IR 05000387/2018001
ML18121A308 | |
Person / Time | |
---|---|
Site: | Susquehanna ![]() |
Issue date: | 05/01/2018 |
From: | James Krafty Reactor Projects Region 1 Branch 4 |
To: | Rausch T Susquehanna |
Krafty J | |
References | |
IR 2018001 | |
Download: ML18121A308 (15) | |
Text
UNITED STATES May 1, 2018
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION - INTEGRATED INSPECTION REPORT 05000387/2018001 AND 05000388/2018001
Dear Mr. Rausch:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station (SSES), Units 1 and 2. On April 13, 2018, the NRC inspectors discussed the results of this inspection with Derek Jones, Plant Manager, 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. NRC 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 a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Resident Inspector at Susquehanna.
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 the NRCs Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
James A. Krafty, Acting Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Numbers: 50-387 and 50-388 License Numbers: NPF-14 and NPF-22
Enclosure:
Inspection Report 05000387/2018001 and 05000388/2018001
Inspection Report
Docket Number(s): 50-387 and 50-388 License Number(s): NPF-14 and NPF-22 Report Number(s): 05000387/2018001 and 05000388/2018001 Enterprise Identifier: I-2018-001-0069 Licensee: Susquehanna Nuclear, LLC (Susquehanna)
Facility: Susquehanna Steam Electric Station, Units 1 and 2 Location: Berwick, Pennsylvania Inspection Dates: January 1, 2018 to March 31, 2018 Inspectors: L. Micewski, Senior Resident Inspector T. Daun, Resident Inspector A. Turilin, Project Engineer J. Furia, Senior Health Physicist M. Modes, Senior Reactor Inspector Approved By: J. Krafty, Acting Chief Reactor Projects Branch 4 Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Susquehannas performance at Susquehanna Steam Electric Station Units 1 and 2 by conducting the baseline inspections described in this report 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. NRC-identified and self-revealed findings, violations, and additional items are summarized in the table below.
Licensee-identified non-cited violations are documented in report section: 71111.15.
Additional Tracking Items Type Issue number Title Report Status Section LER 05000388/2017-008-01 Condition Prohibited by 71153 Closed Technical Specifications Due to a Loose Terminal Block Associated with Primary Containment Isolation Valves LER 05000387(388)/2017-003-00 Loss of Secondary 71153 Closed Containment Zone 3 Due to Fan Trip
Plant Status Unit 1 began the inspection period at 100 percent power. On January 8, 2018, operators reduced power to approximately 75 percent, performed rod pattern adjustments and returned the unit to 100 percent the same day. On February 15, 2018, operators commenced end-of-cycle coast down for the remainder of the cycle. On March 30, 2018, operators commenced reducing power from 76 percent for a planned refueling outage. Unit 1 reached Mode 4 on March 31, 2018 and remained shut down for the remainder of the inspection period.
Unit 2 began the inspection period at 100 percent power. On February 12, 2018, operators reduced power to approximately 65 percent to perform maintenance on a reactor feed pump.
Operators returned the unit to 100 percent the next day, and remained at or near 100 percent 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 Susquehannas performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection Impending Severe Weather
The inspectors evaluated readiness for impending adverse weather conditions for extremely cold temperatures on January 3, 2018 through January 6, 2018.
71111.04 - Equipment Alignment Partial Walkdown
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, high pressure coolant injection during reactor core isolation cooling injection valve relay replacement on January 24, 2018
- (2) Unit 2, residual heat removal (RHR) during division 2 swing bus maintenance on January 30, 2018
- (3) Unit Common, E emergency diesel generator (EDG) while substituted in for D EDG during D EDG mid-cycle overhaul on February 5, 2018
- (4) Unit Common, B emergency service water (ESW) during D subsystem pump maintenance and relay replacement on February 13, 2018
71111.05 - Fire Protection Quarterly Inspection
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Unit Common, D EDG room (fire zone 0-41D) on January 4, 2018
- (2) Unit 2, load center room II-510 and II-507 (fire zones 2-5F and 2-5G) on February 5, 2018
- (3) Unit Common, refuel floor (fire zone 0-8A) on March 1, 2018
- (4) Unit Common, computer room and computer maintenance room and office (fire zones 0-24E and 0-24F) on March 5, 2018
- (5) Unit 1, RHR B pump room (fire zone 1-1E) on March 14, 2018
71111.06 - Flood Protection Measures Internal Flooding
The inspectors evaluated internal flooding mitigation protections in Unit 1, reactor building elevation 749 on February 8, 2018.
71111.07 - Heat Sink Performance Heat Sink (Triennial)
The inspectors evaluated heat exchanger/heat sink performance on the following components:
- (1) Unit 1 and 2, RHR heat exchangers, Section 02.02b
- (2) Unit 2 spray pond, Section 02.02d. Specifically, Sections 02.02d.3 and 02.02d.6 were completed.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance Operator Requalification
The inspectors observed and evaluated licensed operator simulator training, which included a momentary loss of B engineered safeguard system electrical bus, a high level in the scram discharge volume due to a failed closed drain valve, an Anticipated Transient Without Scram, and the failure of select components to automatically start as required on
===February 12, 2018.
Operator Performance (1 Sample)===
The inspectors observed reactor shutdown activities from 76% to MODE 3 on Unit 1 on March 30 - 31, 2018.
