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Category:E-Mail
MONTHYEARML24193A0362024-07-10010 July 2024 NRR E-mail Capture - LIC-109 Acceptance Email - Callaway Plant, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition - EPID L-2024-LLA-0076 ML23362A0572023-12-28028 December 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - SUNSI Review of the Final Safety Analysis Report (FSAR) Revision OL-26 ML23338A0392023-12-0101 December 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Unacceptable with Opportunity to Supplement - Callaway - RR from Requirements of ASME BPV Code, Section Xl, Subsect IWL-Exam & Test-Unbonded Post Tensioning System - EPID L-2023-LLR-0061 ML23208A1052023-07-27027 July 2023 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Regulatory Audit Questions - LAR to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems ML23200A2982023-07-19019 July 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - Final Request for Additional Information (RAI) - Request for Approval of Oqam, Revision 36a - EPID L-2023-LLQ-0000 ML23121A0112023-04-28028 April 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request to Revise TS to Adopt TSTF-501-A Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control - EPID L-2023-LLA-0046 ML23114A2302023-04-24024 April 2023 NRR E-mail Capture - Regulatory Audit Question - Callaway LAR and Exemption for Fuel Transition to Framatome Gaia Fuel - EPIDs - L-2022-LLA-0150 and L-2022-LLE-0030 ML23107A1812023-04-17017 April 2023 NRR E-mail Capture - Regulatory Audit Questions - Callaway LAR and Exemption for Fuel Transition to Framatome Gaia Fuel - EPIDs - L-2022-LLA-0150 and L-2022-LLE-0030 ML23096A0072023-04-0505 April 2023 NRR E-mail Capture - Final Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Revise TS 5.5.16 for Permanent Extension of Integrated Leak Rate Testing - EPID L-2022-LLA-0165 ML23073A0262023-03-13013 March 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - SG Inspection Report Review - EPID L-2022-LRO-0143 ML23037A7092023-02-0606 February 2023 April 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23037A0022023-02-0303 February 2023 NRR E-mail Capture - Callaway - LAR to Adopt AST - EPID L-2021-LLA-0177 - Revised Schedule for Completion of the Project ML23026A0212023-01-24024 January 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Changes to TS for SFP - ML23010A2902023-01-10010 January 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Callaway Plant, Unit 1 - License Amendment Request to Clarify Support System Requirements for the RHR & Crac Systems - ML22346A0132022-12-0909 December 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of LAR to Revise TS 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies - EPID L-2022-LLA-0165 ML22322A0062022-11-17017 November 2022 NRR E-mail Capture - Final - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) Callaway - LAR for Proposed Changes to TS and Exemption Request Use of Framatome Gaia Fuel - L-2022-LLA-0150 & L-2022-LLE-0030 ML22287A0952022-10-14014 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22280A1322022-10-0707 October 2022 NRR E-mail Capture - Final - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway - License Amendment Request for Proposed Changes to Tech Spec Changes for Spent Fuel Pool Storage - EPID L-2022-LLA-0 ML22278A0122022-10-0404 October 2022 NRR E-mail Capture - Draft - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway License Amendment Request for Proposed Changes to Tech Spec Changes for Spent Fuel Pool Storage - EPID L-2022-LLA-013 ML22269A4312022-09-26026 September 2022 November 2022 Emergency Preparedness Program Inspection - Request for Information NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22251A0122022-09-0707 September 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request for Application to Revise TS to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections - EPID L-2022-LLA-0110 NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22216A0072022-07-0808 July 2022 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Draft Acceptance Review (Unacceptable for Review with Opportunity to Supplement) for Framatome Fuel Transition LAR and Exemption - EPIDs L-2022-LLA-0083 and L-2022-LLE-0019) ML22167A0252022-06-15015 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Revision