ML11356A520: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
(One intermediate revision by the same user not shown) | |||
Line 1: | Line 1: | ||
{{Adams | |||
| number = ML11356A520 | |||
| 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) | |||
| author name = Gray M | |||
| author affiliation = NRC/RGN-I/DRP/PB2 | |||
| addressee name = Pollock J | |||
| addressee affiliation = Entergy Nuclear Operations, Inc | |||
| docket = 05000286, 05000247 | |||
| license number = | |||
| contact person = SECY RAS | |||
| case reference number = RAS 21642, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 | |||
| document type = Legal-Pre-Filed Exhibits | |||
| page count = 3 | |||
}} | |||
See also: [[see also::IR 05000286/2011004]] | |||
=Text= | |||
{{#Wiki_filter:RIV000085 | |||
Submitted: December 22, 2011 | |||
EXCERPT | |||
UNITED STATES | |||
NUCLEAR REGULATORY COMMISSION | |||
REGION I | |||
475 ALLENDALE ROAD | |||
KING OF PRUSSIA, PENNSYLVANIA 19406-1415 | |||
November 7, 2011 | |||
Mr. Joseph E. Pollock | |||
Site Vice President | |||
Entergy Nuclear Operations, Inc. | |||
Indian Point Energy Center | |||
450 Broadway, GSB | |||
Buchanan, NY 10511-0249 | |||
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). | |||
Sincerely, | |||
~~:!T | |||
Reactor Projects Branch 2 | |||
Division of Reactor Projects | |||
Docket No. 50-286 | |||
License No. DPR-26 | |||
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 | |||
}} |
Latest revision as of 11:20, 12 November 2019
ML11356A520 | |
Person / Time | |
---|---|
Site: | Indian Point |
Issue date: | 11/07/2011 |
From: | Mel Gray Reactor Projects Branch 2 |
To: | Joseph E Pollock 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
RIV000085
Submitted: December 22, 2011
EXCERPT
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
475 ALLENDALE ROAD
KING OF PRUSSIA, PENNSYLVANIA 19406-1415
November 7, 2011
Mr. Joseph E. Pollock
Site Vice President
Entergy Nuclear Operations, Inc.
Indian Point Energy Center
450 Broadway, GSB
Buchanan, NY 10511-0249
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).
Sincerely,
~~:!T
Reactor Projects Branch 2
Division of Reactor Projects
Docket No. 50-286
License No. DPR-26
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
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