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Category:INSPECTION REPORT
MONTHYEARIR 05000361/19990121999-10-15015 October 1999 Insp Repts 50-361/99-12 & 50-362/99-12 on 990808-0918. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19990091999-08-27027 August 1999 Insp Repts 50-361/99-09 & 50-362/99-09 on 990627-0807. Non-cited Violations Identified.Major Areas Inspected:Maint, Operations,Engineering & Plant Support IR 05000361/19990081999-07-0909 July 1999 Insp Repts 50-361/99-08 & 50-362/99-08 on 990516-0626.One Violation Noted & Being Treated as Noncited Violation:Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20196B5951999-06-0909 June 1999 Errata to Insp Repts 50-361/99-04 & 50-362/99-04.Corrected Pages Replace Pps 14-17 of Insp Repts IR 05000361/19990061999-06-0808 June 1999 Insp Repts 50-361/99-06 & 50-362/99-06 on 990404-0515.Non- Cited Violations Identified.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000361/19980181999-06-0202 June 1999 Revised Pages 1-5,7,10 & 11 for Insp Repts 50-361/98-18 & 50-362/98-18 IR 05000361/19990071999-05-18018 May 1999 Partially Withheld Insp Repts 50-361/99-07 & 50-362/99-07 on 990426-29.Major Areas Inspected:Licensee Physical Security Program.Details Withheld (Ref 10CFR2.790) IR 05000361/19990051999-05-10010 May 1999 Insp Repts 50-361/99-05 & 50-362/99-05 on 990426-30.No Violations Noted.Major Areas Inspected:Plant Support.Failure to Survey Radioactive Matl Prior to Removal from Restricted Area Identified as Unresolved Pending Investigation IR 05000361/19990031999-04-20020 April 1999 Insp Repts 50-361/99-03 & 50-362/99-03 on 990205-0312.One Violation Noted & Being Treated as non-cited Violation.Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000361/19990041999-04-20020 April 1999 Insp Repts 50-361/99-04 & 50-362/99-04 on 990221-0403.Three Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000361/19990011999-03-30030 March 1999 Insp Repts 50-361/99-01 & 50-362/99-01 on 990103-0220.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980191999-01-28028 January 1999 Insp Repts 50-361/98-19 & 50-362/98-19 on 981112-990102.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20199H4521999-01-15015 January 1999 Insp Repts 50-361/98-18 & 50-362/98-18 on 981109-1218. Violations Noted.Major Areas Inspected:Operations, Maintenance & Engineering IR 05000361/19980221999-01-0707 January 1999 Insp Repts 50-361/98-22 & 50-362/98-22 on 981207-11. Violations Noted.Major Areas Inspected:Announced Insp Was Conducted to Review Portions of Radiation Protection Program IR 05000361/19980141999-01-0404 January 1999 Insp Repts 50-361/98-14 & 50-362/98-14 on 981019-1106. Violations Noted.Major Areas Inspected:Review of Design & Licensing Basis for Component CWS & Associated Support Sys & Review of 10CFR50.59 Safety Evaluation Program IR 05000361/19980211998-12-30030 December 1998 Insp Repts 50-361/98-21 & 50-362/98-21 on 981207-11. Violations Noted.Major Areas Inspected:Licensee Physical Security Program IR 05000361/19980201998-12-17017 December 1998 Insp Repts 50-361/98-20 & 50-362/98-20 on 981207-11.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980171998-12-14014 December 1998 Insp Repts 50-361/98-17 & 50-362/98-17 on 981004-1114.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000206/19980191998-12-0404 December 1998 Insp Repts 50-206/98-19 & 50-301/98-19 on 981004.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000361/19980161998-10-20020 October 1998 Insp Repts 50-361/98-16 & 50-362/98-16 on 980823-1003.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20154H3171998-10-0707 October 1998 Insp Repts 50-361/98-12 & 50-362/98-12 on 980713-17. Violations Noted.Major Areas Inspected:Licensee Physical Security Program IR 05000361/19980151998-09-25025 September 1998 Insp Repts 50-361/98-15 & 50-362/98-15 on 980824-28.No Violations Noted.Major Areas Inspected:Licensee Physical Security Program IR 05000361/19980101998-09-0202 September 1998 Insp Repts 50-361/98-10 & 50-362/98-10 on 980817-21.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980131998-09-0101 September 1998 Insp Repts 50-361/98-13 & 50-362/98-13 on 980712-0822.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20237D7261998-08-21021 August 1998 Insp Repts 50-361/98-11 & 50-362/98-11 on 980720-24.No Violations Noted.Major Areas Inspected:Exposure Controls, Controls of Radioactive Matl & Contamination,Surveying & Monitoring & QA Oversight of Radiation Protection Program IR 05000361/19980081998-08-19019 August 1998 Insp Repts 50-361/98-08 & 50-362/98-08 on 980727-31.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980091998-08-0404 August 1998 Insp Repts 50-361/98-09 & 50-362/98-09 on 980709-10.No Violations Noted.Major Areas Inspected:Operational Status of Emergency Preparedness Program,Using Simulator Walkthrough to Focus on Training of Assigned Key Roles for Emergencies IR 05000361/19980071998-07-22022 July 1998 Insp Repts 50-361/98-07 & 50-362/98-07 on 980607-0711. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980061998-06-30030 June 1998 Insp Repts 50-361/98-06 & 50-362/98-06 on 980426-0606.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980011998-05-29029 May 1998 Insp Repts 50-361/98-01 & 50-362/98-01 on 980202-0410.No Violations Noted.Major Areas Inspected:Maintenance, Engineering & Plant Support IR 05000361/19980041998-05-27027 May 1998 Insp Repts 50-361/98-04 & 50-362/98-04 on 980315-0425. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980031998-03-25025 March 1998 Insp Repts 50-361/98-03 & 50-362/98-03 on 980201-0314. Violations Noted.Major Areas Inspected:Plant Operation, Maint,Engineering & Plant Support IR 05000361/19980021998-03-11011 March 1998 Insp Repts 50-361/98-02 & 50-362/98-02 on 980209-13.No Violations Noted.Major Areas Inspected:Licensee Physical Security Program,Including Review of Alarm Stations,Access Control,Vital Area Barriers & Emergency Power Supply ML20202E9011998-02-11011 February 1998 Insp Repts 50-361/97-27 & 50-362/97-27 on 971221-980131. Violation Noted.Major Areas Inspected:Licensee Operations, 21int,engineering & Plant Support IR 05000361/19970261998-01-0505 January 1998 Insp Repts 50-361/97-26 & 50-362/97-26 on 971208-12.No Violations Noted.Major Areas Inspected:Operationsl Status of Licensee Emergency Preparedness Program.Emphasis Was Placed on Changes Occurred Since Last Emergency Preparedness Insp IR 05000361/19970251997-12-30030 December 1997 Insp Repts 50-361/97-25 & 50-362/97-25 on 971109-1220. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19970241997-12-24024 December 1997 Partialy Withheld Insp Repts 50-361/97-24 & 50-362/97-24 on 971117-21 & 1203-05 (Ref 10CFR73.21).Violations Being Considered for Ea.Major Areas Inspected:Physical Security Program IR 05000361/19970211997-11-25025 November 1997 Insp Repts 50-361/97-21 & 50-362/97-21 on 971027-31.One Exercise Weakness Identified.Major Areas Inspected: Implementation of Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise IR 05000361/19970231997-11-19019 November 1997 Insp Repts 50-361/97-23 & 50-362/97-23 on 970928-1108.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19970181997-11-17017 November 1997 Insp Repts 50-361/97-18 & 50-362/97-18,cancelled.No Insp Rept Will Be Issued IR 05000361/19970201997-10-16016 October 1997 Insp Repts 50-361/97-20 & 50-362/97-20 on 970828-0919. Violations Noted.Major Areas Inspected:Licensed Operator Requalification Program Following Guidelines in IP 71001, Licensed Operator Requalification Program Evaluation IR 05000361/19970191997-10-10010 October 1997 Insp Repts 50-361/97-19 & 50-362/97-19 on 970817-0927. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support Re Security Personnel IR 05000361/19970151997-09-10010 September 1997 Insp Repts 50-361/97-15 & 50-362/97-15 on 970630-0902. Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000361/19970171997-09-0404 September 1997 Insp Repts 50-361/97-17 & 50-362/97-17 on 970706-0816. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000361/19970111997-08-20020 August 1997 Insp Repts 50-361/97-11 & 50-362/97-11 on 970602-13 & 0804- 07.Violations Noted.Major Areas Inspected:Licensee Implementation of TSs for Both Units Along W/Resolution of Open Issues Developed Due to Problems W/Licensee Program ML20149J9621997-07-22022 July 1997 Insp Repts 50-361/97-12 & 50-362/97-12 on 970518-0705. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support Re Supervisor Failure to Follow Procedural Requirement for Controlling Security Badge IR 05000361/19970141997-07-14014 July 1997 Partially Withheld Insp Repts 50-361/97-14 & 50-362/97-14 on 970609-13 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Review of Testing & Maint,Plans & Procedures, Audits,Access Authorization & Protection of Safeguards Info IR 05000361/19970131997-07-0202 July 1997 Insp Repts 50-361/97-13 & 50-362/97-13 on 970609-13.No Violations Noted.Major Areas Inspected:Reviewed Program to Maintain Occupational Exposures as Low as Reasonably Achievable & Quality Oversight of Radiation Program IR 05000361/19970091997-06-0202 June 1997 Insp Repts 50-361/97-09 & 50-362/97-09 on 970406-0517.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19970061997-05-28028 May 1997 Insp Repts 50-361/97-06 & 50-362/97-06 on 970317-21 & 970331-0404.URI Identified.Major Areas Inspected:Cap,Fp Program & C/As for Previously Identified Violations & Open Items 1999-08-27