to Radiological Emergency Response Plan Regarding Response & Notification Goals - EPID L-2022-LLA-0024 ML22157A0102022-06-0303 June 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood Ultimate Heat Sink Temporary Temperature Increase to 102.8 Degrees Fahrenheit ML22154A0122022-06-0202 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22151A0512022-05-27027 May 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22137A0292022-05-16016 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22096A0232022-04-0505 April 2022 NRR E-mail Capture - Callaway Plant - Final RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to GL 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML22089A0222022-03-29029 March 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LAR to Adopt TSTF-505 and TSTF-439 - Follow Up Clarifications for the Audit Questions - EPID L-2021-LLA-0197 ML22087A4022022-03-28028 March 2022 NRR E-mail Capture - Callaway - Draft RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to Generic Letter 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML22070A1362022-03-10010 March 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals - EPID L-2022-LLA-0024 ML22047A2312022-02-11011 February 2022 Email Between NRC NSIR and FEMA Regarding Callaway Sirens 021122 ML22003A0852022-01-0303 January 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request to Adopt TSTF-529, Clarify Use and Application Rules - EPID L-2021-LLA-0225 ML21334A5172021-11-30030 November 2021 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of Requested Licensing Action - Application to Adopt TSTF-439 and TSTF-505 - EPID L-2021-LLA-0197 ML21335A0172021-11-30030 November 2021 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of Requested Licensing Action - Application to Adopt TSTF-439 and TSTF-505 - EPID L-2021-LLA-0197 ML21308A0692021-11-0404 November 2021 NRR E-mail Capture - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway Unit 1 - License Amendment Request - Adoption of Alternate Source Term and Revision of TSs - ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 ML21195A0252021-07-13013 July 2021 Email 7-13-21 Request for Information - Callaway EP Exercise Inspection - Sept 2021 ML21125A0452021-05-0404 May 2021 NRR E-mail Capture - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway Plant, Unit 1 - License Amendment Request - Final Resolution to Address Concerns of GSI-191 - EPID L-2021-LLA-0059 ML21007A1622021-01-0606 January 2021 NRR E-mail Capture - Final - Request for Additional Information - (COVID-19) Callaway Plant, Unit 1 - Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs - EPID L-2021-LLE-0242 ML20342A1802020-12-0606 December 2020 NRR E-mail Capture - Callaway - LIC-109 Acceptance Requested Licensing Action - Application to Adopt 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors EPID L-2020-LLA-0235 ML20296A6332020-10-22022 October 2020 NRR E-mail Capture - Callaway Plant, Unit 1 - Exemption from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI (EPID L 2020 Lle 0140 (Covid 19)) - Revised Completion Schedule ML20205L4252020-07-22022 July 2020 NRR E-mail Capture - Callaway Plant, Unit 1 - Acceptance of Requested Licensing Action Request for One-Time License Amendment to Defer Upcoming Steam Generator Inspection (EPID L-2020-LLA-0142)(COVID-19) ML20203M3682020-07-21021 July 2020 NRR E-mail Capture - Draft Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request - Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and 5.3.1.2 - EPID L-2020-LLA-0046 ML20162A1882020-06-10010 June 2020 Request for Supporting Information for the Callaway SPRA Audit Review - Draft Supplement ML20153A7902020-05-29029 May 2020 Emai: RFI for Callaway EP Program Inspection ML20133K6742020-05-11011 May 2020 05000483, Request for Information 2020-002 ML20099G2422020-04-0808 April 2020 NRR E-mail Capture - Acceptance Callaway Containment Tendon COVID-19 Relief Request 2024-07-10
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Criscione, Lawrence From: Criscione, Lawrence Sent: Tuesday, February 01, 2011 2:51 PM To: DSouza, Wendy
Subject:
Sharing invitation: Criscione, Lawrence - Calendar Microsoft Exchange Calendar:
Criscione, Lawrence - Calendar Criscione, Lawrence (Lawrence.Criscione@nrc.gov) has invited you to view his or her Calendar.
