IR 05000289/2015001: Difference between revisions
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No findings were identified. | No findings were identified. | ||
{{a|1R04}} | {{a|1R04}} | ||
==1R04 Equipment Alignment | ==1R04 Equipment Alignment | ||
===.1 Partial System Walkdowns=== | ===.1 Partial System Walkdowns=== | ||
{{IP sample|IP=IP 71111.04Q|count=4}} | {{IP sample|IP=IP 71111.04Q|count=4}}== | ||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
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No findings were identified. | No findings were identified. | ||
{{a|1R05}} | {{a|1R05}} | ||
==1R05 Fire Protection | ==1R05 Fire Protection | ||
===.1 Resident Inspector Quarterly Walkdowns=== | ===.1 Resident Inspector Quarterly Walkdowns=== | ||
{{IP sample|IP=IP 71111.05Q|count=5}} | {{IP sample|IP=IP 71111.05Q|count== | ||
=5}} | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
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No findings were identified. | No findings were identified. | ||
{{a|1R07}} | {{a|1R07}} | ||
==1R07 Heat Sink Performance (711111.07A - 1 sample) | ==1R07 Heat Sink Performance (711111.07A - 1 sample) | ||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
== | |||
The inspectors reviewed the A intermediate closed cooling heat exchanger to determine its readiness and availability to perform its safety functions. The inspectors reviewed the design basis for the component and verified Exelons commitments to NRC Generic Letter 89-13 were being maintained. The inspectors observed actual performance tests for the heat exchangers and/or reviewed the results of previous inspections of the heat exchanger reviewed. The inspectors discussed the results of the most recent inspection with engineering staff and reviewed pictures of the as-found and as-left conditions. The inspectors verified that Exelon initiated appropriate corrective actions for identified deficiencies. The inspectors also verified that the number of tubes plugged within the heat exchanger did not exceed the maximum amount allowed. | The inspectors reviewed the A intermediate closed cooling heat exchanger to determine its readiness and availability to perform its safety functions. The inspectors reviewed the design basis for the component and verified Exelons commitments to NRC Generic Letter 89-13 were being maintained. The inspectors observed actual performance tests for the heat exchangers and/or reviewed the results of previous inspections of the heat exchanger reviewed. The inspectors discussed the results of the most recent inspection with engineering staff and reviewed pictures of the as-found and as-left conditions. The inspectors verified that Exelon initiated appropriate corrective actions for identified deficiencies. The inspectors also verified that the number of tubes plugged within the heat exchanger did not exceed the maximum amount allowed. | ||
Revision as of 00:25, 17 November 2019
| ML15120A460 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 04/30/2015 |
| From: | Silas Kennedy NRC/RGN-I/DRP/PB6 |
| To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
| KENNEDY, SR | |
| References | |
| IR 2015001 | |
| Download: ML15120A460 (27) | |
Text
{{#Wiki_filter: UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406-2713 April 30, 2015 Mr. Bryan Hanson Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUBJECT: THREE MILE ISLAND STATION, UNIT 1 - NRC INTEGRATED INSPECTION REPORT 5000289/2015001
Dear Mr. Hanson:
On March 31, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Three Mile Island, Unit 1 (TMI) facility. The enclosed inspection report documents the inspection results, which were discussed on April 17, 2015 with Mr. Rick Libra, TMI Site Vice President, and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
No NRC-identified or self-revealing findings were identified during this inspection. However, a licensee-identified violation which was determined to be of very low safety significance is listed in this report. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2 of the Enforcement Policy. If you contest the non-cited violation in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at Three Mile Island.
In accordance with Title 10 of the Code of Federal Regulations (CFR) 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs document system (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely, /RA/ Silas R. Kennedy, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-289 License Nos.: DPR-50
Enclosure:
Inspection Report 05000289/2015001 w/Attachment: Supplementary Information
REGION I== Docket No: 50-289 License No: DPR-50 Report No: 05000289/2015001 Licensee: Exelon Generation Company Facility: Three Mile Island Station, Unit 1 Location: Middletown, PA 17057 Dates: January 1 through March 31, 2015 Inspectors: D. Werkheiser, Senior Resident Inspector, Division of Reactor Projects (DRP) J. Heinly, Resident Inspector, DRP E. Burket, Emergency Preparedness Inspector, Division of Reactor Safety (DRS) J. DAntonio, Senior Operations Engineer, DRS J. Petch, Resident Inspector (Acting), DRP D. Silk, Senior Operations Engineer, DRS Approved by: S. Kennedy, Chief Projects Branch 6 Division of Reactor Projects (DRP) Enclosure
SUMMARY
IR 05000289/2015001, 01/01/2015-03/31/2015; Three Mile Island, Unit 1, Integrated Inspection
Report.
This report covered a three-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. A licensee-identified violation of very-low safety significance was documented. The significance of most findings is indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, Significance Determination Process, dated June 2, 2011. Cross-cutting aspects are determined using IMC 0310, Aspects Within Cross-Cutting Areas, dated December 4, 2014. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy, dated February 4, 2015. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision
NRC-Identified and Self-Revealing Findings
No findings were identified.
Other Findings
A violation of very low safety significance that was identified by Exelon was reviewed by the inspectors. Corrective actions taken or planned by Exelon have been entered into Exelons corrective action program. This violation and corrective action tracking number are listed in Section 4OA7 of this report.
REPORT DETAILS
Summary of Plant Status
Unit 1 began the inspection period at 100 percent power and remained at or near 100 percent power for the remainder of the inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection
.1 Readiness for Impending Adverse Weather Conditions
a. Inspection Scope
The inspectors reviewed Exelons preparations for the onset of extreme cold weather during the periods of February 14 - 16 and February 19 - 20, 2015. The inspectors reviewed the implementation of adverse weather preparation procedures before the onset of and during this adverse weather condition. The inspectors walked down the emergency diesel generators and safety-related water systems to ensure system availability. The inspectors verified that operator actions defined in Exelons adverse weather procedure for TMI maintained the readiness of essential systems. The inspectors discussed readiness and staff availability for adverse weather response with operations and work control personnel. Documents reviewed for each section of this inspection report are listed in the Attachment.
b. Findings
No findings were identified. ==1R04 Equipment Alignment
.1 Partial System Walkdowns
==
a. Inspection Scope
The inspectors performed partial walkdowns of the following systems: A makeup pump and A makeup train (high pressure injection) during performance of planned B low pressure injection maintenance on January 6, 2015 B intermediate closed cooling system during performance of the A intermediate closed cooling system planned outage on February 3, 2015 B makeup pump and seal injection alignment during planned C makeup pump maintenance on February 24, 2015 Emergency feedpump 1 and 2B alignment during planned 2A emergency feedpump maintenance on March 4, 2015 The inspectors selected these systems based on their risk-significance relative to the reactor safety cornerstones at the time they were inspected. The inspectors reviewed applicable operating procedures, system diagrams, the Updated Final Safety Analysis Report (UFSAR), technical specifications, work orders, issue reports, and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted system performance of their intended safety functions. The inspectors also performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and were operable.
The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies. The inspectors also reviewed whether Exelon staff had properly identified equipment issues and entered them into the corrective action program for resolution with the appropriate significance characterization.
b. Findings
No findings were identified. ==1R05 Fire Protection