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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20196L0051999-07-0808 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Recently Signed Asset Purchase Agreement Between Illinois Power & Amergen Energy Co & Proposed Transfer of License to Be Submitted to NRC ML20206F2481999-04-22022 April 1999 Informs That Operational Readiness Insp Team Completed Insp at Clinton Power Station Including Two Weeks on Site & Two Separate Instances of Continuous 72 Hours Control Room Observation.Operational Performance Adequate ML20206F2361999-04-21021 April 1999 Documents Completion of Insp Activities Performed During Week of 990412,to Assess Licensee Implemented & Planned Corrective Actions Associated with NRC Manual Chapter 0350 Case Specific Checklist Restart Item II.1 ML20206F2331999-04-19019 April 1999 Discusses Results of Clinton Power Station Corrective Action Insp & Recommendations to Close Demand for Info Ltr.Insp Team Focused on Operations,Maintenance & Plant Support Organizations ML20205B8871999-03-26026 March 1999 Notification of 990415 Meeting with Utils in Knoxville,Tn to Visit Test Site & Discuss Test Program for ECCS Suppression Pool Suction Strainer.Context of Meeting Considered Entirely Proprietary ML20198S0601999-01-0606 January 1999 Notification of 990121 Meeting with Util to Discuss Potential Change to Clinton Degraded Voltage Relay Setpoints ML20154L1161998-10-14014 October 1998 Notification of 981027 Meeting with Util in Rockville,Md to Discuss Licensee Proposed Mod of keep-fill Sys for Feed Water Sys Check Valves to Eliminate Containment Leakage Concern ML20154J9271998-10-13013 October 1998 Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam Administered on 980901 ML20154J7921998-10-13013 October 1998 Forwards NRC Operator Licensing Retake Exam & Insp Rept 50-461/98-301(OL) Administered on 980901 ML20238F5861998-08-28028 August 1998 Notification of 980909 Meeting w/BWR/6S:EOI & Listed Utils in Rockville,Md to Discuss W/Nrc Planned Applications by Licensees to Reduce Operability Requirements During Refueling Outages ML20237E3131998-08-26026 August 1998 Forwards for Public Release,Info Re NRC SMM Held on 980714-15.Summary of January 1998 NRC SMM & Watch List Removal Evaluation Factors Also Encl ML20237D6711998-08-25025 August 1998 Notification of 980917 Meeting W/Util in Rockville,Md to Hold NRC Insp Manual Chapter 0350 Restart Panel Meeting W/Illinois Power to Discuss Progress of Clinton Power Station Toward Restart ML20217C9761998-03-24024 March 1998 Forwards NRC Operating Licensing Exam Rept 50-461/97-313OL (Including Completed & Graded Tests) for Tests Administered on 980126-0202 ML20217C9871998-03-24024 March 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered on 980126-0202 ML20197B6811998-03-0606 March 1998 Notification of 980319 Meeting W/Util in Rockville,Md to Discuss Licensee Proposed Fix for Issue of Degraded Electrical Grid Voltage ML20198R5561998-01-16016 January 1998 Notification of 980127 Meeting W/Illinois Power Co in Rockville,Md to Discuss Potential Fix for Issue of Degraded Voltage ML20199L0221997-11-24024 November 1997 Notification of 971211 Meeting W/Illinois Power Co in Clinton,Il to Discuss Findings of NRC Special Evaluation Team ML20210T2701997-09-11011 September 1997 Notification of Significant Licensee Meeting W/Util on 970924 to Discuss Objectives,Scope & Schedule of Special Evaluation Team Evaluation of Integrated Safety Assessment Being Conducted by Illinois Power Co ML20210H7531997-08-0505 August 1997 Informs That Licensee Restart & Performance Review Panel Has Determined That Plant Has Satisfactorily Completed Items & Corrective Actions Identified as Restraints to Restarting of Cps,W/Exception as Listed ML20149E8691997-07-16016 July 1997 Notification of 970717 Meeting W/Util in Rockville,Md to Discuss Voltage Available from 345 Kv Offsite Electrical Supply & Possible Effect on Plant Equipment in Case of Accident ML20140C3151997-04-0202 April 1997 Notification of 970403 Meeting W/Util in Rockville,Md to Discuss License Amend Application ,re Degraded Voltage Setpoints & Proposed