Text

Integrated Inspection Report 05000280/2021004 and 05000281/2021004
	ML22040A200
Person / Time
Site:	Surry
Issue date:	02/11/2022
From:	Stewart Bailey; Division Reactor Projects II
To:	Stoddard D; Virginia Electric & Power Co (VEPCO)
References
	IR 2021004
	Download: ML22040A200 (23)
	v • d • e

February 11, 2022

SUBJECT:

SURRY POWER STATION - INTEGRATED INSPECTION REPORT 05000280/2021004 AND 05000281/2021004

Dear Mr. Stoddard:

On December 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Surry Power Station. On January 31, 2022, the NRC inspectors discussed the results of this inspection with Johnny Henderson, Director of Safety and Licensing, and other members of your staff. The results of this inspection are documented in the enclosed report.

One finding of very low safety significance (Green) is documented in this report. This finding did not involve a violation of NRC requirements.

If you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; and the NRC Resident Inspector at Surry Power Station. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Stewart N. Bailey, Chief Reactor Projects Branch 4 Division of Reactor Projects

Docket Nos. 05000280 and 05000281 License Nos. DPR-32 and DPR-37

Enclosure:

As stated

Inspection Report

Docket Numbers:

05000280 and 05000281

License Numbers:

DPR-32 and DPR-37

Report Numbers:

05000280/2021004 and 05000281/2021004

Enterprise Identifier: I-2021-004-0021

Licensee:

Virginia Electric and Power Company

Facility:

Surry Power Station

Location:

Surry, VA

Inspection Dates:

October 1, 2021 to December 31, 2021

Inspectors:

D. Bacon, Senior Operations Engineer

A. Butcavage, Reactor Inspector

L. McKown, Senior Resident Inspector

B. Towne, Resident Inspector

Approved By:

Stewart N. Bailey, Chief

Reactor Projects Branch 4

Division of Reactor Projects

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an 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.

List of Findings and Violations

Failure to Implement Spent Fuel Pool Instrumentation Equipment Functionality Requirements Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green FIN 05000280,05000281/2021004-01 Open/Closed

[H.11] -

Challenge the Unknown 71111.15 The inspectors identified a finding (FIN) of very low safety significance (Green) associated with Dominion Energys failure to implement Spent Fuel Pool Instrumentation Equipment Functionality requirements established in CM-AA-BDB-102, Beyond Design Basis FLEX Equipment Unavailability Tracking, Revision 12. Specifically, Dominion Energy did not recognize the red alarm light identified on May 29, 2021 could not be due to a spurious user input battery life expiration alarm as the station previously disabled these triggers.

Additional Tracking Items

Type Issue Number Title Report Section Status URI 05000281/2021004-02 Assessment of the Trip Hook Latch-up of the Unit 2 Turbine Driven Auxiliary Feedwater Pump 71111.19 Open

PLANT STATUS

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

Unit 2 began the inspection period at 91 percent rated thermal power in coastdown in advance of the scheduled refueling outage shutdown performed on October 24, 2021. On December 2, 2021, Unit 2 achieved criticality following the outage returning to rated thermal power on December 5, 2021. Unit 2 operated at or near rated thermal power for the remainder of inspection period.

INSPECTION SCOPES

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

REACTOR SAFETY

71111.01 - Adverse Weather Protection

External Flooding Sample (IP Section 03.03) (1 Sample)

(1) The inspectors evaluated that flood protection barriers, mitigation plans, procedures, and equipment are consistent with the licensees design requirements and risk analysis assumptions for coping with external flooding in December 2021.

Emergency Service Water Pump House

Safeguards Buildings

Emergency Diesel Generators

71111.04 - Equipment Alignment

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

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

(1) Unit 1 station battery charger alignment during surveillance testing on October 20, 2021.

(2) Unit 1 and 2 emergency diesel fuel oil storage and transfer system on November 2, 2021

(3) Unit 2 recirculation spray containment ring on November 4, 2021.

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

(1) The inspectors evaluated system configurations during a complete walkdown of the Unit 2 residual heat removal (RHR) system in shutdown cooling alignment on November 10, 2021.

71111.05 - Fire Protection

Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 Samples)

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

(1) Unit 2 mechanical equipment room #5 on October 19, 2021.

(2) No. 2 emergency diesel generator room on October 19, 2021.

(3) Unit 2 Turbine Building (Basement, Mezzanine, and Deck) on October 26, 2021.

(4) Unit 2 Containment on October 27, 2021.