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000361/19990121999-10-15015 October 1999 Insp Repts 50-361/99-12 & 50-362/99-12 on 990808-0918. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19990091999-08-27027 August 1999 Insp Repts 50-361/99-09 & 50-362/99-09 on 990627-0807. Non-cited Violations Identified.Major Areas Inspected:Maint, Operations,Engineering & Plant Support IR 05000361/19990081999-07-0909 July 1999 Insp Repts 50-361/99-08 & 50-362/99-08 on 990516-0626.One Violation Noted & Being Treated as Noncited Violation:Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20196B5951999-06-0909 June 1999 Errata to Insp Repts 50-361/99-04 & 50-362/99-04.Corrected Pages Replace Pps 14-17 of Insp Repts IR 05000361/19990061999-06-0808 June 1999 Insp Repts 50-361/99-06 & 50-362/99-06 on 990404-0515.Non- Cited Violations Identified.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000361/19980181999-06-0202 June 1999 Revised Pages 1-5,7,10 & 11 for Insp Repts 50-361/98-18 & 50-362/98-18 IR 05000361/19990071999-05-18018 May 1999 Partially Withheld Insp Repts 50-361/99-07 & 50-362/99-07 on 990426-29.Major Areas Inspected:Licensee Physical Security Program.Details Withheld (Ref 10CFR2.790) IR 05000361/19990051999-05-10010 May 1999 Insp Repts 50-361/99-05 & 50-362/99-05 on 990426-30.No Violations Noted.Major Areas Inspected:Plant Support.Failure to Survey Radioactive Matl Prior to Removal from Restricted Area Identified as Unresolved Pending Investigation IR 05000361/19990031999-04-20020 April 1999 Insp Repts 50-361/99-03 & 50-362/99-03 on 990205-0312.One Violation Noted & Being Treated as non-cited Violation.Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000361/19990041999-04-20020 April 1999 Insp Repts 50-361/99-04 & 50-362/99-04 on 990221-0403.Three Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000361/19990011999-03-30030 March 1999 Insp Repts 50-361/99-01 & 50-362/99-01 on 990103-0220.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980191999-01-28028 January 1999 Insp Repts 50-361/98-19 & 50-362/98-19 on 981112-990102.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20199H4521999-01-15015 January 1999 Insp Repts 50-361/98-18 & 50-362/98-18 on 981109-1218. Violations Noted.Major Areas Inspected:Operations, Maintenance & Engineering IR 05000361/19980221999-01-0707 January 1999 Insp Repts 50-361/98-22 & 50-362/98-22 on 981207-11. Violations Noted.Major Areas Inspected:Announced Insp Was Conducted to Review Portions of Radiation Protection Program IR 05000361/19980141999-01-0404 January 1999 Insp Repts 50-361/98-14 & 50-362/98-14 on 981019-1106. Violations Noted.Major Areas Inspected:Review of Design & Licensing Basis for Component CWS & Associated Support Sys & Review of 10CFR50.59 Safety Evaluation Program IR 05000361/19980211998-12-30030 December 1998 Insp Repts 50-361/98-21 & 50-362/98-21 on 981207-11. Violations Noted.Major Areas Inspected:Licensee Physical Security Program IR 05000361/19980201998-12-17017 December 1998 Insp Repts 50-361/98-20 & 50-362/98-20 on 981207-11.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980171998-12-14014 December 1998 Insp Repts 50-361/98-17 & 50-362/98-17 on 981004-1114.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000206/19980191998-12-0404 December 1998 Insp Repts 50-206/98-19 & 50-301/98-19 on 981004.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000361/19980161998-10-20020 October 1998 Insp Repts 50-361/98-16 & 50-362/98-16 on 980823-1003.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20154H3171998-10-0707 October 1998 Insp Repts 50-361/98-12 & 50-362/98-12 on 980713-17. Violations Noted.Major Areas Inspected:Licensee Physical Security Program IR 05000361/19980151998-09-25025 September 1998 Insp Repts 50-361/98-15 & 50-362/98-15 on 980824-28.No Violations Noted.Major Areas Inspected:Licensee Physical Security Program IR 05000361/19980101998-09-0202 September 1998 Insp Repts 50-361/98-10 & 50-362/98-10 on 980817-21.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980131998-09-0101 September 1998 Insp Repts 50-361/98-13 & 50-362/98-13 on 980712-0822.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20237D7261998-08-21021 August 1998 Insp Repts 50-361/98-11 & 50-362/98-11 on 980720-24.No Violations Noted.Major Areas Inspected:Exposure Controls, Controls of Radioactive Matl & Contamination,Surveying & Monitoring & QA Oversight of Radiation Protection Program IR 05000361/19980081998-08-19019 August 1998 Insp Repts 50-361/98-08 & 50-362/98-08 on 980727-31.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980091998-08-0404 August 1998 Insp Repts 50-361/98-09 & 50-362/98-09 on 980709-10.No Violations Noted.Major Areas Inspected:Operational Status of Emergency Preparedness Program,Using Simulator Walkthrough to Focus on Training of Assigned Key Roles for Emergencies IR 05000361/19980071998-07-22022 July 1998 Insp Repts 50-361/98-07 & 50-362/98-07 on 980607-0711. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980061998-06-30030 June 1998 Insp Repts 50-361/98-06 & 50-362/98-06 on 980426-0606.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980011998-05-29029 May 1998 Insp Repts 50-361/98-01 & 50-362/98-01 on 980202-0410.No Violations Noted.Major Areas Inspected:Maintenance, Engineering & Plant Support IR 05000361/19980041998-05-27027 May 1998 Insp Repts 50-361/98-04 & 50-362/98-04 on 980315-0425. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980031998-03-25025 March 1998 Insp Repts 50-361/98-03 & 50-362/98-03 on 980201-0314. Violations Noted.Major Areas Inspected:Plant Operation, Maint,Engineering & Plant Support IR 05000361/19980021998-03-11011 March 1998 Insp Repts 50-361/98-02 & 50-362/98-02 on 980209-13.No Violations Noted.Major Areas Inspected:Licensee Physical Security Program,Including Review of Alarm Stations,Access Control,Vital Area Barriers & Emergency Power Supply ML20202E9011998-02-11011 February 1998 Insp Repts 50-361/97-27 & 50-362/97-27 on 971221-980131. Violation Noted.Major Areas Inspected:Licensee Operations, 21int,engineering & Plant Support IR 05000361/19970261998-01-0505 January 1998 Insp Repts 50-361/97-26 & 50-362/97-26 on 971208-12.No Violations Noted.Major Areas Inspected:Operationsl Status of Licensee Emergency Preparedness Program.Emphasis Was Placed on Changes Occurred Since Last Emergency Preparedness Insp IR 05000361/19970251997-12-30030 December 1997 Insp Repts 50-361/97-25 & 50-362/97-25 on 971109-1220. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19970241997-12-24024 December 1997 Partialy Withheld Insp Repts 50-361/97-24 & 50-362/97-24 on 971117-21 & 1203-05 (Ref 10CFR73.21).Violations Being Considered for Ea.Major Areas Inspected:Physical Security Program IR 05000361/19970211997-11-25025 November 1997 Insp Repts 50-361/97-21 & 50-362/97-21 on 971027-31.One Exercise Weakness Identified.Major Areas Inspected: Implementation of Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise IR 05000361/19970231997-11-19019 November 1997 Insp Repts 50-361/97-23 & 50-362/97-23 on 970928-1108.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19970181997-11-17017 November 1997 Insp Repts 50-361/97-18 & 50-362/97-18,cancelled.No Insp Rept Will Be Issued IR 05000361/19970201997-10-16016 October 1997 Insp Repts 50-361/97-20 & 50-362/97-20 on 970828-0919. Violations Noted.Major Areas Inspected:Licensed Operator Requalification Program Following Guidelines in IP 71001, Licensed Operator Requalification Program Evaluation IR 05000361/19970191997-10-10010 October 1997 Insp Repts 50-361/97-19 & 50-362/97-19 on 970817-0927. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support Re Security Personnel IR 05000361/19970151997-09-10010 September 1997 Insp Repts 50-361/97-15 & 50-362/97-15 on 970630-0902. Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000361/19970171997-09-0404 September 1997 Insp Repts 50-361/97-17 & 50-362/97-17 on 970706-0816. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000361/19970111997-08-20020 August 1997 Insp Repts 50-361/97-11 & 50-362/97-11 on 970602-13 & 0804- 07.Violations Noted.Major Areas Inspected:Licensee Implementation of TSs for Both Units Along W/Resolution of Open Issues Developed Due to Problems W/Licensee Program ML20149J9621997-07-22022 July 1997 Insp Repts 50-361/97-12 & 50-362/97-12 on 970518-0705. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support Re Supervisor Failure to Follow Procedural Requirement for Controlling Security Badge IR 05000361/19970141997-07-14014 July 1997 Partially Withheld Insp Repts 50-361/97-14 & 50-362/97-14 on 970609-13 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Review of Testing & Maint,Plans & Procedures, Audits,Access Authorization & Protection of Safeguards Info IR 05000361/19970131997-07-0202 July 1997 Insp Repts 50-361/97-13 & 50-362/97-13 on 970609-13.No Violations Noted.Major Areas Inspected:Reviewed Program to Maintain Occupational Exposures as Low as Reasonably Achievable & Quality Oversight of Radiation Program IR 05000361/19970091997-06-0202 June 1997 Insp Repts 50-361/97-09 & 50-362/97-09 on 970406-0517.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19970061997-05-28028 May 1997 Insp Repts 50-361/97-06 & 50-362/97-06 on 970317-21 & 970331-0404.URI Identified.Major Areas Inspected:Cap,Fp Program & C/As for Previously Identified Violations & Open Items 1999-08-27
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000361/19990121999-10-15015 October 1999 Insp Repts 50-361/99-12 & 50-362/99-12 on 990808-0918. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19990091999-08-27027 August 1999 Insp Repts 50-361/99-09 & 50-362/99-09 on 990627-0807. Non-cited Violations Identified.Major Areas Inspected:Maint, Operations,Engineering & Plant Support IR 05000361/19990081999-07-0909 July 1999 Insp Repts 50-361/99-08 & 50-362/99-08 on 990516-0626.One Violation Noted & Being Treated as Noncited Violation:Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20196B5951999-06-0909 June 1999 Errata to Insp Repts 50-361/99-04 & 50-362/99-04.Corrected Pages Replace Pps 14-17 of Insp Repts IR 05000361/19990061999-06-0808 June 1999 Insp Repts 50-361/99-06 & 50-362/99-06 on 990404-0515.Non- Cited Violations Identified.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000361/19980181999-06-0202 June 1999 Revised Pages 1-5,7,10 & 11 for Insp Repts 50-361/98-18 & 50-362/98-18 IR 05000361/19990071999-05-18018 May 1999 Partially Withheld Insp Repts 50-361/99-07 & 50-362/99-07 on 990426-29.Major Areas Inspected:Licensee Physical Security Program.Details Withheld (Ref 10CFR2.790) IR 05000361/19990051999-05-10010 May 1999 Insp Repts 50-361/99-05 & 50-362/99-05 on 990426-30.No Violations Noted.Major Areas Inspected:Plant Support.Failure to Survey Radioactive Matl Prior to Removal from Restricted Area Identified as Unresolved Pending Investigation IR 05000361/19990031999-04-20020 April 1999 Insp Repts 50-361/99-03 & 50-362/99-03 on 990205-0312.One Violation Noted & Being Treated as non-cited Violation.Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000361/19990041999-04-20020 April 1999 Insp Repts 50-361/99-04 & 50-362/99-04 on 990221-0403.Three Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000361/19990011999-03-30030 March 1999 Insp Repts 50-361/99-01 & 50-362/99-01 on 990103-0220.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980191999-01-28028 January 1999 Insp Repts 50-361/98-19 & 50-362/98-19 on 981112-990102.