Administrative Actions ML20137F3391997-03-26026 March 1997 Notification of 970421 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Re Thermo-Lag Fire Barriers & Ampacity Derating ML20136F3351997-03-0505 March 1997 Forwards Southwestern Electric Cooperative 970228 Request for Hearing,Submitted in Response to Fr Addressing Commission Consideration of Issuance of Order Approving Transfer of OL from Soyland Power to Illinois Power Co 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 ML20134L6581996-11-19019 November 1996 Notification of 961121 Meeting W/Util in Rockville,Md to Discuss Proposed Transfer of Soyland Power Cooperative Minority Ownership of Facility to Illinois Power Marketing Inc ML20056E7141993-08-19019 August 1993 Notification of 930831 Meeting w/BWR-6 Owners Group in Rockville,Md to Discuss Pending Amend Submittals to Adopt Improved Standardized TS ML20056F3811993-08-12012 August 1993 Notifies of 930830 Meeting W/Util in Rockville,Md to Discuss Licensee GL 89-10 Valve Testing Program Schedule ML20127B6031993-01-0707 January 1993 Summarizes 921217 Telcon Re Implementation of Erosion/ Corrosion Monitoring Program Per Generic Ltr 89-08.Response Acceptable Contingent on Commitment to Formalize Procedural Controls ML20058B1721990-10-25025 October 1990 Notification of 901102 Meeting W/Util in Rockville,Md to Discuss Util Approach on Performing IPE W/Nrc & Contractors ML20059B3281990-07-19019 July 1990 Discusses Author Observation of INPO Evaluation Process at Clinton Nuclear Power Plant on 900514-25.Recommends That NRC Observe Addl INPO Evaluations.Description of INPO Process & List of Qualifications & Experience of INPO Members Encl 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 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 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 1999-07-08
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20196L0051999-07-0808 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Recently Signed Asset Purchase Agreement Between Illinois Power & Amergen Energy Co & Proposed Transfer of License to Be Submitted to NRC ML20206F2481999-04-22022 April 1999 Informs That Operational Readiness Insp Team Completed Insp at Clinton Power Station Including Two Weeks on Site & Two Separate Instances of Continuous 72 Hours Control Room Observation.Operational Performance Adequate ML20206F2361999-04-21021 April 1999 Documents Completion of Insp Activities Performed During Week of 990412,to Assess Licensee Implemented & Planned Corrective Actions Associated with NRC Manual Chapter 0350 Case Specific Checklist Restart Item II.1 ML20206F2331999-04-19019 April 1999 Discusses Results of Clinton Power Station Corrective Action Insp & Recommendations to Close Demand for Info Ltr.Insp Team Focused on Operations,Maintenance & Plant Support Organizations ML20205B8871999-03-26026 March 1999 Notification of 990415 Meeting with Utils in Knoxville,Tn to Visit Test Site & Discuss Test Program for ECCS Suppression Pool Suction Strainer.Context of Meeting Considered Entirely Proprietary ML20198S0601999-01-0606 January 1999 Notification of 990121 Meeting with Util to Discuss Potential Change to Clinton Degraded Voltage Relay Setpoints ML20154L1161998-10-14014 October 1998 Notification of 981027 Meeting with Util in Rockville,Md to Discuss Licensee Proposed Mod of keep-fill Sys for Feed Water Sys Check Valves to Eliminate Containment Leakage Concern ML20154J7921998-10-13013 October 1998 Forwards NRC Operator Licensing Retake Exam & Insp Rept 50-461/98-301(OL) Administered on 980901 ML20154J9271998-10-13013 October 1998 Forwards Facility Submitted Outline & Initial Exam Submittal & as Given Operating Exam Administered on 980901 ML20238F5861998-08-28028 August 1998 Notification of 980909 Meeting w/BWR/6S:EOI & Listed Utils in Rockville,Md to Discuss W/Nrc Planned Applications by Licensees to Reduce Operability Requirements During Refueling Outages ML20237E3131998-08-26026 August 1998 Forwards for Public Release,Info Re NRC SMM Held on 980714-15.Summary of January 1998 NRC SMM & Watch List Removal Evaluation Factors Also Encl ML20237D6711998-08-25025 