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Category:Memoranda
MONTHYEARML23129A6062023-05-0404 May 2023
Special Inspection Team Charters to Evaluate the Circumstances Surrounding the Ground Settling at the Davis-Besse Nuclear Power Station
ML23044A3662023-02-15015 February 2023
Calendar Year 2022 Reactor Oversight Process Baseline Inspection Program Completion - Region III
ML21096A2282021-03-30030 March 2021
FEMA Disapproval of Davis-Besse Exercise Exemption
ML19182A3562019-07-23023 July 2019
Quarterly Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations, Section 2.206 - April 1 to June 30, 2019
ML19162A0102019-06-0707 June 2019
Memorandum to File Environmental Assessment and Finding of No Significant Impact for Firstenergy Nuclear Operating Company'S Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(B) and 72.30(C) for Davis Besse ISFSI
ML16088A2052016-03-28028 March 2016
Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations
ML16088A2042016-03-28028 March 2016
Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template)
ML15205A1692015-08-0707 August 2015
ACRS Review of the Davis Besse Nuclear Plant LRA - Transmittal of the Sser
ML15182A1912015-07-16016 July 2015
Annual Financial Test for a Parent Company Guarantee Given by Firstenergy Solutions Corporation and Firstenergy Corporation
ML15089A1642015-04-27027 April 2015
Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis
IR 05000334/20004122014-07-0808 July 2014
NRC Staff'S Spot-Check Review of First Energy Nuclear Operating Company'S Ownership Interest in Beaver Valley, Units 1 and 2, Perry, and Davis-Besse, Docket No. 05000334, 05000412, 05000440, and 05000346, on June 10, 2014-Finding of No Pote
ML14099A4642014-05-0606 May 2014
Summary of Public Meetings to Discuss Draft Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Davis-Besse Nuclear Generating Station, Unit 1
ML13280A9062013-10-21021 October 2013
Forthcoming Meeting with Firstenergy Nuclear Operating Company (FENOC) to Discuss Voluntary Risk Informed Fire Protection Amendment for Davis-Besse
ML13142A5122013-07-0202 July 2013
Summary of Telephone Conference Call Held on May 21, 2013, Between NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse Nuclear Power Station, LRA
ML13171A2922013-06-13013 June 2013
LTR-13-0540 - Bill Hawkins and Vinod Arora Email San Onofre Nuclear Generating Station (SONGS) Lessons Learn for Davis-Besse
ML13154A4442013-06-0404 June 2013
Rai'S Following Ifib Analysis of Fenoc'S 2013 Decommissioning Funding Status Report for Davis-Besse and Perry
ML12199A2072012-07-17017 July 2012
Public Meeting Notice to Discuss the 2011 End-of-Cycle Performance Assessment
ML12158A4002012-06-0808 June 2012
6/26/2012 Forthcoming Meeting Firstenergy Nuclear Operating Company (FENOC)
ML1206901652012-03-0909 March 2012
Memo - Summary of Public Meeting with Industry Regarding Pwrog'S Boric Acid Corrosion Test Program
ML12018A1652012-01-27027 January 2012
Summary of Telephone Conference Call Held on November 9, 2011, Between the NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse, LRA
ML14028A5462012-01-25025 January 2012
NRC Telecon Regarding Davis-Besse License Renewal Severe Accident Mitigation Alternatives Analysis Questions
ML11363A1712012-01-23023 January 2012
Summary of Telephone Conference Call Held on December 12, 2011 Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Request for Additional Information
ML11355A0952011-12-29029 December 2011
Summary of Telephone Conference Call Held on December 8, 2011, Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning RAIs Pertaining to the Davis-Besse Nuclear Power Station, LRA
ML11348A0212011-12-21021 December 2011
Summary of Telephone Conference Call Held on November 1, 2011 Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis Besse Nuclear Pow
ML11341A1182011-12-14014 December 2011
Summary of Telephone Conference Call Held on June 15, 2011 Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power
ML11339A0862011-12-13013 December 2011
Summary of Telephone Conference Call Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning RAIs Pertaining to the Davis-Besse Nuclear Power Station LRA
ML11327A0082011-12-0202 December 2011
