IR 05000387/2018501
| ML18325A076 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/19/2018 |
| From: | Raymond Mckinley Plant Support Branch 1 |
| To: | Berryman B Susquehanna |
| McKinley R | |
| References | |
| IR 2018501 | |
| Download: ML18325A076 (8) | |
Text
November 19, 2018
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION - EVALUATED EMERGENCY PREPAREDNESS EXERCISE INSPECTION REPORT 05000387/2018501 AND 05000388/2018501
Dear Mr. Berryman:
On October 19, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station (SSES), Units 1 and 2. The NRC inspectors discussed the results of this inspection with you and members of your staff on October 30, 2018. 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 one 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 SSES. 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 NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Raymond R. McKinley, Chief Plant Support Branch Division of Reactor Safety
Docket Numbers: 50-387 and 50-388 License Numbers: NPF-14 and NPF-22
Enclosure:
Inspection Report 05000387/2018501 and 05000388/2018501
Inspection Report
Docket Numbers:
50-387 and 50-388
License Numbers:
Report Numbers:
05000387/2018501 and 05000388/2018501
Enterprise Identifier: I-2018-501-0037
Licensee:
Susquehanna Nuclear, LLC (Susquehanna)
Facility:
Susquehanna Steam Electric Station, Units 1 and 2
Location:
Berwick, Pennsylvania
Inspection Dates:
October 15 - 19, 2018
Inspectors:
J. Ambrosini, Senior Emergency Preparedness Inspector, Division of
Reactor Safety (DRS)
J. DeBoer, Emergency Preparedness Inspector, DRS
P. Elkmann, Senior Emergency Preparedness Inspector, Region IV
T. Setzer, Senior Project Engineer, Division of Reactor Projects
Approved By:
Raymond R. McKinley, Chief
Plant Support Branch
Division of Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring Susquehannas performance at Susquehanna Steam Electric Station, Units 1 and 2, by conducting an evaluated emergency preparedness exercise inspection 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. Licensee-identified non-cited violations are documented in the Inspection Results section of the report: IP 71114.01.
INSPECTION SCOPE
The inspectors conducted the inspection using the appropriate portions of the inspection procedure in effect at the beginning of the inspection unless otherwise noted. Currently approved inspection procedures 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. 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. The inspectors determined the following samples were complete when the inspection procedure requirements were met consistent with Inspection Manual Chapter 2515, Light-Water Reactor Inspection Program - Operations Phase.
REACTOR SAFETY
71114.01 - Exercise Evaluation (1 sample)
The inspectors evaluated the adequacy of Susquehannas conduct of the exercise and its capability to assess staff performance via a formal critique process, as required by Title 10 of the Code of Federal Regulations (10 CFR) 50.47(b)(14). The exercise simulated an inadvertent high pressure coolant injection into the reactor vessel, the failure of main steam isolation valves to close, a loss of coolant accident inside containment, and a leak from the drywell into the reactor building.
71114.08 - Exercise Evaluation - Scenario Review (1 sample)
The inspectors reviewed and evaluated the proposed scenario for biennial emergency plan exercise on September 14.
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below for the period from July 2017 through June 2018.
- (1) Drill and Exercise Performance
- (2) Emergency Response Organization Drill Participation
- (3) Alert and Notification System
INSPECTION RESULTS
Licensee Identified Non-Cited Violation 71114.01 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: 10 CFR 50.54(q)(2) requires, in part, that a licensee shall follow and maintain the effectiveness of an emergency plan that meets the requirements in Appendix E to this Part and, for nuclear power reactor licensees, the planning standards of §50.47(b). 10 CFR 50.47(b)(4) requires, in part, that a standard emergency classification and action level (EAL)scheme is in use by the licensee.
Contrary to the above, from December 2016 to the present, Susquehanna did not have sufficient guidance contained in procedures to assess the availability of the main condenser to support the containment barrier such that a site area emergency would be consistently declared in a timely manner upon loss of two fission product barriers.
Significance/Severity Level: The inspectors assessed the significance of the finding using Inspection Manual Chapter 0609, Appendix B. The inspectors determined that this finding was similar to the example in Table 5.4-1, Significance Examples §50.47(b)(4), which states
[a]n EAL has been rendered ineffective such that any Site Area Emergency would not be declared for a particular off-normal event, but because of other EALs, an appropriate declaration could be made in a degraded manner (e.g., delayed). Thus, the inspectors determined that the finding was of very low safety significance (Green).
Corrective Action Reference: CR-2018-14650
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report On October 30, the inspectors presented the inspection results to Mr. Brad Berryman, Chief Nuclear Officer, and other members of the Susquehanna staff.
DOCUMENTS REVIEWED
Section 1EP1: Exercise Evaluation
SSES Emergency Preparedness Plan
SSES Emergency Preparedness Plan Implementing Procedures
SSES October 16, 2018 Evaluated Exercise Scenario Package
SSES Drill Reports 2016-2018
Condition Reports
CR-2018-14563
CR-2018-14564
CR-2018-14567
CR-2018-14569
CR-2018-14571
CR-2018-14574
CR-2018-14580
CR-2018-14593
CR-2018-14646
CR-2018-14650
CR-2018-14677
CR-2018-14678
Section 1EP8: Exercise Evaluation - Scenario Review
SSES Emergency Preparedness Plan
SSES Emergency Preparedness Plan Implementing Procedures
SSES October 16, 2018 Evaluated Exercise Scenario Package
SSES Drill Reports 2016-2018
Section 4OA1: Performance Indicator (PI) Verification
DEP PI data, July 2017 - June 2018