August 1998 Notification of 980917 Meeting W/Util in Rockville,Md to Hold NRC Insp Manual Chapter 0350 Restart Panel Meeting W/Illinois Power to Discuss Progress of Clinton Power Station Toward Restart ML20217C9761998-03-24024 March 1998 Forwards NRC Operating Licensing Exam Rept 50-461/97-313OL (Including Completed & Graded Tests) for Tests Administered on 980126-0202 ML20217C9871998-03-24024 March 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam for Tests Administered on 980126-0202 ML20197B6811998-03-0606 March 1998 Notification of 980319 Meeting W/Util in Rockville,Md to Discuss Licensee Proposed Fix for Issue of Degraded Electrical Grid Voltage ML20198R5561998-01-16016 January 1998 Notification of 980127 Meeting W/Illinois Power Co in Rockville,Md to Discuss Potential Fix for Issue of Degraded Voltage ML20199L0221997-11-24024 November 1997 Notification of 971211 Meeting W/Illinois Power Co in Clinton,Il to Discuss Findings of NRC Special Evaluation Team ML20210T2701997-09-11011 September 1997 Notification of Significant Licensee Meeting W/Util on 970924 to Discuss Objectives,Scope & Schedule of Special Evaluation Team Evaluation of Integrated Safety Assessment Being Conducted by Illinois Power Co ML20210H7531997-08-0505 August 1997 Informs That Licensee Restart & Performance Review Panel Has Determined That Plant Has Satisfactorily Completed Items & Corrective Actions Identified as Restraints to Restarting of Cps,W/Exception as Listed ML20149E8691997-07-16016 July 1997 Notification of 970717 Meeting W/Util in Rockville,Md to Discuss Voltage Available from 345 Kv Offsite Electrical Supply & Possible Effect on Plant Equipment in Case of Accident ML20140C3151997-04-0202 April 1997 Notification of 970403 Meeting W/Util in Rockville,Md to Discuss License Amend Application ,re Degraded Voltage Setpoints & Proposed Administrative Actions ML20137F3391997-03-26026 March 1997 Notification of 970421 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Re Thermo-Lag Fire Barriers & Ampacity Derating ML20136F3351997-03-0505 March 1997 Forwards Southwestern Electric Cooperative 970228 Request for Hearing,Submitted in Response to Fr Addressing Commission Consideration of Issuance of Order Approving Transfer of OL from Soyland Power to Illinois Power Co 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 ML20134L6581996-11-19019 November 1996 Notification of 961121 Meeting W/Util in Rockville,Md to Discuss Proposed Transfer of Soyland Power Cooperative Minority Ownership of Facility to Illinois Power Marketing Inc ML20056E7141993-08-19019 August 1993 Notification of 930831 Meeting w/BWR-6 Owners Group in Rockville,Md to Discuss Pending Amend Submittals to Adopt Improved Standardized TS ML20056F3811993-08-12012 August 1993 Notifies of 930830 Meeting W/Util in Rockville,Md to Discuss Licensee GL 89-10 Valve Testing Program Schedule ML20127B6031993-01-0707 January 1993 Summarizes 921217 Telcon Re Implementation of Erosion/ Corrosion Monitoring Program Per Generic Ltr 89-08.Response Acceptable Contingent on Commitment to Formalize Procedural Controls ML20058B1721990-10-25025 October 1990 Notification of 901102 Meeting W/Util in Rockville,Md to Discuss Util Approach on Performing IPE W/Nrc & Contractors ML20059B3281990-07-19019 July 1990 Discusses Author Observation of INPO Evaluation Process at Clinton Nuclear Power Plant on 900514-25.Recommends That NRC Observe Addl INPO Evaluations.Description of INPO Process & List of Qualifications & Experience of INPO Members Encl 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 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 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) 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 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 1999-07-08
[Table view] |
Text
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VM49to Statu
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, bdtht4 [ $b MEMORAN00M FOR: R. Bernero, Director. Division of lotilng Water Reactor Licensing, Office of Nuclear Reactor Regulation FROM: Charles E. Norelius, Director. Division of Reactor Projects.
