ML11356A520

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
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

UNITED STATES NUCLEAR REGULATORY

COMMISSION

REGION I 475 ALLENDALE

ROAD KING OF PRUSSIA, PENNSYLVANIA

19406-1415

Mr. Joseph E. Pollock 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