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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20205B6111999-03-26026 March 1999 Notification of 990419 Meeting with Util in Rockville,Md to Discuss Licensing Issues at Plant,Including Racking of Cask Pit for Storage of Spent Fuel ML20153F7981998-09-23023 September 1998 Forwards NRC Operator Licensing Exam Rept 50-346/98-301OL, (Including Completed & Graded Tests) for Tests Administered on 980803-07 ML20153F8291998-09-23023 September 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered During Wk of 980803 ML20236F3581998-06-26026 June 1998 Forwards NRC Insp Mc 0350, Staff Guidelines for Restart Approval, for Oversight Activities for Davis Besse Station ML20236N8641998-06-11011 June 1998 Discusses TS Interpretation on Application of Davis Besse TS 3.6.5.1 & 3.6.5.2.TB Branch Recommends That Davis Besse Consider Converting TS to Improved Standard TS ML20216F3291998-04-13013 April 1998 Accepts 980406 Licensee Request for Approval to Install machine-welded SG Tube Plugs in Accordance W/Provisions of Paragraph IWB-4230, Tube or Tubesheet Hole Plugging by Fusion Welding, of Section XI ML20202E6241997-11-26026 November 1997 Notification of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Assurance Program at Davis-Besse ML20211Q4711997-10-16016 October 1997 Notification of 971113 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Ultimate Heat Sink at Davis-Besse ML20211B5561997-09-23023 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970707-11 ML20211C5091997-09-23023 September 1997 Forwards NRC Operator Licensing Exam Rept 50-346/97-308OL (Including as-given Writtem Exam) for Tests Administered on 970707-10 ML20149E7411997-07-16016 July 1997 Notification of 970821 Meeting W/Util in Rockville,Md to Discuss Instrument Drift Study ML20137U2051997-04-14014 April 1997 Informs That Davis-Besse Nuclear Power Station Nuclear Assurance Dept Will Be Reorganized Into Two Separate Dept; DB Nuclear Assurance & DB Nuclear Support Svc,Effective, 970414 ML20136F9491997-03-13013 March 1997 Notification of 970403 Meeting W/Util in Rockville,Md to Discuss Progress on Thermo-Lag Issue Resolution ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20134P9011996-11-26026 November 1996 Notification of 961204 Meeting W/Clei & Teco in Rockville,Md to Discuss Potential Submittals Concerning Proposed Merger of Centerior Energy Co & Oec ML20149E8161994-08-0202 August 1994 Forwards Fr Notice of License Amend Requests Proposed Merger of Toledo Edison Co & Cleveland Electric Illumianting Co Antitrust Determination ML20059H8361994-01-19019 January 1994 Notification of 940201 Meeting W/Util in Rockville,Md to Discuss Pending Davis-Besse Licensing Actions ML20057F1311993-10-0707 October 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Davis-Besse Implementation of Reg Guide 1.97 for Steam Generator Pressure Instruments ML20127N6121993-01-25025 January 1993 Notification of 920205 Meeting W/Util in Rockville,Md to Discuss Emergency Action Levels Proposed Rev,Submitted 930112 ML20127C0411993-01-0808 January 1993 Notification of 930112 Meeting W/B&W Owners Group in Clearwater Beach,Fl to Discuss Generic Program Plan for License Renewal Initiative ML20127F5461993-01-0707 January 1993 Notification of 930115 Meeting W/Util in Rockville,Md to Discuss Plant Containment Penetration Bellows Tests.Draft Agenda Encl ML20126F5541992-12-0808 December 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Proposed License Amend to Change from Automatic to Manual Closure of Containment Purge & Exhaust Valves in Mode 6 ML20128C2071992-11-0606 November 1992 Notification of 921202 Meeting W/Util in Rockville,Md to Discuss Upcoming Refueling Outage Plans & Recent Plant Performance ML20127C4131992-07-24024 