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MONTHYEARLIC-14-0099, Revised Fourth Ten-Year Interval Inservice Inspection (ISI) Interval2014-11-0303 November 2014 Revised Fourth Ten-Year Interval Inservice Inspection (ISI) Interval Project stage: Request LIC-15-0066, Relief Request Number RR-14, Request for Relief from Paragraph -3142.1(c) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds2015-05-0909 May 2015 Relief Request Number RR-14, Request for Relief from Paragraph -3142.1(c) of ASME Code Case N-729-1 for Reactor Vessel Head Penetration Nozzle Welds Project stage: Request ML15131A4252015-05-11011 May 2015 NRR E-mail Capture - FW: Ft Calhoun--relief Request 14 Reactor Vessel Head Inspections (MF6206) Project stage: Other LIC-15-0069, Response to NRC Request for Additional Information Regarding Relief Request RR-142015-05-13013 May 2015 Response to NRC Request for Additional Information Regarding Relief Request RR-14 Project stage: Response to RAI ML15137A0042015-05-15015 May 2015 NRR E-mail Capture - FCS: RAI Number 2 for RR-14, Rvh Leakage/Asme Code Case N-729-1 Project stage: RAI LIC-15-0070, Response to NRC Request for Additional Information Regarding Relief Request RR-142015-05-16016 May 2015 Response to NRC Request for Additional Information Regarding Relief Request RR-14 Project stage: Response to RAI LIC-15-0071, Supplemental Information Associated with Omaha Public Power District (OPPD) Relief Request RR-142015-05-17017 May 2015 Supplemental Information Associated with Omaha Public Power District (OPPD) Relief Request RR-14 Project stage: Supplement ML15138A0122015-05-17017 May 2015 NRR E-mail Capture - Verbal Authorization for Relief Request RR-14 Project stage: Other ML15147A1552015-05-18018 May 2015 Reactor Vessel Head Penetration Photographs Associated with Omaha Public Power District (OPPD) Relief Request RR-14 Project stage: Other ML15139A0102015-05-26026 May 2015 Summary of 5/17/15 Telephone Call, Verbal Authorization of Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, 4th 10-Year Inservice Inspection Interval Project stage: Other ML15232A0032015-08-21021 August 2015 Relief Request RR-14, Relief from ASME Code Case N-729-1 Requirements for Reactor Vessel Head Penetration Nozzle Welds, Fourth 10-Year Inservice Inspection Interval Project stage: Acceptance Review 2015-05-16
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Category:E-Mail
MONTHYEARML24025A1792024-01-23023 January 2024 State Consultation Response e-mail on Fort Calhoun Station, Unit 1 License Termination Plan License Amendment (License No. DPR-40, Docket No. 50-285) ML24024A2242024-01-22022 January 2024 State Consultation e-mail on Fort Calhoun Station, Unit 1 License Termination Plan License Amendment- (License No. DPR-40, Docket No. 50-285) ML23311A0862023-11-0505 November 2023 Letter to M Morales Re Ft Calhoun License Termination Section 7 Determination for Ipac 2022-0029456 ML23038A1882023-01-31031 January 2023 Request for Additional Time to Respond to Request for Additional Information on License Amendment Request for Approval of License Termination Plan (License No. DPR-40, Docket No. 50-285) ML22222A1192022-08-0808 August 2022 Email Section 106 NHPA- Ft Calhoun Station License Termination Plan ML21069A2482021-03-10010 March 2021 Umax, 07200054, 05000361, 05000362, FSAR Revision 4 for San Onofre ISFSI ML21335A3352021-01-25025 January 2021 January 25, 2021 e-mail from J. Parrott, NRC to C. Cameron, OPPD Use of Resrad Model to Represent Well Water Concentrations in a Basement Substructure (License No. DPR-40, Docket No. 50-285) ML20204B0782020-07-22022 July 2020 Donna Gilmore Email Holtec Umax Materials (07200054, 05000361, 05000362) ML20113F0622020-04-22022 April 2020 E-mail Results of Acceptance Review of OPPD Request for Exemption from 10 CFR 20, App G, Section Iii.E (License No. DPR-40, Docket No. 50-285) ML20100J2272020-03-26026 