71111.12 - Maintenance Effectiveness Routine Maintenance Effectiveness
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) Unit 1, scram discharge volume vent and drain valves not opening when scram reset on January 31, 2018
- (2) Unit 1, fuel pool cooling system on March 16, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Unit Common elevated risk during D EDG post maintenance testing on February 9, 2018
- (2) Unit Common relay replacement and maintenance on D ESW pump on February 13, 2018
- (3) Unit 1 repair of D RHR pump local circuit breaker control switch on March 14, 2018
- (4) Unit 1 online functional test of RHR low pressure logic from remote shutdown panel on March 26, 2018
- (5) Unit 1 online risk associated with logic testing from the remote shutdown panel on March 29, 2018
71111.15 - Operability Determinations and Functionality Assessments
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Unit Common, C ESW pump field jumper installed not in accordance with design drawings on January 17, 2018
- (2) Unit Common, EDG operability when drywell unit cooling fan 2V413B is slow to stop on February 5, 2018
- (3) Unit 1, impact to equipment in reactor building elevation 749 with floor drain blockage on February 8, 2018
- (4) Unit Common, D EDG air receivers ultrasonic testing results less than minimum wall thickness on February 27, 2018
- (5) Unit 1, division 2 core spray with non-restrained ESW replacement piping staged next to room cooler on March 20, 2018
- (6) Unit 1, reactor core isolation cooling oil filter clogging on March 21, 2018
- (7) Unit Common, Zone 3 secondary containment increased inleakage past hatch 1H24 on March 23, 2018
71111.19 - Post Maintenance Testing
The inspectors evaluated post maintenance testing for the following maintenance/repair activities:
- (1) Unit Common, D EDG air receivers internal inspection on February 15, 2018
- (2) Unit Common, C EDG electronic governor replacement on March 6, 2018
- (3) Unit 1, B standby liquid control pump and actuator overhaul on March 13, 2018
- (4) Unit Common, D EDG mid-cycle overhaul on March 13, 2018
- (5) Unit 1, D RHR pump lateral switch repairs on March 15, 2018
- (6) Unit 1, division 1 RHR service water installation of pulsation dampener on March 22, 2018
==71111.20 - Refueling and Other Outage Activities (Partial Sample)
The inspectors evaluated Unit 1 refueling outage 1R20 activities from March 30, 2018 to March 31, 2018. The inspectors completed inspection procedure Sections 03.01.a and 03.01.c1.
71111.22 - Surveillance Testing The inspectors evaluated the following surveillance tests: Routine==
- (1) Unit Common, ESW logic system functional test on January 2, 2018
- (2) Unit Common, E EDG monthly run on January 3, 2018
- (3) Unit Common, B EDG integrated surveillance test on January 29 and 30, 2018
- (4) Unit 1, RHR service water flow surveillance on March 22, 2018
Inservice (1 Sample)
- (1) Unit Common, quarterly ESW flow verification Loop A on February 22, 2018
71114.06 - Drill Evaluation Drill/Training Evolution
The inspectors evaluated the emergency director, dose assessment personnel, and communicators emergency preparedness implementation during five tabletop training exercises between January 26, 2018 and March 9, 2018. The inspectors observed two different scenarios. One scenario involved a simulated airborne radiological release following core damage due to a large amount of foreign material. The second scenario involved a steam leak at the reactor feed pump turbine, that was unable to be isolated due to main steam isolation valve failure.
RADIATION SAFETY
==71124.03 - In-Plant Airborne Radioactivity Control and Mitigation The following inspection activities were completed to close-out the 2016/2017 Reactor Oversight Process biennial cycle:
Use of Respiratory Protection Devices==
The inspectors evaluated respiratory protection.
Self-Contained Breathing Apparatus for Emergency Use
The inspectors evaluated the licensees self-contained breathing apparatus program.
Problem Identification and Resolution (1 Sample)
The inspectors evaluated whether problems associated with radiation monitoring and exposure control (including operating experience) were identified at an appropriate threshold and properly addressed in the corrective action program.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below for the period from January 1, 2017 through December 31, 2017.
- (1) Unit 1 and 2 Unplanned Scrams
- (2) Unit 1 and 2 Unplanned Scrams with Complications
- (3) Unit 1 and 2 Unplanned Power Changes
71153 - Follow-up of Events and Notices of Enforcement Discretion Licensee Event Reports
The inspectors evaluated the following licensee event reports which can be accessed at https://lersearch.inl.gov/LERSearchCriteria.aspx:
- (1) Licensee Event Report (LER) 05000388/2017-008-01, Condition Prohibited by Technical Specifications Due to a Loose Terminal Block Associated with Primary Containment Isolation Valves, on March 22, 2018. The review for this event is documented in Inspection Report 05000387/2017003 and 05000388/2017003.
- (2) LER 05000387(388)/2017-003-00, Loss of Secondary Containment Zone 3 Due to Fan Trip, on March 29, 2018. The review for this event is documented in Inspection Report 05000387/2017001 and 05000388/2017001.