July 1992 Responds to 910322 Memo Requesting Assistance on Whether 10CFR50.59 Review Should Have Been Performed for Broken Pipe in Station Drainage & Discharge Sys Releasing low-level Radioactivity Onsite ML20059D2711990-08-0606 August 1990 Discusses Review of State of Oh & Local Radiological Emergency Response Plans.Determined That No Issues Identified During 890809-09 Exercise to Prevent Finding of Reasonable Assurance for Site ML20148T1891990-04-10010 April 1990 Responds to Request for Info Re Congressional Inquiries on Tracking & Closeout of Issues Raised Re Incident Investigation Team (IIT) Investigations of Plants.Actions Assigned by EDO in Response to Plant IITs Addressed ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20246N8091989-08-30030 August 1989 Notification of 890907 Meeting W/Util in Rockville,Md to Discuss Exemption from App R to 10CFR50 for Specific Configuration of Pressurizer Instrumentation ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20244A4611989-06-0606 June 1989 Notification of 890615 Meeting W/Util & Westinghouse Owners Group in Rockville,Md to Discuss Reactor Vessel Support Embrittlement ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl ML20244A5571989-04-10010 April 1989 Notification of 890502 Meeting W/Util in Rockville,Md to Discuss Nonlinear Piping Analysis to Remove Snubbers & Pipe Supports ML20244A5461989-04-10010 April 1989 Notification of 890503 Meeting W/Util in Rockville,Md to Discuss Using Leak Before Break Methodology on Lines Connected to RCS 1999-03-26
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20205B6111999-03-26026 March 1999 Notification of 990419 Meeting with Util in Rockville,Md to Discuss Licensing Issues at Plant,Including Racking of Cask Pit for Storage of Spent Fuel ML20153F7981998-09-23023 September 1998 Forwards NRC Operator Licensing Exam Rept 50-346/98-301OL, (Including Completed & Graded Tests) for Tests Administered on 980803-07 ML20153F8291998-09-23023 September 1998 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered During Wk of 980803 ML20236F3581998-06-26026 June 1998 Forwards NRC Insp Mc 0350, Staff Guidelines for Restart Approval, for Oversight Activities for Davis Besse Station ML20236N8641998-06-11011 June 1998 Discusses TS Interpretation on Application of Davis Besse TS 3.6.5.1 & 3.6.5.2.TB Branch Recommends That Davis Besse Consider Converting TS to Improved Standard TS ML20216F3291998-04-13013 April 1998 Accepts 980406 Licensee Request for Approval to Install machine-welded SG Tube Plugs in Accordance W/Provisions of Paragraph IWB-4230, Tube or Tubesheet Hole Plugging by Fusion Welding, of Section XI ML20202E6241997-11-26026 November 1997 Notification of 971215 Meeting W/Util in Rockville,Md to Discuss Quality Assurance Program at Davis-Besse ML20211Q4711997-10-16016 October 1997 Notification of 971113 Meeting W/Toledo Edison Co in Rockville,Md to Discuss Ultimate Heat Sink at Davis-Besse ML20211B5561997-09-23023 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970707-11 ML20211C5091997-09-23023 September 1997 Forwards NRC Operator Licensing Exam Rept 50-346/97-308OL (Including as-given Writtem Exam) for Tests Administered on 970707-10 ML20149E7411997-07-16016 July 1997 Notification of 970821 Meeting W/Util in Rockville,Md to Discuss Instrument Drift Study ML20137U2051997-04-14014 April 1997 Informs That Davis-Besse Nuclear Power Station Nuclear Assurance Dept Will Be Reorganized Into Two Separate Dept; DB Nuclear Assurance & DB Nuclear Support Svc,Effective, 970414 ML20136F9491997-03-13013 March 1997 Notification of 970403 Meeting W/Util in Rockville,Md to Discuss Progress on Thermo-Lag Issue Resolution ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20134P9011996-11-26026 November 1996 Notification of 961204 