March 2020 E-mail Notification to the State of Nebraska on the Issuance of the License Amendment for Revised Security Plans to Reflect an ISFSI-only Configuration (License No. DPR-40, Docket Nos. 50-285 and 72-54) ML20100L7232020-03-15015 March 2020 Email: Town of Desoto National Register of Historic Places Eligibility ML19353C3612019-12-11011 December 2019 E-mail to State of Nebraska Informing of the Pending Revision to the Emergency Plan to Reflect Independent Spent Fuel Storage Installation Only Status (License DPR-40, Docket Nos. 50-285 and 72-054) ML19309F1112019-10-11011 October 2019 ISFSI-Only Tech Specs ML19241A1812019-08-21021 August 2019 Request for Additional Information on Proposed Changes to the FCS Emergency Plan and Emergency Action Level Scheme to Reflect an ISFSI-only Status ML19175A0212019-06-19019 June 2019 Acceptance Review - License Amendment Request to Revise Security and Safeguards Requirements to Reflect ISFSI-Only Configuration 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 ML19126A2802019-05-0101 May 2019 Acceptance Review - License Amendment Request for ISFSI-Only EP and EAL Scheme ML18100A2712018-04-0909 April 2018 04-09-18 OPPD E-Mail (FCS Permanently Defueled Emergency Plan Implementation) ML17236A3462017-08-24024 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Permanently Defueled TS (MF9567) ML17236A3442017-08-24024 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun Exemption from 10 CFR 140.11(a)(4), Off-site Primary and Secondary Liability Insurance (MF9664) ML17234A4692017-08-22022 August 2017 NRR E-mail Capture - Final RAI for Fort Calhoun LAR Regarding Removal of Dry Cask Loading Limits (MF9831) ML17194A9732017-07-13013 July 2017 NRR E-mail Capture - Final RAI for Fort Calhoun Ultimate Strength Design for Aux. Bldg LAR (MF8525) ML17191B0212017-07-10010 July 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review of Modification of LC 3.C to Delete Commission-approved CSP ML17184A0042017-06-30030 June 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review of Removal of Dry Cask Loading Limits ML17142A0202017-05-19019 May 2017 NRR E-mail Capture - (External_Sender) Need Corrected Page 6 to TQ-DC-FC-101 ML17144A0132017-05-19019 May 2017 NRR E-mail Capture - Fort Calhoun PSDAR - Findings and Concerns ML17139C5082017-05-19019 May 2017 NRR E-mail Capture - (External_Sender) Need Corrected Page 6 for LIC-17-0043 ML17139C8342017-05-19019 May 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review Partial Exemption from Record Retention Requirements ML17139B6782017-05-18018 May 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review Exemption from 10 CFR 50.54(w)(1), On-Site Property Damage Insurance ML17139B6762017-05-18018 May 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review Exemption from 10 CFR 140.11(a)(4), Off-Site Liability Insurance ML17136A1692017-05-16016 May 2017 NRR E-mail Capture - (External_Sender) OPPD FCS Decommissioning Financial Reports ML17115A4722017-04-25025 April 2017 NRR E-mail Capture - (External_Sender) Corrected Page 18 to TQ-DC-FC-201 ML17114A3112017-04-24024 April 2017 NRR E-mail Capture - Fort Calhoun - Acceptance Review TS Changes to Align for Decommissioning ML17112A0362017-04-20020 April 2017 NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Permanently Defueled EP and EAL Scheme Change LAR ML17090A3942017-03-31031 March 2017 NRR E-mail Capture - Fort Calhoun - Final RAI Regarding Administrative Control TS Change LAR (MF8437) ML17082A0022017-03-22022 March 2017 NRR E-mail Capture - Fort Calhoun Station - Final Nsir/Dpr RAI Regarding Proposed Emergency Planning Exemption ML17081A0192017-03-21021 March 2017 NRR E-mail Capture - Fort Calhoun Station - Final RAI Regarding Proposed Emergency Planning Exemption ML17052A0272017-02-15015 February 2017 NRR E-mail Capture - Fort Calhoun Station, Unit No. 1 - Acceptance of