INSPECTION RESULTS
Licensee Identified Non-Cited Violation 71111.15 This violation of very low safety significant 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: Susquehanna Unit 1 TS section 5.4.1 requires that written procedures shall be implemented covering the applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Susquehannas implementing instruction NDAP-QA-0503, General Housekeeping, Transient Material and Internal Cleanliness, Revision 45 implements aspects of the Regulatory Guide administrative procedures requirements. NDAP-QA-0503 section 6.1.5.h requires, in part, that transient equipment shall be located such that it will not impact safety related equipment during a seismic event. Locate all items at a distance greater than the height of the item from safety related equipment. Additionally, TS 3.5.1 Action Statement I directs immediate entry into Limiting Condition for Operation (LCO)3.0.3 if one core spray subsystem is inoperable with one low pressure coolant injection (LPCI)subsystem inoperable. LCO 3.0.3 requires action to be taken within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit in MODE 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
Contrary to the above, from December 1, 2017 to December 3, 2017, Susquehanna staged a 540 pound, ten foot long replacement pipe on 34 inch high stands within 34 inches of the safety related Unit 1, B Core Spray room cooler. Susquehanna concluded that the room cooler was inoperable because the pipe could have reasonably contacted and damaged the flexible conduit for the power cable to the room cooler during a seismic event. Additionally, from 7:48 a.m. on December 2, 2017 to 1:35 p.m. on December 3, 2017, maintenance was performed on the Unit 1, division 2 LPCI swing bus motor generator which rendered the division 2 LPCI system inoperable. During this time, Susquehanna did not perform the required actions of LCO 3.0.3 and remained in MODE 1.
Significance/Severity Level: This violation is of very low safety significance (Green), since this finding did not represent a loss of system, a loss of function of at least a single train for greater than its TS allowed outage time, or a loss of a non-TS train.
Corrective Action Reference(s): CR-2017-20227; CR-2018-01717; CR-2018-02250
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 13, 2018, the inspectors presented the quarterly resident inspector inspection results to Derek Jones, Plant Manager, and other members of the staff.
DOCUMENTS REVIEWED
Procedures
NDAP-00-1913, Seasonal Readiness, Revision 10
OI-AD-029, Emergency Load Control, Revision 17
ON-NATPHENOM-001, Severe Weather/Natural Phenomena, Revision 56
NDAP-00-0030, Severe Weather/Natural Disaster Preparation, Revision 12
Condition Reports (*initiated in response to inspection)
CR-2017-14989 CR-2018-00378 CR-2018-00931 CR-2018-01073
CR-2018-02126 CR-2018-02452 CR-2018-02492 CR-2018-02494
CR-2018-02500
Drawings
FF62008, Common Fire Barrier Upgrade Conduit Interface at Concrete Q-Decking or
Penetration Seal Sketch, Sheet 26, Revision 1
FF62008, Common Fire Barrier Upgrade Conduit Interface at Concrete Q-Decking or
Penetration Seal Sketch, Sheet 1, Revision 2
FF62009, Unit 1 Fire Barrier Upgrade E1K758 Wrapped Raceway Sketch, Sheet 361,
Revision 0
M-182, Common P&ID Diesel Generator E Building Air Flow Diagram, Sheet 2, Revision 9
M-134, Common P&ID Diesel E Auxiliaries (Starting Air Systems), Sheet 6, Revision 7
M-5200, Common Diesel Generator E Bldg., General Arrangement Sections, Sheet 2,
Revision 2
M-156, Unit 1 HPCI Lubricating and Control Oil P&ID, Sheet 1, Revision 9
M-156, Unit 1 P&ID HPCI Turbine- Pump, Sheet 1, Revision 36
Miscellaneous
Level of Effort Checklist, CR-2017-14989
71111.05AQ
Miscellaneous
FP-013-198, Diesel Generator Bay D Fire Zone 0-41D Elevations 677, 660 and 710,
Revision 4
FP-213-258, Load Center Room (II-510) Load Center Room (II-507) Fire Zone 2-5F, 2-5G
Elevation 749-1, Revision 5
FP-013-141, Computer Maintenance Area (C-205, 206, 207) and Corridor (C-200, 204) Fire
Zones 0-24F, 0-24B Elevation 698-0, Revision 7
FP-013-140, Computer Room (C-202) Fire Zone 0-24E Elevation 698-0, Revision 7
FP-113-105, RHR Pump Room B (I-13) Fire Zone 1-1E Elevation 645-0, Revision 3
FP-013-132, Common Refueling Floor 9I-810, II-810) Fire Zone 0-8A Elevation 818-1,
Revision 4
Condition Reports (*initiated in response to inspection)
CR-2018-02051
Drawings
C-2729, Unit 1 Reactor Building Station Flood Barrier Plan of Elevation 749-1, Sheet 1,
Revision 1
Miscellaneous
EC-FLOD-1001, Evaluation of Response to INPO ER 11-1, Recommendations 3 & 4 for Station
Flooding, Revision 2
EC-FLOD-0001, Internal Flooding Evaluations for Moderate Energy Pipe Cracks and Sprinkler
system Actuations, Revision 3
Procedures
NEIM-00-1165, Cooling Tower Structural Inspections, Revision 1
NDAP-QA-1163, Structural Monitoring Program, Revision 4