Region III SU6 JECT: ILLIN0!$ POWER COMPANY, CLINTON UNIT 1 STATUS OF PREPAREDNESS FORLICENSING(94300)
This is the fourth niemorandum forwarded to you in accordance with IE MC 94300 to provide information on the preparedness for licensing of Clinton Unit 1.
Enclosures 1 through 4 include items requiring inspection and resolution before a finding of readiness for operation can be endorsed by Region III. The categories used are consistent with those used by the applicant. Illinois Power estimates a fuel load date of March 31, 1986. Region !!! considers May 1986, as an optimistic time frame for a licensing decision, contingent upon satisfactory resolution of the issues presented in the enclosures to this meno.
If you have any questions concerning this matter, please contact me or Mr. T. P. Gwynn.
Charles E. Morelius, Director Division of Reactor Projects
Enclosures:
- 1. Outstanding Itses including Enforcement. Unresolved Items and Allegations
- 2. Preoperational and Acceptar.ce 6 Testing status fdf80
- 3. Construction Status ' -
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See Attached Otstr h tion R. Bernero 2 Distribution cc w/ enclosures:
J. Taylor, IE J. Partlow, IE B. Siegel, NRR SRI, Clinton A. 8. Davis, RI!!
C. Paperiello, R111 E. Greenman, RI!!
F. Hawkins, RIII M. Phillips, RIII J. Hind, RIII J. Harrison, RIII D. Danielson, RIII J. Muffett, RIII L. Reyes, RI!!
J. Creed, RIII -
R. Greger, RIII M. Schumacher, RIII R. Warnick, RIII F. Jablonski, RIII R. Ring, RIII W. Guldemand, RIII 6
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ENCLOSURE 1 f
Outstandtnt items including Enforcement. Unresolvec. Items, Deficiency Repo~ts.
Bulletins, circulars. and A11eestions*
-- . _ _ _ _ _ _ _ _ _ _ _ . . . __ .._ . . . . ........ .o ......-...y .-,
are expected to be closed by fuel lo,ad; however, some items have been deferred and are reported as such in this report. It is anticipated that other items will be deferred and will be reported as such in updates of this report.
- 1. Open. Unresolved, and Enforcement Items (2_00_ Total)
Attachment 1 to Enclosure 1 lists the items that must be closed prior to fuel load; there are 166 open items.11 unresolved items, and 5 enforcement items.
Attachment 2 to Enclosure 1 lists the items that must be closed prior to exceeding 55 power; there are ten open items, and one enforcement item.
Attachment 3 to Enclosure 1 lists the items that will be closed some time beyond power operation; there are six open items, and one enforcement item.
- 2. _ Deficiency Reports - 10 CFR 50.55{e) and Part 21 Reports (25 Total)
Attachment 4 to Enc 1r ure 1 lists the reports that must be closed prior to fuel load; there i 1 17 Part 50.55(e) reports, and 8 Part 21 reports.
- 3. 1E Bulletins and circulars (15 Total)
Attachment 5 to Enclosure 1 lists the items that must ce closed prior to fuel load; there are four bulletins and five circulars. '
Attachment 6 to Enclosure 1 lists the items that must be closed prior to exceeding 55 power; there is one circular.
Attachment 7 to Enclosure 1 lists the items that will be closed at sometime beyond power operation; there are five bulletins.
- 4. Open Allegations (18 Total)
There are currently 18 open allegation files that are assigned to Region III ,
staff. It is expected that these allegations will be inspected prior to
' mid-April 1986. Closure of 'the allegations will depend on the outcome of the inspections and acceptance of the licensee responses / actions if
, any are required. 1
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' : :i' :.;:., ;* v dM' . : 2-d4s1 AllegationtracEinaNumoers:
AMS No. Ritt 85-A-0106 AMS Mo. Ell!-85-A-0111
~ AM5 No. R!!I 85-A-0113 AMS No. RIII-85 A 0144 AMS No. R!!!-85-A 0155f AMS No. Ell!-85-A-0159 AMS No. All!-85-A-0163 AMS No. R111-85-A-0169 AMS No. RI!! 85-A-0177 AM5 No. El!!-85-A 01829 AMS po. Rit!-85-A-0187 AM5 No. RI!!-85-A-0201 AMS No. Rill-86 A 0013
- Amatting enforcement action by RI; all Rit! **chnical inspection com.11ete 9 Referred to Itcensee There are ftve allegations to be reviewed and assigred tracking numbers.