Requested Amendment Revise Permanently Defueled Emergency Plan and EAL Scheme ML17033A9692017-02-0202 February 2017 NRR E-mail Capture - Fort Calhoun Station - Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment ML16350A0392016-12-15015 December 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8858) Fort Calhoun, Unit 1 - License Amendment Request (LAR) 16-06; Removal of License Condition 3.D., Fire Protection Program ML16351A0432016-12-15015 December 2016 NRR E-mail Capture - (External_Sender) Fort Calhoun Station Offsite Response Organizations ML16334A3002016-11-29029 November 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8525) Fort Calhoun, Unit 1 - License Amendment Request LAR-16-04 to Revise Current Licensing Basis to Use Aci Ultimate Strength Requirements ML16333A0992016-11-28028 November 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8452), Fort Calhoun, Unit 1 - Request for Exemption from Specific Provisions in 10 CFR 73.55 ML16333A2312016-11-28028 November 2016 NRR E-mail Capture - Acceptance Review (CAC No. MF8843)Fort Calhoun, Unit 1, Request for Rescission of Interim Compensatory Measure B.1.a from EA-02-026, Order for Interim Safeguards and Security Compensatory Measures. ML16286A0812016-10-12012 October 2016 NRR E-mail Capture - Acceptance Review Fort Calhoun Station, Unit 1, License Amendment Request 16-03, Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning ML16278A0292016-10-0303 October 2016 NRR E-mail Capture - Acceptance Review Fort Calhoun Station Radiological Emergency Response Plan (RERP) for Decommissioning ML16257A0262016-09-12012 September 2016 NRR E-mail Capture - (External_Sender) OPPD Slides for 9/13/16 Pre-Application Meeting on Class 1 Structures ML16207A0182016-07-22022 July 2016 NRR E-mail Capture - Acceptance Review ML16137A0092016-05-16016 May 2016 NRR E-mail Capture - Acceptance Review CAC No. MF7574 ML16131A7312016-05-10010 May 2016 NRR E-mail Capture - (External_Sender) Question Rvi Inspection Results 2024-01-23
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NRR-PMDAPEm Resource From: Lyon, Fred Sent: Sunday, May 17, 2015 6:17 PM To: Lyon, Fred; HANSHER, BILL R Cc: SIMPKIN, TERRENCE W; EDWARDS, MICHAEL L; CORTOPASSI, LOUIS P; WILSON, JEFFREY L; GOODMAN, HARRY A; MAASSEN, KRISTEN G; MCMANIS, JOE L; Alley, David; Markley, Michael; Wilson, George; Hagar, Bob
Subject:
Verbal Authorization for Relief Request RR-14 By telecon on May 17, 2015, David Alley and Michael Markley, et al., of the NRC staff, provided verbal authorization for RR-14 to Lou Cortopassi, Jeff Wilson, et al., of the OPPD staff for FCS:
VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST -14 ALTERNATE INSPECTION OF REACTOR VESSEL CLOSURE HEAD PENETRATION NOZZLES FT CALHOUN STATION, UNIT 1 OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated May 9, 2015, as supplemented by letters dated May 13, 16 and 17, 2015, Omaha Public Power District (the licensee) submitted Relief Request -14 for the inspection of reactor vessel head nozzles at Fort Calhoun Station, Unit 1. In Relief Request-14, the licensee proposed to use alternative inspection requirements for reactor vessel head nozzles with respect to American Society of Mechanical Engineers (ASME) Code Case N-729-1 as conditioned in 10 CFR 50.55a(g)(6)(ii)(D) until the end of operating cycle 28 or until a degraded reactor vessel head nozzle is detected.
The NRC staff reviewed the licensees results of current bare metal visual examinations of the reactor vessel head nozzles, the potential of nozzle ejection and reactor vessel head degradation resulting from the boric acid corrosion, and the proposed inspection plan that the licensee will be performing in the next refueling outage in Fall 2016.
The NRC staff finds that:
- 1. The licensee has demonstrated that nozzle ejection and reactor vessel head degradation are not likely in the next fuel cycle.
