IR 05000244/2013002

IR 05000244-13-002; 01/01/2013 - 03/31/2013; R.E. Ginna Nuclear Power Plant, LLC (Ginna); Operability Determinations and Functionality Assessments

ML13116A204
Person / Time
Site:	Ginna
Issue date:	04/26/2013
From:	Daniel Schroeder Reactor Projects Branch 1
To:	Joseph Pacher Constellation Energy Nuclear Group
Schroeder D
References
IR-13-002
Download: ML13116A204 (38)

Text

{{#Wiki_filter:UNITED STATES ril 26, 2013

SUBJECT:

R.E. GINNA NUCLEAR POWER PLANT, LLC - NRC INTEGRATED INSPECTION REPORT 05000244/2013002

Dear Mr. Pacher:

On March 31, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your R.E. Ginna Nuclear Power Plant, LLC (Ginna). The enclosed inspection report documents the inspection results, which were discussed on April 12, 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.

This report documents one NRC-identified finding of very low safety significance (Green). This finding was determined to involve a violation of NRC requirements. However, because of the very low safety significance, and because it was entered into your corrective action program, the NRC is treating this finding as a non-cited violation (NCV), consistent with Section 2.3.2 of the NRC Enforcement Policy. If you contest the NCV in this report, you should provide a response within 30 days of the date of this inspection report, with the basis of 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 Ginna. In accordance with 10 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 component of the NRCs Agencywide Documents Access 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 No. 50-244 License No. DPR-18

Enclosure:

Inspection Report No. 05000244/2013002 w/Attachment: Supplementary Information

REGION I== Docket No.: 50-244 License No.: DPR-18 Report No.: 05000244/2013002 Licensee: Constellation Energy Nuclear Group, LLC Facility: R.E. Ginna Nuclear Power Plant, LLC Location: Ontario, New York Dates: January 1 through March 31, 2013 Inspectors: N. Perry, Senior Resident Inspector D. Dodson, Resident Inspector T. Fish, Senior Operations Engineer B. Fuller, Operations Engineer T. Moslak, Health Physicist Approved by: Daniel L. Schroeder, Chief Reactor Projects Branch 1 Division of Reactor Projects Enclosure

SUMMARY

IR 05000244/2013002; 01/01/2013 - 03/31/2013; R.E. Ginna Nuclear Power Plant, LLC (Ginna); Operability Determinations and Functionality Assessments.

This report covered a 3-month period of inspection by resident inspectors and announced inspections performed by regional inspectors. Inspectors identified one finding of very low safety significance (Green), which was a non-cited violation (NCV). A findings significance is indicated by a color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, Significance Determination Process (SDP), dated June 2, 2011. Cross-cutting aspects are determined using IMC 0310, Components Within Cross-Cutting Areas, dated October 28, 2011. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy, dated January 28, 2013. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 4.

Cornerstone: Initiating Events

Green.

The inspectors identified a NCV of Ginna Operating License Condition 2.C.(3), Fire Protection, for failure to implement and maintain in effect all fire protection features described in licensee submittals referenced in and as approved or modified by the NRCs Safety Evaluation Report, dated February 1979 and subsequent supplements. Specifically, Constellation did not identify, account for, or evaluate 250 pounds of non-fire retardant treated plywood that has likely been installed in the screen house building (fire zone SH-2)since original construction and 434 pounds of other combustible material in the screen house. Immediate corrective actions included entering this issue into the corrective action program (CR-2013-001507 and CR-2013-001714). Additional planned corrective actions include revising the combustible loading analysis and replacing the installed plywood with a non-combustible material.

The inspectors determined that the failure to treat all wood with fire retardant and maintain its combustible loading analysis accurate and up-to-date was more than minor, because it was associated with the protection against external factors attribute of the Initiating Events cornerstone and affected the cornerstone objective to limit the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, Constellation did not identify non-fire retardant treated wood and accurately account for the amount of combustibles present in the screen house and was required to recalculate the areas combustible loading to assure the assumptions made in Ginnas exemption request from the technical requirements of Section III.G.3 of 10 CFR 50, Appendix R, were still met. Additionally, this issue is similar to example 3I described in IMC 0612, Appendix E, Examples of Minor Issues. The inspectors evaluated the finding using IMC Attachment 0609.04, Initial Characterization of Findings, and IMC 0609 Appendix F, Fire Protection Significance Determination Process, because the finding involved a failure to adequately implement fire prevention and administrative controls. A low degradation rating was assigned to this finding because the combustible loading of the screen house remained within its current LOW range, and the fire protection program element was expected to display nearly the same level of effectiveness as it would have without the degradation. Therefore, the inspectors determined the finding is of very low safety significance (Green). In accordance with IMC 0612, the finding does not have a cross-cutting aspect, because the performance deficiency likely occurred during original plant construction and is not reflective of present plant performance. (Section 1R15)

REPORT DETAILS

Summary of Plant Status

R.E. Ginna Nuclear Power Plant, LLC (Ginna) began the inspection period operating at full rated thermal power and operated at full power for the entire period.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

Readiness for Impending Adverse Weather Conditions

a. Inspection Scope

The inspectors reviewed Constellations preparations for the onset of cold weather on January 23 and 25, 2013. The inspectors reviewed the implementation of adverse weather preparation procedures before the onset of and during this adverse weather condition. The inspectors walked down areas in the auxiliary building, screen house, turbine building, standby auxiliary feedwater (AFW) building, and the cable tunnel. The inspectors verified that operator actions defined in Ginnas adverse weather procedure 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 emergency diesel generator (EDG) during B EDG planned maintenance on February 1, 2013 Service water (SW) system during B SW motor and pump maintenance on February 20, 2013 Turbine-driven AFW system during B motor-driven AFW system planned maintenance on February 26, 2013 B component cooling water (CCW) system during A CCW heat exchanger (HX)maintenance on March 13, 2013 B EDG during offsite circuit 767 planned maintenance on March 29, 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 Updated Final Safety Analysis Report (UFSAR), technical specifications (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 Constellation had properly identified equipment issues and entered them into the corrective action program (CAP)for resolution with the appropriate significance characterization.

b. Findings

No findings were identified.

.2 Full System Walkdown

a. Inspection Scope

On February 26, 2013, the inspectors performed a complete system walkdown of accessible portions of the A AFW system to verify the existing equipment lineup was correct. The inspectors reviewed operating procedures, surveillance tests, drawings, equipment line-up check-off lists, and the UFSAR to verify the system was aligned to perform its required safety functions. The inspectors also reviewed electrical power availability, component lubrication and equipment cooling, hangar and support functionality, and operability of support systems. 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 the components and observed operating parameters of equipment to verify that there were no deficiencies. Additionally, the inspectors reviewed a sample of related CRs to ensure Constellation staff appropriately evaluated and resolved any deficiencies.

b. Findings

No findings were identified. ==1R05 Fire Protection