NSEI-AD-103, System Engineering Instruction for Outage Inspection of the Cooling Tower,
Revision 1
NSEP-AD-0002, Station Health Process, Revision 16
Maintenance Orders/Work Orders
PCWO 2144095
PCWO 2102869
PCWO 1995536
Calculations
Nuclear Engineering Calculation Cover Sheet NEPM-QA-0221-1, Calculation EC-016-1003,
Heat Sink - Maximum Water Loss Design Basis Analysis, Revision 6
Design Calculation 22A2597, Heat Exchanger, Residual Heat Removal, Revision 1
Miscellaneous
Spray Pond Level Readings for February 2 - 27, 2018
RHR Chemistry Surveillance, February 3, 2017 and February 9, 2017
2E205A, 2017 Chemistry Sample Report
2E2058, 2015 Final Eddy Current Results Map
Miscellaneous
GO-100-004
GO-100-005
OP-AD-300
Condition Reports (*initiated in response to inspection)
CR-2017-11560 CR-2018-04438 CR-2018-04439
Miscellaneous
EACE for CR 2017-11560, Revision 0
ACT-01-CR-2017-11560
ACT-05-CR-2017-11560
Condition Reports (*initiated in response to inspection)
CR-2018-03945
Miscellaneous
Protected Equipment, Unit 1 B RHR Pump
SO-149-020 On-line Function Test of RHR LP B from RSDP
Schedulers Evaluation for Susquehanna Unit 1 & 2 March 24- 28, 2018
Condition Reports (*initiated in response to inspection)
CR-2018-00301 CR-2018-01870 CR-2018-02051 CR-2018-02237
CR-2018-02238* CR-2018-02372 CR-2018-02398 CR-2018-02494
CR-2018-02513 CR-2018-03152 CR-2018-04322*
Action Requests
AR-2017-20603 AR-2018-02561
Drawings
E-146, Common Schematic Diagram ESW Pump C, Sheet 5, Revision 27
E109-13, Unit 1 Medium Voltage Switchgear Safeguard Connection Diagram Bus 1C IA20303,
Sheet 54, Revision 21
E-146, Common Schematic Diagram ESW Pump 0P504C, Sheet 6, Revision 50
E-347-3, Unit 1 Connection Diagram 4.16KV Switchgear 1A203, Sheet A, Revision 36
E-347-3, Unit 1 Connection Diagram 4.16KV Switchgear 1A203, Sheet C
FF-105800, Design report of Air Starting Receiver
ACT-01-CR-2018-02398
M-150, Unit 1 P&ID RCIC Turbine Lube Oil, Revision 2
Miscellaneous
NDAP-QA-0703-1, Prompt Operability Determination CR-2018-02051
BOP-UT-18-008, Supplemental Report
NDE-UT-014, UT Thickness Examination
SE-270-001, Revision 16, Attachment A
SO-170-001, Revision 3, Attachment A
SE-070-011, Revision 16, Attachment A
SE-270-011, Revision 15, Attachment A
SE-070-011, Revision 19, Attachment A
Level of Effort Checklist, CR-2018-02250
EC-034-0016, Verification of Reactor Building Coolers Selection, Revision 0
EC-RISK-0521, Reactor Building- Effects of Loss of HVAC on Components, Revision 4
EC-LOCA-0500, COTTAP Analysis RB Post DBA Temperature Issue, Revision 5
EC-034-0567, Power Uprate Impact Review- Reactor Building HVAC System, Revision 5
Procedures
OT-024-147, Diesel Generator C Restoration, Revision 0
SO-153-004, Quarterly Standby Liquid Control Flow verification, Revision 45
SO-149-008, 2 YR- RHR Logic System Functional Test (Div 2) Online
Condition Reports (*initiated in response to inspection)
CR-2018-02398 CR-2018-03945
Work Orders
2041900
2066604
Procedures
SO-024-B01, Diesel Generator B Integrated Surveillance Test, Revision 1
SO-024-014, Monthly Diesel Generator E Operability Test, Revision 50
SO-054-001C, 24 Month Logic System Functional test of the ESW System Pump C Start and
Reset Logic, Revision 1
SO-054-A03, Quarterly ESW Flow Verification Loop A, Revision 17
SO-116-A03, Quarterly RHR Service Water System Flow Verification Division 1, Revision 14
Condition Reports (*initiated in response to inspection)
CR-2018-00102 CR-2018-00167 CR-2018-01984 CR-2018-01990
Condition Reports (*initiated in response to inspection)
CR-2018-03161 CR-2018-03162 CR-2018-03194
71151
Miscellaneous
DI-2017-08601
Procedures
HP-TP-759, Inspection and Testing of Firehawk SCBA Protective Equipment, Revision 5
Miscellaneous
Respiratory Protection/TEDE ALARA Worksheets for RWP 20180034, LRW Filter and
RWP 20180035, Carwash
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BOULEVARD, SUITE 100
KING OF PRUSSIA, PA 19406-2713
May 1, 2018
Mr. Timothy S. Rausch
President and Chief Nuclear Officer
Susquehanna Nuclear, LLC
769 Salem Blvd. NUCSB3
Berwick, PA 18603
SUBJECT: SUSQUEHANNA STEAM ELECTRIC STATION - INTEGRATED
INSPECTION REPORT 05000387/2018001 AND 05000388/2018001
Dear Mr. Rausch:
On March 31, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection
at Susquehanna Steam Electric Station (SSES), Units 1 and 2. On April 13, 2018, the NRC
inspectors discussed the results of this inspection with Derek Jones, Plant Manager, 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. NRC
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 a non-cited violation
(NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest the violation or significance of the NCV, you should provide a response within
days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear
Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with
copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC
Resident Inspector at Susquehanna.