- 2. The licensees bare metal visual examinations did not identify any areas of significant corrosion,
- 3. The licensee has demonstrated that there was an alternate possible source other than nozzle leakage for the relevant condition for each of the nozzles for which relief is requested.
- 4. The licensees chemistry analysis provided some additional supporting information for leakage sources other than possible nozzle leakage
- 5. The licensee will use administrative controls such that at an unidentified leak rate increase of greater than 0.1 gallons per minute above stable baseline, actions will be taken to identify the source of leakage. If the source is not identified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, actions will be taken to shutdown the plant.
- 6. The licensee will perform a bare metal visual examination of all reactor vessel head nozzles in accordance with ASME Code Case N-729-1 on the first cold shutdown of greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that occurs after at least 4 months of operation.
1
- 7. For the Fall 2016 inspection, the licensee will perform bare metal visual examinations in combination with ultrasonic examinations or surface examinations of all reactor vessel head nozzles in accordance with ASME Code Case N-729-1 as conditioned in 10 CFR 50.55a(g)(6)(ii)(D).
Based on the above, the NRC staff has determined that the proposed alternative inspection performed in Spring 2015 provides reasonable assurance that the structural integrity of the reactor vessel head and attached nozzles will be maintained until the next refueling outage, which is scheduled for Fall 2016.
The NRC staff concludes that Relief Request-14 will provide reasonable assurance of the structural integrity of the reactor vessel head and attached nozzles. The NRC staff concludes that complying with the specified inspection in accordance with ASME Code Case N-729-1 would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2) and is in compliance with the requirements of the ASME Code,Section XI, ASME Code Case N-729-1 as conditioned by 10 CFR 50.55a(g)(6)(ii)(D). Therefore, on May 17, 2015, as authorized by David Alley, Chief, Component Performance, Non-Destructive Examination, and Testing Branch, and Michael Markley, Chief, Plant Licensing Branch IV-1, Office of Nuclear Reactor Regulation, the NRC authorizes the use of Relief Request-14 at Fort Calhoun Station, Unit 1 until the end of operating cycle 28, scheduled for Fall 2016, or until a degraded reactor vessel head nozzle is detected.
All other requirements of ASME Code,Section XI, and 10 CFR 50.55a(g)(6)(ii)(D) for which relief was not specifically requested and authorized by the NRC staff remain applicable, including the third party review by the Authorized Nuclear In-service Inspector.
This verbal authorization does not preclude the NRC staff from asking additional clarification questions regarding Relief Request RR-14 while preparing the subsequent written safety evaluation.
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Hearing Identifier: NRR_PMDA Email Number: 2079 Mail Envelope Properties (A56E37EC1CBC8045910287CEF5E7AE6C037C28B6A4E0)
Subject:
Verbal Authorization for Relief Request RR-14 Sent Date: 5/17/2015 6:17:28 PM Received Date: 5/17/2015 6:02:14 PM From: Lyon, Fred Created By: Fred.Lyon@nrc.gov Recipients:
"SIMPKIN, TERRENCE W" <twsimpkin@oppd.com>
Tracking Status: None "EDWARDS, MICHAEL L" <medwards@oppd.com>
Tracking Status: None "CORTOPASSI, LOUIS P" <lcortopassi@oppd.com>
Tracking Status: None "WILSON, JEFFREY L" <jlwilson@oppd.com>
Tracking Status: None "GOODMAN, HARRY A" <hagoodman@oppd.com>
Tracking Status: None "MAASSEN, KRISTEN G" <kmaassen@oppd.com>
Tracking Status: None "MCMANIS, JOE L" <jmcmanis@oppd.com>
Tracking Status: None "Alley, David" <David.Alley@nrc.gov>
Tracking Status: None "Markley, Michael" <Michael.Markley@nrc.gov>
Tracking Status: None "Wilson, George" <George.Wilson@nrc.gov>
Tracking Status: None "Hagar, Bob" <Bob.Hagar@nrc.gov>
Tracking Status: None "Lyon, Fred" <Fred.Lyon@nrc.gov>
Tracking Status: None "HANSHER, BILL R" <bhansher@oppd.com>
Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 4780 5/17/2015 6:02:14 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: