4, Initial Characterization of Findings, Table 2, dated October 7, 2016, and the finding was determined to adversely affect the Barrier Integrity cornerstone under the active components of boundary (valve, seals) area to measure. Specifically, the pressurizer PORV block valve was not available to provide the operators with the ability to detect a stuck-open safety or relief valve and to isolate a stuck-open PORV. An independent bounding risk analysis was performed by a regional senior reactor analyst in accordance with NRC Inspection Manual Chapter 0609 Appendix A. The analysis assumed a non-recoverable failure to operate of the 2-RC-MOV-2536 block valve with no common cause impact for a period of 57 days. The analysis determined that the increase in core damage frequency due to the PD was less than 1E-7/year, a Green finding of very low safety significance.

Corrective Action References: CR1113030

EXIT MEETINGS AND DEBRIEFS

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

  • On July 3, 2019, the inspectors presented the integrated inspection results to Mr. Fred Mladen and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Type Designation Description or Title Revision or Procedure Date 60855.1 Miscellaneous Loading for Surry 05/28/2019 Spent Fuel Pool S1-OP-19-03 Fuel Handling Report Procedures 0-OP-FH-072 NUHOMS 32 PTH Dry Shielded Canister Loading and 29 Handling HP-1061.500 NUHOMS Spent Fuel Cask Preparation/Loading and 6 Transport to ISFSI 71111.01 Calculations ME-12152 Loss of Ventilation in the Cable Vault and Tunnel 0 Corrective Action CR1118627 Calculation provides elevated temperature at DBA with loss 03/19/2019 Documents of ventilation. Corrective Action CR1124184 Unit 1 upper cable vault ventilation O.O.S. and high 05/30/2019 Documents temperature Resulting from Inspection Procedures 0-OSP-ZZ-003 Hot Weather Preparation 8 71111.04 Drawings 113E244A Reactor Protection System Reactor Trip Matrices - Surry 20 Power Station - Unit 2 Miscellaneous 1-19-SW-00010 Safety Tagout of 1-SW-P-1B April 30, 2019 Procedures 0-OP-SW-002A Emergency Service Water System Alignment 10 1-OP-CH-002 Charging Pump A Operations 24 1-OP-CH-003 Charging Pump B Operations 26 1-OPT-FW-003 Turbine Driven Auxiliary Feedwater Pump 1-FW-P-2 54 2-PT-8.1 Reactor Protection System Logic (for Normal Operations) 40 71111.04S Corrective Action CR1086466, Documents CR1091946, CR1092279, CR1116987, CR1121992, CR1123110, CR1123469 Drawings 11448-FB-2A Fire Protection - Arrangement, Surry Power Station 22 Inspection Type Designation Description or Title Revision or Procedure Date 11448-FB-3A Yard, Water & Fire Protection Lines, Surry Power Station - 27 Unit 1 11448-FB-47A Flow/Valve Operating Numbers Diagram, Fire Protection & 34 Domestic Water System, Surry Power Station - Unit 1 Miscellaneous Module Nuclear Control Room Operator Development Program 10/06/2017 NCRODP-6-S-6- Surry Power Station: Fire Protection System S SDBD-SPS-FP System Design Basis Document for Fire Protection System 17 Procedures 0-AP-48.00 Fire Protection-Operations Response (with 5 attachments) 37 0-LPT-FP-006 Inspection of Hose Stations and Fire Extinguishers - 8 RCA/North Yard 0-OP-FP-006 Operation of Fire Protection Systems 17 1-OP-52.2A Fire Protection System Alignment 16 CM-AA-FPA-100 Fire Protection/Appendix R (Fire Safe Shutdown) Program 13 71111.05A Drawings 11548-FE-51R Wiring Diagram Internal and External Fire Protection Panel, 4 Surry Power