IR 05000280/2019002

NRC Integrated Inspection Report 05000280/2019002 and 05000281/2019002; 07200055/2019001

ML19217A072
Person / Time
Site:	Surry
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)

Text

August 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

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

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 7115

List of Findings and Violations

No findings or violations of more than minor significance were identified.

Additional Tracking Items

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

71153 Closed

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.

71111.01 - Adverse Weather Protection

Summer Readiness Sample (IP Section 03.01) (1 Sample)

(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) (5 Samples)

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)

1. 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) (1 Sample)

(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) (6 Samples)

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) (1 Sample)

(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) (1 Sample)

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)===

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) (7 Samples)

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) (6 Samples)

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) (7 Samples)

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

1. 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)

(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) (1 Sample)

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)===

(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) (2 Samples)

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)

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

(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

Procedure

Type

Designation

Description or Title

Revision or

Date

60855.1

Miscellaneous

Loading for Surry

Spent Fuel Pool

05/28/2019

S1-OP-19-03

Fuel Handling Report

Procedures

0-OP-FH-072

NUHOMS 32 PTH Dry Shielded Canister Loading and

Handling

HP-1061.500

NUHOMS Spent Fuel Cask Preparation/Loading and

Transport to ISFSI

71111.01

Calculations

ME-12152

Loss of Ventilation in the Cable Vault and Tunnel

Corrective Action

Documents

CR1118627

Calculation provides elevated temperature at DBA with loss

of ventilation.

03/19/2019

Corrective Action

Documents

Resulting from

Inspection

CR1124184

Unit 1 upper cable vault ventilation O.O.S. and high

temperature

05/30/2019

Procedures

0-OSP-ZZ-003

Hot Weather Preparation

71111.04

Drawings

113E244A

Reactor Protection System Reactor Trip Matrices - Surry

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

1-OP-CH-002

Charging Pump A Operations

1-OP-CH-003

Charging Pump B Operations

1-OPT-FW-003

Turbine Driven Auxiliary Feedwater Pump 1-FW-P-2

2-PT-8.1

Reactor Protection System Logic (for Normal Operations)

71111.04S

Corrective Action

Documents

CR1086466,

CR1091946,

CR1092279,

CR1116987,

CR1121992,

CR1123110,

CR1123469

Drawings

11448-FB-2A

Fire Protection - Arrangement, Surry Power Station

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

11448-FB-3A

Yard, Water & Fire Protection Lines, Surry Power Station -

Unit 1

11448-FB-47A

Flow/Valve Operating Numbers Diagram, Fire Protection &

Domestic Water System, Surry Power Station - Unit 1

Miscellaneous

Module

NCRODP-6-S-6-

S

Nuclear Control Room Operator Development Program

Surry Power Station: Fire Protection System

10/06/2017

SDBD-SPS-FP

System Design Basis Document for Fire Protection System

Procedures

0-AP-48.00

Fire Protection-Operations Response (with 5 attachments)