Meeting W/Clei & Teco in Rockville,Md to Discuss Potential Submittals Concerning Proposed Merger of Centerior Energy Co & Oec ML20149E8161994-08-0202 August 1994 Forwards Fr Notice of License Amend Requests Proposed Merger of Toledo Edison Co & Cleveland Electric Illumianting Co Antitrust Determination ML20059H8361994-01-19019 January 1994 Notification of 940201 Meeting W/Util in Rockville,Md to Discuss Pending Davis-Besse Licensing Actions ML20057F1311993-10-0707 October 1993 Notification of 931020 Meeting W/Util in Rockville,Md to Discuss Davis-Besse Implementation of Reg Guide 1.97 for Steam Generator Pressure Instruments ML20127N6121993-01-25025 January 1993 Notification of 920205 Meeting W/Util in Rockville,Md to Discuss Emergency Action Levels Proposed Rev,Submitted 930112 ML20127C0411993-01-0808 January 1993 Notification of 930112 Meeting W/B&W Owners Group in Clearwater Beach,Fl to Discuss Generic Program Plan for License Renewal Initiative ML20127F5461993-01-0707 January 1993 Notification of 930115 Meeting W/Util in Rockville,Md to Discuss Plant Containment Penetration Bellows Tests.Draft Agenda Encl ML20126F5541992-12-0808 December 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Proposed License Amend to Change from Automatic to Manual Closure of Containment Purge & Exhaust Valves in Mode 6 ML20128C2071992-11-0606 November 1992 Notification of 921202 Meeting W/Util in Rockville,Md to Discuss Upcoming Refueling Outage Plans & Recent Plant Performance ML20127C4131992-07-24024 July 1992 Responds to 910322 Memo Requesting Assistance on Whether 10CFR50.59 Review Should Have Been Performed for Broken Pipe in Station Drainage & Discharge Sys Releasing low-level Radioactivity Onsite ML20059D2711990-08-0606 August 1990 Discusses Review of State of Oh & Local Radiological Emergency Response Plans.Determined That No Issues Identified During 890809-09 Exercise to Prevent Finding of Reasonable Assurance for Site ML20148T1891990-04-10010 April 1990 Responds to Request for Info Re Congressional Inquiries on Tracking & Closeout of Issues Raised Re Incident Investigation Team (IIT) Investigations of Plants.Actions Assigned by EDO in Response to Plant IITs Addressed ML20055C3521990-02-26026 February 1990 Notification of 900305 Meeting W/Util in Rockville,Md to Discuss Status of Licensing Activities for Facility ML20248E9391989-09-29029 September 1989 Forwards AEOD Technical Review Rept on Debris in Containment Recirculation Pumps.No Occurrences Found to Involve Actual Accumulation of Debris in Containment Sumps.Immediate Corrective Actions Completed ML20248C8311989-09-20020 September 1989 Request for Hearing by Alchemie.* Forwards Response & Request for Hearing,In Response to NRC 890818 Order Modifying License & Order to Show Cause Why Licenses Should Not Be Revoked,For Appropriate Action ML20247H9261989-09-0909 September 1989 Advises That SALP Meeting for Facilities Scheduled for 891115.Assessment Input Should Be Submitted by 891016 ML20246N8091989-08-30030 August 1989 Notification of 890907 Meeting W/Util in Rockville,Md to Discuss Exemption from App R to 10CFR50 for Specific Configuration of Pressurizer Instrumentation ML20245E8501989-08-0707 August 1989 Advises of Reassignments in Project Mgt Duties Due to Recent Reorganization of Standardization & Life Extension Project Directorate ML20245H6451989-08-0404 August 1989 Requests Closure of Outstanding Action Item 87-0198,per 870617 Request Re Review & Evaluation of Acceptability of Fairbanks-Morse Diesel Generator Bearings.Action Completed W/Submittal of Transfer of Lead Responsibility to NRR ML20248D1431989-07-27027 July 1989 Forwards Proposed Generic Ltr Requesting Voluntary Licensee Participation in ERDS & Requests That Proposed Generic Ltr Be Sent to All Licensees of