IR 05000220/2013004

IR 05000220-13-004, 05000410-13-004; 07/01/2013 - 09/30/2013; Nine Mile Point Nuclear Station (Nmpns), Units 1 and 2; Routine Integrated Inspection Report

ML13317B750
Person / Time
Site:	Nine Mile Point
Issue date:	11/13/2013
From:	Daniel Schroeder Reactor Projects Branch 1
To:	Costanzo C Constellation Energy Nuclear Group
Schroeder D
References
IR-13-004
Download: ML13317B750 (35)

Text

{{#Wiki_filter:UNITED STATES ber 13, 2013

SUBJECT:

NINE MILE POINT NUCLEAR STATION, LLC - NRC INTEGRATED INSPECTION REPORT 05000220/2013004 AND 05000410/2013004

Dear Mr. Costanzo:

On September 30, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Nine Mile Point Nuclear Station, LLC (NMPNS) Units 1 and 2. The enclosed inspection report documents the inspection results, which were discussed on October 24, 2013, with you 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 findings were identified during this inspection.

In accordance with Title 10 of the Code of Federal Regulations 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 component of the NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely, /RA/ Daniel L. Schroeder, Chief Reactor Projects Branch 1 Division of Reactor Projects Docket Nos: 50-220 and 50-410 License Nos: DPR-63 and NPF-69

Enclosure:

Inspection Report 05000220/2013004 and 05000410/2013004 w/ Attachment: Supplementary Information

REGION I== Docket Nos: 50-220 and 50-410 License Nos: DPR-63 and NPF-69 Report Nos: 05000220/2013004 and 05000410/2013004 Licensee: Constellation Energy Nuclear Group, LLC (CENG) Facility: Nine Mile Point Nuclear Station, LLC (NMPNS) Units 1 and 2 Location: Oswego, NY Dates: July 1, 2013, through September 30, 2013 Inspectors: K. Kolaczyk, Senior Resident Inspector E. Miller, Resident Inspector J. Ambrosini, Senior Resident Inspector J. DeBoer, Project Engineer B. Dionne, Health Physicist S. Hammann, Senior Health Physicist P. Kaufman, Senior Reactor Inspector J. Krafty, Resident Inspector J. Laughlin, Emergency Preparedness Inspector Approved by: Daniel L. Schroeder, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure

SUMMARY

IR 05000220/2013004, 05000410/2013004; 07/01/2013 - 09/30/2013; Nine Mile Point Nuclear

Station (NMPNS), Units 1 and 2; Routine Integrated Inspection Report.

The report covered a 3-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. The inspectors identified no findings during this period. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4.

No findings were identified.

REPORT DETAILS

Summary of Plant Status

Unit 1 began the inspection period at 100 percent power. On July 3, 2013, power was decreased to 90 percent to start recirculation pump 15. Power was returned to 100 percent later that day. On July 8, Unit 1 was shut down due to elevated unidentified leakage in the primary containment. Following identification of the source of the leakage and the completion of repairs to the reactor water cleanup vent valve 33-61, Unit 1 returned to 100 percent power on July 12. On July 13, power was reduced to 75 percent for a rod pattern adjustment and later that day returned to 100 percent power. On September 9, Unit 1 decreased power to 90 percent to perform turbine stop valve testing and remove recirculation pump 13 from service.

Reactor power was returned to 100 percent later that day. Unit 1 remained at full power for the remainder for the inspection period.

Unit 2 began the inspection period at 100 percent power. On July 19, 2013, reactor power was decreased to 98 percent due to high condensate pump discharge header temperature. Power was returned to 100 percent later that day. On September 7, Unit 2 reduced power to 85 percent to conduct turbine stop valve testing, returning to full power that same day. On September 21, Unit 2 reduced power to 70 percent to perform a control rod pattern adjustment and scram time testing. Unit 2 returned to full power on September 22 and operated at full power for the remainder of the inspection period.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

Readiness for Seasonal Extreme Weather Conditions

a. Inspection Scope

The inspectors performed a review of the stations readiness for the onset of seasonal high temperatures. The review focused on Unit 1 batteries 11 and 12 and emergency diesel generators (EDGs) 102 and 103 on July 17, 2013. The inspectors reviewed the Updated Final Safety Analysis Report (UFSAR), technical specifications (TSs), and the corrective action program (CAP) to determine what temperatures or other seasonal weather could challenge these systems, and to ensure CENG personnel had adequately prepared for these challenges. The inspectors reviewed station procedures including CENGs seasonal weather readiness procedure and applicable operating procedures.

The inspectors performed walkdowns of the selected systems to ensure station personnel identified issues that could challenge the operability of the systems during hot weather conditions. 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: Unit 2 Division I standby gas treatment system (SGTS) following functional testing on July 18, 2013 Unit 1 uninterruptible power supply (UPS) system for the reactor protection system bus 11 following the trip of the alternating current (AC) breaker for UPS 162A and B on July 22, 2013 Unit 1 offsite power systems following testing on EDG 102 on July 25, 2013 Unit 2 high-pressure core spray (HPCS) system while the reactor core isolation cooling (RCIC) system was out of service (OOS) for planned maintenance on August 6, 2013 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 UFSAR, TSs, work orders (WOs), condition reports (CRs), 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 CENG staff had properly identified equipment issues and entered them into the CAP for resolution with the appropriate significance characterization.

b. Findings

No findings were identified.

.2 Full System Walkdown

a. Inspection Scope

On September 17, 2013, the inspectors performed a complete system walkdown of accessible portions of the Unit 1 primary containment isolation valves to verify the existing equipment lineup was correct. The inspectors reviewed operating procedures, drawings, completed surveillances, and the UFSAR to verify the system was aligned to perform its required safety functions. The inspectors performed field walkdowns of accessible portions of the system to verify system components and support equipment were aligned correctly and operable. The inspectors examined the material condition of components and observed operating parameters of equipment to verify that there were no deficiencies. Additionally, the inspectors reviewed a sample of related CRs and WOs to ensure CENG personnel appropriately evaluated and resolved any deficiencies.

b. Findings

No findings were identified. ==1R05 Fire Protection