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Category:E-Mail
MONTHYEARML23341A2002023-12-0707 December 2023 Email - Indian Point Energy Center Generating Units 1, 2, and 3 Implementation Notice of Amendment No. 67, 300 and 276 to Independent Spent Fuel Storage Installation Only Emergency Plan (Ioep) ML23332A0802023-11-0808 November 2023 Email from State of New York on the Revised License Amendment for Indian Point Energy Center ISFSI Only Emergency Plan ML23325A1632023-11-0808 November 2023 State of New York Comments on the Revised License Amendment for Indian Point Unit 2 and 3 Technical Specification Changes Reflecting Permanent Removal of Spent Fuel ML23331A9542023-11-0808 November 2023 Email - State of New York Comments on the Revised License Amendment for Indian Point Unit 2 and 3 Technical Specification Changes Reflecting Permanent Removal of Spent Fuel ML23144A3452023-05-25025 May 2023 Adam Kahn of Monsey, New York Email Against Treated Water Release from Indian Point Site ML23144A3442023-05-25025 May 2023 Peggy Kurtz of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3392023-05-25025 May 2023 David Morris of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3502023-05-25025 May 2023 Dan Kwilecki of Montebello, New York Email Against Treated Water Release from Indian Point Site ML23144A3422023-05-25025 May 2023 Peter Duda of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3382023-05-25025 May 2023 Dawn Giambalvo of Jersey City, New Jersey Email Against Treated Water Release from Indian Point Site ML23136B1622023-05-15015 May 2023 Town of North Salem, County of Westchester, New York Board Resolution Letter Regarding Treated Water Release from Indian Point Site ML23109A0632023-04-17017 April 2023 Email Acceptance Review for IP2 and IP3 Amended Facility License and Technical Specification to Reflect Permanent Removal of Spent Fuel from Spent Fuel Pits ML23055A1112023-02-23023 February 2023 Alyse Peterson Email- NYSERDA No Comments on Indian Point Unit 2 - Regarding Holtec License Amendment Request to Revise Permanently Defueled Technical Specifications and Staffing Requirements with Spent Fuel Transfer to ISFSI (Dockets 50-24 ML23049A0032023-02-14014 February 2023 NRC Acceptance Email to Holtec for License Amendment Request for Approval of New ISFSI-Only Emergency Plan and Associated EAL Scheme ML22313A1682022-11-0909 November 2022 NRC Response to Updates to the Proposed Amended IP2 Master Trust ML22308A0912022-11-0303 November 2022 Email Acknowledgement for IP2 and IP3 Amended Facility License and Technical Specification to Reflect Permanent Removal of Spent Fuel from Spent Fuel Pits ML22276A1642022-09-29029 September 2022 New York State Revised Draft EA Response E-Mail ML22271A8492022-09-28028 September 2022 E-Mail Transmitting Revised Indian Point Exemption Draft EA ML22269A3452022-09-22022 September 2022 Email Objection to Holtec IP2 Master Decommissioning Trust Agreement for Indian Point Nuclear Generating Facility Unit 1 and 2, EPID L-2022-LLA-0072 ML22259A1992022-09-0202 September 2022 Acceptance for License Amendment Request to Modify Staffing Requirements Following SFP Transfer to Dry Storage ML22265A0142022-08-31031 August 2022 Email Acknowledgement for Amended and Restated Holtec IP3 Master Decommissioning Trust Agreement for Indian Point Nuclear Generating Facility Unit 3 ML22242A2592022-08-19019 August 2022 E-mail from K. Sturzebecher, NRC, to B. Noval, HDI, Acknowledgement for Amended and Restated Holtec IP2 Master Decommissioning Trust Agreement for Indian Point Nuclear Generating Facility Unit 1 and 2 ML22228A1332022-08-0909 August 2022 Acknowledgement for License Amendment Request to Modify Staffing Requirements Following SFP Transfer to Dry Storage ML22215A0432022-08-0101 August 2022 E-Mail Transmitting NYS NSA Exemption Comments & Draft EA Review Completion ML22208A0292022-07-19019 July 2022 E-Mail Transmitting Indian Point Exemption Draft EA ML22168A0072022-06-16016 June 2022 Acceptance Review for License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML22112A0102022-04-21021 April 2022 Acceptance Review: Request for Exemption from 10 CFR 50.54(w)(1) Concerning Indian Point Energy Center Onsite Property Damage Insurance ML22112A0122022-04-21021 April 2022 Acceptance Review: Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance for Indian Point Energy Center ML22103A2432022-04-13013 April 2022 E-mail - Request for