- Wendy, Attached is the letter I sent to Mr. Bell on January 2 0 th. I sent it via the mail, but I also emailed him a copy on that same day. I copied the email to Mr. Lee, Mr. Banks and Ms. Raspa.
I also emailed Mr. Bell and Mr. Lee on January 2 6th enquiring ifthey would be willing to meet with me as part of the NRC's Open Door Policy.
I have not yet received any indication that OIG received my January 201h letter, nor have I been given any indication by Mr. Bell or Mr. Lee that they would be willing or not willing to meet with me as part of the Open Door Policy.
I came by the 51h floor today to see find out if my letter had been received and to find out when I might expect a response, if any. I don't need to meet with Mr. Banks, but if he (or anyone else from OIG) would like to meet with me, please review my calendar and schedule an appointment.
Thank you for your assistance, Lawrence S. Criscione Reliability & Risk Engineer RES/DRAIOEGIB Church Street Building Mail Stop 2A07 (301) 251-7603
January 20, 2011 Hubert Bell, Inspector General U.S. Nuclear Regulatory Commission Office of the Inspector General Mail Stop 05-E13 11555 Rockville Pike Rockville, MD 20852
Dear Mr. Bell:
I was once a US NRC licensed Senior Reactor Operator at Callaway Plant. In February 2007 1accidently uncovered an inadvertent passive shutdown of the reactor which occurred on October 21, 2003 and which, in my opinion, was intentionally covered up by the control room operators. This allegation was investigated by Region IVas allegations RIV-2007-A-0028 and RIV-2007-A-0096. Two of your inspectors (Mark Banks and Rossana Raspa) are somewhat familiar with the incident.
Although they refuse to use the adjective "passive", Region WV does agree with me that around 10:18 am on October 21, 2003 the reactor at Callaway Plant passively shut down due to a combination of buildup of Xenon-135 and a sharp 4°F rise in average reactor coolant temperature. It is my contention that this passive shutdown was "inadvertent" in that it went unnoticed by the NRC licensed operators for over an hour (until the channel 2 Source Range Nuclear Instrument energized at 11:25 am and caused an annunciator on the reactor plant's main control board to annunciate). It is unclear to me what Region IV's position is on whether the passive shutdown "inadvertently" occurred or whether it was intentionally allowed to occur; all that Region IVwill transparently state to me is that my allegation that the passive shutdown was "inadvertent" could not be substantiated. However, Region IVdid substantiate that no negative reactivity was actively inserted until more than 106 minutes after the reactor passively shut down and that "...appropriateattention to reactivity management would have the operatorsinsert the control rods well before the time they were actually inserted."
Region IVhas also stated to me that "There were essentially no safety implicationsfrom the plant configuration and adequate shutdown margin was maintained throughout the 90- to 100-minute period from the turbine trip to the insertion of the control rods." Although I agree that there were no safety implications "from the plant configuration", I do not agree that there were no safety implications from the incident itself. NRC licensed control room operators recklessly relying on an informal estimation that transient Xenon-135 levels would be sufficient to prevent an inadvertent reactor restart has immense safety implications: we (the public) expect that NRC licensed operators will actively and conservatively control the nuclear fission reaction and will NOT passively rely on informal estimations of transient fission product poisons when both active means to control the fission reaction are available (i.e. control rods and boron) and formal means to evaluate the adequacy of Xenon-135 are available (i.e.
a Shutdown Margin calculation). The fact that after-the-fact calculations demonstrated that shutdown margin was adequate does not mean there were "no safety implications". Relying on luck is not an
acceptable strategy for operating a large commercial reactor. The nuclear fission reaction must always be actively controlled and when transient fission product poisons are utilized for maintaining safety margins their levels must be formally calculated BEFORE relying on them.
In a February 26, 2010 letter to me, Region IVstated:
The inspectorsnoted that the crew had completed a shutdown margin verificationjust priorto tripping the main turbine, as required by the shutdown procedure. The shutdown margin verification ensured that had a design basis accident occurred at that time, adequatenegative reactivity was availableto maintain the plant shutdown.