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20199H4521999-01-15015 January 1999 Insp Repts 50-361/98-18 & 50-362/98-18 on 981109-1218. Violations Noted.Major Areas Inspected:Operations, Maintenance & Engineering IR 05000361/19980221999-01-0707 January 1999 Insp Repts 50-361/98-22 & 50-362/98-22 on 981207-11. Violations Noted.Major Areas Inspected:Announced Insp Was Conducted to Review Portions of Radiation Protection Program IR 05000361/19980141999-01-0404 January 1999 Insp Repts 50-361/98-14 & 50-362/98-14 on 981019-1106. Violations Noted.Major Areas Inspected:Review of Design & Licensing Basis for Component CWS & Associated Support Sys & Review of 10CFR50.59 Safety Evaluation Program IR 05000361/19980211998-12-30030 December 1998 Insp Repts 50-361/98-21 & 50-362/98-21 on 981207-11. Violations Noted.Major Areas Inspected:Licensee Physical Security Program IR 05000361/19980201998-12-17017 December 1998 Insp Repts 50-361/98-20 & 50-362/98-20 on 981207-11.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980171998-12-14014 December 1998 Insp Repts 50-361/98-17 & 50-362/98-17 on 981004-1114.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000206/19980191998-12-0404 December 1998 Insp Repts 50-206/98-19 & 50-301/98-19 on 981004.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support IR 05000361/19980161998-10-20020 October 1998 Insp Repts 50-361/98-16 & 50-362/98-16 on 980823-1003.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20154H3171998-10-0707 October 1998 Insp Repts 50-361/98-12 & 50-362/98-12 on 980713-17. Violations Noted.Major Areas Inspected:Licensee Physical Security Program IR 05000361/19980151998-09-25025 September 1998 Insp Repts 50-361/98-15 & 50-362/98-15 on 980824-28.No Violations Noted.Major Areas Inspected:Licensee Physical Security Program IR 05000361/19980101998-09-0202 September 1998 Insp Repts 50-361/98-10 & 50-362/98-10 on 980817-21.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980131998-09-0101 September 1998 Insp Repts 50-361/98-13 & 50-362/98-13 on 980712-0822.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20237D7261998-08-21021 August 1998 Insp Repts 50-361/98-11 & 50-362/98-11 on 980720-24.No Violations Noted.Major Areas Inspected:Exposure Controls, Controls of Radioactive Matl & Contamination,Surveying & Monitoring & QA Oversight of Radiation Protection Program IR 05000361/19980081998-08-19019 August 1998 Insp Repts 50-361/98-08 & 50-362/98-08 on 980727-31.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980091998-08-0404 August 1998 Insp Repts 50-361/98-09 & 50-362/98-09 on 980709-10.No Violations Noted.Major Areas Inspected:Operational Status of Emergency Preparedness Program,Using Simulator Walkthrough to Focus on Training of Assigned Key Roles for Emergencies IR 05000361/19980071998-07-22022 July 1998 Insp Repts 50-361/98-07 & 50-362/98-07 on 980607-0711. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980061998-06-30030 June 1998 Insp Repts 50-361/98-06 & 50-362/98-06 on 980426-0606.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980011998-05-29029 May 1998 Insp Repts 50-361/98-01 & 50-362/98-01 on 980202-0410.No Violations Noted.Major Areas Inspected:Maintenance, Engineering & Plant Support IR 05000361/19980041998-05-27027 May 1998 Insp Repts 50-361/98-04 & 50-362/98-04 on 980315-0425. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980031998-03-25025 March 1998 Insp Repts 50-361/98-03 & 50-362/98-03 on 980201-0314. Violations Noted.Major Areas Inspected:Plant Operation, Maint,Engineering & Plant Support IR 05000361/19980021998-03-11011 March 1998 Insp Repts 50-361/98-02 & 50-362/98-02 on 980209-13.No Violations Noted.Major Areas Inspected:Licensee Physical Security Program,Including Review of Alarm Stations,Access Control,Vital Area Barriers & Emergency Power Supply ML20202E9011998-02-11011 February 1998 Insp Repts 50-361/97-27 & 50-362/97-27 on 971221-980131. Violation Noted.Major Areas Inspected:Licensee Operations, 21int,engineering & Plant Support IR 05000361/19970261998-01-0505 January 1998 Insp Repts 50-361/97-26 & 50-362/97-26 on 971208-12.No Violations Noted.Major Areas Inspected:Operationsl Status of Licensee Emergency Preparedness Program.Emphasis Was Placed on Changes Occurred Since Last Emergency Preparedness Insp IR 05000361/19970251997-12-30030 December 1997 Insp Repts 50-361/97-25 & 50-362/97-25 on 971109-1220. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19970241997-12-24024 December 1997 Partialy Withheld Insp Repts 50-361/97-24 & 50-362/97-24 on 971117-21 & 1203-05 (Ref 10CFR73.21).Violations Being Considered for Ea.Major Areas Inspected:Physical Security Program IR 05000361/19970211997-11-25025 November 1997 Insp Repts 50-361/97-21 & 50-362/97-21 on 971027-31.One Exercise Weakness Identified.Major Areas Inspected: Implementation of Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise IR 05000361/19970231997-11-19019 November 1997 Insp Repts 50-361/97-23 & 50-362/97-23 on 970928-1108.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19970181997-11-17017 November 1997 Insp Repts 50-361/97-18 & 50-362/97-18,cancelled.No Insp Rept Will Be Issued IR 05000361/19970201997-10-16016 October 1997 Insp Repts 50-361/97-20 & 50-362/97-20 on 970828-0919. Violations Noted.Major Areas Inspected:Licensed Operator Requalification Program Following Guidelines in IP 71001, Licensed Operator Requalification Program Evaluation IR 05000361/19970191997-10-10010 October 1997 Insp Repts 50-361/97-19 & 50-362/97-19 on 970817-0927. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support Re Security Personnel IR 05000361/19970151997-09-10010 September 1997 Insp Repts 50-361/97-15 & 50-362/97-15 on 970630-0902. Violations Noted.Major Areas Inspected:Maint & Engineering IR 05000361/19970171997-09-0404 September 1997 Insp Repts 50-361/97-17 & 50-362/97-17 on 970706-0816. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering & Plant Support IR 05000361/19970111997-08-20020 August 1997 Insp Repts 50-361/97-11 & 50-362/97-11 on 970602-13 & 0804- 07.Violations Noted.Major Areas Inspected:Licensee Implementation of TSs for Both Units Along W/Resolution of Open Issues Developed Due to Problems W/Licensee Program ML20149J9621997-07-22022 July 1997 Insp Repts 50-361/97-12 & 50-362/97-12 on 970518-0705. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support Re Supervisor Failure to Follow Procedural Requirement for Controlling Security Badge IR 05000361/19970141997-07-14014 July 1997 Partially Withheld Insp Repts 50-361/97-14 & 50-362/97-14 on 970609-13 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Review of Testing & Maint,Plans & Procedures, Audits,Access Authorization & Protection of Safeguards Info IR 05000361/19970131997-07-0202 July 1997 Insp Repts 50-361/97-13 & 50-362/97-13 on 970609-13.No Violations Noted.Major Areas Inspected:Reviewed Program to Maintain Occupational Exposures as Low as Reasonably Achievable & Quality Oversight of Radiation Program IR 05000361/19970091997-06-0202 June 1997 Insp Repts 50-361/97-09 & 50-362/97-09 on 970406-0517.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19970061997-05-28028 May 1997 Insp Repts 50-361/97-06 & 50-362/97-06 on 970317-21 & 970331-0404.URI Identified.Major Areas Inspected:Cap,Fp Program & C/As for Previously Identified Violations & Open Items 1999-08-27
[Table view] Category:UTILITY
MONTHYEARIR 05000206/19900351990-11-0909 November 1990 Insp Repts 50-206/90-35,50-361/90-35 & 50-362/90-35 on 901009-12.No Violations Noted.Major Areas Inspected:Adequacy of Health Physics Program in Area of Respirator Protection Equipment Training IR 05000206/19900331990-10-0303 October 1990 Insp Repts 50-206/90-33,50-361/90-33 & 50-362/90-33 on 900904-07.No Violations Noted IR 05000206/19900261990-07-23023 July 1990 Insp Repts 50-206/90-26,50-361/90-26 & 50-362/90-26 on 900625-29.No Violations Noted.Major Areas Inspected:Followup Items,Occupational Exposure,Control of Radioactive Matls & Contamination Surveys & Monitoring IR 05000206/19900221990-06-27027 June 1990 Insp Repts 50-206/90-22,50-361/90-22 & 50-362/90-22 on 900429-0602.Deviation Noted.Major Areas Inspected:Operations Program Including,Operational Safety Verification,Security, Radiological Protection,Evaluation of Plant Trips & Events IR 05000206/19890261989-09-22022 September 1989 Insp Repts 50-206/89-26,50-361/89-26 & 50-362/89-26 on 890828-0901.No Violations Noted.Major Areas Inspected:Plant Water Chemistry Control & Chemical Analysis,Radiochemical Analysis & QA of Plant Chemistry Activities IR 05000206/19890231989-09-20020 September 1989 Insp Repts 50-206/89-23,50-361/89-23 & 50-362/89-23 on 890814-18.No Violations Identified.Major Areas Inspected: Radwaste Sys,Followup of Open Items & Tours of Facility. One Unresolved Item Identified Re Scope of Audits IR 05000206/19890141989-07-24024 July 1989 Insp Repts 50-206/89-14,50-361/89-14 & 50-362/89-14 on 890430-0617.No Violations Noted.Major Areas Inspected: Operations Program,Including Radiological Protection, Security & Evaluation of Plant Trips & Events IR 05000206/19890151989-06-16016 June 1989 Insp Repts 50-206/89-15,50-361/89-15 & 50-362/89-15 on 890508-26.Major Areas Inspected:Licensee Events,Written Repts of Nonroutine Events,Followup of Unresolved & Open Items,Periodic & Special Repts & Occupational Exposure IR 05000361/19890191989-06-14014 June 1989 Enforcement Conference Repts 50-361/89-19 & 50-362/89-19 on 890602.Violations Noted.Major Areas Discussed:Concerns Re Inoperability of Emergency Chillers at Facility IR 05000206/19890081989-05-0202 May 1989 Insp Repts 50-206/89-08,50-361/89-08 & 50-362/89-08 on 890313-23.Violation Noted.Major Areas Inspected:Periodic & Special Repts,Shipping of Low Level Wastes for Disposal & Transportation & Radwaste Mgt IR 05000206/19890121989-04-19019 April 1989 Insp Repts 50-206/89-12,50-361/89-12 & 50-362/89-12 on 890320-24.No Deficiencies or Violations Noted.Major Areas Inspected:Previous Insp Findings,Followup of Licensee Event & Status of Emergency Preparedness Program IR 05000206/19880281989-02-13013 February 1989 Insp Repts 50-206/88-28,50-361/88-29 & 50-362/88-31 on 881118-890112.Violations Noted.Major Areas Inspected: Operational Safety Verification,Radiological Protection, Security,Evaluation of Plant Trips & Events & LERs Review IR 05000361/19880131988-09-0808 September 1988 Insp Repts 50-361/88-13 & 50-362/88-14 on 880601-14.No Unsafe Operational Conditions Identified.Major Areas Inspected:Emergency Operating Instructions,Including Control Room & Plant Walkdown & Simulator IR 05000362/19880221988-08-23023 