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 the NRCs Public Document
Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR), Part 2.390,
Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
James
- A. Krafty, Acting Chief
Reactor Projects Branch 4
Division of Reactor Projects
T. Rausch 2
Docket Numbers: 50-387 and 50-388
License Numbers: NPF-14 and NPF-22
Enclosure:
Inspection Report 05000387/2018001 and 05000388/2018001
cc w/encl: Distribution via ListServ
SUNSI Review Non-Sensitive Publicly Available
Sensitive Non-Publicly Available
OFFICE RI/DRP RI/DRP RI/DRP
NAME LMicewski SBarber JKrafty
DATE 04/30/18 05/01/18 05/01/18
U.S. NUCLEAR REGULATORY COMMISSION
Inspection Report
Docket Number(s): 50-387 and 50-388
License Number(s): NPF-14 and NPF-22
Report Number(s): 05000387/2018001 and 05000388/2018001
Enterprise Identifier: I-2018-001-0069
Licensee: Susquehanna Nuclear, LLC (Susquehanna)
Facility: Susquehanna Steam Electric Station, Units 1 and 2
Location: Berwick, Pennsylvania
Inspection Dates: January 1, 2018 to March 31, 2018
Inspectors:
- L. Micewski, Senior Resident Inspector
- T. Daun, Resident Inspector
- A. Turilin, Project Engineer
- J. Furia, Senior Health Physicist
- M. Modes, Senior Reactor Inspector
Approved By:
- J. Krafty, Acting Chief
Reactor Projects Branch 4
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Susquehannas
performance at Susquehanna Steam Electric Station Units 1 and 2 by conducting the baseline
inspections described in this report 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. NRC-identified and
self-revealed findings, violations, and additional items are summarized in the table below.
Licensee-identified non-cited violations are documented in report section: 71111.15.
Additional Tracking Items
Type Issue number Title Report Status
Section
LER 05000388/2017-008-01 Condition Prohibited by 71153 Closed
Technical Specifications
Due to a Loose
Terminal Block
Associated with Primary
Containment Isolation
Valves
LER 05000387(388)/2017-003-00 Loss of Secondary 71153 Closed
Containment Zone 3
Due to Fan Trip
Plant Status
Unit 1 began the inspection period at 100 percent power. On January 8, 2018, operators
reduced power to approximately 75 percent, performed rod pattern adjustments and returned
the unit to 100 percent the same day. On February 15, 2018, operators commenced end-of-
cycle coast down for the remainder of the cycle. On March 30, 2018, operators commenced
reducing power from 76 percent for a planned refueling outage. Unit 1 reached Mode 4 on
March 31, 2018 and remained shut down for the remainder of the inspection period.
Unit 2 began the inspection period at 100 percent power. On February 12, 2018, operators
reduced power to approximately 65 percent to perform maintenance on a reactor feed pump.
Operators returned the unit to 100 percent the next day, and remained at or near 100 percent
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 Susquehannas performance
and compliance with Commission rules and regulations, license conditions, site procedures, and
standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Impending Severe Weather (1 Sample)
The inspectors evaluated readiness for impending adverse weather conditions for extremely
cold temperatures on January 3, 2018 through January 6, 2018.
71111.04 - Equipment Alignment
Partial Walkdown (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1) Unit 1, high pressure coolant injection during reactor core isolation cooling injection
valve relay replacement on January 24, 2018
(2) Unit 2, residual heat removal (RHR) during division 2 swing bus maintenance on
January 30, 2018
(3) Unit Common, E emergency diesel generator (EDG) while substituted in for D EDG
during D EDG mid-cycle overhaul on February 5, 2018
(4) Unit Common, B emergency service water (ESW) during D subsystem pump
maintenance and relay replacement on February 13, 2018
71111.05 - Fire Protection
Quarterly Inspection (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected
areas:
(1) Unit Common, D EDG room (fire zone 0-41D) on January 4, 2018
(2) Unit 2, load center room II-510 and II-507 (fire zones 2-5F and 2-5G) on
February 5, 2018
(3) Unit Common, refuel floor (fire zone 0-8A) on March 1, 2018
(4) Unit Common, computer room and computer maintenance room and office (fire zones
0-24E and 0-24F) on March 5, 2018
(5) Unit 1, RHR B pump room (fire zone 1-1E) on March 14, 2018
71111.06 - Flood Protection Measures
Internal Flooding (1 Sample)
The inspectors evaluated internal flooding mitigation protections in Unit 1, reactor building
elevation 749 on February 8, 2018.
71111.07 - Heat Sink Performance
Heat Sink (Triennial) (3 Samples)
The inspectors evaluated heat exchanger/heat sink performance on the following
components:
(1) Unit 1 and 2, RHR heat exchangers, Section 02.02b
(2) Unit 2 spray pond, Section 02.02d. Specifically, Sections 02.02d.3 and 02.02d.6 were
completed.
71111.11 - Licensed Operator Requalification Program and Licensed Operator Performance
Operator Requalification (1 Sample)
The inspectors observed and evaluated licensed operator simulator training, which included
a momentary loss of B engineered safeguard system electrical bus, a high level in the
scram discharge volume due to a failed closed drain valve, an Anticipated Transient Without
Scram, and the failure of select components to automatically start as required on
February 12, 2018.