In addition to the above allegations. the Office of Investigation has responsibiltty for investigating sta reports of alleged wrongdoing.
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Presserational and Acceptance Testine Status '
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. jpt'gg[ Af - 6 4 complete. The overalf status of the test progree is If sted below. NOTE:
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s.ne tessa includee in the status below may not be required prior to fuel lead.
P CJ' L.4 w m, w -'"# y ._.'_* No.
-Tests 11 0 .
- Started No.*+ Resulta kM 4-ge Completed
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++- Preoperational/
Acceptance Tests 120 95 75 Reviewed f~
47 Ch 4 +
[jf,M@kN.*bj *As of March 1. 1984 p.*A. ~
q 7' My +33 have exceptions that su st be resolved
- 24 have exceptions that e t be resolved y? The itcensee may provide the NRC with a Itst of tests not intended to be k-Y.@b. _
completed prior to fuel Itad. Following NRC approval of the requested a -tions thubeyilast.5tatun will be revised to reflect thqst tgits MM.bih!MN$NkDNN@3@Mb $NSN
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required ta be completed prter ta fuel Toad. .. J e
- Status of Mest*c Punch itst of Deff eteTcies As of February n , U86 Gategorization is by IP).
6.PN6/M ~ Def tetenetts tiat have not yst been essigned a category 4.252 Deficiencies that impact Integrated ICC5 Test 178 Deficiencies that impact fuel load 17.910 Defittenctes that must be resolved prior to initial Criticality 13.116 Deficiencies that must be resolved prior to exceeding 51 power 696 Deficiencies tfist 1spact Casiercial Operation 233 Deficiencies required to be resolved by first refueling or after 53a Deficiencies that are not required to *ae corrected 5.138 total Deficiencies 42.113 i
I ne a rH( W ' 06 W/314 NW Kt:610N 34 P07 1.
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[NCLO$URE 3
, gastruction Status
.' As of January 28. 1986, the licensee nported the status of construction as
= com,iete .ith the e coptions as - ted beio.,
9 Estimated 1 Construction Arees Not 1005 Cosolete Comotete by ticensee
,f, L P1R15 i
~?T Insulation 91 I@,N.@f Electrical
,- [ Conduits 97 Conduit hangers 99
' I. T
- 2 0 rhy: Miscellaneous - - - -
N.A Penetration Seals
-gjjj M Potating to 94 I ?.D i
! I.h hotet The licensee infomelly esttmates that all constructico commodities are
^- Q. J '< {yIf,['*$* ?- sm 99.55 complete except es noted above. The Itcensee is no longer Trachtet constrwettoe percent complete but is tracking individual items.
[k.n-4-
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, critical Peth items to Fuel toad (licensee identified as of January 31. l986)
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I All items include some aspect oft precoerotional testing and systems demonstrations:preoperational procedure review;
- 4, deficiency reports, allegations, and punch itst items; and coupletion ofresolution of open items.
. ;;;p, =-W Checkout"~h and Initial Operation testing. The delays noted below
, SWE by each system or eroe are all relative to the itcensee's scheduled fuel loads , ,)
date of Merch 31, 1906. Based on the delays noted below, the Itcensee N p t, fg'[,h estimates a fuel23.
forecasts April load 1 date of March 31, 1986. The critical path analysts Ql1 +
s the fuel load fate. 4 9
- I' ' Ab 1. FireProtection(-16 days)
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c, . . , ..c : 2.
.r;:>*%qi g9=*r3 Control Roan Venttistion System (-12 days)
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- s. - Finet Menditng Egeipment (-11 days) 5.