Additional Information - License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme for Permanently Defueled Condition for Indian Point Energy Center ML22104A0342022-04-13013 April 2022 E-mail from Z. Cruz, NRC to J. Fleming, Holtec - Request for Additional Information Related to Request for Exemption from Portions of 10 CFR 50.47 and Part 50 Appendix E for Indian Point Energy Center ML22038A2572022-02-0707 February 2022 E-mail from Z. Cruz, NRC, to J. Fleming, HDI - Acceptance Review: License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme to Address Permanently Defueled Condition for Indian Point Energy Center ML22035A1862022-02-0404 February 2022 E-mail to J. Fleming, Holtec, from Z. Cruz Perez, NRC - Acceptance Review: Exemption Requests from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E, Section IV for Indian Point Energy Center ML22028A1032022-01-28028 January 2022 E-mail Dated 1/28/2022, Transmittal of Draft Safety Evaluation for Proposed License Amendment Revision to Licensing Basis to Incorporate the Installation and Use of of New Auxiliary Lifting Device ML22038A1592022-01-24024 January 2022 NRR E-mail Capture - (External_Sender) 2021 IPEC Annual Sturgeon Impingement Report ML22006A0442022-01-0505 January 2022 Email from Z Cruz to J Fleming Request for Additional Information - HDI Indian Point Post-Shutdown Decommissioning Activities Report ML21337A2952021-12-0303 December 2021 Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (E-mail Dated 12/3/2021) ML21335A3692021-12-0101 December 2021 Acceptance Review: Indian Point Energy Center - Exemption Request from 10 CFR Part 20 App G Section Iii.E ML21266A2972021-08-18018 August 2021 8/18/2021 E-mail from H. Specter to R. Guzman Public Comments to NRC, Indian Point Post-Shutdown Decommissioning Activities Report Public Meeting on July 29, 2021 ML21225A6142021-08-0909 August 2021 Email from NRC to the Tuscarora Nation Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A5682021-08-0909 August 2021 Email from NRC to the Stockbridge-Munsee Community Band of Mohican Indians Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A5012021-08-0909 August 2021 Email from NRC to the Shinnecock Indian Nation Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21224A3032021-08-0909 August 2021 Email from NRC to the Mashantucket Pequot Tribe of Connecticut Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A4252021-08-0909 August 2021 Email from NRC to the Oneida Nation of Wisconsin Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A3142021-08-0606 August 2021 Email from NRC to the Oneida Indian Nation Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A4402021-08-0606 August 2021 Email from NRC to the Onondaga Nation of Wisconsin Announcing the IPEC PSDAR Meeting on August 18, 2021 ML21225A5462021-08-0606 August 2021 Email from NRC to the St. Regis Mohawk Tribe Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A5352021-08-0606 August 2021 Email from NRC to the Tonawanda Band of Seneca Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21266A2942021-07-25025 July 2021 E-mail from Paul Blanch to NRC (N. Sheehan, D. Screnci) Public Comments to NRC, Indian Point Post-Shutdown Decommissioning Activities Report Public Meeting, July 29, 2021 ML21197A2002021-07-16016 July 2021 (E-mail 7/16/2021) NRC Staff Assessment and RAI Closeout HDI Fleet Decommissioning Quality Assurance Program and Indian Point Energy Center Quality Assurance Program Manual ML21194A4082021-07-13013 July 2021 (7-13-2021) E-mail NRR Review Hour Estimate Change Supporting the Hi-Lift Crane Proposed License Amendment Request Review 2023-05-25
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1 IPRenewal NPEmails From: Haagensen, Brian Sent: Monday, May 23, 2016 7:32 AM To: Rich, Sarah; Newman, Garrett
Subject:
FW: Blog Item Re: Indian Point Baffle Bolts Attachments:
ATT1-Baffle-Former Bolts2_520.docx FYI From: Pickett, Douglas Sent: Monday, May 23, 2016 7:18 AM To: Rihm, Roger <Roger.Rihm@nrc.gov>
Cc: Tifft, Doug <Doug.Tifft@nrc.gov>; McNamara, Nancy <Nancy.McNamara@nrc.gov>; Dentel, Glenn <Glenn.Dentel@nrc.gov>; Haagensen, Brian <Brian.Haagensen@nrc.gov>; Gray, Mel <Mel.Gray@nrc.gov>; Sheehan, Neil <Neil.Sheehan@nrc.gov>; Screnci, Diane <Diane.Screnci@nrc.gov>
Subject:
Blog Item Re: Indi an Point Baffle Bolts Roger - You might find the attached blog item useful in your Congressional responses regarding the Indian Point baffle bolt issue.