Summary of Telephone Conference Call Held on September 29, 2011, Between the NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse, LRA
ML11327A0792011-12-0202 December 2011
Summary of Telephone Conference Call Held on Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis Besse Nuclear Power Station
ML11327A0872011-12-0202 December 2011
Summary of Telephone Conference Call Held on July 27, 2011, Between the NRC and Firstenergy Nuclear Operating Company Concerning RAI Pertaining to the Davis-Besse, LRA
ML11279A2182011-10-0606 October 2011
Memo - Task Interface Agreement - Evaluation of Compliance with Code for Examination of Flange Stud Holes on the Replacement Vessel Head at the Davis-Besse Nuclear Power Station (TIA 2011-015)
ML11242A0032011-09-12012 September 2011
Summary of Conference Call Held on August 4, 2011, Between the NRC and FENOC Concerning Requests for Additional Information Pertaining to the Davis-Besse License Renewal Application
ML1122701392011-08-15015 August 2011
Request for Additional Information Response Clarification from Davis-Besse Nuclear Power Station in Support of License Renewal Application Review
ML11173A2002011-08-0101 August 2011
Summary of Public Scoping Meetingsconducted Related to the Review of the Davis-Besse Nuclear Power Station, Unit 1, LRA
ML11193A2032011-07-26026 July 2011
Final Response to TIA 2011-001, Davis-Besse Nuclear Power Station Safety-Related Batteries Electrical Separation Design and Licensing Bases
ML11174A2322011-06-21021 June 2011
for the Record-06-21-2011: NRC Ensures Public Safety Through Rigorous Oversight of Nuclear Power Plant Safety Standards
ML1108202762011-06-0303 June 2011
Summary of Site Audit Related to the Review of the License Renewal Application for Davis-Besse Nuclear Power Station, Unit 1
ML11174A2472011-05-31031 May 2011
for the Record-05-31-2011: NRC Chairman Gregory B. Jaczko'S Statement on Nrc'S Commitment to Safety
ML1110806902011-04-20020 April 2011
Notice of Meeting with First Energy Nuclear Operating Company (FENOC) to Discuss a Proposed LAR to Delete Technical Specification 5.5.8g, Steam Generator (SG) Program Auxiliary Feedwater Header Inspections
ML1028702612010-10-22022 October 2010
11/04/10 Notice of Meeting to Discuss the License Renewal Process and Environmental Scoping for Davis-Besse Nuclear Power Station License Renewal Application Review
ML1029106182010-10-14014 October 2010
Documentation of Telephone Conversation Between Mr. David Lochbaum Regarding Follow-Up Questions Related to NRC Letter Dated July 28, 2010 (ML102040807)
ML1028503032010-10-12012 October 2010
Acceptance of License Renewal Application, Davis-Besse Nuclear Power Station
ML0935101922009-12-14014 December 2009
Completion of Davis-Besse Lessons Learned Task Force Recommendation 3.3.4(8)
ML0825606772008-09-15015 September 2008
Presentation Disc
ML0814207532008-05-20020 May 2008
Summary of Public Meeting with Firstenergy Nuclear Operating Company to Discuss the 2008 Davis-Besse End-of-Cycle Performance Assessment
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0723302222007-08-28028 August 2007
09/12/2007 Notice of Meeting with Firstenergy to Discuss the August 3, 2007 License Amendment Request for Conversion to Improved Technical Specifications for Davis-Besse, Unit 1
ML0722108432007-08-0707 August 2007
Request for Renewal of Deviation to the Reactor Oversight Process Action Matrix for Davis-Besse Nuclear Power Station
ML0717103462007-06-21021 June 2007
Revised Notice of Meeting with Firstenergy to Discuss Response to Nrc'S 05/14/2007, Demand for Information Regarding Fenoc'S Re-analysis of the Timeline and Root Causes for the 2002 Davis-Besse Reactor Pressure Vessel Head Degradation Event
ML0716202122007-06-13013 June 2007
Notice of Meeting with Firstenergy Regarding May 14, 2007 Demand for Information Davis-Besse
ML0712803322007-05-18018 May 2007
April 2007 Report on the Status of Public Petitions Under Title 10 of the Code of Federal Regulations (10 Cfr), Section 2.206
2023-05-04
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- byk REG&x UNITED STATES NUCLEAR REGULATORY COMMISSION I-a,
- 0 LISLE, ILLINOIS 60532 February 22, 2004 MEMORANDUM TO: Christine Lipa, Chief Branch 4 Division of Reactor Projects FROM: David Hills, Chief IRA!