0-LPT-FP-006

Inspection of Hose Stations and Fire Extinguishers -

RCA/North Yard

0-OP-FP-006

Operation of Fire Protection Systems

1-OP-52.2A

Fire Protection System Alignment

CM-AA-FPA-100

Fire Protection/Appendix R (Fire Safe Shutdown) Program

71111.05A

Drawings

11548-FE-51R

Wiring Diagram Internal and External Fire Protection Panel,

Surry Power Station, Unit 2

Procedures

0-FCA-7.00

Limiting Mechanical Equipment Room 3 or Fire

71111.05Q Drawings

11448-FM-071D

Flow/Valve Operating Numbers Diagram Circulating and

Service Water System Surry Power Station Unit 1

11548-FM-071A

Flow/Valve Operating Numbers Diagram Circulating and

Service Water System Surry Power Station Unit 2

103

Engineering

Changes

Standing Order

SO-19-002

Alternative Method to provide Flood Isolation of MER 3

May 2, 2019

Fire Plans

0-FS-FP-225

Alternate AC Diesel Room - Construction Site Elev. 35 Feet

Procedures

0-AP-13.00

Turbine Building or MER 3 Flooding

0-EPM-0901-05

Mechanical Equipment Rooms 3 and 4 Smoke Detector Test

0-FS-FP-162

Auxiliary Building Elevation 45 Feet - 10 Inches

0-FS-FP-163

Fuel Building Elevation 6 Feet - 10 Inches and 15 Feet - 10

Inches

0-FS-FP-164

Fuel Building Elevation 27 Feet - 6 Inches and 45 Feet - 10

Inches

0-FS-FP-225

Alternate AC Diesel Room

Work Orders

204187733

Mechanical Equipment Room 3 and Mechanical Equipment

Room 4 Smoke Detector Test

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

204187733

Mechanical Equipment Rooms 3 and 4 Smoke Detector Test

71111.11Q Corrective Action

Documents

CR1125393

Last minute EP Inject Message Request

Miscellaneous

EAL Matrix

Surry Power Station Emergency Action Level Matrix

Procedures

2-OP-CH-007

Blender Operations

2-OP-TM-005

Unit Ramping Operations

71111.12

Corrective Action

Documents

CR1122082,

CR1122157,

CR1122159,

CR1122199,

CR1122272,

CR1122337

Engineering

Evaluations

S-PMTE-2002-

011

Replace the mechanical seals on 1/2-CH-P-1A/B/C

9/11/2002

S-PMTE-2005-

0355

PM to replace mechanical seals

10/19/2005

Procedures

0-MCM-0109-01

Charging Pump Overhaul

0-MCM-0114-01

Emergency Service Water Pump Maintenance

0-MCM-0417-52

William Powell Swing Check Valve Inspection and Overhaul

Model 2342

VPAP-1001

Quality Control (QC) Inspection Program

Work Orders

38077550701

Emergency Service Water Pump 1-SW-P-1B Replacement

and Testing

April 30,

2019

38103275045

0-NSP-BS-005 1825 Day Freq. PT: Monitoring of Structures

11/26/2018

71111.13

Corrective Action

Documents

CR1124809

High pressure feedwater heater '1B' moisture separator

drain tank normal level control valve erratic operation

06/12/2019

Miscellaneous

Radiological Risk Screening Worksheet for NUHOMS cask

campaign

dated

2/25/2019

EOOS

Schedulers Risk

Evaluation for

Surry Power

Station

April 10,

2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

EOOS

Schedulers Risk

Evaluation for

Surry Power

Station

April 18,

2019

Procedures

0-DRP-049

Time Critical Operator Actions

Work Orders

204199267

71111.15

Corrective Action

Documents

CR1122509,

CR1122600,

CR1122662,

CR1122689

1-SW-P-1B High Vibrations

CR1124848

Main Control Room Chiller '4A' Failure to Start, first

attempted start since 2017

06/11/2019

CR112529

Failure to complete diagnosis of fire due to performance of

parallel Time Critical Operator Actions

06/26/2019

CR1125718

Delayed Undervoltage Light during Unit 2 Train A Reactor

Protection Logic Testing

06/25/2019

Operability

Evaluations

Engineering Logs

1-SW-P-1B ESW Pump high vibrations.

May 7, 2019

Station Narrative

Log Follow-ups

for CR1122159

Degradation of 1-SW-P-1B Foundation Rebar and Concrete

Degradation

May 1 and 2,

2019

Procedures

OP-AA-102

Operability Determination

71111.18

Calculations

CE-2056

Surry Emergency Service Water Pump Heavy Load Rigging

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

01-SW-P-1C

Engineering

Changes

S1-17-155

Emergency Service Water Pump Fuel Oil Line Jumper

SU-19-00112

Emergency Service Water Pump House Flood Protection

Restoration Following Postulated Load Drop of 1-SW-P-1B

Engineering

Evaluations

ETE-SU-2019-

0008

Emergency Service Water Pump NUREG-0612 Heavy Load

Requirements

ETE-SU-2019-

1007

Repair Disposition for 1-SW-P-1B Pump Pit Plate

71111.19

Corrective Action

Documents

CR1121088

Interlock switch for 2-MS-TV-4 found out of adjustment.