71111.06 - Flood Protection Measures

Cable Degradation (IP Section 03.02) (1 Sample)

The inspectors evaluated cable submergence protection in:

(1) Cable vaults 1-EP-MH-1, 1-EP-MH-2, 1-EP-MH-3 associated with WO38204216570, on October 24, 2021.

71111.07A - Heat Sink Performance

Annual Review (IP Section 03.01) (1 Sample)

The inspectors evaluated readiness and performance of:

(1) Unit 1, component cooling water heat exchangers A, B, C, & D, on December 15, 2021.

===71111.08P - Inservice Inspection Activities (PWR)

PWR Inservice Inspection Activities Sample (IP Section 03.01)===

Main article: IP 71111.08

(1) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from11/1/21 to11/30/21:

03.01.a - Nondestructive Examination and Welding Activities.

Ultrasonic Examination (UT), Component ID: 11548-WMKS-0117A1-1 / 14-RH-101 / 1-03, Elbow to Pipe Weld, NDE Report ISl-2-UT-21-019, ASME Class 1

Magnetic Particle Examination (MT), Component ID: 11548-WMKS-0103A2-1

/ 30-SHP-122 / H0, ASME Class 2

UT Examination, CRD-48, CRD-55, and CRD-67, ASME Section XI, BO Full Penetration Weld of Adaptor to Penetration, ASME Class 1

Penetrant Examination (PT), Component ID: 11548-WMKS-0117A1-1 / 14-RH-101 / H016-2, Integral Attachments, RH System, ASME Class 2

MRP-227 Examinations of Rector Vessel Internals, Surry Unit 2 Phase 1, UT of Baffle Bolts, VT of CRDM Guide Tube Guide Cards, VT Core Barrel Upper Flange Weld, Lower Core Barrel Flange Welds, VT of Thermal Shield Support Block Cap Screws

ASME Section. XI, IWE, VT, Comp. ID, 11548-IWE/E1.11A, Containment Floor Slab to Metal Liner Interface Area

Weld No. 1-05A, WO 38204217640, Line No. 2"-RC-500-1502, 02-RC--102-VALVE, NDE Rpt. No BOP-PT-21-16

Weld No. 2-20A, WO 38204235324, Descript.14"-WFPD-113-601 / 2-FW-43, Final, NDE Rpt. No BOP-MT-21-108

03.01.b - Pressurized-Water Reactor Vessel Upper Head Penetration Examination Activities.

RVCH VT-2 Leakage exam IAW N-729: Sample Penetration Videos for # 14,

16, #18 and #44. Plus RVLIS and Vent Line Penetrations

03.01.c - Pressurized-Water Reactor Boric Acid Corrosion Control Activities.

CR-1183703, Weld Repair for Tubing, Fitting Leak, 02-CH-ICV-3642-VALV, WO 3820424851

CR1161992, CA8245219, Boric Acid Evaluation for 02-CS--73-VALVE, Leakage

CR1183722, Boric Acid Evaluation IAW N-566-2, for Valve 2-RC-HCV-2557A, Valve Material, and Bolts

Review of Initial Containment Walkdown Inspection Results

03.01.d - Pressurized-Water Reactor Steam Generator Tube Examination Activities.

Site Eddy Current Examinations on: Sg "2A",SG "2B", SG "2C", in accordance with Document No.: 51-9333405-000

Observations SG "C" Hot Leg Row 6, Col. 48,

Observations SG "B" HL Row 42, Col, 40, Row 10, Col 58, Row21, Col 21.

Site Secondary side visual examinations] SG "2A" '2B" "2C"

CR 1185827, WO 38204223840, Steam Drum Inspection on "2C" Steam Generator, Indications on Moisture Separator Top Deck, Lower Bank

71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance

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

(1) The licensee completed the requalification annual operating tests required to be administered to all licensed operators in accordance with Title 10 of the Code of Federal Regulations 55.59(a)(2), "Requalification Requirements," of the NRC's "Operator's Licenses." During the week of December 6, 2021, the inspector performed an in-office review of the overall pass/fail results of the individual operating tests and crew simulator operating tests in accordance with Inspection Procedure (IP)

===71111.11, "Licensed Operator Requalification Program." These results were compared to the thresholds established in Section 3.03, "Requalification Examination Results," of IP 71111.11.

The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating tests completed on March 11, 2021.

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

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

(1) The inspectors observed and evaluated licensed operator performance in the Control Room during the planned shutdown for Unit 2 fall refueling outage on October 24, 2021

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

Main article: IP 71111.11

(1) The inspectors observed and evaluated operations in the simulator during an Emergency Preparation drill including a tornado in the switchyard, partial loss of all AC power, and a small break loss of coolant accident on October 14, 2021.