Station, Unit 2 Procedures 0-FCA-7.00 Limiting Mechanical Equipment Room 3 or Fire 13 71111.05Q Drawings 11448-FM-071D Flow/Valve Operating Numbers Diagram Circulating and 15 Service Water System Surry Power Station Unit 1 11548-FM-071A Flow/Valve Operating Numbers Diagram Circulating and 103 Service Water System Surry Power Station Unit 2 Engineering Standing Order Alternative Method to provide Flood Isolation of MER 3 May 2, 2019 Changes SO-19-002 Fire Plans 0-FS-FP-225 Alternate AC Diesel Room - Construction Site Elev. 35 Feet 1 Procedures 0-AP-13.00 Turbine Building or MER 3 Flooding 31 0-EPM-0901-05 Mechanical Equipment Rooms 3 and 4 Smoke Detector Test 6 0-FS-FP-162 Auxiliary Building Elevation 45 Feet - 10 Inches 4 0-FS-FP-163 Fuel Building Elevation 6 Feet - 10 Inches and 15 Feet - 10 1 Inches 0-FS-FP-164 Fuel Building Elevation 27 Feet - 6 Inches and 45 Feet - 10 3 Inches 0-FS-FP-225 Alternate AC Diesel Room 1 Work Orders 38204187733 Mechanical Equipment Room 3 and Mechanical Equipment Room 4 Smoke Detector Test Inspection Type Designation Description or Title Revision or Procedure Date 204187733 Mechanical Equipment Rooms 3 and 4 Smoke Detector Test 0 71111.11Q Corrective Action CR1125393 Last minute EP Inject Message Request Documents Miscellaneous EAL Matrix Surry Power Station Emergency Action Level Matrix 4 Procedures 2-OP-CH-007 Blender Operations 40 2-OP-TM-005 Unit Ramping Operations 36 71111.12 Corrective Action CR1122082, Documents CR1122157, CR1122159, CR1122199, CR1122272, CR1122337 Engineering S-PMTE-2002- Replace the mechanical seals on 1/2-CH-P-1A/B/C 9/11/2002 Evaluations 011 S-PMTE-2005- PM to replace mechanical seals 10/19/2005 0355 Procedures 0-MCM-0109-01 Charging Pump Overhaul 38 0-MCM-0114-01 Emergency Service Water Pump Maintenance 29 0-MCM-0417-52 William Powell Swing Check Valve Inspection and Overhaul 11 Model 2342 VPAP-1001 Quality Control (QC) Inspection Program 20 Work Orders 38077550701 Emergency Service Water Pump 1-SW-P-1B Replacement April 30, and Testing 2019 38103275045 0-NSP-BS-005 1825 Day Freq. PT: Monitoring of Structures 11/26/2018 71111.13 Corrective Action CR1124809 High pressure feedwater heater '1B' moisture separator 06/12/2019 Documents drain tank normal level control valve erratic operation Miscellaneous Radiological Risk Screening Worksheet for NUHOMS cask dated campaign 2/25/2019 EOOS April 10, Schedulers Risk 2019 Evaluation for Surry Power Station Inspection Type Designation Description or Title Revision or Procedure Date EOOS April 18, Schedulers Risk 2019 Evaluation for Surry Power Station Procedures 0-DRP-049 Time Critical Operator Actions 16 Work Orders 38204199267 71111.15 Corrective Action CR1122509, 1-SW-P-1B High Vibrations Documents CR1122600, CR1122662, CR1122689 CR1124848 Main Control Room Chiller '4A' Failure to Start, first 06/11/2019 attempted start since 2017 CR112529 Failure to complete diagnosis of fire due to performance of 06/26/2019 parallel Time Critical Operator Actions CR1125718 Delayed Undervoltage Light during Unit 2 Train A Reactor 06/25/2019 Protection Logic Testing Operability Engineering Logs 1-SW-P-1B ESW Pump high vibrations. May 7, 2019 Evaluations Station Narrative Degradation of 1-SW-P-1B Foundation Rebar and Concrete May 1 and 2, Log Follow-ups Degradation 2019 for CR1122159 Procedures OP-AA-102 Operability Determination 15 71111.18 Calculations CE-2056 Surry Emergency Service Water Pump Heavy Load Rigging 0 

