IR 05000220/2019013
| ML19295E729 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/21/2019 |
| From: | Marc Ferdas NRC/RGN-I/DRP/PB7 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| Ferdas M | |
| References | |
| IR 2019013 | |
| Download: ML19295E729 (8) | |
Text
October 21, 2019
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNITS 1 AND 2 - TEMPORARY INSTRUCTION 2515/193 INSPECTION REPORT 05000220/2019013 AND 05000410/2019013
Dear Mr. Hanson:
On September 26, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Nine Mile Point Nuclear Station, Units 1 and 2 and discussed the results of this inspection with Mr. Todd Tierney, Plant Manager, and other members of your staff. The results of this inspection are documented in the enclosed report.
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/
Marc S. Ferdas, Team Leader Technical Support and Assessment Team Division of Reactor Projects
Docket Nos. 05000220 and 05000410 License Nos. DPR-63 and NPF-69
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000220 and 05000410
License Numbers:
Report Numbers:
05000220/2019013 and 05000410/2019013
Enterprise Identifier: I-2019-013-0013
Licensee:
Exelon Generation Company, LLC
Facility:
Nine Mile Point Nuclear Station, Units 1 and 2
Location:
Oswego, NY
Inspection Dates:
September 23, 2019 to September 26, 2019
Inspectors:
S. Haney, Senior Project Engineer
C. Cahill, Senior Reactor Analyst
K. Mangan, Senior Reactor Inspector
Approved By:
Marc S. Ferdas, Team Leader
Technical Support and Assessment Team
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a Temporary Instruction 2515/193 inspection at Nine Mile Point Nuclear Station, 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.
List of Findings and Violations
No findings or violations of more than minor significance 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
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
2515/193 - Inspection of the Implementation of EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions
Inspection of the Implementation of EA-13-109: Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation under Severe Accident Conditions (1 Sample)
- (1) Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the reliable hardened containment wetwell vent as described in the plant specific submittals and the associated safety evaluations (ADAMS Accession Nos. ML18355A737 - Unit 1 and ML18255A121 - Unit 2), and determined that the licensee was in compliance with NRC Order EA-13-109 Phase 1, Reliable, Severe Accident Capable Wetwell Venting System (ADAMS Accession No. ML13143A321).
The inspectors verified that the licensee satisfactorily:
Installed the hardened containment vent system (HCVS) to meet the performance objectives outlined in Section A.1.1 of Attachment 2 to the Order EA-13-109;
Installed the HCVS system with the design features specified in Section A.1.2 of Attachment 2 to the Order EA-13-109;
Designed the HCVS to meet the quality standards described in Section A.2 of 2 to the Order EA-13-109;
Developed and implemented adequate maintenance and testing of HCVS equipment to ensure their availability and capability;
Developed and issued procedures to safely operate the HCVS using normal power supplies during extended loss of alternating current power (ELAP) and a postulated severe accident scenario, and integrated the procedures into existing plant procedures; and
Trained their staff to assure personnel can proficiently operate the HCVS.
Based on samples selected for review, the inspectors verified that the licensee satisfactorily implemented appropriate elements of the reliable wetwell venting strategy as described in the plant specific submittals and the associated safety evaluation (ADAMS Accession Nos. ML18355A737 - Unit 1 and ML18255A121 - Unit 2) and determined that the licensee was in compliance with NRC Order EA-13-109 Phase 2, Reliable, Severe Accident Capable Drywell (or alternative strategy) Venting System (ADAMS Accession No. ML13143A321).
The inspectors verified that the licensee satisfactorily developed a strategy making it unlikely that the licensee would need to vent from the containment drywell that includes the following:
Implemented the severe accident water addition (SAWA)/severe accident water management (SAWM) systems as defined, and fulfilled functional requirements for installed and portable equipment.
Installed and/or identified the previously-installed instrumentation necessary to implement SAWM.
Developed and implemented adequate maintenance and testing of SAWA/SAWM equipment to ensure availability and capability.
Developed and issued procedures to safely operate the SAWA/SAWM during an ELAP and during postulated severe accident scenario, and integrated their procedures into their existing plant procedures such that entry into and exiting from the procedures are clear when using existing plant procedures.
Trained their staff to assure personnel can proficiently operate the HCVS during an ELAP and accident scenario.
The inspectors verified that any noncompliance with requirements and standards identified during the inspection were entered into the licensee's corrective action program.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On September 26, 2019, the inspectors presented the Temporary Instruction 2515/193 inspection results to Mr. Todd Tierney, Plant Manager, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2515/193
Calculations
A.10.1-P-051
Nitrogen Requirement for Operation of the HCVS Valves
S14-54HX019
Spent Fuel Pool Heat Up During Severe Accident Resulting
from an ELAP Event
S22.4-
201.13M002
HCVS Valve Motive Gas Supply Sizing
Corrective Action
Documents
AR 04241162
AR 04275007
Engineering
Changes
ECP-13-000086
ECP-17-000279
Miscellaneous
CC-NM-118-1003
Nine Mile Point Nuclear Station Unit 1, Final Integrated Plan
Document - Mitigating Strategies NRC Order EA-12-049
CC-NM-118-1004
Nine Mile Point Nuclear Station Unit 2, Final Integrated Plan
Document - Mitigating Strategies NRC Order EA-12-049
CC-NM-118-1005
Final Integrated Plan HCVS Order EA-13-109 for Nine Mile
Point Nuclear Power Station - Unit 1 (NMP1)
CC-NM-118-1006
Final Integrated Plan HCVS Order EA-13-109 for Nine Mile
Point Nuclear Power Station - Unit 2 (NMP2)
N-NM-EP-FLEX-
TECH
FLEX Related ERO Technical Training
Report QR-
351024565-1
Qualification Report for Absolyte GP VRLA Battery and A12B
Series Battery Charger
VENRPT-15-
000013
Seismic Qualification Summary for Hardened Containment
Vent Components
Procedures
CC-NM-118
Site Implementation of Diverse and Flexible Coping
Strategies (FLEX) and Spent Fuel Pool Instrumentation
Program
CC-NM-118-101
Beyond Design Basis Administrative Controls
00400
EP-AA-124-F-03
FLEX Communications Equipment Testing and Inventorying
of the Site and Site-Specific EOF Fixed and Portable Satellite
System
C
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
N1-DRP-FLEX-
ELEC
Emergency Damage Repair - BDB/FLEX Generator
Deployment Strategy
00400
N1-DRP-FLEX-
MECH
Emergency Damage Repair - BDB/FLEX Plump Deployment
Strategy
00700
N1-EOP-4.1
Primary Containment Venting
200.01
N1-PM-M5
Monthly Checklist
00501
N2-DRP-FLEX-
ELEC
Emergency Damage Repair - BDB/FLEX Generator
Deployment Strategy
00300
N2-DRP-FLEX-
MECH
Emergency Damage Repair - BDB/FLEX Plump Deployment
Strategy
00500
N2-EOP-6.21
Containment Venting
N2-PM-M008
Monthly Checklist
01300
S-DRP-COMM
BDBEE Communication Procedure
Self-Assessments AR 04249579
Work Orders
C93470077
C93632926
C93659488
C93660043
C93660263
C93671603
C93675035
C93689483