IR 05000247/2013005: Difference between revisions

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==1R04 Equipment Alignment==
==1R04 Equipment Alignment


===.1 Partial System Walkdowns===
===.1 Partial System Walkdowns===
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==1R05 Fire Protection==
==1R05 Fire Protection


===.1 Resident Inspector Quarterly Walkdowns===
===.1 Resident Inspector Quarterly Walkdowns===
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==1R11 Licensed Operator Requalification Program==
==1R11 Licensed Operator Requalification Program
 
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Licensed Operator Requalification (71111.11A* and 71111.11B - 2 samples)
Licensed Operator Requalification (71111.11A* and 71111.11B - 2 samples)



Revision as of 06:58, 17 November 2019

IR 05000247-13-005, 05000286-13-005; 10/01/2013 - 12/31/2013; Indian Point Power Station, Units 2 and 3; Routine Integrated Inspection Report
ML14045A254
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 02/14/2014
From: Arthur Burritt
Reactor Projects Branch 2
To: Ventosa J
Entergy Nuclear Operations
References
IR-13-005
Download: ML14045A254 (37)


Text

{{#Wiki_filter:UNITED STATES ary 14, 2014

SUBJECT:

INDIAN POINT POWER STATION - NRC INTEGRATED INSPECTION REPORT 05000247/2013005 AND 05000286/2013005

Dear Mr. Ventosa:

On December 31, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Indian Point Power Station, Units 2 and 3. The enclosed inspection report documents the inspection results, which were discussed on January 8, 2014, 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 NRC-identified or self-revealing findings were identified during this inspection. However, inspectors documented two licensee-identified violations which were determined to be of very low safety significance in this report. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2 of the Enforcement Policy.

If you contest the violations or significance of the NCVs, 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 Indian Point Power Station.

As a result of the Safety Culture Common Language Initiative, the terminology and coding of cross-cutting aspects were revised beginning in calendar year (CY) 2014. New cross-cutting aspects identified in CY 2014 will be coded under the latest revision to Inspection Manual Change (IMC) 0310. Cross-cutting aspects identified in the last six months of 2013 using the previous terminology will be converted to the latest revision in accordance with the cross-reference in IMC 0310. The revised cross-cutting aspects will be evaluated for cross-cutting themes and potential substantive cross-cutting issues in accordance with IMC 0305 starting with the CY 2014 mid-cycle assessment review. In accordance with Title 10 of Code of Federal Regulations (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 of from the Publicly Available Records component of the NRCs document system Agencywide Documents Access Management 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/ Arthur L. Burritt, Chief Reactor Projects Branch 2 Division of Reactor Projects Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64

Enclosure:

Inspection Report 05000247/2013005 and 05000286/2013005 w/Attachment: Supplementary Information

REGION I== Docket Nos: 50-247 and 50-286 License Nos: DPR-26 and DPR-64 Report Nos: 05000247/2013005 and 05000286/2013005 Licensee: Entergy Nuclear Northeast (Entergy) Facility: Indian Point Power Station, Units 2 and 3 Location: 450 Broadway, GSB Buchanan, NY 10511-0249 Dates: October 1, 2013, through December 31, 2013 Inspectors: J. Stewart, Senior Resident Inspector A. Patel, Resident Inspector T. Lamb, Acting Resident Inspector T. Fish, Senior Operations Engineer J. Furia, Senior Health Physicist J. Kulp, Senior Resident Inspector, Oyster Creek D. Orr, Reactor Inspector E. Torres, Resident Inspector, Calvert Cliffs Accompanied by: L. McKown, Project Engineer J. Petch, Project Engineer Approved By: Arthur L. Burritt, Chief Reactor Projects Branch 2 Division of Reactor Projects Enclosure

SUMMARY

IR 05000247/2013005, 05000286/2013005; 10/01/2013 - 12/31/2013; Indian Point Power

Station, Units 2 and 3; Routine Integrated Inspection Report.

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

Other Findings

Two violations of very low safety significance identified by Entergy were reviewed by the inspectors. Corrective actions taken or planned by Entergy have been entered into Entergys corrective action program (CAP). These violations and corrective action tracking numbers are listed in Section 4OA7 of this report.

REPORT DETAILS

Summary of Plant Status

Indian Point Unit 2 began the inspection at 100 percent power and remained at or near full power for the duration of the inspection period.

Indian Point Unit 3 began the inspection at 100 percent power and remained at or near full power for the duration of the inspection period.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

.1 Readiness for Seasonal Extreme Weather Conditions

a. Inspection Scope

The inspectors performed a review of Entergys readiness for the onset of seasonal low temperatures. The review focused on the auxiliary boiler feed pump building ventilation system and the emergency diesel generators (EDGs). The inspectors reviewed the Updated Final Safety Analysis Report (UFSAR), Technical Specifications, control room logs, and the CAP to determine what temperatures or other seasonal weather could challenge these systems, and to ensure Entergy personnel had adequately prepared for these challenges. The inspectors reviewed station procedures, including Entergys seasonal weather preparation 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 cold weather conditions. Documents reviewed for each section of the inspection report are listed in the Attachment.

b. Findings

No findings were identified.

.2 External Flooding

a. Inspection Scope

On October 2 and 3, the inspectors performed an inspection of the external flood protection measures for Indian Point Unit 3. The inspectors reviewed Technical Specifications, procedures, and the UFSAR, Chapter 2.5, which describes the design flood levels and protection areas containing safety-related equipment, to identify areas that may be affected by external flooding. The inspectors conducted a walkdown of specific vulnerable areas of the plant, including the 15 foot levels of the turbine building, auxiliary feedwater building, and intake building, to ensure that Entergy staff maintained flood protection measures in accordance with design specifications. The inspectors also reviewed operating procedures for mitigating external flooding during severe weather to determine if Entergy established adequate measures to protect against external flooding events.

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 and Unit 3

  • EDGs and 480V switchgear rooms following grid disturbance and loss of Y94 transmission line and offsite feeder 95891 on October 24, 2013 Unit 2
  • 22 and 23 safety injection (SI) pumps using Entergys procedure 2-COL-10.1.1, Safety Injection System, while 21 SI pump was tagged out for maintenance on November 19, 2013
  • SI system using Entergys procedure 2-COL-10.1.1, Safety Injection System, and flow diagram 9321-F-27353, prior to 22 SI pump testing on December 18, 2013.

Unit 3

  • 32 and 33 EDGs using Entergys procedure 3-COL-EL-005, Diesel Generators, when 31 EDG was removed from service for planned maintenance on October 7, 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, Technical Specifications, work orders, condition reports, and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted the systems 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 Entergy 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 November 6 through 14, 2013, the inspectors performed a complete system walkdown of accessible portions of the Unit 2 Service Water 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, hanger and support functionality, and operability of support systems. The inspectors performed field walkdowns of accessible portions of the systems 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 condition reports and work orders to ensure Entergy appropriately evaluated and resolved any deficiencies.

b. Findings

No findings were identified. ==1R05 Fire Protection

.1 Resident Inspector Quarterly Walkdowns