August 1988 Insp Rept 50-362/88-22 on 880718-0805.Violation Noted.Major Areas Inspected:Activities Re as Left Type-A Containment Integrated Leak Rate Test,Including Review of Procedures & Records & Interviews W/Personnel ML20151U4091988-08-0202 August 1988 Insp Repts 50-361/88-10 & 50-362/88-10 on 880502,16-27 & 0606-10.Violations & Deviations Noted.Major Areas Inspected: Engineering,Maint,Surveillance Testing,Operations,Health Physics,Qa & Administration ML20151S9511988-07-20020 July 1988 Insp Repts 50-361/88-18 & 50-362/88-19 on 880627-0701. Violation Noted.Major Areas Inspected:Representative Subsystems of post-accident Monitoring Sys at Facility, Plant Conformance W/Rev 2 to Reg Guide 1.97 IR 05000362/19880131988-06-24024 June 1988 Insp Rept 50-362/88-13 on 880502-0603.No Violations Noted. Major Areas Inspected:Inservice Insp Activities & Insp Procedures 30703,73051,73052,73753,73755,92701 & 92703 Covered IR 05000206/19880141988-06-0606 June 1988 Insp Repts 50-206/88-14,50-361/88-12 & 50-362/88-12 on 880516-20.No Violations Noted.Major Areas Inspected:Licensee Corporate Investigation of Drug Program.Rept Partially Withheld IR 05000206/19880011988-01-22022 January 1988 Insp Repts 50-206/88-01,50-361/88-01 & 50-362/88-01 on 880104-08.No Violations Noted.Major Areas Inspected:Drug Testing.Rept Partially Withheld IR 05000361/19870271987-11-0606 November 1987 Insp Rept 50-361/87-27 on 871013-19.No Violations Noted. Major Areas Inspected:Inservice Insp Activities,Including Insp Procedures 73052,73753 & 73755 ML20236E9001987-10-14014 October 1987 Insp Rept 50-361/87-24 on 870903,04 & 14-18 & 1001 Telcon.No Violations Noted.Major Areas Inspected:Licensee Response to 870831 Event Involving Packing Ejection from Unisolable Shutdown Cooling Sys Valve & Resultant Primary Coolant Leak ML20238E2241987-09-0404 September 1987 Corrected Page 16 to Insp Rept 50-362/87-25,correcting MSIV to Read Mfiv & Deleting (D) After 50.73(a)(2)(v) in Paragraph 8.e IR 05000362/19870251987-09-0101 September 1987 Insp Rept 50-362/87-25 on 870803-28.Two Potential Violations Noted.Major Areas Inspected:Repair Activities Associated W/ Atmospheric Steam Dump Valve 3HV-8419 & Main Feedwater Isolation Valve 3HV-4048 IR 05000206/19870141987-08-31031 August 1987 Insp Repts 50-206/87-14,50-361/87-13 & 50-362/87-15 on 870524-0704.Violations Noted.Major Areas Inspected: Operational Safety Verification,Evaluation of Plant Trips & Events,Monthly Surveillance Activities & Maint Activities IR 05000206/19870231987-08-12012 August 1987 Insp Repts 50-206/87-23,50-361/87-21 & 50-362/87-23 on 870727-31.No Violations Noted.Major Areas Inspected: Substance Abuse Program IR 05000206/19870181987-06-16016 June 1987 Mgt Meeting Repts 50-206/87-18,50-361/87-17 & 50-362/87-19 on 870528.No Violations Noted.Major Areas Discussed:Issues of Current Interest Re Plant IR 05000362/19870131987-05-28028 May 1987 Insp Rept 50-362/87-13 on 870508-14.No Items of Noncompliance Noted.Major Areas Inspected:Evaluation of Licensee 870507 Revised Rept of Exposure to Hand of Worker Apparently in Excess of Regulatory Limit ML20206N9781987-04-10010 April 1987 Insp Rept 50-362/86-37 on 861215,870112-16 & 0316-20. Violations Noted:Failure to Control Licensed Matl to Maintain Exposure within Regulatory Limits,Perform Required Surveys & Provide Immediate Notification of Events to NRC IR 05000206/19860491987-02-26026 February 1987 Insp Repts 50-206/86-49,50-361/86-38 & 50-362/86-38 on 861220-870207.Violation Noted:Failure to Properly Implement Fire Protection Requirements IR 05000206/19870011987-02-20020 February 1987 Insp Repts 50-206/87-01,50-361/87-01 & 50-362/87-01 on 870126-30.No Violations or Deviations Noted.Major Areas Inspected:Emergency Preparedness Program,Notifications & Communications & Followup on Eight IE Info Notices IR 05000206/19860451987-01-0909 January 1987 Insp Repts 50-206/86-45,50-361/86-34 & 50-362/86-33 on 861115-1220.Violation Noted:Failure to Comply W/Station Procedures for Calibr of Radiation Monitoring Equipment IR 05000206/19860441987-01-0202 January 1987 Insp Repts 50-206/86-44,50-361/86-33 & 50-362/86-32 on 861117-1216.No Violations or Deviations Noted.Major Areas Inspected:Design Control & Independent Insp & Insp Procedures 30703 & 37700 ML20212E5531986-12-17017 December 1986 Insp Repts 50-361/86-25 & 50-362/86-26 on 860922-1003. Violation Noted:Failure to Maintain Fireproofing Matl in Cable Raceway as Required by Design IR 05000206/19860231986-10-30030 October 1986 Emergency Response Facilities Appraisal Rept 50-206/86-23 on 860722-25.No Significant Deficiencies or Violations Noted. Major Areas Appraised:Licensee Implementation of Suppl 1 to NUREG-0737 Requirements & Regulations IR 05000206/19860391986-10-10010 October 1986 Partially Withheld Matl Control & Accounting Safeguards Insp Rept 50-206/86-39 on 860922-26 & 1003 (Ref 10CFR2.790). No Violation Noted.Major Areas Inspected:Matl Control & Accounting,Including Reactor & Mgt Meetings IR 05000206/19860321986-08-25025 August 1986 Insp Repts 50-206/86-32,50-361/86-22 & 50-362/86-22 on 860804-08.No Violations Identified.Major Areas Inspected: Emergency Preparedness Exercise & Associated Critique & Followup of LER IR 05000361/19860191986-07-25025 July 1986 Insp Repts 50-361/86-19 & 50-362/86-19 on 860501-0705.No Violations or Deviations Noted.Major Areas Inspected:Monthly Surveillance Activities,Operational Safety Verification, Plant Trips & Events,Ler Review & Refueling Activities IR 05000206/19860301986-07-0101 July 1986 Insp Repts 50-206/86-30 & 50-361/86-21 on 860616-27.No Violation Noted.Major Areas Inspected:Inservice Insp Activities,Open Items,Part 21 Item & Bulletins ML20206T4801986-06-30030 June 1986 Insp Repts 50-361/86-15 & 50-362/86-15 on 860513-16. Violation Noted:Failure to Provide Workers W/Instructions on Emergency Response to Unit 2 Containment Bldg Strobe Lights IR 05000206/19860331986-06-25025 June 1986 Insp Rept 50-206/86-33 on 860618-19.No Violation Noted. Major Areas Inspected:App R Fire Protection Program IR 05000361/19860111986-06-20020 June 1986 Insp Repts 50-361/86-11 & 50-362/86-11 on 860328-0512. Violation Noted:Water Level Indicator Installed W/O Appropriate Procedure & Failure to Comply W/Station Procedure for Reactor Startup IR 05000206/19860271986-05-30030 May 1986 Enforcement Conference Rept 50-206/86-27 on 860522.Major Areas Discussed:Loss of Power & Water Hammer Event on 851121,corrective Actions & NRC Enforcement Policy IR 05000206/19860091986-04-25025 April 1986 Insp Repts 50-206/86-09,50-361/86-08 & 50-362/86-08 on 860215-0327.Violation Noted:Failure to Comply W/Approved Housekeeping & Fire Protection Procedures for Weekly Insp of Combustibles & Transient Fire Loads IR 05000206/19860011986-03-21021 March 1986 Emergency Preparedness Insp Repts 50-206/86-01,50-361/86-01 & 50-362/86-01 on 860106-10 & 0203-07.No Violations Noted. Major Areas Inspected:Emergency Preparedness Program Changes,Public Info & Shift Staffing IR 05000206/19860081986-02-21021 February 1986 Mgt Meeting Rept 50-206/86-08 on 860219.Major Areas Discussed:Licensee Plan & Schedule to Address 851121 Event Prior to May 1986 Restart IR 05000206/19860061986-02-21021 February 1986 Meeting Insp Repts 50-206/86-06,50-361/86-07 & 50-362/86-07 on 860206.No Violations or Deviations Noted.Major Areas Discussed:Plans to Reduce Quantity of Radioactive Matls in Liquids Discharged from Site IR 05000362/19850351985-12-0909 December 1985 Insp Rept 50-362/85-35 on 851122-1206.No Violation or Deviation Noted.Major Areas Inspected:Containment Integrated Leak Rate Test (Cilrt),Including Procedure Review,Interviews W/Personnel,Witnessing Portions of Cilrt & Containment IR 05000362/19850311985-10-23023 October 1985 Insp Rept 50-362/85-31 on 851015-18.No Violation or Deviation Noted.Major Areas Inspected:Inservice Insp Activities IR 05000361/19850221985-09-19019 September 1985 Insp Repts 50-361/85-22 & 50-362/85-21 on 850812-23.No Violation or Deviation Noted.Major Areas Inspected:Mgt Controls Re Procedures,Policies & Administrative Orders & Mgt Involvement in Implementation as Applied to Operation IR 05000361/19850231985-07-19019 July 1985 In-ofc Insp Repts 50-361/85-23 & 50-362/85-22 on 850702 & 12.No Noncompliance Noted.Major Areas Inspected:Results of Radiochemical Test Sample Provided by NRC 1990-07-23
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARPNO-IV-99-043, on 991016,earthquake of Magnitude 7 Occurred. Plant Operations Were Not Disrupted.Unusual Event Classifications Were Exited within 1 H at Both Facilities.No Damage Was Indicated & No Residual Plant Effects Observed1999-10-18018 October 1999 PNO-IV-99-043:on 991016,earthquake of Magnitude 7 Occurred. Plant Operations Were Not Disrupted.Unusual Event Classifications Were Exited within 1 H at Both Facilities.No Damage Was Indicated & No Residual Plant Effects Observed IR 05000361/19990121999-10-15015 October 1999 Insp Repts 50-361/99-12 & 50-362/99-12 on 990808-0918. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19990091999-08-27027 August 1999 Insp Repts 50-361/99-09 & 50-362/99-09 on 990627-0807. Non-cited Violations Identified.Major Areas Inspected:Maint, Operations,Engineering & Plant Support IR 05000361/19990081999-07-0909 July 1999 Insp Repts 50-361/99-08 & 50-362/99-08 on 990516-0626.One Violation Noted & Being Treated as Noncited Violation:Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20196B5951999-06-0909 June 1999 Errata to Insp Repts 50-361/99-04 & 50-362/99-04.Corrected Pages Replace Pps 14-17 of Insp Repts IR 05000361/19990061999-06-0808 June 1999 Insp Repts 50-361/99-06 & 50-362/99-06 on 990404-0515.Non- Cited Violations Identified.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support IR 05000361/19980181999-06-0202 June 1999 Revised Pages 1-5,7,10 & 11 for Insp Repts 50-361/98-18 & 50-362/98-18 ML20207E6701999-06-0202 June 1999 Corrected NOV from Insp on 981109-1218.Violations Noted:On 980907,Procedure SO23-1-3.1 Not Implemented by Operators,In That,When Chiller E335 Lube Oil Level Was Out of Sight High in Upper Sight Glass for More than 15 IR 05000361/19990071999-05-18018 May 1999 Partially Withheld Insp Repts 50-361/99-07 & 50-362/99-07 on 990426-29.Major Areas Inspected:Licensee Physical Security Program.Details Withheld (Ref 10CFR2.790) IR 05000361/19990051999-05-10010 May 1999 Insp Repts 50-361/99-05 & 50-362/99-05 on 990426-30.No Violations Noted.Major Areas Inspected:Plant Support.Failure to Survey Radioactive Matl Prior to Removal from Restricted Area Identified as Unresolved Pending Investigation IR 05000361/19993011999-05-0606 May 1999 NRC Operator Licensing Exam Repts 50-361/99-301 & 50-362/99-301 Administered on 990416.Exam Results:Two RO & Two SRO Applicants Passed Exam IR 05000361/19990031999-04-20020 April 1999 Insp Repts 50-361/99-03 & 50-362/99-03 on 990205-0312.One Violation Noted & Being Treated as non-cited Violation.Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000361/19990041999-04-20020 April 1999 Insp Repts 50-361/99-04 & 50-362/99-04 on 990221-0403.Three Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support IR 05000361/19990011999-03-30030 March 1999 Insp Repts 50-361/99-01 & 50-362/99-01 on 990103-0220.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20211K4341999-03-26026 March 1999 Partially Withheld Investigation Rept 4-1998-041. Noncompliance Noted.Major Areas Investigated:Coercion & Discrimination Against Access/Ffd Audit Team by SCE Management ML20204B3471999-03-16016 March 1999 Notice of Violation from Insp on 981109-1218.Violation Noted:Train B Emergency Chilled Water Sys Was Inoperable on Two Separate Periods (980806-26 & 0904-25),while Units 2 & 3 Were in Mode 1.No Action Was Taken to Restore Operability PNO-IV-99-018, on 990305,declared SONGS Units 2 & 3 Alert Because Potential Bomb Threat Occurred.Device Was 12-inch long,2-inch Diameter Copper Pipe,With Both Ends Capped. Licensee Notified State & Local Officials1999-03-0505 March 1999 PNO-IV-99-018:on 990305,declared SONGS Units 2 & 3 Alert Because Potential Bomb Threat Occurred.Device Was 12-inch long,2-inch Diameter Copper Pipe,With Both Ends Capped. Licensee Notified State & Local Officials ML20211K4421999-02-0505 February 1999 Partially Withheld Investigation Rept 4-1998-043.No Noncompliances Noted.Major Areas Investigated:Discrimination Against Contract Employee by Contract Foreman for Reporting Safety Concerns IR 05000361/19980191999-01-28028 January 1999 Insp Repts 50-361/98-19 & 50-362/98-19 on 981112-990102.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20211K4511999-01-26026 January 1999 Partially Withheld Investigation Rept 4-1998-045.No Nonconformance Noted.Major Areas Investigated:Discrimination Against Former Contract Employee by Supervisor for Reporting Concerns to Nuclear Safety Concerns Program IA-99-234, Partially Withheld Investigation Rept 4-1998-045.No Nonconformance Noted.Major Areas Investigated:Discrimination Against Former Contract Employee by Supervisor for Reporting Concerns to Nuclear Safety Concerns Program1999-01-26026 January 1999 Partially Withheld Investigation Rept 4-1998-045.No Nonconformance Noted.Major Areas Investigated:Discrimination Against Former Contract Employee by Supervisor for Reporting Concerns to Nuclear Safety Concerns Program ML20199H4481999-01-15015 January 1999 Notice of Violation from Insp on 981109-1218.Violation Noted:On 980907,procedure SO23-1-1.3 Not Implemented by Operators,Therefore Chiller E335 Lube Oil Pump Operating Time Exceeded Approximately 15 Seconds ML20199H4521999-01-15015 January 1999 Insp Repts 50-361/98-18 & 50-362/98-18 on 981109-1218. Violations Noted.Major Areas Inspected:Operations, Maintenance & Engineering ML20206R2091999-01-0707 January 1999 Notice of Violation from Insp on 981207-11.Violations Noted:Workers Did Not Inform Health Physics Control Personnel of Work Location Prior to Entry in Radiological Controlled Area IR 05000361/19980221999-01-0707 January 1999 Insp Repts 50-361/98-22 & 50-362/98-22 on 981207-11. Violations Noted.Major Areas Inspected:Announced Insp Was Conducted to Review Portions of Radiation Protection Program IR 05000361/19980141999-01-0404 January 1999 Insp Repts 50-361/98-14 & 50-362/98-14 on 981019-1106. Violations Noted.Major Areas Inspected:Review of Design & Licensing Basis for Component CWS & Associated Support Sys & Review of 10CFR50.59 Safety Evaluation Program ML20198S7971999-01-0404 January 1999 Exam Repts 50-361/98-302 & 50-362/98-302 on 981115-1203.Exam Results:Out of Nine SRO Applicants & Five RO Applicants,Ten Applicants Satisfied Requirements of 10CFR55 & Appropriate Licenses Have Been Issued ML20198S9171999-01-0404 January 1999 Notice of Violation from Insp on 981019-1106.Violation Noted:As of 981106,appropriate Quality Standards as Described in UFSAR Section 9.2.2.1 & in App 3.2A Not Specified & Included in Design Documents for Electrical IR 05000361/19980211998-12-30030 December 1998 Insp Repts 50-361/98-21 & 50-362/98-21 on 981207-11. Violations Noted.Major Areas Inspected:Licensee Physical Security Program ML20198N5221998-12-30030 December 1998 Notice of Violation from Insp on 981207-11.Violation Noted: Approximately 70% of Security Officers Had Not Been Trained or Qualified with 9 Milimeter Rifle Prior to Being Allowed to Perform on-shift Security Duties with That Rifle IR 05000361/19980201998-12-17017 December 1998 Insp Repts 50-361/98-20 & 50-362/98-20 on 981207-11.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980171998-12-14014 December 1998 Insp Repts 50-361/98-17 & 50-362/98-17 on 981004-1114.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000206/19980191998-12-0404 December 1998 Insp Repts 50-206/98-19 & 50-301/98-19 on 981004.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support ML20203B7051998-11-0404 November 1998 EN-98-065:informs Commission That Staff Intends to Exercise Enforcement Discretion Per Section VII.B.6 of Enforcement Policy & Not Propose Civil Penalty Nor Issue NOV to Licensee for Severity Level III Violation IR 05000361/19980161998-10-20020 October 1998 Insp Repts 50-361/98-16 & 50-362/98-16 on 980823-1003.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20154H3131998-10-0707 October 1998 Notice of Violations from Insp on 980713-17.Violations Noted:Licensee Had Not Established Specific Procedures for Employment of Compensatory Measures Resulting from Security Computer Failure ML20154H3171998-10-0707 October 1998 Insp Repts 50-361/98-12 & 50-362/98-12 on 980713-17. Violations Noted.Major Areas Inspected:Licensee Physical Security Program IR 05000361/19980151998-09-25025 September 1998 Insp Repts 50-361/98-15 & 50-362/98-15 on 980824-28.No Violations Noted.Major Areas Inspected:Licensee Physical Security Program PNO-IV-98-041, on 980918,control Room Operators Observed Alarm on One Channel of Main Condenser Steam Jet Air Ejector Radiation Monitoring Equipment,Which Indicated That Activity of Condenser Exhaust Had Increased by About Two Decades1998-09-18018 September 1998 PNO-IV-98-041:on 980918,control Room Operators Observed Alarm on One Channel of Main Condenser Steam Jet Air Ejector Radiation Monitoring Equipment,Which Indicated That Activity of Condenser Exhaust Had Increased by About Two Decades IR 05000361/19980101998-09-0202 September 1998 Insp Repts 50-361/98-10 & 50-362/98-10 on 980817-21.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980131998-09-0101 September 1998 Insp Repts 50-361/98-13 & 50-362/98-13 on 980712-0822.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support ML20237D7261998-08-21021 August 1998 Insp Repts 50-361/98-11 & 50-362/98-11 on 980720-24.No Violations Noted.Major Areas Inspected:Exposure Controls, Controls of Radioactive Matl & Contamination,Surveying & Monitoring & QA Oversight of Radiation Protection Program IR 05000361/19980081998-08-19019 August 1998 Insp Repts 50-361/98-08 & 50-362/98-08 on 980727-31.No Violations Noted.Major Areas Inspected:Plant Support IR 05000361/19980091998-08-0404 August 1998 Insp Repts 50-361/98-09 & 50-362/98-09 on 980709-10.No Violations Noted.Major Areas Inspected:Operational Status of Emergency Preparedness Program,Using Simulator Walkthrough to Focus on Training of Assigned Key Roles for Emergencies ML20236V6041998-07-22022 July 1998 Notice of Violation from Insp on 980607-0711.Violation Noted:Abnormal Operating Instruction S023-13-3,temporary Change Notice 4-2,not Appropriate for Circumstances in That Procedure Did Not Differentiate Between Various Weather IR 05000361/19980071998-07-22022 July 1998 Insp Repts 50-361/98-07 & 50-362/98-07 on 980607-0711. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19983011998-07-15015 July 1998 NRC Operator Licensing Exam Repts 50-361/98-301 & 50-362/98-301 Administered on 980614-19.All Applicants Passed Written Exam.Seven of Eight Applicants Passed All Sections of Operating Test IR 05000361/19980061998-06-30030 June 1998 Insp Repts 50-361/98-06 & 50-362/98-06 on 980426-0606.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support IR 05000361/19980011998-05-29029 May 1998 Insp Repts 50-361/98-01 & 50-362/98-01 on 980202-0410.No Violations Noted.Major Areas Inspected:Maintenance, Engineering & Plant Support ML20248C3611998-05-27027 May 1998 Notice of Violation from Insp on 980315-0425.Violation Noted:Instrument & Control Technicians Failed to Implement Procedure SO123-II-9-3 1999-08-27
[Table view] |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No._50-206/86-23 Docket No. 50-206'
License No. DPR-13 Licensee: Southern California Edison Company P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name: San Onofre' Nuclear Generating Station, Unit 1 Inspection at: San Orofre Site, San Diego County, California Inspection Conducted: July 22-25, 1986 Inspector: hhMt A G. M. Temple, Emergency Preparedness Analyst
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/c/Jo/8L Date S'igned
. Team Members: G.~F. Martin, Research Scientist, Battelle-Pacific Northwest Laboratories (PNL)
W. V. DeMier, Research Scientist, PNL M. K. Lindell, Research Scientist, Battelle-Human Affairs Research Centers D. H. ' Schultz, Reactor Operations Engineer, Comex Corporation
/0/30/ 4
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' Approved by: v F.. Fish, Chief, Emergency Preparedness DatTe Signed Section Summary:
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Inspection on July 22-25, 1986 (Report No. 50-206/86-23)
Areas Inspected: n announced appraisal of the Emergency Response Facilities (ERFs) was conducted using IE Inspection Procedure 82212 to determine,if the licensee has successfully implemented the requirements in Supplement 1 to NUREG-0737 and the regulations. The appraisal covered the Technical Support Center (TSC) and Operations Support Center (OSC), as well as the instrumentation, supplies, and equipment for these facilitie ,
Results: No significant deficiencies or violations of NRC requirements wer .