Power Reactors,Except for Participants & Licensees of Listed Plants ML20247B7541989-07-19019 July 1989 Confirms That Licensee 880711,890221 & 0630 Responses to NRC Bulletin 88-004, Potential Safety-Related Pump Loss, Acceptable.Licensing Action for TACs 69886,69887,69893 & 69894 Considered Complete ML20247E6721989-07-17017 July 1989 Proposes Closeout of Plant Correspondence Control Ticket Re Environ Conservation Organization Request for Notification Whenever License Amend Requests Result in Impairment of Plant Operability.Intervenor Will Be Placed on Svc List ML20246K5991989-07-12012 July 1989 Notification of 890725 Meeting W/Util in Birmingham,Al to Discuss Status of Current Licensing Activities & Corporate Initiatives for Plants.Meeting Agenda Encl ML20246L6801989-07-10010 July 1989 Notification of Significant Licensee Meeting 89-101 W/Util on 890718 in King of Prussia,Pa to Discuss Util Engineering Reorganization ML20247A9561989-07-0606 July 1989 Notification of 890717 Meeting W/Lead Plant Utils in Rockville,Md to Discuss Implementation of Revised STS ML20246D8841989-06-19019 June 1989 Staff Requirements Memo Re 890601 Briefing on Operating Reactors & Fuel Facilities in Rockville,Md.Commission Expressed Disappointment in Long Term Operating Performance of Turkey Point Nuclear Power Plant ML20244A4611989-06-0606 June 1989 Notification of 890615 Meeting W/Util & Westinghouse Owners Group in Rockville,Md to Discuss Reactor Vessel Support Embrittlement ML20246H3771989-05-12012 May 1989 ALAB-913.* Advises That Time Provided within Which Commission May Act to Review Aslab Decision ALAB-913 Expired.Commission Declined Review.Decision Became Final on 890501.W/Certificate of Svc.Served on 890512 ML20246P9601989-05-10010 May 1989 Discusses 890413 Meeting W/Rosemount & Industry Re Malfunctions of Rosemount Transmitters.List of Attendess, Agenda,Nrc Info Notice 89-042 & Viewgraphs Encl NUREG-1353, Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-13531989-05-0202 May 1989 Board Notification 89-003:forwards Listed Documents Re Spent Fuel Pool Accidents for Resolution of Generic Issue 82, Beyond DBA in Spent Fuel Pools, Including NUREG-1353 ML20245E9781989-04-17017 April 1989 Forwards Regulatory History AC83-2 Re Licensee Action During Natl Security emergency,10CFR50 (54FR7178) ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20244E2681989-04-12012 April 1989 Summary of Operating Reactors Events Meeting 89-015 on 890412.Discussion of Events,List of Attendees & Three Significant Items Identified for Input Into NRC Performance Indicator Program & Summary of Reactor Scrams Also Encl 1999-03-26
[Table view] |
Text
l o ur \
'o UNITED STATES g
U[ o NUCLEAR REGULATORY COMMISSION O p WASHINGTON, D. C. 20555
% . . . . . ,o! February 19, 1986 MEMORANDUM FOR: Judge James P. Gleason, Chairman Ad Hoc Review Group on the Davis-Besse Incident FROM: Victor Stello, Jr.
Acting Executive Director for Operations
SUBJECT:
INFORMATION FOR THE AD H0C REVIEW GROUP In connection with the Review Group's efforts to collect applicable reference materials and background information for use in its deliberations, I thought it might be useful to provide the enclosed package of documents, some of which you may not have. These documents generally reflect the efforts of the staff over a period of about 6 months (extending from August 1985 to February 1986) to reflect upon and review from a generic standpoint the potential lessons which may be derived from the June event at Davis-Besse. You will note that the preliminary insights trom the December Rancho Seco event are starting to be reflected in the more recent staff activities.
If we can be of further assistance in support of the Review Group's efforts, please do not hesitate to call upon us.
A ctor tello, '.
Acting Executi e Director for Operations
Enclosure:
Documents t
4 0 3 9 Y DJ3
/
i "
L kEB 211986 f'o
/
Mr. Hal B. Tucker, Chairman B&W Owners Group Executive Comittee Suite 220 7910 Woodmont Avenue Bethesda, Maryland 20814
Dear Mr. Tucker:
I am responding to your letter dated January 27,.1986 that provided comments by the Babcock & Wilcox Owners Group regarding the NRC's Incident Investigation Program (IIP). You provided comments and endorsed the equipment quarantining concerns expressed in a letter from the Westinghouse Owners Group dated January 9, 1986.
I appreciate the concerns raised by the Westinghouse Owners Group, and I have -
taken actions to ensure that the impact of quarantining equipment is minimized
' and the control of quarantined equipment does not interfere with the basic authority and responsibility of the licensee. My letter to the Westinghouse Owners Group is enclosed for your information. In this letter, I describe the concept of quarantining equipment that will be included in the IIP procedures.
Your letter provided additional comments concerning the determination of root causes of significant prcblems associated with the quarantined equipment. We certainly encourage your Group's initiatives to develop guidance addressing the key elerrents of an effective and practical root-cause determination process.
The results of your activity should be of real benefit to industry as an aid in determining the root causes of significant operating events in a systematic manner whether or not an IIT is involved.
I welcome support by the Owners Groups in assuring that the IIP procedures are practical, effective and clear. I also agree with your suggestion that further information exchange between our organizations is desirable. As noted in my letter to the Westinghouse Owners Group, we plan to conduct workshops in each Region this fall in order to solicit comments and suggestions on the IIP procedures. Further, we hope to obtain industry participation in the investiga-tive process, and we should discuss how best to achieve this goal. Thus, I have asked Jack Heltemes, who administers the IIP, to contact you and schedule a meeting at a mutually convenient time for further discussions.
I ynowoy:
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[s m%, UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20555 y
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JAN 2 91986 .
Mr. D. Hunter, Vice President Yankee Atomic Electric Company 1671 Worcester Road Framingham, MA 01701
Dear Mr. Hunter:
SUBJECT:
YOUR LETTER DATED JANUARY 9, 1986 PROVIDING COMMENTS BY THE WESTINGHOUSE OWNERS GROUP ON THE NRC'S INCIDENT INVESTIGATION -
PROGRAM We apprecidte very much the coments of the Westinghouse Owners Group on the NP.C's Incident Investigation Program (IIP). We appreciate your concern concerning the " quarantining" of equipment, and we share your objective to minimize the impact of the quarantined equipment on plant operations or restoration.
As Jack Heltemes discussed with you, our IIP concept limits the scope of quarantined equipment to that directly and significantly involved in the event.
Further, a*. all times the licensee can take any action involving quarantined i equipment deemed necessary to: achieve or maintain safe plant conditions, prevent further equipment degradation, or conduct testing or inspection activities required by the plant's technical specifications. The period of quarantining is to the point where the NRC agrees that the probable root cause of failure has been identified. The actual preparation of the troubleshooting l
procedure and the conduct of inspection, troubleshooting and corrective main-tenance activities is, of course, under the control of the licensee.
l As noted previously, it is our objective that the IIT procedures minimize any i schedular impact and disruption to the licensee's activities. We recognize that some impact may result, but we certainly do not wish to interfere with the basic authority and responsibility of the utility management.
I have directed AE00 to proceed with the development of procedures governing the conduct of NRC Incident Investigation Teams and to issue these procedures initially for trial use and comment. We would welcome the review and comment on these procedures by the Westinghouse Owners Group and other organizations.
Toward this end, I have asked that regional workshops be conducted to discuss the program and implementing procedures and to receive the reaction and comments from those involved with the process. We now estimate that these 4
workshops will be held this fall.
y(pOhDWhN ~
096 '
i ,
d Mr. D. Hunter '
Again, we appreciate your concerns. We look forward to receiving your comments on the interim procedures, but in the meantime, if a meeting would be l helpful, we would be pleased to get together with you. Please contact either myself or Jack Heltemes to arrange for a mutual convenient time.
Sincerely.
Original signed by 71ctor St ello ,.
Victor Stello, Jr. I Acting Executive Director for Operations e
1 @
5 l
Mr. Hal B. Tucker As you know, comments by the Owners Groups on NRC programs are cordially invited and I appreciate your interest and comments. If you should have additional comments, please feel free to contact me or Jack Heltemes (301/
492-4484).
Sincerely, Origina. s ,a*d by yiotot Stello Victor Stello, Jr.
Acting Ex'ecutive Director for Operations
Enclosure:
As stated
- DISTRIBUTION PDR AE0D CF AE0D SF V. Stello J. Roe T. Rehm J. Sniezek J. Taylor
, H. Denton
- ED0'.R/F73 M. Bridgers (ED0-1383)
C. J. Heltemes F. Hebdon W. Lanning K. Seyfrit K. Black IIS RF IIS SF FC :AEOD: IS :AE00: :EDO : : : :
JAME :WLan 1 g:cs :CJH temes :VStello : : : : ;
____:____________:____________:____________.____________.____________.____________.___________ j iATE :02//7/86
- 02/18f86 :02/ /86 : : : : i 0FFICIAL RECORD COPY
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- i. J
FEB 211986 MEMORANDUM FOR: Chairman Palladino Commissioner Roberts Commissioner Asselstine Commissioner Bernthal Commissioner Zech FROM: Victor Stello, Jr.
Acting Executive Director for Operations
SUBJECT:
STAFF REQUIREMENTS - MEMORANDUM FROM SECRETARY DATED JANUARY 23, 1986 RE: SEQUOYAH FUELS CORPORATION By memorandum dated January 23, 1986, from the Secretary, the Commission requested that the staff provide a plan for addressing the January 4,1986, event at the Sequoyah Fuels Corporation (SFC) facility at Gore, Oklahoma. The enclosure to this memorandum provides the plan. It describes the scope of tasks undertaken as a result of the event and includes projected completion dates, where available. For a few tasks, completion dates depend on the nature of findings in other tasks or on actions by others outside the NRC and cannot yet be projected with precision.
In addition to the plan, the January 23, 1986, memorandum from the Secretary requested answers to the following:
- 1. When the report of the site investigation team will be available and what the scope of the report will be.
Answer: See Item 1 of the plan.
- 2. Staff priorities and schedule for resolving issues at the site, including how and when will restart of the facility be decided.
Answer: The enclosed plan answers the question of priorities and schedules.
Item 6 of the plan treats the question of restart based on current information.
- 3. When staff believes they will be prepared to provide a follow-on briefing 1 for the Commission including lessons learned.
Answer: The staff believes an appropriate time to provide a status p briefing to the Commission would be in early March 1986 after
',Dy the Augmented Investigation Team completes its report, which is g
h[ projected for February 28, 1986. A subsequent briefing including lessons learned will be scheduled, if the Commission wishes, g D , ((f after the Lessons Learned Group completes its report, wh projected for late April 1986.
Ajt . .- .
y.
l 1
1 The Comissioners 2 l l
- 4. The staff recommendation on asking Kerr-McGee officials to brief the Comission.
Answer: The staff suggests that Kerr-McGee officials be available when the staff briefs the Comission in early March to provide information to the Comission as appropriate.
- 5. Information from the staff on whether there are any other federal or state agencies responsible for regulating the chemical hazard at the Sequoyah facility, and if so, what the responsibilities are.
Answer: See Item 5 of the plan.
In addition to the request for information from the Comission, the January 23, 1986, memorandum from the Secretary contained the following questions from Commissioners Asselstine and Bernthal.
Comissioner Asselstine requested:
- 1. Information on whether the Resource Conservation and Recovery Act provisions apply to the Sequoyah facility.