Q ' "' ?. <
~. v. . Que11ftestion of Radiochemistry Laboratory (-9 days)
"g 6. precess Sampling System (-8 days)
- 7. Centret nea Ortv system (.y dare) k.- cb.C.:a.: Ares / process nestatten menttertas syeten (-s ders)~ ~
- y k
. u~rs Q;M .;rir s g Q ug w ri < , p.~ pote semen system (-1 day) m-.m,h_
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ENCLOSURE 4 ,
Status et Inspection Required By MC 2512, 2S13, and 2514 All modules in the NRC Region III inspection program required to be complete, prior to fuel load, have been completed except those noted on the following pages.
The Division and Section responsible for completing the modules are identified in the parentheses following the module title. Abbreviations used for the organization are listed below:
Division of Reactor Projects DRP Division of Reactor Safety DRS Materials and Processes Section M&PS Plant Systems Section PSS Test Programs Section TPS Operational Programs Section OPS Quality Assurance Programs Section QAPS Operator Licensing Section OLS Division of Radiation Safety and Safeguards DRSS Emergency Preparedness Section EPS Physical Security Section SG Facilities Radiation Protection Section FRPS Radiological Effluent and Chemistry Section RECS 4
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b MAR 07 '86 07217 NRC REGIGH 3A P09 Enclosure 4 2
. l MC 2512 - Construction Phase _.
l Module Number Percent Reason Not Titie _ _ _
Complete Complete 63050 Containment Structural Integrity 100% Note 1 Test (DRP/ ORS-PSS) 65051 Low-level Radioactive Waste Storage 0% hote ?
(ORS-MPS,PSS/DRSS-FRPS)
The MC 2512 program is essentially complete as of December 31. 1985, except as noted above.
Note 1: Inspection activity complete, report pending. This testing may have to be repeated prior to initial plant operation.
Note 2: Construction of the low level radioactive waste storage facility is not scheduled to begin until after the schedule for fuel load. This inspection will be completed as part of the 2515 program.
3 E ,
MAR 87 '86 07:18 NRC REGION 3A P10 Enclosure 4 3 MC 2513 - Preope_ rational Testing and Operational Preparedness _Phas,e.
Module Percent Reason Not Number T1t1e Compiete _C,omplete 25555 Emergency Preparedness Implementation 90% Note 5 Appraisal Program (TI 2513/55)
(DRSS-EPS) 35740 QA Program - QA QC Administration 801 Note 1 (DRS-QAPS) 35743 QA Program - Maintenance (DRS-QAPS) 50% Note 10 35744 QA Program - Design Chan 80% Note 1 Modifications (DRS-QAPS)ges and 35745 A Program - Surveillance Testing 10% Note 1 DRS-QAPS) 35746 QA Program - Procurement Control 50% Note 10 (ORS-QAPS) t 35747 QA Program - Recei t. Storage and 50% Note 10 Handling (DRS-QAPS 35748 QAProgram-Records (DR$-QAPS) 70% Note 1 35749 QA Pro 50% Note 10 D es gram - Tests and Experiments l W PS) 35750 QA Program - Test and Measurement 70% Note 10 Equipment (DRS-QAPS) 42400 Plant Procedures Inspection (DRP) 90% Note 3 l 42450 Operating Procedures Inspection (DRP) 10% Note 1 ,'
42451 Maintenance Procedures Inspection (DRP) 80% Note 1 42452 Emergency Procedures Inspection (DRP) 0% Note 1 ,
60501 Fuel Receipt and Storage (DRP) 90% Note 10 m ._
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ttAR G7 '86 07:19 HRC REGION 3A P11 l
l Enclosure 4 4 t
