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Category:Memoranda
MONTHYEARML22147A0932022-06-0606 June 2022
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Cancelling Numerous Inspection Report Numbers
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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)
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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
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5/13/2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Cooper Nuclear Station and Fort Calhoun Station, Unit 1
ML13346A0822013-12-12012 December 2013
Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Cooper Nuclear Station and Fort Calhoun Station, Unit 1
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Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors
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06/26//2013 Notice of Public Meeting with Nebraska Public Power District to Discuss Progress and Status Plans for Addressing Substantive Cross-Culting Issues in the Areas of Human Performance and Problem Identification and Resolution
ML12340A2682012-11-27027 November 2012
CNS Memo DED12-0003 Response to 10 CFR 50.54(f) Section 2.3 Seismic, Enclosing Engineering Evaluation 12-E18, Revision 0
ML11250A1712011-09-14014 September 2011
Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs)
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Notice of Meeting with Nebraska Public Power District to Discuss Cooper'S Request to Revise TS 3.4.3, Safety/Relief Valves (Srvs) and Safety Valves (Svs), to Reduce Number of Required SRVs for Overpressure Protection
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Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors
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Notice of Forthcoming Meeting with Nebraska Public Power District to Discuss Future License Amendment Request for Cooper Nuclear Station Related to TSTF-493, Revision 4, Clarify Application of Setpoint Methodology for LSSS Functions
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S. Wastler Memo Technical Assistance Request - Review of Proposed Amendment to the Cooper Power Station Physical Security Plan (TAC L24478)
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ACRS Review of the Cooper Nuclear Station, License Renewal Application Safety Evaluation Report
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the Nuclear Regulatory Commission Staff Spot-Checks Review of Cooper Nuclear Station June 30, 2010 - Finding of No Potential Issues in Bank Statements
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Summary of Telephone Conference Call Held on May 18, 2010, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper Nuclear Station Lic
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Federal Register Notice Regarding the ACRS Subcommittee Meeting on Plant License Renewal, May 5, 2010
ML1006903852010-04-0606 April 2010
Advisory Committee on Reactor Safeguards Review of the Cooper Nuclear Station License Renewal Application - Safety Evaluation Report with Open Items
ML1007700292010-03-24024 March 2010
04/07/2010 Notice of Forthcoming Meeting to Discuss the Draft Supplemental Environmental Impact Statement for the License Renewal of Cooper Nuclear Station
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Ltr to William Maier, State Liaison Officer from State of Missouri, Department of Natural Resources, Dated 12/23/2009
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Cy 2009 Baseline Inspection Completion
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Summary of Telephone Conference Call Held on 1/8/2010, Between the U.S. NRC and Nebraska Public Power District Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper Nuclear Station
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November 9, 2009, Summary of Telephone Conference Call Held on Between NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information for Cooper License Renewal
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09/21/2009-Summary of Telephone Conference, Between USNRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to RAI, for Cooper Nuclear Station License Renewal
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Summary of Telephone Conference Call Held on October 5, 2009, Between the NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information, for CNS LRA
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Summary of Telephone Conference Call Held on 09/14/09, Between the U.S. NRC Staff and NPPD, Related to a Request for Additional Information (RAI) and Clarification for Certain Responses to Rais, for Cooper Nuclear Station License Renewal
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Summary of Telephone Conference Call Held on 9/17/09, Between the NRC and Nebraska Public Power District, Related to a Clarification for Certain Responses to Requests for Additional Information, for Cooper Nuclear Station License Renewal
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09/02/09 Summary of Telephone Conference Call Between NRC Staff and NPPD, Related to a Clarification for Certain Responses to Requests for Additional Information, for Cooper Nuclear Station License Renewal
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07/07/2009 Meeting Summary, Telephone Conference Call Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Requests for Additional Information, for Cooper Nuclear Station License Renewal