Mechanical Engineering Branch Division of Reactor Safety SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION DRS INPUT TO INTEGRATED REPORT 50-346/04-02 Attached is the report input for Davis Besse Nuclear Power Station, Inspection Report 50-346/04-02. This report input documents completion of an inspection to review and close URI 50-346/02-014-06 -Question Regarding Licensee Compliance with Code Relief Valve Requirements. I have reviewed this input and have determined it is ready for distribution to the licensee and dissemination to the publi Attachment: Input to Inspection Report 50-346/04-02 CONTACT: M. Holmberg, DRS (630) 829-9748 DOCUMENT NAME: ML040540581.wpd receive mo a copy of this document. Indicate In the box: 'C' * Copy without attachmentfenclosure 'E' * Copy with attachment/enclosure 'N' No copy OFFICE Rill N RIII IN I NAME MHolmberg:tr DHills DATE 02/18/04 02/22/04 OFFICIAL RECORD COPY A"'
Cover Letter X Input below, no findings of significance were identifie Title Page Inspector: M. Holmberg, Reactor Inspector SUMMARY OF FINDINGS Modify second paragraph as follows:
The inspections were conducted by resident and inspectors based in the NRC Region III office. Inspector-Identified and Self-Revealed Findingqs None. Licensee-Identified Violations None. OTHER ACTIVITIES 4OA2 Identification and Resolution of Problems (71152)
.1 (Closed) URI 05000346/2002014-06: Question Regarding Licensee Compliance with Code Relief Valve Requirement In November of 2002, the NRC identified a concern for potentially inadequate over-pressure (OP) protection for the containment air coolers (CACs), decay heat removal (DHR) coolers, emergency diesel generator jacket water (EDGJW) heat exchangers and associated system piping. For example, the NRC had questioned the use of locked open valves between the relief valve and the Code components requiring relief protection with respect to meeting the American Society of Mechanical Engineers (ASME) Code requirements for positive controls and interlocks on stop valve On January 23, 2004, the inspectors completed an on-site inspection of this concern focused on the location of the system relief valves to ensure OP protection was provided for the CACs, EDGJW heat exchangers and DHR coolers under operating/design basis conditions. The inspectors discussed the specific requirements and system configurations associated with OP protection with NRC staff in the Office of Nuclear Reactor Regulation and no concerns for Code compliance were identified. Specifically, the inspectors confirmed that:
The EDGJW coolers and CACs were not Code stamped vessels and thus did not have component level design requirements governing OP protection. The
OP protection for the CACs was provided by pressure relief devices for the service water system in which the CACs were installe * The DHR coolers were Code stamped vessels, which had component level OP protection requirements from the original design Code (ASME Code, Section III and Section VIII, 1968 Edition). The inspectors confirmed that the configuration and location of the system OP protection devices was consistent with these requirement * For the component cooling water, service water and decay heat removal piping systems which contained these components, the applicable design Code was the ASME Code, Section III, 1971 Edition. This design Code contained specific requirements associated with the location, capacity and types of relief protection required. The inspectors confirmed that the configuration and location of the system OP protection devices was consistent with these requirements for the piping sections containing these component For these systems and components, the licensee had not produced a written document that explicitly identified how the applicable OP protection requirements from the design Codes were implemented. The inspectors were concerned that without an explicit written OP protection record, changes in plant operating lineups or system components could render the Code OP protection strategy ineffective and result in damaged equipment. Based upon this observation, the licensee implemented corrective actions (CR 04-00582) to document the OP protection strategy for these systems and components in controlled safety-related calculation The inspectors did not identify any normal or emergency operating system configurations or lineups that would result in isolating the CACs, EDG JW coolers and DHR coolers from OP protection devices, without considering these components and associated piping systems inoperable. Further, no deviations from applicable Code requirements were identified with respect to location of relief protection devices for these components. This URI is closed.
