ML12335A611
| ML12335A611 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 12/22/2011 |
| From: | - No Known Affiliation |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| RAS 21642, 50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01 | |
| Download: ML12335A611 (2) | |
Text
United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of:
Entergy Nuclear Operations, Inc.
(Indian Point Nuclear Generating Units 2 and 3)
ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 l 05000286 Exhibit #:
Identified:
Admitted:
Withdrawn:
Rejected:
Stricken:
Other:
RIV000097-00-BD01 10/15/2012 10/15/2012 RIV000097 Submitted: December 22, 2011 v"V'Io. REGU~J' l~"
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Unit 1 Status for ENe presentation notes
- 1. Dry cask storage of unit 1 fuel: Our project plan for fuel removal from unit 1 is proceeding on schedule as discussed at the most recent ENC meeting (begin late '07 finish early '08). The critical path for unit 1 relies on completion of the unit 2 crane to support stacking of the unit 1 fuel canisters in unit 2 prior to placement on the pad. The unit 1 team is also actively involved in assisting the unit 2 project effort with procedure writing, creation of "requirement tracking matrix" to aid in procedure development and training, and administrative process closure.
- 2.
SAFSTOR:
- a.
Current status: Retired System Isolation Boundary (RSIB) review is approximately 90% complete with final completion expected by late February
'07.
- b. Upon completion of the RSIB review a new process and potentially minor modifications will be developed to control the retired system boundaries.
- c.
Although significant improvements were made in 2006, substandard conditions associated with peeling paint, poor lighting and water intrusion still exist and will be worked on a priority basis in '07.
- 3. Unit 1 Fuel handling Crane: An electrical upgrade is currently underway to improve the existing bridge crane. A technical specification amendment request to allow use of the crane which is non single failure proof and non safety related is in progress. The proposed amendment will be reviewed by the SRC on January 29th. This is similar to the River Bend submittal approved by the NRC.
Ground Water Status
- 1. Unit 2 Spent Fuel Pool Leak Leak collection box installed over crack in fuel pool wall has collected water Since April 5, 2006. To date, there have not been any fresh isotopes from the Unit 2 pool identified in the samples.
- 2. Monitoring Wells and Sampling A total of 36 monitoring wells have been drilled. Well development and testing is still in progress for the last phase of wells. Sampling of wells has been on-going. Many samples are split with the NRC and NYS for comparative analysis A sample point in the Unit 1 Containment Spray sump for access to ground water level and activity east of this sump has been drilled. This is a potential path for the Sr-90 plume.
A new Unit 1 West Pool Demineralizer has been installed to run the system 2417. To date this demineralizer has removed a substantial amount of contaminants. The Sr90 has been reduced from 210,000 to 2940 pCi/I. A reduction is also seen in the nearby wells.
A tracer test is being performed where we will inject a dye (tracer) in two locations. This will verify the groundwater assumptions. Injection is planned for Jan 29. Unit 2 dye injection will be first. Collectors (tea bags) in our wells and sumps will confirm the groundwater flow on site. This test is expected to take about 3 months.
The samples were collected from a Control location north of the plant. NRC and NYS want to review our program and assumptions.
I PEC00062939
- 4. A new Recovery Well (RW-l) has been drilled in the Unit 2 FSB. The purpose of the well is to remove tritium from the source close to the pool. Based on the results of the pilot test, design parameters are being developed for the permanent system. This system will not impact the Unit 1 Sr-90 Plume. The permanent system installation is planned for completion in May 2007. The sample results from the Recovery Well pilot test indicated tritium levels have decreased significantly during the 3-day pump test. This is an indicator for Unit 2 pool leakage. No fresh radio-nuclides have been identified in any of the samples. This test also moved some Cesium toward the monitoring well. We are not sure if it is from Unit 2 or dragged from Unit 1.
- 5.
Stakeholder Communication IPEC00062940 A Conference call is held every two weeks with our local stakeholders. An early February 2007 meeting at IPEC is being planned to meet newly elected stakeholders and present a current status of the project.