identifie /
8611070218 861031 PDR ADOCK 05000206 G PDR
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., FOR THE. DETAILED ERF. EVALUATION
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w 1.0 Technical Support Center . ... ... . ...... .... ... 1
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. ' ' Physical Facilities . .. . . .... ..... ....... I g'
1.- l .1 ' Design, Location, and Habitability. . . . . . ... 1
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,1 Size and Layout . . .......... . . .... 2
'1. Equipment and Supplies. . . ............ 2 1. . Communication Systems . ........... ... 3 1. Power Supplies. . . . . . . ...... ...... 3 1.' 1. 6 Conclusio ... . .... ........ . ... 4 1.2 N Information Management. .. . .......... .. .... 5 1. Variables and Parameters. . . . . . . . .... .. 5-1. Foxboro Fox 3-Data Acquisition and Display System. ..... ........ . ... 7 1.2.3_ Health Physics Computer System. . ..... . ...~9 1.2.4- Manual Information Systems and Display Interfaces. .. . ........ . . ...... 9 1. . Reactor Technical Support . ..... . ... . . . - 10 1. Dose Assessment / Source Term . .... .... . . 11 1. Conclusio .... ... ......... .. . 13 1.3 Functional Capability . ... ......... . .... . 14 1. Operations and Control Room Support . . 14
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1. Onshift Dose Assessment . ...... ... ... . 14-1. Conclusion. ... . ... ...... . .. . . . . 15 2.0 Operations Support Cente . .. .... . ........ ... . 15
~ Physical-Facilities . . .. . ... .... ... ... . . 15 2. . Design, Location, and Habitability. . . . . . . . 15 2. Equipment and Supplies. .. ...... ... . . 16 2. Communication . . ... .. .... . .. . . . 16 2. Conclusio . .. . ... . . .... . .. . . . 16
- 2.2 Functional Capability . .. . ... . ..... . .... . 16 2. Staffing and Activation . . . .... ... . . . 16 2. Conclusion. . . . . ... . ..... .... . . 16
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3.0 Exit Interview ~ . . . . .. . .. . ... . . ........ . . 16
Attachment A -~ Persons Contacted i
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DETAILED ERF EVALUATION a
1.0 Technical Support-Center (TSC)
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1.1 Ph'ysical Facilities
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1. Design, Location, and Habitability
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The San Onofre Nuclear Generating Station'(SONGS) Unit 1
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cTSC is-located in the Unit 1 Control and Administration Building, adjacent to the Control Room (CR). .Due to the
, close proximity, the CR can be accessed from the TSC-within a matter of-' seconds. The TSC has been built to the California Uniform Building Code-(Revision 0.67). Gamma shielding for the TSC is provided by only two walls (north and west), both-of which consist of two feet thick concrete. The whole body dose to personnel in the CR and TSC does not meet the requirements of General Design
+ - 5 ' Criterion (GDC)- 19 nor Supplement 1 to NUREG-0737. .Until -
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October 1982. the CR and TSC shared the same heating',
ventilation and air conditioning (HVAC) system. By October 1982, a separate-HVAC system was installed for th '
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TSC in order to accommodate the heat loads associated with
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the number of emergency response personnel ' assigned to the
- TSC.and the pcesence of computer equipment. The new TSC '
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HVAC was designed snd installed to be similar to'the CR
. , HVAC. NUREG-0737 Item III.D.3.4,-Control-Room
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, 'Habitabilit'y, has not yet been resolved for SONGS- ,- -
" 3 Associated with this review, an NRC staff inspection was conducted on May 20-22, 1986 and a number of deviations
from current acceptance criteria'related to the CR ventilation system were identified. Since the TSC and the CR have similar HVACs, the deviations associated with
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the CR apply ~to the TSC. 'In order to meet'the
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requirements'of GDC-19, the licensee has taken credit for shift changes (two for.the'TSC), respirator protection
'(assumed to be a factor of 50), and the use of thyroid
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blocking agents (potassium iodide (KI)). The licensee assumed a protection factor of 20 for the K Based on this' evaluation, the TSC habitability does not meet the requirements of Supplement I to NUREG-0737. However, on October 10, 1986 the licensee submitted proposed upgrades to the Unit 1 CR HVAC system which in numerous cases deviate from NUREG-0737' Item III.D.3.4 and GDC-19 acceptance criteri If the NRR staff concludes that these CR deviations from the GDC-19 criteria are acceptable, then the TSC need not meet the GDC-19 dose criteria as long as it meets the same dose criteria as the CR, except for seismic qualification and automatic initiation of the HVAC. Resolution of the TSC deviations will depend.upon the level a radiological habitabilit found acceptable for the CR by NRR during the ungoing NUREG-0737 Item III.D.3.4 revie .
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1. Size'and Layout
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The TSC ~ consists of approximately 900 square feet of space
.that is divided into four areas. The Emergency, Assessment areat consists of approximately 450 square' feet.of space for-Technical Assessment.and Radiological Assessment. The Emergency Coordinator (EC) area and the Emergency Communication area'are approximately 125-and 150. square feetr respectively. NRC personnel are assigned to.an area +
approximately 175 square feet. Since the amount.of'
available space is quite limited for the number of personnel in the TSC; a significant amount of congestion
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during. full activation would be expected. The space <
limitations are more significant with respect to circulation than for operational space.- The layout tends
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to_ control the impacts:of noise because-of the location of ,
permanent and moveable _ partitions within the TSC. The appraisal staff judged the size _ and layout to be marginal to support its function and consideration should be given to-increasing.available spac +
,1. ' Equipment and Supplies The TSC has=been supplied with an excellent technical
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determined by the users, and consists of all resources
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conceivably needed by the TSC staff to perform their
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function. Copies of 'the Emergency Plan (EP), offsite emergency response. plans, Emergency Plan Implementing-L
Procedures _(EPIPs)',-Administrative Procedures, Operating
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Procedures, Emergency Procedures, System Descriptions, Technical Specifications, and Final Safety Analysis Report (FSAR) are examples of plant reference materials '
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. av'ailable. ' Source-reference' materials.such as engineering handbooks-for electrical / mechanical engineers, steam '
tables, and other.information, are also available. Each TSC manager is provided with a responsibility-specific loose-leaf binder that includes pertinent forms, procedures, telephone lists, etc. Tabs are included to provide easy location of sections within the binde s Drawings are available in.hardcopy form in a stick file of Piping and Instrument Drawings (P& ids) electrical and instrument one-line diagrams, plant-layout diagrams, and others. .In addition to these drawings, a microfiche file contains all the hardcopy drawings, plus numerous architect / engineer and vendor drawings for selected components. A reader printer is installed in the TSC for the fiche fil In^the event any other source material, 4 for example, component technical manuals, is desired, the onsite Corporate Document Management (CDM) Center is a short distance away (3-5 minute walk, outside the protected area)'. The.CDM is computer _ linked to Southern California Edison's (SCE) corporate headquarters for any .
documents not held onsit , . .
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s The.TSC was'noted to;be adequately equipped with other
. materials for accident ~ assessment and management. Locked emergency. lockers, under strict inventory. control, provide radiological equipment storage, and storage for
, administrative supplies such as paper.and hand-held ,
calculators. Pertinent status boards are posted _or ready-
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for'immediate use. Several maps, including. demographic, radiological, and geological types, are.available.-
Onsite, near-site, and large-scale maps are included.
l-The radiological equipment and supplies provided in the Unit 1 TSC are the same as those:provided in the Units 2/3 TSC. This matter was evaluated during the Units 2/3 Emergency Response Facilities (ERF) /.ppraisal conducted i March, 1984, and the findings were documented in Section 1.1.3 of inspection report numbers 50-361/84-08 and
- 50-362/84-07. This portion of the previous inspection was
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not duplicate . _-Communication Systems The communication systems utilized in the Unit 1 TSC are the same as those used in the Units-2/3 TSC. This area was evaluated during the Units 2/3.ERF Appraisal conducted in March, 1984, and the findings were documented in Section 1.1.4 of inspection report numbers 50-361/84-08 and 50-362/84-07. This portion.of the previous inspection
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was not duplicate ,
1.1.5 - . Power Supplies
- Continuity of power was considered for the' following' major
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Foxb.oro Fox 3 Computer and' peripherals (data
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acquisition system)
Health Physics computer terminal
HVAC
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Normal lightin *- -Eniergency! Lighting
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- Communications - telephone, paging, evacuation siren During emergency conditions that result in a reactor trip,
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station power to the two separate 4 Kilovolt (KV) busses (1C and 2C) that power emergency safeguards equipment is provided from two separate offsite 220 KV source In the event of loss of both of these feeders, the station diesel generators (two) may power busses IC and 2 .
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The data acquisition system (Fox 3)!forzthe Unitf1 TSC.is
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powered from a 120 VAC Uninterruptible Power Supply (UPS).
Severalf peripherals, located in the TSC, are 'not <xt the UPS; restoration'of site power from either station emergency diesel restores power to the peripherals through wall plugs that are clearly marked and keyed for such
'se rvice. The Health Physics Computer System (HPCS)
!- central processor and peripherals', located in the Units-2/3 TSC, are powered from an UPS. The Unit 1 HPCS TSC-
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terminal and: printer are powered in a similar fashion to the Fox 3 peripherals,; distinctive wall plugs capable of
- being powered from station diesels. The.TSC INAC is powered from Motor Control' Center (MCC) 3A. On a loss of power, MCC 3A islde-energized, but may be restored from offsite or the station diesel generators, as appropriate.