Operator Performance (1 Sample)
The inspectors observed reactor shutdown activities from 76% to MODE 3 on Unit 1 on
March 30 - 31, 2018.
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness (2 Samples)
The inspectors evaluated the effectiveness of routine maintenance activities associated
with the following equipment and/or safety significant functions:
(1) Unit 1, scram discharge volume vent and drain valves not opening when scram reset on
January 31, 2018
(2) Unit 1, fuel pool cooling system on March 16, 2018
71111.13 - Maintenance Risk Assessments and Emergent Work Control (5 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent
work activities:
(1) Unit Common elevated risk during D EDG post maintenance testing on February 9,
2018
(2) Unit Common relay replacement and maintenance on D ESW pump on February 13,
2018
(3) Unit 1 repair of D RHR pump local circuit breaker control switch on March 14, 2018
(4) Unit 1 online functional test of RHR low pressure logic from remote shutdown panel on
March 26, 2018
(5) Unit 1 online risk associated with logic testing from the remote shutdown panel on March
29, 2018
71111.15 - Operability Determinations and Functionality Assessments (7 Samples)
The inspectors evaluated the following operability determinations and functionality
assessments:
(1) Unit Common, C ESW pump field jumper installed not in accordance with design
drawings on January 17, 2018
(2) Unit Common, EDG operability when drywell unit cooling fan 2V413B is slow to stop on
February 5, 2018
(3) Unit 1, impact to equipment in reactor building elevation 749 with floor drain blockage on
February 8, 2018
(4) Unit Common, D EDG air receivers ultrasonic testing results less than minimum wall
thickness on February 27, 2018
(5) Unit 1, division 2 core spray with non-restrained ESW replacement piping staged next to
room cooler on March 20, 2018
(6) Unit 1, reactor core isolation cooling oil filter clogging on March 21, 2018
(7) Unit Common, Zone 3 secondary containment increased inleakage past hatch 1H24 on
March 23, 2018
71111.19 - Post Maintenance Testing (6 Samples)
The inspectors evaluated post maintenance testing for the following maintenance/repair
activities:
(1) Unit Common, D EDG air receivers internal inspection on February 15, 2018
(2) Unit Common, C EDG electronic governor replacement on March 6, 2018
(3) Unit 1, B standby liquid control pump and actuator overhaul on March 13, 2018
(4) Unit Common, D EDG mid-cycle overhaul on March 13, 2018
(5) Unit 1, D RHR pump lateral switch repairs on March 15, 2018
(6) Unit 1, division 1 RHR service water installation of pulsation dampener on
March 22, 2018
71111.20 - Refueling and Other Outage Activities (Partial Sample)
The inspectors evaluated Unit 1 refueling outage 1R20 activities from March 30, 2018 to
March 31, 2018. The inspectors completed inspection procedure Sections 03.01.a and
03.01.c1.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Routine (4 Samples)
(1) Unit Common, ESW logic system functional test on January 2, 2018
(2) Unit Common, E EDG monthly run on January 3, 2018
(3) Unit Common, B EDG integrated surveillance test on January 29 and 30, 2018
(4) Unit 1, RHR service water flow surveillance on March 22, 2018
Inservice (1 Sample)
(1) Unit Common, quarterly ESW flow verification Loop A on February 22, 2018
71114.06 - Drill Evaluation
Drill/Training Evolution (1 Sample)
The inspectors evaluated the emergency director, dose assessment personnel, and
communicators emergency preparedness implementation during five tabletop training
exercises between January 26, 2018 and March 9, 2018. The inspectors observed two
different scenarios. One scenario involved a simulated airborne radiological release
following core damage due to a large amount of foreign material. The second scenario
involved a steam leak at the reactor feed pump turbine, that was unable to be isolated due
to main steam isolation valve failure.
RADIATION SAFETY
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
The following inspection activities were completed to close-out the 2016/2017 Reactor
Oversight Process biennial cycle:
Use of Respiratory Protection Devices (1 Sample)
The inspectors evaluated respiratory protection.
Self-Contained Breathing Apparatus for Emergency Use (1 Sample)
The inspectors evaluated the licensees self-contained breathing apparatus program.
Problem Identification and Resolution (1 Sample)
The inspectors evaluated whether problems associated with radiation monitoring and
exposure control (including operating experience) were identified at an appropriate threshold
and properly addressed in the corrective action program.
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below for the
period from January 1, 2017 through December 31, 2017. (6 Samples)
(1) Unit 1 and 2 Unplanned Scrams
(2) Unit 1 and 2 Unplanned Scrams with Complications
(3) Unit 1 and 2 Unplanned Power Changes
71153 - Follow-up of Events and Notices of Enforcement Discretion
Licensee Event Reports (2 Samples)
The inspectors evaluated the following licensee event reports which can be accessed at
https://lersearch.inl.gov/LERSearchCriteria.aspx:
(1) Licensee Event Report (LER) 05000388/2017-008-01, Condition Prohibited by
Technical Specifications Due to a Loose Terminal Block Associated with Primary
Containment Isolation Valves, on March 22, 2018. The review for this event is
documented in Inspection Report 05000387/2017003 and 05000388/2017003.