Doug
Douglas V. Pickett, Senior Project Manager Indian Point Nuclear Generating Unit Nos. 2 & 3 Douglas.Pickett@nrc.gov 301-415-1364
Hearing Identifier: IndianPointUnits2and3NonPublic_EX Email Number: 6733 Mail Envelope Properties (67026fe5b7844e739722890d91ad1513)
Subject:
FW: Blog Item Re: Indian Point Baffle Bolts Sent Date: 5/23/2016 7:31:36 AM Received Date: 5/23/2016 7:31:37 AM From: Haagensen, Brian Created By: Brian.Haagensen@nrc.gov Recipients: "Rich, Sarah" <Sarah.Rich@nrc.gov>
Tracking Status: None "Newman, Garrett" <Garrett.Newman@nrc.gov> Tracking Status: None Post Office: R1PWMSMRS02.nrc.gov
Files Size Date & Time MESSAGE 780 5/23/2016 7:31:37 AM ATT1-Baffle-Former Bolts2_520.docx 21804 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
More on Baffle Bolts By John Lubinski Director, Division of Engineering
Office of Nuclear Reactor Regulation We described degradation in baffle-former bolts at Indian Point Unit 2 in an April 27 blog post. The damaged bolts were discovered by Entergy, th e plant operator, while inspecting the bolts during a refueling outage. Since then, PSEG, the operator of the Salem nuclear power plant in New Jersey, discovered some degraded bolts while inspecting the baffles of Unit 1.
To recap, the bolts hold in place a series of vertical metal plat es. Known as baffle plates, they help direct water up through the nuclear fuel assemblies, where it is heated and subsequently used for power production. The baffle plates are a ttached to eight levels of horizontal plates called baffle-former plates, which are in turn connected to the reactor core barrel.
Because of these findings, the NRC has initiated its process for dealing with emerging issues to evaluate the extent of the problem and assess possible responses.
Here's what we know so far:
We are confident this issue lacks an immediate sa fety concern that would lead us to shut down U.S. nuclear power plants or prevent the startup of plants in refueling outages.
The phenomenon is not a surprise. Degraded baffle-former bolts were detected in French reactors in the late 1980s and 1990s, and the NRC published an Information Notice in 1998 alerting the U.S. industry.
That prompted several plants to inspect their bolts, and some even made adjustments to their baffles or replaced bolts as a result. Guidance from the Electric Power Research Institute, evaluated and approved by the NRC and adopted by the industry's own materials management program, calls for visual and ultrasonic inspectio ns during a certain period in a reactor's lifespan.
The current findings at Indian Point and Salem resulted from this operational experience.
As we said earlier, degradation of the baffle-former bolts poses little safety risk during normal operations. If bolt parts come loose during normal operations and damage fuel, the condition will be detected by routine monitoring of radioactivity in the reactor coolant water. During refueling outages, plant operators look for debris on the bottom of the reactor vessel as another indication of potential issues. Even during an accident, the danger of core damage would be minimal. For these reasons, the NRC does not believe it necessary to shut down any additional plants and order immediate inspections.
That doesn't mean we can ignore the condition, of course. Plants with degraded bolts are required to perform analyses and/or replace the damaged bolts before restarting. Missing bolt parts (such as a bolt head) must be accounted for or recovered, or the licensee must perform a "loose-parts evaluation" prior to restarting. The NRC staff will independently assess the root-cause and safety significance of the bolt degradation at each reactor and take appropriate regulatory action.
So how many plants might have this problem? Only Westinghouse-designed pressurized-water reactors with four reactor coolant loops have reported significant bolt damage. Although there are 29 such plants in the United States, the issue appears to be further lim ited by two factors: The damaged bolts have all been of a certain type of stainless steel, and they've all been in reactors with baffles in a "downflow" configuration, m eaning the water entering the reactor is pushed downward between the baffle and the core barrel, which creates more pressure across the plates and stress in the bolts.
There are only seven four-loop Westinghouse reactors at four sites with both the susceptible bolt material and a downflow configuration: Indian Point Units 2 and 3, Salem Units 1 and 2, D.C.
Cook Units 1 and 2, and Diablo Canyon Unit 1. (Dia blo's Unit 2 has been reconfigured to an upflow baffle.) We are asking the operators of D.C. Cook and Diablo Canyon to consider the recent findings and implications for their plants, including their plans for future bolt inspections.
Bolt degradation starts to appear sometime after 25 "effective full-power years" of operation (based on actual operation, not calendar years since licensing). So the NRC-approved EPRI guidance advises PWR operators to inspect their baffle-former bolts sometime between 25 and 35 effective full-power years. The NRC requires the inspections as part of aging management plans for reactors with renewed licenses.
As a result of the findings at Indian Point 2, En tergy decided it will conduct detailed ultra-sonic testing of baffle-former bolts in Indian Point 3 during its next outage in spring 2017, instead of March 2019 as previously scheduled. PSEG had b een conducting visual inspections every other outage, and because of their discovery of degraded bolts during the current inspection of Salem 1, they decided to conduct the ultrasonic test now rather than in 2023 as previously planned. PG&E indicated to the NRC that it will inspect the baffles on Diablo Canyon 1 during its next scheduled outage in spring 2017.
While the industry is reacting to the recent findings at Indian Point 2 and Salem 1, the NRC will continue to assess baffle-former bolt degradation for any potential implications to the rest of the U.S. commercial reactor fleet.