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. Normal' lighting to the TSC is provided.through a transformer from the 4 KV 2C bus, thus the station diesel L
, generators may provide power in'the event of a reactor trip and/or a loss of offsite power. The TSC flxed emergency lighting consists of one wall-mounted-
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eight-hour, battery. powered emergency lighting pack (two j; '
lights aimed at the two ingress / egress routes). .It is
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recommended that appropriate relay activated, battery
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powered emergency lighting be installed in the TSC to 4_ permit:the TSC to maintain its function in the event of a
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. , ; loss of all onsite power. Allzcommunications systems are
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capable of being powered from the diesel generators; many
, systems, such'as the Emergency Notification System (ENS)
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.and Health Physics Network (HPN), are also provided with an UP ,
1.1.6- Conclusion
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, . Based on the' findings in.Section 1.1, this portion of'the U- '
_ licensee's program meets the requirements of Supplement 1
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to-NUREG-0737. However, the Region intends to track the
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-following open item:
w Pending resolution of.the CR habitability issue,
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evaluate the adequacy of the TSC habitabilit (86-23-01)-(Section 1.1.1)
The following items are suggested for improving your
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program:
, (1) Provide the.TSC with additional emergency lightin (Section 1.1.5)
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(2) Enlarge the size and impr~ove the layout of the'TSC to
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accommodate assigned personnel (Section 1.l.2)
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-1. Variables and~ Parameter '~
The' licensee h'asJinstalled two computer _ systems to provid l , , the TSC staff ~with an emergency data acquisition system to determine the. safety status of,the plant and the potential
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for radiation' exposures to the_public during plant-
. emergencies. ;The Foxboro Fox 3 makes use of approximately
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. continuous .on-line sub-set of the Regulatory Guide (RG)
. 1.97,, Revision 2, parameters to the TSC. The HPCS provides input of meteorological, area, and process radiation monitors .for accident assessment- and dose projectio ~
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As indicated'above, the parameters provided to the TSC are
- a sub-set of RG 1.97, Revision 2, that SONGS 1.has selected as the critical plant parameters. Correspondence dated December 16, 1985, has.been submitted from SCE to NRR concerning the RG 1.97 review conducted in accordance-
- with Supplement 1 to NUREG-0737. A resolution is expected j- from NRR by approximately June, 1987. The appraisal team noted numerous deviations between RG 1.97 guidance and
, the submittal of SCE. Complicating the evaluation of the
- submittal is the ~ fact- that SCE performed the evaluation by l first_ determining the SONGS 1 variables, specifically.
I required for post-accident operations, in accordance with Emergency Operating Instructions (E0Is) or EPIPs. Then, SONGS ~1 instruments were identified which fulfilled.the E0I/EPIP step. These identified instruments were then compared to RG 1.97, Revision 2, for design and qualification requirements. Discrepancies were
- identified, justified, and. recommendations formulate Thus, the submittal lists deviations between SONGS 1 instruments available, and the SONGS'l list'of required instruments derived from a task analysis of procedure As an example of this problem, Quench Tank Level',
Temperature, and Pressure are listed in-RG 1.97, Revision 2,-Table ?, as Type D variables. Table 5-2, " Comparison-of SONGS 1 Site-Specific Variables and RG 1.97 Generic Variables" of the SCE submittal lists these variables as
"Not Included" and "Not required in response to accident
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condition," meaning, presumably, that observation of these parameters is not required by an E01 or an EPI In fact, all three parameters are available in the C Notwithstanding the above situation, the appraisal team evaluated parameters available to the Fox 3 data acquisition system,.using RG 1.97, Revision 2, as a basia for a minimum acceptable data set in the TSC. The team noted several missing parameters that would be necessary for prompt and adequate TSC staff evaluation of various hypothetical accident scenarios. For example:
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Type B Variable - Reactivity Control: ' Neutron Flux
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oCR - Source, Intermediate and. Power Range: available TSC - Source, Power Rangei available
/ SCE. technical personnel stated that. intermediate
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power range' instrumentation was not necessary to adequately monitor core reactivity conditions in the
- LTSC under, e.g., anticipated transient without scram p c(ATWS) conditions. A callLto the CR could be made to.
j determine power level.
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Type B Variable - Reactivity control: Control Rod :
Position
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CR.- Individual Rod Position: available TSC' " Reactor Tripped / Normal": 'available (not rod position).
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Rod position'could be determined by calling the CR.'
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Type D Variable - Residual Heat-Removal'(RHR) or
, Decay Heat-Removal System: RHR System Flow
~RHR' Heat Exchanger Outlet
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. Temperature CR - Availability unknown TSC - Not available
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SCE stated that these parameters are " Required for' cold shutdown. Not. required in. response to accident conditions.", thus, the' availability of-the parameters in the CR was not' addressed in the RG11.97 review. The appraisal team noted, however,: that 'the system description
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procedure SD-S01-320, " Residual Heat Removal' System",
listed as the third function under " Functions / Design Basis", "To provide 1on term emergency core cooling capability...following a loss of coolant accident".
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Type D Variable - Safety Injection System: Flow in High Pressure Injection (HPI) System
CR - Available
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TSC; ,Available SCE stated in th'eir RG 1.97 review (submittal) that the
- 1 variables,are "Not Included" and "NA to SONGS". A review'
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- - of the feedwater system description indicates that the 2 a feedwater system functions as the equivalent of a HPI
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. system !and 'is ". . .used for safety. injection operations". This latter example particularly illustrates the confusing
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- . Numerous other examples were noted to be absent from the
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. data set'of tFe TSC. In general, no alternative h parameters were made available to substitute for the 4 . missing parameters of RG.I.97, except the isolated case m 'such as " rod position" noted above. The one other simila example noted-by the appraisal team concerned the Type B Variable for " Maintaining Containment Integrity:
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Containment Isolation Valve Position". Instead of the
" Closed not-closed" parameter of RG 1.97, the Fox 3 displays " Containment Isolation Initiation" as a bistable state; thus, the TSC.would be unable to determine the status of containment isolation valves without consulting the C Although the Emergency Operations Facility (EOF) was not a portion of this appraisal, the appraisal team reviewed the real-time. data acquisition system available to the EOF staff from Unit 1. It was noted that the E0F "Emergtacy Support Organization Procedures Manual" lists responsibilities similar to the TSC staff; a Technical Group is stationed in.the EOF with various engineering disciplines to " Assist in assessing the operations related mitigation efforts being performed by the CR and TSC personnel". The appraisal team determined that fourteen (14) preselected parameters of the data set available to the Fox 3 acquisition system are transmitted to the EOF, at one minute intervals, on a printe The fourteen parameters represent the maximum number of variables which can be transmitted at any one time. Re-structuring the data set to include different variables for a different accident sequence requires approximately ten (10) minutes; the appraisal team noted that only one individual on site is capable of performing the configuration change. Based on the information provided, the appraisal team concluded that upon completion of NRR's evaluation of the SCE submittal concerning RG 1.97 variables, the licensee should assure that the appropriate variables essential for the performance of TSC and EOF functions are made available on a real-time basis, in accordance with NUREG-0737, Supplement .2.2 Foxboro Fox 3 - Data Acquisition and Display System The Foxboro Fox 3 data acquisition system collects and stores safety-related data for the plant and provides a mechanism for retrieving and displaying the data in any of several concise formats. The system consists of: a 16-bit microprocessor (CPU) with 64 kilobytes (K) of memory, an operator's console (color monitor with special keyboard), two hard-disk drives (one of which serves as a spare), two floppy disk drives, two alarm typers, a logging typer, a slave color monitor, a black and white cathode ray tube (CRT) " status" terminal, a video copier (black and white), a Foxboro universal field multiplexer (UFM), and a Foxboro SPEC 200 isolation substation. All of the Fox 3 equipment is located in the TSC except for one alarm typer located in the EOF. An acoustic coupler and dial-up (300 baud) phnne line provide the data link between the Fox 3 and the EOF type . . . ._ _ __ ._ _ . . .. .- _ . . _ _ . _ . . . .
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The CPU,hard-disk drives, alarm printer, slave color monitor, and UFM are on an UPS to assure that data'
i ,
collection,- data ' storage, and alarm printing functions -
will not be interrupted if normal power to the Fox 3 is z
<
lost. The operability of system peripheral. devices, such
, g as types, disk drives and operator's console, is automatically. checked at_one minute intervals. . Detection of an " inoperable" state for a device causes a reconnect ,
atteapt'to'be initiated. tor that device. -If the reconnect
_
attemptiis-not' successful, then the device state is signalled by. an audible " SOS alarm. Also, a display on -
the status.CRT-shows what device is inoperable and provides instructions for obtaining help'in restarting the devic '
Fifty-seven analog and digital' inputs are currently being
. monitored at scan rates of once per second for critical ,
, :F parameters and once every five seconds for non-critical ones. Transmission rate between UFM and CPU is 50,000
'
baud. Although the UFM has. capacity for 192 inputs, the actual. number that can be processed by the Fox 3 is much-smaller.due to the limitations imposed by the 64 K memory
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for the CPU. Current operation with 57 inputs leaves less
'
ithan 2 K of free memory. If.it turns out that more:
.
variables need to be brought'into the Fox 3 system, the existing memory may not be adequate. Adequate disk
- storage for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of data from 57 inputs at one minute:
intervals is provided by the Foxboro SPEC 200 isolation
-
subsystem. .All SPEC 200 hardware is qualified for class i y
-
1-E nuclear service, and conforms to IEEE 323-74 and IEEE
. ,
344-75. The. isolation ~ subsystem converts thermocouple, resistance temperature detector, milliampere and millivolt
'
L signals into'0-10 volt signals through a
.," transformer-coupled (E/E) isolation device before passing
,,them~on to.the UFM as non-lE signals. Dry contact inputs
~
-
are isolated through a Foxboro electronic contact output U ,. C isolatok. ~Both isolation devices are designed to
, withstand.up'to 600 VAC at.the device output. Cyclic
' redundancy checking and software checks, on range, are-
~
,
v used for error che.cking. Additional checking occurs when j .
'
CR'personnelicompare the values displayed in the CR to
~
, :those displayed by the Fox 3 on the slave CRT which is
,
mounted for viewing from the CR. The Fox 3 system was .
s'bjected u to pre-operational testing (TP-TMI-2.2.2b-5) and post-operational testing (TP-TMI-2.2.2b-10). Loop inputs to Fox 3 were tested in accordance with " Surveillance
>
,
Procedure for Reactor Protection Systems, Loop inputs to
,
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" Fox 3"., S01-II- System maintenance requirements over the past five years have been minimal, indicating good
'
- system reliability.