                                              & Load Drop Evaluation for 01-SW-P-1A, 01-SW-P-1B, &

01-SW-P-1C Engineering S1-17-155 Emergency Service Water Pump Fuel Oil Line Jumper 3 Changes SU-19-00112 Emergency Service Water Pump House Flood Protection 0 Restoration Following Postulated Load Drop of 1-SW-P-1B Engineering ETE-SU-2019- Emergency Service Water Pump NUREG-0612 Heavy Load 0 Evaluations 0008 Requirements ETE-SU-2019- Repair Disposition for 1-SW-P-1B Pump Pit Plate 0 1007 71111.19 Corrective Action CR1121088 Interlock switch for 2-MS-TV-4 found out of adjustment. April 17, Documents 2019 Inspection Type Designation Description or Title Revision or Procedure Date CR1122502, Pushbutton start needs reset, throttle linkage repair, 1-SW- CR1122504, P-1B packing leakage, fuel filter leak, loose base plate bolts CR1122558, CR1122559, CR1122572, CR1122744 Drawings 11448-FM-072D Flow/Valve Operating Numbers Diagram Component 32 and 37 Cooling Water System, Sheets 1 and 2 respectively Procedures 0-MCM-0107-01 Component Cooling Pump Maintenance 13 0-MCM-0417-52 William Powell Swing Check Valve Inspection and Overhaul 11 Model 2342 0-OP-AAC-001 AAC Diesel Generator Operation 30 0-OPT-SW-002 Emergency Service Water Pump 1-SW-P-1B 68 0-OPT-SW-008 Emergency Service Water Pump 1-SW-P-1B 27 Comprehensive Test 1-PT-18.8 Charging Pump Service Water Performance 38 1-PT-41.1 Component Cooling Water Pumps Performance Test 35 2-OSP-TM-001 Turbine Inlet Valve Freedom Test 46 2-PT-8.1 Reactor Protection System Logic (for Normal Operations) 40 Work Orders 38103680975 38103680975 Unit 2 Turbine Stop Valve Interlock Verification 0 38103711862 and 38103401882 204192362 204199804 06/26/2019 71111.22 Corrective Action CR1120556, Documents CR1120552 Corrective Action CR1120807 Non-ISI elevated vibes Point 9 Documents CR1120821 1-CS-115 externally leaking by Resulting from CR1120834 1-CS-PP-1B Pump seal drain boric acid accumulation. Inspection Engineering SU-13-01025 Implementation of the Beyond Design Basis Diverse and 06/16/2014 Changes Flexible Coping Strategies (FLEX) Program Inspection Type Designation Description or Title Revision or Procedure Date Engineering ETE-CPR-2014- Site Acceptance Testing (SAT) and Periodic Performance 2 Evaluations 1002 Verification Testing Acceptance Criteria for BDB FLEX Strategy Pumps - North Anna 1&2 and Surry 1&2 Procedures 0-MPM-1960-01 Semi-Annual or Annual Test of BDB Flex Equipment 15 0-NSP-CW-006 Canal Level Probe Removal, Inspection and Cleaning 6 0-OP-BDB-003 BDB 120/240 VAC Generator Operator Aid 1 0-OP-BDB-007 BDB High Capacity Pump Operating Aid 0 1-FSG-1 Long Term RCS Inventory Control 4 1-FSG-8 Alternate RCS Boration 4 1-OPT-CH-002 Charging Pump Operability and Performance Test for 1-CH- 59 P-1B 1-OPT-CS-002 Containment Spray System Test 18 2-OPT-EG-001 Number 2 Emergency Diesel Generator Monthly Start 77 Exercise Test 2-OPT-SI-005 LHSI Pump Test 34 71114.06 Corrective Action CR1125343 SJUN19FS Obj 4 (Notifications) Met with Problem Documents CR1125452 SJUN19FS Obj 20 (Exercise Conduct) Met with Problem Procedures EPIP-1.01 Emergency Manager Controlling Procedure 60 EPIP-3.06 Corporate Emergency Response Center Activation 0 EPIP-3.10 CERC Technical Support Controlling Procedure 0 EPIP-4.36 CERC Accident Assessment Controlling Procedure 0 71151 Miscellaneous 1Q/2019 Performance Indicators - Surry 1 and 2 - Reactor 06/25/2019 Coolant System Leakage 1Q/2019 Performance Indicators - Surry 1 and 2 - Safety 06/25/2019 System Functional Failures Unit 2 Control Room Narrative Log, 04/01/2018 - 3/31/2019 1Q/2019 Performance Indicators - Surry 1 and 2 - Reactor 06/25/2019 Coolant System Activity Unit 1 Control Room Narrative Log, 04/01/2018 - 3/31/2019 NEI 99-02 Regulatory Assessment Performance Indicator Guideline 7 71152 Corrective Action CA7489560 Documents CR015505, CR020890, Inspection Type Designation Description or Title Revision or Procedure Date CR021127, CR572210, CR1044721, CR1116262, and CA018234 CR1114023 Corrective Action CR1121189 Evaluate OPS aggregate impact based on NRC April 18, Documents observations and recommendations. 2019 Resulting from CR1121192 Self assessments for OP-AA-1700 (OAI) not performed from April 18, Inspection 2011 to 2017. 2019 Miscellaneous Equipment Reliability Top 10 Focus Items 04/23/2019 Equipment Reliability Top 10 Focus Items 01/22/2019 OAI Units 1 and 2 Operations Aggregate Impact March 1 and April 1, 2019 RO Logs Units 1 and 2 RO Abnormal Status Reports April 4, 2019 SPS Units 1 and TS 3.1 Reactor Coolant System Amendment Technical 250 and 251 Specifications SPS Units 1 and 4.2.7 Leakage 50 UFSAR Procedures 0-OP-BR-001 Boron Recovery Tank Transfer to the Surry Radwaste 11 Facility 1-OP-ZZ-002 Maintenance of Plant Operations 36 OP-AA-1700 Operations Aggregate Impact 8 Self-Assessments PIR1074492 Informal Self-Assessment on Surry Power Station's February Operations Aggregate Impact 2017 Work Orders 38052036702 Valve 01-CC-573 Replacement 38078187402 Valve 2-CC-322 Replacement 38103686836 Valve 01-BR-145 Bonnet Overhaul 204193252 Actuator / Valve Overhaul 17| ]]

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