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Category:E-Mail
MONTHYEARML24025A0952024-01-24024 January 2024
Clarifications Related to the NRC Staff'S EA for Crystal River
ML23180A0562023-06-13013 June 2023
ADP-CR3, Crystal River Unit 3 Email from J. Jernigan to Tim Barvitskie Confirmation That Enclosure 22 Radiological Groundwater Characterization Report
ML21117A2902021-04-26026 April 2021
Acceptance of License Amendment Request Related to the ISFSI-Only Physical Securityplan
ML21096A0432021-04-0505 April 2021
Acceptance of License Amendment Request Related to the ISFSI-Only Emergency Plan
ML19344C8052019-11-12012 November 2019
Response from NEIMA Local Community Advisory Board Questionnaire 11-12-2019 H Danenhower
ML19310D8602019-10-24024 October 2019
E-Mail Dated October 24, 2019, from Mark Vansicklen, Duke Energy Florida, to John Hickman, NRC, Providing Background Information for the Crystal River Partial Site Release Request
ML19344C7872019-10-0303 October 2019
Response from NEIMA Local Community Advisory Board Questionnaire 10-03-2019 D Taylor
ML19310D8212019-09-13013 September 2019
E-Mail Dated September 13, 2019, from John Hickman, NRC, to Mark Vansicklen, Duke Energy Florida, Requesting Background Information for the Crystal River Partial Site Release Request
ML19130A2082019-05-0808 May 2019
Email - NRC Email to FEMA Dated May 8, 2019: NRC Response to Comment on FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition
ML19070A3112019-03-0606 March 2019
Document Title or Accession No. E-Mail Dated 3/6/2019 from John Hickman, NRC, to Phyllis Dixon, Duke Energy Florida, LLC, Regarding NRC Acceptance Review of Partial Site Release Request for Crystal River Unit 3
ML19071A0662019-03-0606 March 2019
E-Mail Dated 3/6/2019 from John Hickman, NRC, to Phyllis Dixon, Duke Energy Florida, LLC, Regarding NRC Acceptance Review of a Request to Revise the ISFSI Only Emergency Plan for Crystal River Unit 3
ML18263A1462018-09-11011 September 2018
NRR E-mail Capture - Logbook Entry: 09/11/2018 a Kemp'S Ridley Sea Turtle (Federal Endangered Species) Carcass Was Recovered from the Crystal River Energy Complex Unit 2 Fossil Unit
ML16054A2402015-12-10010 December 2015
E-44108 Attachment 10 E-mail from Steven Edwards (Due Energy) to Don Shaw (Areva) for Brunswick Nuclear Plant, Oconee Nuclear Station, and Robinson Nuclear Plant
ML15176A2692015-06-25025 June 2015
NRR E-mail Capture - NRC Acceptance Review for LAR #317 Regarding Changes in Managment Titles
ML15043A1042015-02-0505 February 2015
NRR E-mail Capture - Mf Crystal River TAC
ML15015A6722015-01-15015 January 2015
NRR E-mail Capture - NRC Acceptance Review for LAR - Application for Order Approving Transfer of License and for Conforming License Amendment
ML14344A9992014-12-0909 December 2014
NRR E-mail Capture - Severe Weather Exemption
ML14258A7432014-09-0505 September 2014
NRR E-mail Capture - FW: Comparison of Crystal River'S Exemption Secy Paper with Kewaunee'S
ML14290A1992014-08-27027 August 2014
NRR E-mail Capture - Draft RAIs for Ep/Eal LAR
ML14163A2512014-06-0303 June 2014
NRR E-mail Capture - Request for Additional Information - Exemption for Conducting Annual force-on-force Exercises
ML14153A0842014-05-29029 May 2014
NRR E-mail Capture - Logbook Entry: 05/29/2014
ML14153A6912014-05-21021 May 2014
NRR E-mail Capture - Request for Additional Information - Decommissionign Trust Fund Exemption Request
ML14132A2052014-05-0909 May 2014
NRR E-mail Capture - MF3089 - Defueled TS Amendment Request for Additrional Information
ML14114A2792014-04-10010 April 2014
NRR E-mail Capture - MF3089 Defueled TS Request for Additional Information
ML14113A3632014-04-10010 April 2014