(2) LER 05000387(388)/2017-003-00, Loss of Secondary Containment Zone 3 Due to
Fan Trip, on March 29, 2018. The review for this event is documented in Inspection
Report 05000387/2017001 and 05000388/2017001.
INSPECTION RESULTS
Licensee Identified Non-Cited Violation 71111.15
This violation of very low safety significant 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: Susquehanna Unit 1 TS section 5.4.1 requires that written procedures shall be
implemented covering the applicable procedures recommended in Regulatory Guide 1.33,
Revision 2, Appendix A, February 1978. Susquehannas implementing instruction NDAP-QA-
0503, General Housekeeping, Transient Material and Internal Cleanliness, Revision 45
implements aspects of the Regulatory Guide administrative procedures requirements. NDAP-
QA-0503 section 6.1.5.h requires, in part, that transient equipment shall be located such that
it will not impact safety related equipment during a seismic event. Locate all items at a
distance greater than the height of the item from safety related equipment. Additionally, TS 3.5.1 Action Statement I directs immediate entry into Limiting Condition for Operation (LCO)
3.0.3 if one core spray subsystem is inoperable with one low pressure coolant injection (LPCI)
subsystem inoperable. LCO 3.0.3 requires action to be taken within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit in
MODE 2 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and MODE 3 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.
Contrary to the above, from December 1, 2017 to December 3, 2017, Susquehanna staged a
540 pound, ten foot long replacement pipe on 34 inch high stands within 34 inches of the
safety related Unit 1, B Core Spray room cooler. Susquehanna concluded that the room
cooler was inoperable because the pipe could have reasonably contacted and damaged the
flexible conduit for the power cable to the room cooler during a seismic event. Additionally,
from 7:48 a.m. on December 2, 2017 to 1:35 p.m. on December 3, 2017, maintenance was
performed on the Unit 1, division 2 LPCI swing bus motor generator which rendered the
division 2 LPCI system inoperable. During this time, Susquehanna did not perform the
required actions of LCO 3.0.3 and remained in MODE 1.
Significance/Severity Level: This violation is of very low safety significance (Green), since this
finding did not represent a loss of system, a loss of function of at least a single train for
greater than its TS allowed outage time, or a loss of a non-TS train.
Corrective Action Reference(s): CR-2017-20227; CR-2018-01717; CR-2018-02250
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 13, 2018, the inspectors presented the quarterly resident inspector inspection
results to Derek Jones, Plant Manager, and other members of the staff.
DOCUMENTS REVIEWED
Procedures
NDAP-00-1913, Seasonal Readiness, Revision 10
OI-AD-029, Emergency Load Control, Revision 17
ON-NATPHENOM-001, Severe Weather/Natural Phenomena, Revision 56
NDAP-00-0030, Severe Weather/Natural Disaster Preparation, Revision 12
Condition Reports (*initiated in response to inspection)
CR-2017-14989 CR-2018-00378 CR-2018-00931 CR-2018-01073
CR-2018-02126 CR-2018-02452 CR-2018-02492 CR-2018-02494
CR-2018-02500
Drawings
FF62008, Common Fire Barrier Upgrade Conduit Interface at Concrete Q-Decking or
Penetration Seal Sketch, Sheet 26, Revision 1
FF62008, Common Fire Barrier Upgrade Conduit Interface at Concrete Q-Decking or
Penetration Seal Sketch, Sheet 1, Revision 2
FF62009, Unit 1 Fire Barrier Upgrade E1K758 Wrapped Raceway Sketch, Sheet 361,
Revision 0
M-182, Common P&ID Diesel Generator E Building Air Flow Diagram, Sheet 2, Revision 9
M-134, Common P&ID Diesel E Auxiliaries (Starting Air Systems), Sheet 6, Revision 7
M-5200, Common Diesel Generator E Bldg., General Arrangement Sections, Sheet 2,
Revision 2
M-156, Unit 1 HPCI Lubricating and Control Oil P&ID, Sheet 1, Revision 9
M-156, Unit 1 P&ID HPCI Turbine- Pump, Sheet 1, Revision 36
Miscellaneous
Level of Effort Checklist, CR-2017-14989
71111.05AQ
Miscellaneous
FP-013-198, Diesel Generator Bay D Fire Zone 0-41D Elevations 677, 660 and 710,
Revision 4
FP-213-258, Load Center Room (II-510) Load Center Room (II-507) Fire Zone 2-5F, 2-5G
Elevation 749-1, Revision 5
FP-013-141, Computer Maintenance Area (C-205, 206, 207) and Corridor (C-200, 204) Fire
Zones 0-24F, 0-24B Elevation 698-0, Revision 7
FP-013-140, Computer Room (C-202) Fire Zone 0-24E Elevation 698-0, Revision 7
FP-113-105, RHR Pump Room B (I-13) Fire Zone 1-1E Elevation 645-0, Revision 3
FP-013-132, Common Refueling Floor 9I-810, II-810) Fire Zone 0-8A Elevation 818-1,
Revision 4
Condition Reports (*initiated in response to inspection)
CR-2018-02051
Drawings
C-2729, Unit 1 Reactor Building Station Flood Barrier Plan of Elevation 749-1, Sheet 1,
Revision 1
Miscellaneous
EC-FLOD-1001, Evaluation of Response to INPO ER 11-1, Recommendations 3 & 4 for Station
Flooding, Revision 2
EC-FLOD-0001, Internal Flooding Evaluations for Moderate Energy Pipe Cracks and Sprinkler
system Actuations, Revision 3
Procedures
NEIM-00-1165, Cooling Tower Structural Inspections, Revision 1
NDAP-QA-1163, Structural Monitoring Program, Revision 4
NSEI-AD-103, System Engineering Instruction for Outage Inspection of the Cooling Tower,
Revision 1
NSEP-AD-0002, Station Health Process, Revision 16
Maintenance Orders/Work Orders
PCWO 2144095
PCWO 2102869
PCWO 1995536
Calculations
Nuclear Engineering Calculation Cover Sheet NEPM-QA-0221-1, Calculation EC-016-1003,
Heat Sink - Maximum Water Loss Design Basis Analysis, Revision 6
Design Calculation 22A2597, Heat Exchanger, Residual Heat Removal, Revision 1
Miscellaneous
Spray Pond Level Readings for February 2 - 27, 2018
RHR Chemistry Surveillance, February 3, 2017 and February 9, 2017
2E205A, 2017 Chemistry Sample Report
2E2058, 2015 Final Eddy Current Results Map
Miscellaneous
GO-100-004
GO-100-005
OP-AD-300
Condition Reports (*initiated in response to inspection)
CR-2017-11560 CR-2018-04438 CR-2018-04439
Miscellaneous
EACE for CR 2017-11560, Revision 0
ACT-01-CR-2017-11560
ACT-05-CR-2017-11560
Condition Reports (*initiated in response to inspection)
CR-2018-03945
Miscellaneous
Protected Equipment, Unit 1 B RHR Pump
SO-149-020 On-line Function Test of RHR LP B from RSDP
Schedulers Evaluation for Susquehanna Unit 1 & 2 March 24- 28, 2018
Condition Reports (*initiated in response to inspection)
CR-2018-00301 CR-2018-01870 CR-2018-02051 CR-2018-02237
CR-2018-02238* CR-2018-02372 CR-2018-02398 CR-2018-02494
CR-2018-02513 CR-2018-03152 CR-2018-04322*
Action Requests
AR-2017-20603 AR-2018-02561
Drawings
E-146, Common Schematic Diagram ESW Pump C, Sheet 5, Revision 27
E109-13, Unit 1 Medium Voltage Switchgear Safeguard Connection Diagram Bus 1C IA20303,
Sheet 54, Revision 21
E-146, Common Schematic Diagram ESW Pump 0P504C, Sheet 6, Revision 50
E-347-3, Unit 1 Connection Diagram 4.16KV Switchgear 1A203, Sheet A, Revision 36
E-347-3, Unit 1 Connection Diagram 4.16KV Switchgear 1A203, Sheet C
FF-105800, Design report of Air Starting Receiver
ACT-01-CR-2018-02398
M-150, Unit 1 P&ID RCIC Turbine Lube Oil, Revision 2
Miscellaneous
NDAP-QA-0703-1, Prompt Operability Determination CR-2018-02051
BOP-UT-18-008, Supplemental Report
NDE-UT-014, UT Thickness Examination
SE-270-001, Revision 16, Attachment A
SO-170-001, Revision 3, Attachment A
SE-070-011, Revision 16, Attachment A
SE-270-011, Revision 15, Attachment A
SE-070-011, Revision 19, Attachment A
Level of Effort Checklist, CR-2018-02250
EC-034-0016, Verification of Reactor Building Coolers Selection, Revision 0
EC-RISK-0521, Reactor Building- Effects of Loss of HVAC on Components, Revision 4
EC-LOCA-0500, COTTAP Analysis RB Post DBA Temperature Issue, Revision 5
EC-034-0567, Power Uprate Impact Review- Reactor Building HVAC System, Revision 5
Procedures
OT-024-147, Diesel Generator C Restoration, Revision 0
SO-153-004, Quarterly Standby Liquid Control Flow verification, Revision 45
SO-149-008, 2 YR- RHR Logic System Functional Test (Div 2) Online
Condition Reports (*initiated in response to inspection)
CR-2018-02398 CR-2018-03945
Work Orders
2041900
2066604
Procedures
SO-024-B01, Diesel Generator B Integrated Surveillance Test, Revision 1
SO-024-014, Monthly Diesel Generator E Operability Test, Revision 50
SO-054-001C, 24 Month Logic System Functional test of the ESW System Pump C Start and
Reset Logic, Revision 1
SO-054-A03, Quarterly ESW Flow Verification Loop A, Revision 17
SO-116-A03, Quarterly RHR Service Water System Flow Verification Division 1, Revision 14
Condition Reports (*initiated in response to inspection)
CR-2018-00102 CR-2018-00167 CR-2018-01984 CR-2018-01990
Condition Reports (*initiated in response to inspection)
CR-2018-03161 CR-2018-03162 CR-2018-03194
71151
Miscellaneous
DI-2017-08601
Procedures
HP-TP-759, Inspection and Testing of Firehawk SCBA Protective Equipment, Revision 5
Miscellaneous
Respiratory Protection/TEDE ALARA Worksheets for RWP 20180034, LRW Filter and
RWP 20180035, Carwash