IR 05000334/2019010
| ML19102A032 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/11/2019 |
| From: | Matt Young NRC Region 1 |
| To: | Bologna R FirstEnergy Nuclear Operating Co |
| References | |
| IR 2019010 | |
| Download: ML19102A032 (9) | |
Text
April 11, 2019
SUBJECT:
BEAVER VALLEY UNITS 1 AND 2 - PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT 05000334/2019010 AND 05000412/2019010
Dear Mr. Bologna:
On March 21, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed a problem identification and resolution inspection at your Beaver Valley Units 1 and 2. On March 21, 2019, the NRC inspectors discussed the results of this inspection with R. Pennfield, General Plant Manager and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC inspection team reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
The team also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments.
Based on the samples reviewed, the team determined that your staffs performance in each of these areas adequately supported nuclear safety.
Finally, the team reviewed the stations programs to establish and maintain a safety-conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the teams observations and the results of these interviews the team found no evidence of challenges to your organizations safety-conscious work environment. Your employees appeared willing to raise nuclear safety concerns through at least one of the several means available.
The NRC inspectors did not identify any finding or violation of more than minor significance. 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/
Matthew R. Young, Chief Projects Branch 6
Docket Nos.: 05000334 and 05000412 License Nos.: DPR-66 and NPF-73
Enclosure:
Inspection Report 05000334/2019010 and 05000412/2019010
Inspection Report
Docket Numbers:
05000334 and 05000412
License Numbers:
Report Numbers:
05000334/2019010 and 05000412/2019010
Enterprise Identifier: I-2019-010-0004
Licensee:
FirstEnergy Nuclear Operating Co.
Facility:
Beaver Valley, Units 1 and 2
Location:
Shippingport, PA 15077-0004
Inspection Dates:
March 04, 2019 to March 21, 2019
Inspectors:
J. Brand, Reactor Inspector
S. Elkhiamy, Reactor Inspector
J. Krafty, Senior Resident Inspector
S. Shaffer, Senior Project Engineer
Approved By:
Matthew R. Young, Chief
Projects Branch 6
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a problem identification and resolution inspection at Beaver Valley Units 1 and 2 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.
Findings and violations being considered in the NRCs assessment are summarized in the table below.
List of Findings and Violations
No findings were identified.
Additional Tracking Items
None.
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 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.
OTHER ACTIVITIES - BASELINE
71152B - Problem Identification and Resolution Biennial Team Inspection (IP Section 02.04)
The inspectors performed a biennial assessment of the licensees corrective action program, use of operating experience, self-assessments and audits, and safety conscious work environment.
- Corrective Action Program Effectiveness - The inspectors assessed the corrective action programs effectiveness in identifying, prioritizing, evaluating, and correcting problems.
- Operating Experience, Self-Assessments and Audits - The inspectors assessed the effectiveness of the stations processes for use of operating experience, audits, and self-assessments.
- Safety Conscious Work Environment - The inspectors assessed the effectiveness of the stations programs to establish and maintain a safety-conscious work environment.
INSPECTION RESULTS
Observation The inspectors reviewed the stations corrective action program and the stations implementation of the program to evaluate its effectiveness in identifying, prioritizing, evaluating, and correcting problems, and to confirm that the station was complying with NRC regulations and licensee standards for corrective action programs. Based on the samples reviewed, the inspectors determined FENOCs performance in each of these areas supported nuclear safety.
The inspectors also evaluated the stations processes for use of industry and NRC operating experience information and the effectiveness of the stations audits and self-assessments. Based on the samples reviewed, the inspectors determined that FENOCs performance in each of these areas supported nuclear safety.
Finally, the inspectors reviewed the stations programs to establish and maintain a safety conscious work environment, and interviewed station personnel to evaluate the effectiveness of these programs. Based on the inspectors observations and the results of these interviews, the inspectors found no evidence of challenges to the organizations safety conscious work environment. A cross section of FENOC employees were interviewed, and all stated a willingness to raise nuclear safety concerns through at least one of the several means available.
Observation 71152B Operating Experience Screening Process is not consistently implemented in accordance with the requirements of NOBP-LP-2100, FENOC Operating Experience Process. Specifically, in accordance with step 4.1.2 the screening process provides for three possible outcomes: Not applicable, Information only, or Evaluation, all of which require documenting justification. The inspectors noted many examples while reviewing Operating Experience where screening documentation was not provided nor justification made for not evaluating in accordance with station procedures. In one case, OE-2017-0236, FW heater control, met the criteria for an evaluation since it affects plant reliability or availability (i.e. reactivity management level 4 event and plant power excursion), however no screening or justification was documented.
Contributing to the inconsistent application of requirements may be vague or interpretative guidance.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On March 21, 2019, the inspector presented the Biennial Problem Identification and Resolution Inspection to Mr. Rod Penfield and other members of the licensee staff.