April 17,

2019

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CR1122502,

CR1122504,

CR1122558,

CR1122559,

CR1122572,

CR1122744

Pushbutton start needs reset, throttle linkage repair, 1-SW-

P-1B packing leakage, fuel filter leak, loose base plate bolts

Drawings

11448-FM-072D

Flow/Valve Operating Numbers Diagram Component

Cooling Water System, Sheets 1 and 2

and 37

respectively

Procedures

0-MCM-0107-01

Component Cooling Pump Maintenance

0-MCM-0417-52

William Powell Swing Check Valve Inspection and Overhaul

Model 2342

0-OP-AAC-001

AAC Diesel Generator Operation

0-OPT-SW-002

Emergency Service Water Pump 1-SW-P-1B

0-OPT-SW-008

Emergency Service Water Pump 1-SW-P-1B

Comprehensive Test

1-PT-18.8

Charging Pump Service Water Performance

1-PT-41.1

Component Cooling Water Pumps Performance Test

2-OSP-TM-001

Turbine Inlet Valve Freedom Test

2-PT-8.1

Reactor Protection System Logic (for Normal Operations)

Work Orders

38103680975

38103680975

Unit 2 Turbine Stop Valve Interlock Verification

38103711862

and

38103401882

204192362

204199804

06/26/2019

71111.22

Corrective Action

Documents

CR1120556,

CR1120552

Corrective Action

Documents

Resulting from

Inspection

CR1120807

Non-ISI elevated vibes Point 9

CR1120821

1-CS-115 externally leaking by

CR1120834

1-CS-PP-1B Pump seal drain boric acid accumulation.

Engineering

Changes

SU-13-01025

Implementation of the Beyond Design Basis Diverse and

Flexible Coping Strategies (FLEX) Program

06/16/2014

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

Engineering

Evaluations

ETE-CPR-2014-

1002

Site Acceptance Testing (SAT) and Periodic Performance

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

0-NSP-CW-006

Canal Level Probe Removal, Inspection and Cleaning

0-OP-BDB-003

BDB 120/240 VAC Generator Operator Aid

0-OP-BDB-007

BDB High Capacity Pump Operating Aid

1-FSG-1

Long Term RCS Inventory Control

1-FSG-8

Alternate RCS Boration

1-OPT-CH-002

Charging Pump Operability and Performance Test for 1-CH-

P-1B

1-OPT-CS-002

Containment Spray System Test

2-OPT-EG-001

Number 2 Emergency Diesel Generator Monthly Start

Exercise Test

2-OPT-SI-005

LHSI Pump Test

71114.06

Corrective Action

Documents

CR1125343

SJUN19FS Obj 4 (Notifications) Met with Problem

CR1125452

SJUN19FS Obj 20 (Exercise Conduct) Met with Problem

Procedures

EPIP-1.01

Emergency Manager Controlling Procedure

EPIP-3.06

Corporate Emergency Response Center Activation

EPIP-3.10

CERC Technical Support Controlling Procedure

EPIP-4.36

CERC Accident Assessment Controlling Procedure

71151

Miscellaneous

1Q/2019 Performance Indicators - Surry 1 and 2 - Reactor

Coolant System Leakage

06/25/2019

1Q/2019 Performance Indicators - Surry 1 and 2 - Safety

System Functional Failures

06/25/2019

Unit 2 Control Room Narrative Log, 04/01/2018 - 3/31/2019

1Q/2019 Performance Indicators - Surry 1 and 2 - Reactor

Coolant System Activity

06/25/2019

Unit 1 Control Room Narrative Log, 04/01/2018 - 3/31/2019

NEI 99-02

Regulatory Assessment Performance Indicator Guideline

71152

Corrective Action

Documents

CA7489560

CR015505,

CR020890,

Inspection

Procedure

Type

Designation

Description or Title

Revision or

Date

CR021127,

CR572210,

CR1044721,

CR1116262, and

CA018234

CR1114023

Corrective Action

Documents

Resulting from

Inspection

CR1121189

Evaluate OPS aggregate impact based on NRC

observations and recommendations.

April 18,

2019

CR1121192

Self assessments for OP-AA-1700 (OAI) not performed from

2011 to 2017.

April 18,

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

Technical

Specifications

TS 3.1 Reactor Coolant System

Amendment

250 and 251

SPS Units 1 and

UFSAR

4.2.7 Leakage

Procedures

0-OP-BR-001

Boron Recovery Tank Transfer to the Surry Radwaste

Facility

1-OP-ZZ-002

Maintenance of Plant Operations

OP-AA-1700

Operations Aggregate Impact

Self-Assessments PIR1074492

Informal Self-Assessment on Surry Power Station's

Operations Aggregate Impact

February

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