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Summary of Tele Conf Call with Nebraska Public Power Districts to Discuss Clarifications for the Severe Accident Mitigation Alternative Documented in the NRC Request for Additional Information Letter Dated May 1, 2009
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Summary of Telephone Conference Call Held on June 16, 2009, Between the NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Requests for Additional Information, for Cooper Nuclear Station License Renewal
ML0920303052009-07-29029 July 2009
Summary of Telephone Conference Call Held on 7/9/2009, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification for Certain Requests for Additional Information, for Cooper Nuclear Station License Renewal
ML0915900222009-06-11011 June 2009
Summary of Teleconference Held on 5/27/09, Between the U.S. NRC Staff and Nebraska Public Power District, Related to a Clarification on Certain RAIs (RAI 3.3.2.2.3.3-1, RAI 3.3.2.2.7.3-1, and RAI 3.3.2.2.7.3-2), for Cooper License Renewal
ML0915604962009-06-10010 June 2009
Summary of Telephone Conference Call Held on May 20, 2009, Between the USNRC Staff and NPPD, Related to a Clarification on Certain RAI (RAI B.1.15-3 and RAI B.1.15-4), for CNS Renewal
ML0909704142009-04-30030 April 2009
Summary of Site Audit Related to the Review of the License Review Application for Cooper Nuclear Station, Unit 1
ML0909103082009-04-14014 April 2009
Summary of Public Environmental Scoping Meeting Related to the Review of the Cooper Nuclear Station, Licensed Renewal Application
ML1008803542009-03-0909 March 2009
CN -2009-09- Public Forms
ML0810900022008-04-22022 April 2008
Summary of Telephone Conference Verbal Authorization for Cooper Relief Request RI-35
ML0807400842008-03-14014 March 2008
Draft Regulatory Guide for Comment
ML0707302142007-03-13013 March 2007
Inaccuracy in Response to the Request for Additional Regarding Crediting Service Water for Reactor Equipment Cooling Post Loss-of-Coolant Accident - Cooper
2022-06-06
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Text
November 4, 2005 MEMORANDUM TO: John Hanna, Senior Resident Inspector Division of Reactor Projects FROM: Kriss M. Kennedy, Chief, Projects Branch C /RA/
Division of Reactor Projects
SUBJECT:
SPECIAL INSPECTION CHARTER TO EVALUATE SERVICE WATER EVENT AT COOPER NUCLEAR STATION In response to an event that led to the inoperability of the service water system at Cooper Nuclear Station on October 20, 2005, a Special Inspection is being chartered. You are hereby assigned to conduct the Special Inspection. Nick Taylor, Resident Inspector, Cooper Nuclear Station, has been assigned to assist you during this inspection.
A. Basis On October 20 at 9:09 a.m. with service water Pumps A, B, and C running, operators started service water Pump D. Following the start of service water Pump D, at 9:10 a.m., the control room operators received a high differential pressure alarm on service water Strainer B followed by a high differential pressure alarm on service water Strainer A. Both service water cross-connect valves (SW-MO-36/37) closed on low service water header pressure. Operators observed that the service water header pressure in Loop A was approximately 42 psig and 15-20 psig in Loop B. The differential pressure across Service Water Strainer A peaked at 20 psid and recovered in approximately 3 minutes following the automatic initiation of strainer backwash. The differential pressure across service water Strainer B peaked at 20.9 psid; however, the automatic initiation of backwash did not result in a sufficient decrease in differential pressure and operators bypassed the strainer. Following these actions, the service water system header pressures returned to normal. During the event, operators declared both loops of service water inoperable due to exceeding the strainer differential pressure structural integrity limit of 15 psid. With both loops of service water inoperable, operators declared both emergency diesel generators inoperable.
The high differential pressure across the strainers was the result of debris (small rocks) which was introduced into the service water system following the start of service water Pump D. The high debris loading clogged the strainers. Cooper Nuclear Station experienced a similar event in November 2004 and has experienced other challenges to the proper operation of the service water system resulting from debris over the last several years.
Management Directive 8.3, NRC Incident Investigation Program, was used to evaluate the level of NRC response for this event. In evaluating the deterministic criteria of MD 8.3, it was determined that introduction of debris into the service water system involved repetitive failures or events involving safety-related equipment or deficiencies in operations. Since the deterministic criteria was met, the service water event was
John Hanna evaluated for risk. The preliminary Estimated Conditional Core Damage Probability was determined to be between 2.0E-6 and 2.0E-5. In accordance with MD 8.3, the results of the risk assessment indicates that NRC response to this event falls between the overlap region to conduct a Special Inspection and no additional inspection, and the region that requires a Special Inspection.