NRR E-mail Capture - MF3415/MF2981 RAI on EP Exemptions, EAL Scheme Change and E Plan Amendment
ML14118A2872014-02-20020 February 2014
NRR E-mail Capture - Request for Additional Information: Exemptions to the Radiological Emergency Plan Requirements
ML14045A0012014-02-12012 February 2014
NRR E-mail Capture - RAI: Adminstrative Controls
ML14031A1752014-01-27027 January 2014
NRR E-mail Capture - CR3 Certified Fuel Handler Training and Retraining Program Approval - RAI Request
ML14017A0772014-01-16016 January 2014
NRR E-mail Capture - Brunswick 1 and 2, Crystal River Unit 3, Harris Unit 1, and Robinson Unit 2 - Acceptance for Review of License Amendment Request for Cyber Security Plan Implementaion Milestone 8 (TAC Nos. MF3263 - MF3267)
ML14027A0332013-12-16016 December 2013
NRR E-mail Capture - Eplan and EAL Scheme Change Request for Additional Information (LAR #315)
ML13336A9112013-12-0202 December 2013
NRR E-mail Capture - Periodic Update to the Crystal River 3 Containment Petition
ML13198A1422013-07-17017 July 2013
NRR E-mail Capture - Draft RAI - Request to Amend Section 5.0 of the CR-3 Technical Specifications (MF1504)
ML13157A2062013-05-31031 May 2013
NRR E-mail Capture - Logbook Entry: 5/31/2013
ML13155A2062013-05-29029 May 2013
NRR E-mail Capture - Petition Status Update - Containment for Crystal River
ML13120A0412013-04-29029 April 2013
NRR E-mail Capture - Status Update for Petition on Crystal River 3
ML13095A4002013-04-0505 April 2013
E-mail - Acceptance of Requested Licensing Action Change of Licensee Name
ML13052A2402013-02-0808 February 2013
LTR-13-0131 - E-mail Tom Gurdziel Concerns Crystal River, Unit 3
ML13015A2832013-01-14014 January 2013
NRR E-mail Capture - Status of 10 CFR 2.206 Petition Related to Crystal River 3
ML13011A1482013-01-10010 January 2013
NRR E-mail Capture - CR-3 EPU LAR - Additional RAI from Eeeb (ME6527)
ML12304A0682012-10-26026 October 2012
NRR E-mail Capture - RAIs Regarding Crystal River 30-day Report for ECCS Model Changes Pursuant to 10 CFR 50.46 Requirements (ME8408)
ML12297A3922012-10-23023 October 2012
NRR E-mail Capture - Draft Bypass Test Plan
ML12268A3592012-09-24024 September 2012
NRR E-mail Capture - Acceptance Review for LAR Regarding Cyber Security Plan Implementation Schedule Milestones
ML12208A0142012-07-25025 July 2012
NRR E-mail Capture - State Consultation
ML12184A3442012-07-0202 July 2012
NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Discussion/Clarification of Emcb Draft RAIs
ML12144A0102012-05-22022 May 2012
NRR E-mail Capture - Acceptance Review Determination: CR-3 - Relief Request #12-001-MX for Option to Use ASME Code Case N-791 for Containment Repair
ML12107A0682012-04-0404 April 2012
NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Clarifications for Component Performance & Testing Branch (Eptb)
ML12100A1022012-03-30030 March 2012
NRR E-mail Capture - Acceptance Review for CR3 - LAR 312- Departure from a Method of Evaluation for Aux Bldg Over Head Crane, Implementation Schedule Change
ML12023A1272012-01-23023 January 2012
NRR E-mail Capture - Acceptance Review Determination for TAC ME7729: CR3 - Relief Request #11-001-MX, Containment Surveillance Schedule, Fourth 10-Year ISI Interval
ML12019A2662012-01-17017 January 2012
NRR E-mail Capture - Crystal River Nuclear Plant - Enforcement Petition 10 C.F.R. 2.206
ML12019A2672012-01-17017 January 2012
NRR E-mail Capture - Crystal River Nuclear Plant - Enforcement Petition 10 C.F.R. 2.206
2024-01-24
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Text
-Masters, Anthony From: Herrin, Dennis W. [Dennis.Herrin @pgnmail.com]
Sent: Wednesday, November 18, 2009 11:14 AM To: Masters, Anthony Cc: Portmann, Rick; Lese, Joseph A.