4OA6 Meetings
.2 Interim Exit Meetings An interim exit meeting was conducted for:
Closure of URI 50-346/02-014-06 with Mr. B. Allen on January 23, 2004
KEY POINTS OF CONTACT Licensee B. Allen, Plant Manager J. Grabnar, Manager, Design Engineering P. Mahoney, Design Engineerin LIST OF ITEMS OPENED CLOSED AND DISCUSSED Open None Closed 50-346/02-014-06 URI Question Regarding Licensee Compliance with Code Relief Valve Requirements.
Discussed None LIST OF DOCUMENTS REVIEWED 40A2 Problem Identification and Resolution Condition Report 04-00161; CAC Outlet Valves; dated January 6, 2004 Condition Report 03-10371; Various Containment Air Cooler Related Equipment; dated December 1, 2003 Condition Report 03-06837; Various; dated August 22, 2003 Condition Report 02-07640; No ASME Code Review Documented; dated October 8, 2002 Condition Report 02-06860; Various Heat Exchangers; dated September 27, 2002 PCAQR 88-0737; ASME Code Relief Protection; dated September 20,1988 SE-95-0056; Removal of Containment Air Cooler Relief Valves; dated July 3, 1995 OS-020 Sh 1; Operational Schematic Service Water System; Revision 64 OS-020 Sh 2; Operational Schematic Service Water System; Revision 33 OS-004 Sh 1; Operational Schematic Decay Heat Removal Low Pressure Injection System; Revision 36
OS-004 Sh 2; Operational Schematic Decay Heat Removal Low Pressure Injection System; Revision 04 OS-021 Sh 1; Operational Schematic Component Cooling Water System; Revision 31 OS-021 Sh 2; Operational Schematic Component Cooling Water System; Revision 21 OS-021 Sh 3; Operational Schematic Component Cooling Water System; Revision 9 OS-041 Sh 1; Operational Schematic Emergency Diesel Generator Systems; Revision 19 DB-OP-06316; Diesel Generator Operating Procedure; Revision 12 DB-OP-06012; Decay Heat and Low Pressure Injection System Operating Procedure; Revision 16 DB-OP-06016; Containment Air Cooling System Procedure; Revision 13 DB-OP-06262; Component Cooling Water System Procedure; Revision 7 DB-OP-02000; RPS, SFAS, SFRS Trip, or SG Tube Rupture; Revision 12 EWR 02-0343-00; Containment Air Cooler Upgrades; dated June 7, 2003 UFSAR Change Notice 97-073; Code Discrepancies; dated July 31, 1992 Specification No. 7749-M-400; Technical Specification for Containment Air Cooler Units; dated February 22, 1977 Specification No. 1024/1069; Heat Exchangers for Auxiliary System Service; dated November 14,1968 Specification No. M-200; Piping Classes; Revision 6 Drawing M-033; Decay Heat Removal System and Emergency Core Cooling Systems; Revision 21 Drawing M-033B; Decay Heat Removal Train 1; Revision 43 Drawing M-033C; Decay Heat Removal Train 2; Revision 19 Drawing M-0368; Component Cooling Water System; Revision 31 Drawing M-036; Component Cooling Water System; Revision 15 Drawing M-041; Service Water System; Revision 18 Drawing M-041 C; Service Water System for Containment Air Coolers; Revision 24
LIST OF ACRONYMS USED ADAMS Agencywide Document Access and Management System ASME American Society of Mechanical Engineers CAC Containment Air Cooler CCW Component Cooling Water CR Condition Report DHR Decay Heat Removal EDGJW Emergency Diesel Generator Jacket Water OP Over-pressure URI Unresolved Item