DOCUMENTS REVIEWED
Procedures
NOP-LP-2001, Corrective Action Program, Revision 46
NOBP-LP-2011, FENOC Cause Analysis, Revision 25
1/2OM-56B.4A.E, Unit 1/2 Safe Shutdown Intent and Methodology, Revision 0
NORM-OP-1002, Conduct of Operations, Revision 7
NOBP-LP-2100, FENOC Operating Experience Process, Revision 18
1/2-ADM-0600, Environmental Protection Programs, Revision 5
1/2-ADM-0605, Control of Water and Wastewater Disposal and Draining Activities, Revision 7
1/2OM-35.4A.A, voltage Schedule Guidance, Revision 15
2OST-30.13B, Train B Service Water System Full Flow Test, Revision 45
2OST-36.7, Offsite to Onsite Power Distribution System Breaker Alignment Verification,
Revision 20
Condition Reports
CR-2018-08406
CR-2018-07052
CR-2018-04735
CR-2017-04023
CR-2017-05260
CR-2018-03574
CR-2017-08308
CR-2018-06128
CR-2018-10075
CR-2016-13722
CR-2017-08406
CR-2016-13722
CR-2016-14253
CR-2017-00036
CR-2017-02997
CR-2018-07262
CR-2018-08392
CR-2018-08311
CR-2018-06843
CR-2018-11224
CR-2017-12282
CR-2017-01830
CR-2017-01836
CR-2017-06990
CR-2017-02410
CR-2017-02493
CR-2018-08392
CR-2016-13722
CR-2017-05957
CR-2017-01836
CR-2016-14253
CR-2017-02997
CR-2017-08406
CR-2018-04285
CR-2017-09825
CR-2009-62810
CR-2013-15679
CR-2015-05473
CR-2015-11473
CR-2016-00190
CR-2016-03633
CR-2016-10087
CR-2016-12107
CR-2017-02305
CR-2017-04022
CR-2017-04146
CR-2017-04211
CR-2017-05270
CR-2017-05721
CR-2017-06376
CR-2017-07506
CR-2017-08205
CR-2017-10327
CR-2017-10852
CR-2017-10857
CR-2017-11030
CR-2017-11191
CR-2017-11220
CR-2017-12308
CR-2018-00258
CR-2018-00283
CR-2018-00470
CR-2018-00665
CR-2018-00709
CR-2018-01542
CR-2018-01549
CR-2018-02456
CR-2018-03372
CR-2018-04780
CR-2018-05063
CR-2018-07447
CR-2018-07760
CR-2018-07933
CR-2018-08299
CR-2018-08730
CR-2018-10384
CR-2018-10653
CR-2018-11228
CR-2019-00075
CR-2019-00264
CR-2019-00851
CR-2019-01418
Miscellaneous Documents
Standing Order 18-006
OE-2018-0136, IN1803 Operating Experience Regarding Failure to meet TS Requirements
Changing Conditions
OE-2017-0349, Feedwater Heater Level Control Valve Failure to Control Level
IN1804, Failure of Operators to trip the Plant when experiencing unstable conditions.
SA-BN-2017-0614, 2R19 Shutdown Defense in Depth Post Outage Critique
SA-BN-2017-0595, 2017 Semi-Annual EPlan Health Physics Drill #1-6/13/17
OFO-2018-0012, 2018 Emergency Preparedness Audit
IER L1-17-5, Line of Sight to the Reactor Core
SA-BN-2017-0766, Beaver Valley 2016 Annual Snap Shot Assessment on Clearance Process,
Procedure and Practices.
ATA 2019-2685
ATA-2018-1216
B-062B, Safeguards Area Ventilation - Loads and Air Rates, Revision 3
B-244. Evaluation of Capacity of 2HVR-ACU-207A, B (Safeguard Area), Revision 1
DCP-1604, Test Package for IWP #1604-1, Revision 0
DMC-3606, Isokinetic Flow Assessment and Penetration of Airborne Particles for RM-1VS-109,
RM-1VS-110, and RM-1GW-109, Revision 0
DMC-3811, Beaver Valley Unit 2 Safeguards building Heatup Analysis Using MAAP-DBA,
Revision 0
ECP-17-0389, Isokinetic Flow Assessment and Penetration of Airborne Particles for
RM-1VS-109, RM-1VS-110, and RM-1GW-109, Revision 0
EER 600965045
EER 601191559
EER 601191560
EER 601206768
Inservice Testing Program Health Report 2014 through 2018
MS-C-18-01-13, Design Control, Engineering Programs and ASME
N-785, Minimum Service Water Pressure Setpoint to Protect SWS Pumps - Emergency Diesel
Test Acceptance Curves, Revision 2
N-800, Minimum Service Water Flow Requirements for the Unit 2 Emergency Diesel Generator
Coolers, Revision 0
N-864, Service Water System Performance Calculation, Revision 0
OE-2017-0561, IN 1706 Battery and Short Circuits on DC Systems
Pennsylvania Department of Environmental Protection Letter Dated April 12, 2017
SA-BN-2017-0626, Tier 1 Calculations Self Assessment
SA-BN-2018-1139, NOP-ER-3001 Problem Solving and Decision Making
SA-BN-2018-1298, Pre-PI&R 2019 NRC Inspection Assessment
SA-BN-2019-1326, Snapshot SA-CSA Owner JFG
Standing Order 13-014
Unit 2 Control Room Logs July 17, 2017
Unit 2 Service Water System Health Report 2014 through 2018