I requested a copy of this "shutdown margin verification" through the Freedom of Information Act and was told that it is not an NRC record and cannot be provided. I believe that the reason it could not be provided is because it does not exist. It is my contention that on October 21, 2003 there was no formal calculation performed to show that from 10:13 am (the time of the manual turbine trip) to 12:05 pm (the time control bank insertion began) Xenon-135 levels were adequate to ensure "that had a design basis accidentoccurred at that time, adequate negative reactivity was available to maintain the plant shutdown." I allege the following:
- 1. On October 21, 2003 the operating crew at Callaway Plant did NOT complete a shutdown margin verification just prior to tripping the main turbine, The only "shutdown margin verification" that I know of at Callaway Plant which "ensured that had a design basis accident occurred...adequate negative reactivity was available to maintain the plant shutdown" was surveillance OSP-SF-00001. This surveillance procedure was NOT performed prior to tripping the turbine, and on October 21, 2003 there was no completed performance of this procedure which validated the reactor conditions from 10:13 am through 12:05 pm contained adequate negative reactivity to maintain the plant shutdown had a design basis accident occurred.
- 2. Although it is possible the crew had completed a "Xenon Prediction", the Xenon Prediction procedure is not a substitute for a Shutdown Margin surveillance (OSP-SF-00001). The Shutdown Margin surveillance ensures that there is adequate negative reactivity to prevent the reactor from inadvertently restarting during a design basis accident. The Xenon Prediction calculation provides the crew with estimated Xenon-135 levels so they know how much positive reactivity must be added to keep the reactor critical. They are different calculations and are performed for different reasons. Itis not accurate to state that a Xenon Prediction "ensured that had a design basis accident occurredat that time, adequate negative reactivity was available to maintain the plant shutdown."
- 3. By allowing Callaway Plant to substitute a Xenon Prediction for a Shutdown Margin calculation, Region IVisfailing to ensure that health and safety measures are appropriately addressed.
- 4. By stating to me that "The inspectors noted that the crew had completed a shutdown margin verificationjust prior to tripping the main turbine" and then refusing to provide me a copy of that "shutdown margin verification" Region IVis failing to appropriately transact nuclear regulation publicly and candidly.
I respectfully request the intervention of the Inspector General on resolving the four items above, Specifically, I request that one of the following actions be performed:
" Region IVadmit to me, in writing, that on October 21, 2003 the crew at Callaway Plant did NOT complete a formal shutdown margin verification just prior to tripping the main turbine and that, during the 106 minutes in which the reactor was shutdown with the control rods still at their last critical rod heights, there was no formal calculation in effect which showed "that had a design basis accident occurred at that time, adequatenegative reactivity was availableto maintain the plant shutdown,"
OR
" Region IVprovided me a copy of the "shutdown margin verification"which was performed by the crew "justprior to tripping the main turbine". Appropriate redactions may be made to this document. I just want to be able to see the procedure which was performed, the time it began, the time it was completed, and the calculations which were done. I do NOT need the names of the performers or any other personal information which is normally redacted.
I do not know what process you will use to handle this request, but please note that I do NOT request anonymity or confidentiality in any way. I have copied several individuals on this correspondence who have been assisting me in various ways in addressing my concerns regarding the October 21, 2003 shutdown. Please be open and transparent with them and anyone else who wishes to discuss my concerns.
I currently work in Rockville, MD and make it home to Illinois infrequently. Please copy all correspondence to me at my personal emailaddress (b)(6)I If you have any questions, please feel free to contact mea Very respectfully, Lawrence S. Criscione, PE Cc: Congressman Dennis Kucinich Representative Jeanette Mott Oxford, Missouri legislature David Lochbaum, Union of Concerned Scientists Dr. Charles N. Davis, University of Missouri