Nodule Percent Reason Not Number Title. Complete Comple_te 70300 Preoperational Test Procedure Review 95% Note 1 (DRS-TPS) 1 70304 Preoperational Testing Procedure 90% Note 1 Review - Engineered Safety Features {
~
Test (DRS-TPS) <
l 70306 Preoperational Testing Procedure 05 Note 1 1 Review - Loss of Offsite Power Test I (DRS-TPS) 70312 Preoperational Test Witnessing 70% Note 1 Verification (DRS-TPS/DRP) 70315 Preoperational Test Witness - Engineered 80% Note 1 Safety Features Test (DRS-TPS/DRP) 70316 Preoperational Test Witness - 1.oss 0% Note 1 l of Offsite Power Test (DRS-TPS/DRP)
~
70322 Evaluation of Test Results - Engineered 45% Note 1 Safety Features Test (DRS-TPS) 70323 Evaluation of Test Results Containment 20% Note 8 Containment System: Integrated Leak Rata Test (DRS-0PS) 70325 Evaluation of Test Results - '
0% Note 7 I Reactor Protection System Test l (DRS-TPS) i 1
70326 Evaluation of Test Results - Loss 0% Notes 4 of Offsite Power Test (DRS-TPS) and 7 _
1 70329 Verification that Tests are 40% Notes 4 I Evaluated by Licensee (ORS-TPS) and 7 70370 Testing of Pipe Supports and 50% Note 1 -
Restraint Systems (DRS-MSPS) 70400 Preoperational Test Results 35% Notes 7 Evaluation (DRS-TPS) and 10
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MAR 07 '86 07:21 HRC REGIDH 3A P12 Enclosure 4 5 ,
Module Percent Reason Not Number_
_ Title- Complete Complete 70441 Emergency / Aux Power Supply Test 65% Note 1 Witness (DRS-TPS) 70442 Containment Combustible Gas Control 80% Note 9 System Test Witnessing (DRS-TPS/0RP) 70444 Containment hofation Valve System 80% Note 1 Test Witnessing (DRS-TPS/DRP) 70541 Emergency / Aux Power Test Results 40% Note 1 Evaluation (DRS-TPS) 70542 Containment System - Combustible Gas 01 Notes 4 Control System - Test Results Evaluation and 9 (DRS-TPS) 70544 Containment Isolation Valves - Test 25% Note 1 Result Evaluation (DRS-TPS) 70556 Standby Liquid Control System Test - 80% Note 1 -
Test Results Evaluation (DRS-TPS) 70$57 Of Notes 4 RCIC Test Results Evaluation (DRS-TPS) and 7 71301 Technical Specification Review (DRP) 70% Note 1 71302 Preop Test Program Implementation 30% Note 11 (DRP) 79501 LWR Water Chemistry Control and 90% Note 1 Chemical Analysis (DRSS-RECS) 79502 Plant Systems Affecting Water 90% Note 1 Chemistry (Preop and Supplemer.tal)
(DRSS-RECS) 81018 Security Plan and I lesenting 90% Note 3 Procedures (DRSS-SGS 81020 Management Effectiveness (DRSS-SGS) 90% Note 6
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- MAR 07 '86 07:22 HRC REGION 3A P13 Enclosure 4 6 Nodule Percent Reason Not Number Title- Complete Complete 81022 Security Organization (DRSS-SGS) 70% Note 6 81034 Security Program Audit (DRSS-SGS) 90% Note 6 01038 Records and Reports (DRSS-SGS) 20% Note 6 81042 Testing and Maintenance (DRSS-SGS) 50% Note 6 81046 Locks, Keys and Combinations 50% Note 6 (DRSS-SGS) l 81057 Physical Barriers - Protected 901 Note 6 l Areas (DRSS-SGS) l 81054 Physical Barrier - Vital Areas, 70% Note 6 MAA. and CAA (DRSS-SGS) 810$8 Security Systesa Power Supply 30% Note 6 ,
(DRSS-SGS) i 81062 Lighting (DRSS-SGS) 70% Note 6 81064 Compensatory Measures (DR$5-SGS) 50% Note 6 i
R1066 Assessment Aids (DRSS-SGS) 80% Note 6 81070 Access Control - Personnel 80% Note 6 (DRSS-SGS) 81072 Access Control - Packages 40% Note 6 (DR$$-$6$)
81074 Access Control - Vehicles 40% Note 6 (DRSS-SGS) .
81078 Detection Aids - Protected Areas 905 Mote 6 (DRSS-SSS) 81000 Detection Aids - VA. MAA, and CAA 501 Note 6 *
(DRSS-SGS) 81084 Alarm Stations (DRSS-SGS) 90% Note 6 81088 Consuunications (DRSS-SGS) 70% Note 6 81501 General Requirements T&Q Plan 705 Note 6 81601 Safeguards contingency Plan 30% Note 6 (DRSeSGS) i l
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l'iAR O'7 '86 07124 HRC REGIDH 3A- P14 Enclosure 4 7 Module . Percent Reason Not ,
humber Title Comolete Complete 81810 Physical Protection Safeguards 20% Note 6 Infonnation (DRSS-SGS) 83524 External Occupational Exposure 901 Mote 8 Control and Personal Dosimetry (DRSS-FRPS) 83525 Internal Exposure control and 70% Note 8 Assessment (DR55-FRPS) 83527 Facilities and Equipment (DRSS-FRPS) 60%, Note 8 83528 Maintaining Occupational Exposures 95% Note 8 Al. ARA (DRSS-FRPS) 84522 Solid Waste (Preoperational and 90% Note 7 i Startup) (DRSS-FRPS) '
l 84524 Gaseous Waste System Prooperational 955 Note 7 l and Startup (DRSS-FRPS)
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84525 Radiological and Chemical 80% Note 1 Confirmatory Measurements (DRSS-RECS) 86102 Naterial Control and Accounting 90% Note 1 (DRSS-SG) 91300 Inspection of Title 10 Requirements 05 Note 1 (DRP)
TI 2515/62 Post Fire Safe Shutdown (DRS-0PS) 05 Note 1 It is estimated that the MC 2513 Program is approximately 39P complete as of ,
'- ::r M . 1986. *Besed on 104 total modules. niey Mmh op Note 1: Inspection in progress or scheduled.
I Mote 2: Preoperational testing is still in progress and is being witnessed -
- in accordance with an established schedule.
l ^1 Note 3: Wetting for approved procedures from ifcensee. !
l Note 4: Waiting for approved test results from licensee. ;
- Note 5
- Inspection activity complete, report pending or awaiting licensee l response, E __
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' MAR 07 '86 07:25 NRC REGION 3A P15 1
Enclosure 4 8 Note 5: Licensee must first complete snd implement the Security systm.
Note 7: Waiting completion of preoperational testing prior to module completion.
Note 8: Waiting completion of facilities and programatic licensee activities prior to module completion.
Note 9: Waiting on licensee to perform test.
Note 10: Progrannatic portion of modules are complete to support fuel load, implementation portion will be completed in six months after fuel load.
Note 11: This is a recurring (quarterly) inspection which will continue to be done until fuel load.
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MAR 97 '86 07:26 HRC REGION 3A P16 Enclosure 4 9 MC 2514 - Startup Testing Phase Module Percent Reason Not Number Title Complete Complete 72300* Startup Test Procedure Review 0% Note 1 72400 Overall Startup Test Program 10% Note 2 (ORS-TPS) 1 72500 Initial Fuel Loading Procedure 80% Note 2 l Review (DRS-TPS) l 72502 Initial Criticality Procedure 0% Note 1 Review (DRS-TPS) 72504 Neetup Phase Procedure Review 0% Note 1 (DRS-TPS) 72510 Power Ascension Procedure Review- 0% Note 1 72514 Startup Test Procedure Review- 0% Note 1 Turbine Trip (DRS-TPS) 72516 Startup Test Procedure Review- 0% Note 1 Shutdown from Outside the Control Room (DRS-TPS) 72517 Startup Test Procedure Review 0% Note 1 Loss of Offsite Power (DRS-TPS) 72518 Startup Test Procedure Review- 20% Note 2 Core Performance (DRS-TPS) l T12514/01 0.L. Applicant Inspection Requirements 355 Note 2 i d
. It is estimated that the MC 2514 Program is approximately 1319 complete as of -
March 1,1986.g WBesed on 11 Modules,
- Note 1
- Waiting for approved test from licensee.
Note 2: Inspection in progress or scheduled.
l l Note 3: MC 2514 Master Inspection Plan is being finalized at this time based on the applicant's Power Ascension Program Acceleration Program.
'For tracking procedure review and verification of startup test program.
1
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