ML11356A520: Difference between revisions

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| number = ML11356A520
| number = ML11356A520
| issue date = 11/07/2011
| issue date = 11/07/2011
| title = Riverkeeper (RIV) Pre-Filed Evidentiary Hearing Exhibit RIV000085, Indian Point Nuclear Generating Unit 3 - NRC Integrated Inspection Report 05000286-2011004 (November 7, 2011)
| title = Riverkeeper (RIV) Pre-Filed Evidentiary Hearing Exhibit Riv000085, Indian Point Nuclear Generating Unit 3 - NRC Integrated Inspection Report 05000286-2011004 (November 7, 2011)
| author name = Gray M
| author name = Gray M
| author affiliation = NRC/RGN-I/DRP/PB2
| author affiliation = NRC/RGN-I/DRP/PB2

Revision as of 00:37, 19 February 2018

Riverkeeper (RIV) Pre-Filed Evidentiary Hearing Exhibit Riv000085, Indian Point Nuclear Generating Unit 3 - NRC Integrated Inspection Report 05000286-2011004 (November 7, 2011)
ML11356A520
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 11/07/2011
From: Mel Gray
Reactor Projects Branch 2
To: Pollock J E
Entergy Nuclear Operations
SECY RAS
References
RAS 21642, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01
Download: ML11356A520 (3)


See also: IR 05000286/2011004

Text

Mr. Joseph Site Vice President Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB Buchanan, NY 10511-0249 November 7, 2011

SUBJECT: INDIAN POINT NUCLEAR GENERATING UNIT 3-NRC INTEGRATED INSPECTION REPORT 05000286/2011004

Dear Mr. Pollock:

On September 30, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Indian Point Nuclear Generating Unit 3. The enclosed integrated inspection report documents the inspection results, which were discussed on October 24, 2011, 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 Commission's rules and regulations and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings were identified. In accordance with 10 CFR 2.390 of the NRC's "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 NRC's document system (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). Docket No. 50-286 License No. DPR-26

Sincerely,Reactor Projects Branch 2 Division of Reactor Projects

Enclosure:

Inspection Report 05000286/2011004

w/Attachment:

Supplementary Information cc w/encl: Distribution via ListServ


. 15 Dose Calculations The inspectors reviewed three radioactive liquid waste discharge permits and three radioactive gaseous waste discharge permits from Unit 2; and five radioactive liquid waste discharge permits and four radioactive gaseous waste discharge permits from Unit 3. The inspectors verified that the projected dose to members of the public were accurate and based on representative samples of the discharge path. The inspectors evaluated the methods used to determine the isotopes in the source term to ensure applicable radionuclides were included, within delectability standards. The inspectors reviewed the current 10 CFR Part 61 analyses to ensure hard-to-detect radionuclides were included in the source term. The inspectors reviewed changes in Entergy's offsite dose calculations since the last inspection. The inspectors verified that the changes were consistent with the ODCM and Regulatory Guide 1.1 09. The inspectors reviewed meteorological dispersion and deposition factors used in the ODCM and effluent dose calculations to ensure appropriate factors were being used for public dose calculations. The inspectors reviewed the latest Land Use Census and verified that changes have been factored into the dose calculations. GPI Implementation The inspectors reviewed the identified leakage or spill events, and entries recorded in the station's decommissioning file as required by 10 CFR 50.75 (g). The inspectors verified that the recent soil excavation from the demolished Nuclear Environmental Monitoring Laboratory preliminarily indicated some trace cesium contamination, was being characterized and was documented in the decommissioning file. The inspectors verified that onsite groundwater sample results and a description of any significant onsite leaks/spills into groundwater for each calendar year were documented in the Annual Radiological Environmental Operating Report (AREOR) for radiological environmental monitoring program (REMP) or the Annual Radiological Effluent Release Report (ARERR) for the RETS. Problem Identification and Resolution The inspectors verified that problems associated with the effluent monitoring and control program were being identified by Entergy staff at an appropriate threshold and were properly addressed for resolution in the corrective action program. b. Findings and Observations No findings were identified. Groundwater Contamination On June 27, 2011 while reviewing the second quarter 2011 groundwater monitoring well sample results, Entergy personnel identified an increase in tritium concentrations in Unit 1 monitoring wells MW-56 and MW-57 (76,000 pCi/L and 20,000 pCi/L, respectively). Subsequently, Entergy personnel conducted an investigation of this unexpected Enclosure 16 condition. Previously, in 2008, the Unit 1 spent fuel was removed and the Unit 1 spent fuel pools were subsequently drained, which terminated the previously known source of groundwater contamination from the Unit 1 facility. Currently, the source of the contamination has not been identified; however, several possible causes are being evaluated by Entergy staff. This condition has been captured in CR-IP2-2011-3173. The inspectors determined there is no dose impact to the public based on the current scope of this groundwater contamination condition and will continue to follow-up the issue via normal baseline inspection modules. 4. OTHER ACTIVITIES 40A 1 Performance Indicator (PI) Verification (71151) .1 Mitigating Systems Performance Index (5 samples) a. Inspection Scope The inspectors reviewed Entergy's submittal of the Mitigating Systems Performance Index for the following systems for the period of July 1, 2010 through June 30, 2011: * Unit 3 Emergency AC Power System * Unit 3 High Pressure Injection System * Unit 3 Heat Removal System * Unit 3 Residual Heat Removal System * Unit 3 Cooling Water System To determine the accuracy of the performance indicator data reported during those periods, the inspectors used definitions and guidance contained in NEI Document 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6. The inspectors also reviewed Entergy's operator narrative logs, CRs, event reports, and NRC integrated inspection reports to validate the accuracy of the submittals. b. Findings No findings were identified . . 2 Emergency Preparedness (3 samples) a. Inspection Scope The inspectors reviewed data for the IPEC Emergency Preparedness Performance Indicators (EP Pis), which are: (1) Drill and Exercise Performance; (2) ERO Drill Participation; and (3) Alert and Notification System Reliability. The last NRC EP inspection at IPEC was conducted in the third quarter of 2010, so the inspectors reviewed supporting documentation from EP drills, training records, and equipment tests from July 2010 through June 2011, to verify the accuracy of the reported PI data. The review of these Pis was conducted in accordance with IP 71151, using the acceptance criteria documented in NEI 99-02, "Regulatory Assessment Performance Indicator Guidelines," Revision 6. Enclosure