Answer: Wastes generated, treated, stored, or disposed of by SFC at its Gore, Oklahoma, facility that are not source, byproduct, or special nuclear material, are subject to the Resource Conservation and Recovery Act and the regulations of the State of Oklahoma since they are authorized by the Environmental Protection Agency to issue RCRA permits.
- 2. That the staff inform him as to whether the public and state and local officials were informed of the pending application for renewal of the Sequoyah facility's operatinn license prior to its September 1985 renewal.
Ar.swer: All informatice relating to SFC's application for license renet.al was made uailable to the public in the Local Public Document Room tt the Sa!Msaw City Library in Sallisaw, Oklahoma. Also, during the preparation of the Environmental Assessment (EA), relating to the renewal review, the staff and its contractor, Oak Ridge National Laboratory, met with appro-priate State officials to discuss environmental issues. Prior
- .0 the issuance of the t enmcd lieme, a Finding of No Significant Impact er.d n,tice of availability of the EA was published in thc Federal Regist_er.
Comissioner Bernthal requested:
- 1. Information on the normal free velame for the type of cylinder that ruptured during the event at the Sequoyah facility.
Answer: The normal free volume for a loadeo Model No. 48Y UF 6 cylinder is 7.1 ft3 TM s is bssed on a fill limit of 27,560 lbs. UF at 6
maximum 250 F (liquid density 203.3 lb/ft3) and a minimum certified internal volume of 142.7 ft8
The Commissioners 3
- 2. Information on whether the prohibition on heating the overfilled cylinder to remove excess uranium hexafluoride was in response to DOE's 1978 circular.
Answer: The 1978 circular to which Commissioner Bernthal refers is a revision of an earlier document titled, " Uranium Hexafluoride, Handling Procedures, and Container Criteria" (OR0 651), issued by the Atomic Energy Commission (AEC) in 1966. This earlier document also contained the prohibition against heating to remove excess weight from cylinders and was widely distributed throughout the industry, including Kerr-McGee. SFC also has in its possession the 1978 revision. It seems likely that the prohibition in the licensee's operating procedures against heating to remove excess weight in the cylinders has its origins in the 1966 AEC circular or its subsequent revisions.
Original Signed by
, Victor Stelig ,
Victor Stello, Jr.
Acting Executive Director for Operations
Enclosure:
As stated cc: OPE OGC SECY DISTRIBUTION NMSS 860087 BDalrymple JPartlow, IE RWilde JSniezek FC Central Files DBangart, RIV EHeumann DBMausshardt NMSS R/F RFonner, ELD CCudd WTCrow FCUF R/F JRoe HDenton, NRR VLTharpe TRehm, ELD JTaylor, IE RMinogue, RES Docket File 40-8027 BClausser GCunningham, ELD JGDavis PDR RMartin, RIV RECunningham LPDR Ncgg 3
- SEE PREVIOUS CONCURRENCE _ Revised per A0/ED0 2/19/86 1
0FC: *FC :*FC :*FCUF :* ELD :*RIV :*IE :*FC l NAME : B Da l rympl e/a s : RWi l de : WTCrow :RFonner :RBangart :JPartlow :DRChapell DATE:2/ /86 :2/ /86:2/ /86 :2/ /86 :2/ /86 :2/ /86 :2/ /86 0FC: *FC :*NMSS :*NMSS :E00 : : :
NAME:RECunningham:DBMausshardt:JGDavis:VStel)#: : :
______________.____________________________V_________ _____________..._____.
DATE:2/ /86 :2/ /86 :2/ /86:?/l//86: : : l l
OFFICIAL RECORD COPY
Staff Plans for Follow-on Tasks Resulting from the Sequoyah Fuels Corporation (SFC) Facility Accident on January 4, 1986
- 1. Report of Augmented Investigation Team (AIT) (Region IV)
The AIT is preparing a report which documents and describes the incident.
The report will present factual information and chronologies of events to describe the incident together with a qualitative description of the near-term response actions taken by Region IV and other agencies. The report is scheduled for February 28, 1986.
