IR 05000333/2019013
| ML19345D572 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  (DPR-059) |
| Issue date: | 12/10/2019 |
| From: | Marc Ferdas Division Reactor Projects I |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| References | |
| IR 2019013 | |
| Download: ML19345D572 (8) | |
Text
December 10, 2019
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - TEMPORARY INSTRUCTION 2515/193 INSPECTION REPORT 05000333/2019013
Dear Mr. Hanson:
On November 7, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at James A. FitzPatrick Nuclear Power Plant and discussed the results of this inspection with Mr. Chris Adner, Operations Director, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
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/
Marc S. Ferdas, Team Leader Technical Support and Administrative Team Division of Reactor Projects
Docket No. 05000333 License No. DPR-59
Enclosure:
As stated
Inspection Report
Docket Number:
05000333
License Number:
Report Number:
Enterprise Identifier: I-2019-013-0019
Licensee:
Exelon Generation Company, LLC
Facility:
James A. FitzPatrick Nuclear Power Plant
Location:
Oswego, NY
Inspection Dates:
November 4, 2019 to November 8, 2019
Inspectors:
F. Arner, Senior Reactor Analyst
T. Daun, Resident Inspector
Approved By:
Marc S. Ferdas, Team Leader
Technical Support and Administrative 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 James A.
FitzPatrick Nuclear Power Plant, 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 Exelon implemented appropriate elements of the reliable hardened containment wetwell vent as described in the plant specific submittal and the associated safety evaluation (ADAMS Accession No. ML18360A635) and NRC Order EA-13-109 Phase 1, Reliable, Severe Accident Capable Wetwell Venting System (ADAMS Accession No. ML13143A321).
The inspectors verified that Exelon:
- 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 Exelon implemented appropriate elements of the reliable wetwell venting strategy as described in the plant specific submittal and the associated safety evaluation (ADAMS Accession No. ML18360A635) and 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 Exelon:
- developed a strategy making it unlikely that Exelon would need to vent from the containment drywell;
- 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; and
- 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 Exelon'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 November 7, 2019, the inspectors presented the Temporary Instruction 2515/193 inspection results to Mr. Chris Adner, Operations Director, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2515/193
Calculations
JAF-CALC-15-
00013
Hardened Containment Vent System: N2 Bottle and Venting
Capacity
JAF-CALC-15-
00031
FLEX Strategy - Portable Generator System Sizing
JAF-CALC-17-
00104
HCVS Phase 2 SAWA Hydraulic Analysis
Corrective Action
Documents
220576
288408
3992547
4084456
4084578
4088244
4091301
4091760
4091828
4109111
20276
26448
4159500
CR-JAF-2017-
01155
Corrective Action
Documents
Resulting from
Inspection
295041
295115
295114
Drawings
Flow Diagram Fire Protection Water Piping System 76
Site Utilities Fire Protection Water Supply Flow Diagram
Flow Diagram Drywell Inerting CAD
Flow Diagram Residual Heat Removal System 10
Flow Diagram Residual Heat Removal System 10
Flow Diagram Instrument Air Reactor Building and Drywell
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
System 39
SK-EC620605-01
Process Flow Diagram Severe Accident Water Addition
(SAWA) Severe Accident
Water Management (SAWM)
Procedures
Station Blackout
CC-JF-118-1004
HVCS Final Integrated Plan
CC-JF-118-101
Beyond Design Basis Administrative Controls
RPV Control
HCVS Manual Valve Panel Valve Testing
FSG-001
Initial Assessment and FLEX Equipment Staging
FSG-003
Alternate Reactor Vessel Cooling
FSG-004
Alternate Containment Cooling
FSG-101
Beyond Design Basis External Events EP Communications
FSG-ELAP
Extended Loss of AC Power (ELAP)
SAOG-1
RPV and Primary Containment Injection
SAOG-2
RPV, Containment, and Radioactivity Release Control
SPEC-15-00001
Hardened Containment Vent System: Instrumentation and
Batteries
East Diesel Fire Pump 76 P-4 Performance Test
2-15-19
Work Orders
336844
374741
4666902
4935135
2336966
2619359