Region IV has reviewed the results of the MD 8.3 evaluation and determined that a Special Inspection is warranted. Based on previous inspections of these issues, and inspection that has occurred since the October 20 event, the following specific concerns have been identified that warrant further inspection and assessment:
- The timeliness and adequacy of corrective actions that Cooper Nuclear Station has already implemented or plans to implement to correct the cause of these events;
- The adequacy of Cooper Nuclear Stations interim compensatory measures to prevent challenges to the service water system while the longer term corrective actions are being implemented; and
- The assumptions and basis used by the licensee to evaluate the ability of the service water system to continue to meet design requirements.
This Special Inspection is chartered to identify the circumstances surrounding this event, determine if the licensees long-term corrective actions are timely and adequate, and to determine if the licensees interim compensatory actions are adequate.
B. Scope The inspection is expected to perform data gathering and fact-finding in order to address the following:
- 1. Develop a complete description of the service water event that occurred on October 20, 2005, and a complete sequence of events, including operator and system response, related to the event.
- 2. Develop a list of similar challenges to the service water system resulting from debris and actions taken by the licensee to correct the problem.
- 3. Identify and evaluate the adequacy and timeliness of the licensees long-term corrective actions established prior to the event on October 20, 2005, and any changes following the event, to address the adverse impact of debris on the service water system.
- 4. Identify and evaluate the adequacy of the licensees compensatory measures established prior to and following the event on October 20, 2005, to address the adverse impact of debris on the service water system.
John Hanna 5. Identify and assess additional actions planned by the licensee in response to this event, including the timeline for their completion of these actions.
- 6. Evaluate the assumptions and basis used by the licensee to determine the ability of the service water system to continue to meet design requirements.
- 7. Assess the impact that the increased debris loading, and operation of the service water system with one or more strainers bypassed, has had on safety-related equipment cooled by service water.
- 8. Identify the changing conditions that have resulted in the increase in service water system debris loading in recent years.
- 9. Compare the results of your inspection with the licensing and design basis for Cooper Nuclear Station.
- 10. Evaluate pertinent industry operating experience to the event, including the effectiveness of any action taken in response to the operating experience.
- 11. Determine if there are any generic issues related to the service water event.
Promptly communicate any potential generic issues to regional management.
- 12. Assess the safety significance of any inspection findings.
C. Guidance Inspection Procedure 93812, "Special Inspection," provides additional guidance to be used by the Special Inspection Team. Your duties will be as described in Inspection Procedure 93812. The inspection should emphasize fact-finding in its review of the circumstances surrounding the event. It is not the responsibility of the team to examine the regulatory process. Safety concerns identified that are not directly related to the event should be reported to the Region IV office for appropriate action.
You will formally begin the special inspection with an entrance meeting to be conducted no later than November 7, 2005. The inspection will include a review of the results of the licensees root cause analysis. You should brief Region IV management during the course of your inspections and prior to your exit meeting. A report documenting the results of the inspection should be issued within 30 days of the completion of the inspection.
This Charter may be modified should you develop significant new information that warrants review. Should you have any questions concerning this Charter, contact me at (817) 860-8144.
John Hanna cc via E-mail:
B. Mallett T. Gwynn J. Dixon-Herrity, OEDO A. Howell D. Chamberlain A. Vegel K. Kennedy V. Dricks W. Maier W. Walker D. Terao, NRR B. Benney, NRR
John Hanna SISP Review Completed: ___KMK_____ ADAMS: / YesG No Initials: _KMK___
/ Publicly Available G Non-Publicly Available G Sensitive / Non-Sensitive S:\DRP\DRPDIR\CHARTER\CNS Service Water Special Inspection.wpd RIV:SPE:DRP/C C:DRP/D WCWalker KMKennedy KMK for /RA/
11/4/05 11/4/05 OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