- 2. Report of Physical Cause of Cylinder Rupture (Region IV)
The staff with the assistance of experts from DOE contractors have preliminarily concluded, based on visual appearance, that the cause of the
, cylinder rupture was stress failure due to hydraulic pressure. SFC agreed to conduct the metallurgical analyses on the UF 6 cylinder at a private facility, that would be approved by NRC, in order to firmly establish the cause of cylinder failure. SFC submitted a plan for conducting the analyses on the cylinder, and this plan received final approval from Region IV on January 29, 1986. Battelle Laboratory has been selected to perform the analyses. Region IV, with an expert observer frota Lawrence Livermore Laboratory, will oversee the analysis conducted on the cylinder.
The preliminary metallurgical analysis results will be incorporated into the AIT Report to be completed February 28, 1986. The final report on the metallurgical analysis will be issued as a supplement to the AIT report or as a separate report.
- 3. Report on Assessment of Public Health Impacts (NMSS)
The initial meeting to establish the Ad Hoc Interagency task group for public health impacts was held on January 14, 1S86. In addition to NRC staff, membership in the task group includes representatives from the Environmental Protection Agency, Department of Energy, Center for Disease Control, University of Rochester, Oklahoma State Department of Health, EG&G, Oak Ridge National Laboratory, and Lawrence Livermore National Laboratory. The data collection was completed on January 31, 1986. A second meeting of the group took place on February 6 and 7,1986, to begin preparation of the assessment report. The first draft of the assessment is scheduled for February 14, 1986. The final report is scheduled for the week of March 3, 1986.
- 4. Coordination with the Department of Transportation (DOT) on the Adequacy of UF Cylinder as in a Low Specific Activity (LSA) container for transhort(NMSS)
The initial letter to DOT from NMSS was sent on January 14, 1986, on this subject. The letter provided a brief description of the UFg cylinder rupture and posed several questions as to the adequacy of L5A container requirements for safe transportation of UF . Requirements for LSA containers arebasedonradiologicalcharacteristics$fcontainercontent. The risk
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from UF6 is dominated by its chemical characteristics. DOT was requested to analyse the issue since UF is shipped from SFC under DOT regulations.
AverbalreplywasreceivedobJanuary 24, 1986, indicating that DOT had established a task group to examine the issues in the staff's January 14, 1986 letter. DOT staff has not yet indicated when they expect to complete their analysis, but it will probably not be until they review the report described in item 2.
- 5. Report on the Role of other Federal / State Agencies in Regulatory, Radiological, Chemical, and Industrial Safety at Nuclear Fuel Processing Facilities (IE)
Meetings with representatives from EPA, OSHA, and FEMA were held on i January 22, and 31, 1986. Points of contact were established to define '
understanding of present regulatory roles with respect to nuclear fuel processing facilities. IE plans to complete a report in April 1986 which describes agency roles, identifies problems, and outlines plans for resolution of problems should they exist.
- 6. Plan for Permitting Restart of the Sequoyah Fuels Facility (NMSS/IE/ Region IV)
The staff defines restart of the facility as resumption of UF production. The Sequoyah Fuels Corporation plan for restart ks expected in the latter part of February 1986. The date of restart, however, cannot be established at this time since it will depend not only on the licensee plan but also on findings contained in studies listed above as well as some possible requirements not yet established which the licensee will need to meet before startup. These requirements might include equip-ment modification, changes in operating procedures, operator training, etc.
- 7. Report on Lessons Learned (Region I - Chair, NMSS - Staff Administrative Support)
The draft memorandum directing the formation of a Lessons Learned group was sent to Office Directors and Regional Administrators requesting comments and concurrence on January 22, 1986. Members of the Lessons Learned Group have been identified. They consist of staff drawn from NRC organizations not directly involved with the SFC license. A final memorandum establishing the Lessons Learned Group will be issued shortly. The Group is expected '
to begin its work in mid-March as some of the reports listed above become l available and complete its analysis near the end of April when all the appropriate reports are available.
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