71111.12 - Maintenance Effectiveness

Aging Management (IP Section 03.03) (1 Sample)

The inspectors evaluated the effectiveness of the aging management program for the following SSCs that did not meet their inspection or test acceptance criteria:

(1) Unit 2 recirculation spray nozzles on November 4, 2021.

71111.13 - Maintenance Risk Assessments and Emergent Work Control

Risk Assessment and Management Sample (IP Section 03.01) (6 Samples)

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

(1) Change in risk at Unit 2 high level intake structure due to emergent failure of hose house #15 hydrant (CR1182734) on October 14, 2021.

(2) Unit 2 high pressure turbine enclosure heavy lift, station battery testing, and safety significant pre-outage ventilation lineup changes on October 20, 2021.

(3) Protected system lineup during H bus functional testing on October 26, 2021

(4) Unit 2 elevated risk due to prolonged time at lowered inventory (reactor flange) from head installation error on November 21, 2021.

(5) Unit 2 plant cooldown from Hot Shutdown to Cold Shutdown via steam generator atmospheric PORVs, due to steam leak in main steam valve house on November 29, 2021.

(6) Elevated site risk due to Unit 2 emergency condensate storage tank auxiliary feedwater recirculation line leakage (CR1187639), on December 10, 2021.

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)

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

(1) CR1181764, Unit 1, B charging pump motor inboard bearing darkened oil sample on October 7, 2021.

(2) CR1182734, hose house #15 hydrant failure on October 14, 2021.

(3) CR1183214, Number 2 emergency diesel generator nonconforming seismic strap bolting on October 21, 2021.

(4) CR1186371, Beyond design basis spent fuel pit indication uninterruptible power supply battery failure on November 24, 2021.

(5) CR1187639, Unit 2 emergency condensate storage tank auxiliary feedwater recirculation line leakage on December 10, 2021.

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (2 Samples)

The inspectors evaluated the following temporary or permanent modifications:

(1)2-MCM-1150-01, Unit 2 Reactor Disassembly and Reassembly, Revision 45 one time only changes 1, 2, & 3 following human performance event associated with improper installation of reactor vessel head studs on November 21, 2021.

(2) ETE-SU-2021-0072 & CR1186299, Classification of piping between main steam trip and non-return valves on November 18, 2021.

71111.19 - Post-Maintenance Testing

Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)

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

(1) Correction of deficiencies from Section XI inspection (WO38103760049) on November 12, 2021.

(2) Emergency diesel generator 2 operational performance test following outage scope maintenance and start circuit design change (DCN 04-004 & WO38204218250), on November 5, 2021.

(3) Repair of steam leak at Unit 2 main steam trip valve steam trap bypass valve seal weld connection (CR1186767) on November 30, 2021.

(4) Operational performance test of Unit 2 turbine driven auxiliary feedwater pump following outage maintenance (WO38204219508), on December 01, 2021.

(5) Unit 1 new regulator installed for pressurizer backup air supply bank 'A' failed during post-maintenance testing (CR1188322 & CR1188455), on December 28, 2021.

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)

(1) The inspectors evaluated unit 2 refueling outage 2R30 activities from October 24 to December 2, 2021.

71111.22 - Surveillance Testing

The inspectors evaluated the following surveillance tests:

Surveillance Tests (other) (IP Section 03.01)

Main article: IP 71111.22

(1)2-OPT-EG-001, No. 2 emergency diesel generator monthly start exercise test, on October 19, 2021 (2)2-OPT-ZZ-001, Engineered safety features actuation with undervoltage and degraded voltage - 2H bus, on October 26, 2021

Inservice Testing (IP Section 03.01) (2 Samples)

(1)1-OPT-RS-001, Containment outside recirculation spray pump flow and leak test (38204209707) on November 9, 2021 (2)2-OPT-RC-001, 2-RC-PCV-2455C power operated relief valve stroke time testing (CR1186258) on November 24, 2021

Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)

(1) Reactor Coolant Letdown Containment Penetration (Penetration 28) Type 'C' test and post test valve operability stroke (2-CH-TV-2204B), work order 382042199004 on November 12,

OTHER ACTIVITIES - BASELINE

===71151 - Performance Indicator Verification

The inspectors verified licensee performance indicators submittals listed below:

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

Main article: IP 71151

(1) Unit 1 (October 1, 2020 - September 30, 2021)

(2) Unit 2 (October 1, 2020 - September 30, 2021)