Subject:
FW: Additional NRC Responses Attachments: !NRC Request #52 Information.docx; !NRC Request #55 Information.docx More answers to your questions. I am still following up with Joe Lese on two older questions.
A~emi6i W. JNevin Lead Engineer - Licensing & Regulatory Programs Progress Energy Florida, Inc.
Crystal River Unit 3 352-563-4633 Voicenet 240-3299 Dennis.Herrin@ pnmail.com From: Portmann, Rick Sent: Wednesday, November 18, 2009 9:41 AM To: Herrin, Dennis W.; Jones, Tai Cc: Dyksterhouse, Don
Subject:
Additional NRC Responses Dennis - Attached are 2 more responses to the NRC. I've put them in the NRC folder {L:\Shared\2009 NRC SPECIAL INSPECTION TEAM Q-A\DYKSTERHOUSE Q-A}. Thanks, Rick
/
1,2_1t
I Request #52, NRC SIT Question Information
- 52. SP-182, Rev. 16 (Dated 5/22/09) Reactor Building Structural Integrity Tendon Surveillance Program, Enclosure 5 is titled "Reduced Force Dome Tendons" and lists 18 tendons. What is meant by this term "reduced force"? When, how, and why did they become reduced? D 125 is shown on this list and is also listed as tested in the 3 rd Surveillance. Please Clarify.
Response to the above question:
Following the investigation and evaluation of the 1976 Dome delamination event the dome tendons were re-stressed to predetermined values, of which approximately every 8 th tendon was stressed at a value much, much lower than the remaining tendons (Approx. 646 KIPS vs. 1635 KIPS). These tendons are exempt from tendon lift-off, and wire removal testing.
During the random selection process if one of these exempt tendons (or in general a tendon that is inaccessible or due to interferences cannot be safely tested per the IWL code) happens to be selected for testing, then a substitute tendon located as close as possible to the exempt tendon gets selected for examination and testing. Although still classified as exempt, the original exempt tendon is still subject to the examination tendon anchorage, free water and corrosion protection medium examination requirements if possible.
A review of the 3 rd Surveillance tendon lift-off data shows that tendon D123 was tested. No test data was found for D125.
Request #55, NRC SIT Question Information
- 55. VT-07-111 and VT-07-289 documents some cracks and spalls and measured depths. How were the depths obtained for the cracks and spalls?
Response to the above question:
The question above was asked with one of the inspectors who performed the examination, his reply is below:
Direct Visual Examination was conducted on RBCN-O015 during R15 using the suspended work platform, a man lift (around the equipment hatch), and a step ladder (lower elevations not accessible by suspended work platform or man lift).
Using the procedure and criteria provided in the Engineering letter as threshold for recording, the VT-3C was performed and any areas of distress identified were further evaluated during a VT-1C. The VT-3C also considered areas of distress not previously identified, as well as changes to previously identified areas of distress.
During the VT-1C, previously existing areas of distress were compared with previous data and further characterized to document changes to previous data recorded. Areas of distress not previously identified were characterized and recorded. In all cases, size and depth were dimensioned and recorded with a tape measure and 6" scale. A short length of 3/32" bare wire welding rod was used for tight spots where the 6" scale would not fit. Technique used with the bare wire was to insert into the opening, and measure maximum depth against the 6" scale.