! In addition to the. collection and display of measured 4 variables, the Fox 3 system supports a program for
{ predicting Xenon (Xe) reactivity. This program is always i ,
... - - - _ , - _ _ _ - _ - . - _ _ _ . , . . . , . . - _ . _ . . . . . , - - - , , . . _ - . - . , . _ _ _ - . , , . _ , , _ . _ . - _ . _ . _ . , - -.._o , . _ _ _ ,
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executed ,at a priority lower than that assigned to any of -
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the safety-function programs, thereby assuring that the Xe reactivity prediction task will not adversely affect the
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primary function of.the syste . Health Physics Computer System The'Hewlett-Packard model HP-9845 computer, located:in the
~
TSC,- is identical .in configuration to the HP-9845s in the EOF which were covered in the ERF Appraisal of SONGS 2/3 in. March, < 1984.-
1. Manual Information Systems and Display Interfaces Plant systems, meteorological and radiological data can be collected in the CR by a dedicated _ communicator who can record the data on a preformatted form and transmit these
-
. data'to the;TSC. Data received in'the TSC'can.be recorded and posted on the' principal status board. The data are reviewed by trained enginee's r who screen variable values-for consistency with previous readings of that variable
~
and for consistency with the values of other. variable Each of-the principal areas in.the TSC contain large scale di~ splay boards. The Technical Assessment area contains a plant status board that has predetermined variable names, each of.which is labeled in terms of units-of measurement and time of observation. The Radiological-Assessment _ area has wall mounted Emergency Planning Zone.(EPZ) maps that are mounted on rollers. The EC area ~has' a blank marker board and a Notification Status Board used to monitor the required and actual times for nctifications transmitted to local agencies verbally (within 15 minutes), by teletype (within 30 minutes) and to the NRC (within 60 minutes).
.
The Emergency Communications area has'a wall; mounted display that indicates the alternative circuits that can bc used to transmit a meccage'to_a decired dentinatio ~ ~
The TSC also contains a Foxboro Fox 3 computer that is J '
used to display analog and digital plant status inputs.
- The Fox 3 data displays are' hierarchically organized and l_ can be accessed from a main menu. However, there are
!- displays that contain' incomplete or potentially misleading information. User prompts should more completely describe
_
, the input format for.any data entry inputs, such as
'
_ starting. hours for trends, and indicate the default value-for, that input parameter. Potentially misleading displays
'should be fixed or eliminated. Historical trends, for
"
example,'should automatically stop at.the present' hour;
' -
'e.g. , a 12:00 -request for a 10-minute increment plot starting at 1:00 should only contain seven points. The
.'
, . . .
core exit thermocouple. data that are curiently unavailable j 0 -
should'be blanke'd out or otherwise converted to nonnumeric i , characters.
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-10
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- User documentationLfor the Fox 3-is not available at the terminal:and what documentation exists is insufficient for the novice or infrequent. user. 'There should be-documentation available~in the TSC at all-times. The
- = primary copy'should be located in a drawer at the terminal and a-backup located in the emergency kit or other secure
~
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location. The documentation should describe the' control keys and principal displays. -The description of each display should list the exact keyfentry sequence' required
-
to bring up.the displa .2.5' Reactor Technical Support
. Most parameters available to the TSC electronic data
. acquisition system-(Fox 3) may be trended in multipl ways, with on-screen or on printer presentation In addition, a screen print function permits a representation on a video hard-copier. 'Most inadequacies in' trending and forecasting capability are a function of; missing. variables as an input'to the. Fox 3. Further? enhancements to the Fox 3 may be limited by memory size, however, the appraisal team noted that'little, if any, correlation exists between" abnormal thermal / hydraulic data and Emergency Action-levelsi(EALs). Thus, limited assistance is provided for the -TSC staff in recognizing changing emergency
-
classifications due to plant variables exceeding EALs. It is recommended-that alerting. functions,'such as a flashing
value, for plant parameters correlated to EALs be provided
,
where possible. Only one pre-calculated correlation of a
.
plant parameter to accidentEconditions was noted by the t . -,
-
appraisal team. _ Chemistry procedure S0123-III-8.8,
'!-
" Alternate Methods of Post-Accident Parameter Sampling",
includes a graph depicting the' extent of fuel damage as a function of containment Hi-Range Rad Monitor dose rat ,
.
It was noted that a GAP activity release or 10% fuel damage condition at' shutdown results in a containment dose
^
,
3 -
,- -rate of 10 E+2 R/hr.- Various accident studies auch an
, >
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WASH-1400 indicate an-approximate containment dose rate-3 '
'
, _ for that magnitude of fuel' damage as 10 E+5 R/hr. The
?' ' licensee'should ensure that the plant specific fuel
.
+
damage / dose rate correlation actually differs from i - '-
theoretical studies by three orders of magnitude, due to
'- '
plant specific' conditions, such as sensor configuration,
?> etc., and is~ not, in fact, an erro It is also recommended'that the-licensee ensures to the maximum
, extent 1possible, that other pre-calculated graphs and charts are prepared to minimize calculational time during
, accident transients. For example, core damage as a l_
-
function of coolant chemistry'(specific isotopec), or dose
'
rates outside containment as a function of dose rates in containment may be pre-calculated.
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. 1.2.6' Dose A'ssessment/ Source Term
- ;Th.ough discussions with licensee personnel and review of
appropriate documentation, it was determined that many of-the dose.. assessment. capabilities of SONGS UnitL1 are
-
identical to those'in use at Units 2/3. Since these
- '
. ..
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~ capabilities were evaluated during the SONGS-Units 2/3 ERF
,
'
,
,-appraisal conducted in March,~ 1984, where.it was edetermined-that no significant changes.had occurred, thos . portions of the previous inspection were.not duplicate '
'
- The following areas of the. licensee's dose assessment
, ' program have been determined to be essentially the same'as ,
,.
'
.previously evaluated during the-Units 2/3 inspection; computerized dose assessment using the Emergency Assessment and Response System (EARS) computer program, "
'
' meteorology,.and the calculational methodology used in manual dose assessment procedure EPIP S01-VIII-40.100,
" Source Term and Dose Assessment". For furthe ;; ,
information regarding these areas, please refer to Section j_ 1.2.5 of inspection' report numbers 50-361/84-08 and
'
50-362/84-0 ^
Following an accident, the primary release point through which releases of airborne' radioactivity could occur is
,
the plant ~ vent. Air is. exhausted by the-Sphere Purge and Exhaust System fans;from the-reactor containment, the
' Reactor Auxiliary Building (RAB), .and the Fuel. Storage .
-
' Building.through high efficiency filter banks. Also,
' feeding into the plant vent is the condenser air ejector L . exhaust. ..The.following 10 gaseous effluent monitors are.
[ available for source term evaluation:
l
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Detector- 'Name Type ' Range Detected R-l211' Containment Sphere Scintillator' 10El-10E4 Iodine-131
"
and Stack Particulate
'
(SC)' Counts per: (I-131)
. Monitor' ' Minute (cpm)
,
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10El-10E6 cpm- Cobalt-60 (Co-60)
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,
Contai at Sphere Geiger-
~
. R-1212 10El-10E4 cpm Xe-133-
, and' Stack Particulate Mueller (GM) 10El-10E6 cpm Krypton-85^
.
Monitor ,
(Kr-85)
- R-1214l , Stack Gas Monitor GM 10El-10E4 cpm Xe-133 <
10El-10E4 cpm Kr-85 i
R-1215 Condenser Air Ejector GM 10El-10E4 cpm Xe-133-Gas Monitor- '10El-10E6 cpm Kr-85
,
R-1219 Stack Gas Monitor SC 10El-10E7 cpm Beta l R-1220 Stack Gas Monitor SC 10El-10E7 cpm Beta i
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R-1221- : Stack Iodine Monitor SC 10El-10E7 cpm I-131
' R-1254 ' Wide Range Gas Monitor SC 10E-7-10E-l' Xe-131 Curies / Cubic Centimeter (Ci/cc)
, Cadmium- 10E-4-10E2 Ci/cc Telerium 10E-1-10E5 Ci/cc (Cd-Te)
R-1256A&B East Steam Dump Header GM 10E-1-10E4 mr/hr Gamma Monitor Ion Chamber 10E-1-10E4 R/hr Gamma R-1258A&B . West Steam Dump Header GM 10E-1-10E4 mr/hr Gamma Monitor Ion Chamber 10E-1-10E4.R/hr Gamma Other key post-accident monitoring capabilities are provided by the containment high range monitors and the
,
Post-accident Sampling System (PASS). The containment
- high range monitors (R-1255 and R-1257) are two physically separate, redundant channels. Each channel consists of an ion chamber which measures gamma radiation inside containment from 1 to 10E8 R/hr. The PASS provides a-means to remotely collect reactor coolant and containment atmosphere samples following an accident, remotely indicates results'of chemical analyses of these samples, and dilutes the samples for further analysis. Samples are
~
remotely analyzed via an intrinsic Germanium (Ge)
detecto EPIP S01-VIII-40.100 provides a procedure for calculating source terms from available information sources. This procedure. provides for source term determination from PASS
~
results, Stack Monitors R-1254 and R-1219, Main Steam Line Monitors R-1256A&B'and R-1258A&B, Containment High Range-Monitors R-1255 and R-1257, and from field monitoring results. The appraisal staff reviewed this procedure and noted that: (1) there were no references to other related procedures or helpful sources of information; (2) the table of contents did not list Attachment 4,
" Determination of Source Term Based on Main Steam Line Monitor Reading 24 Hours After Shutdown";-(3) the body of the procedure does not mention the use of Attachment 4; (4) Section C.2 incorrectly lists the order of accuracy for monitor / methods to be used for source term calculation ,
and~is inconsistent with the order listed in the note to
' ,
Attachment 1 and Section C.2 of S023-VII-40.100; and (5)
'Section C.2 and Attachment I reference and use the Emergency Radiation Monitoring System,(ERMS) which consists of monitors R-1250, R-1251, and R-1252 which are no longer in servic Procedure S0123-III-8.8, " Alternate Methods of Post-Accident Parameter Sampling", provides alternate means of
~
- determining parameters normally obtained through PASS, if 4 ,
,
s e
.
the system is inoperable. Contained in this procedure is a graph for estimating percent failed fuel from containment high range monitor reading TSC dose assessment personnel have access to effluent and area radiation monitor readings from the CR or from the HPCS. A review of the monitors polled by the EARS program revealed that data is still being obtained from the ERMS monitors even through they are no longer being maintaine This error could create serious problems with dose assessment if these data were used during an emergency since this system is still referenced in the EPIPs.
1.2.7 Conclusion Based on the findings in Section 1.2, this portion of the licensee's program meets the requirements of Supplement 1 to NUREG-0737. However, the Region intends to track the following open items: Pending completion of NRR's evaluation of SCE's RG 1.97 submittal, assure that the appropriate variables, essential for the performance of TSC and E0F functions, are made available on a real-time basi (86-23-02) (Section 1.2.1) Ensure that the plant specific fuel damage / dose rate correlation actually differs from generic accident studies by three orders of magnitude, as opposed to being an erro (86-23-03) (Section 1.2.5) Remove the ERMS monitors as input to the EARS computer and all other mention or use of the ERMS monitors (R-1250, R-1251 and R-1252) from the EPIP (86-23-04) (Section 1.2.6)
The following items are suggested for improving your program: j (1) Determine the appropriate course of action if the existing memory in the Fox 3 is not adequate to support additional variable (Section 1.2.2)
(2) Eliminate the Fox 3 displays that contain incomplete or potentially misleading information (e.g.,
historical trends, core exit thermocouple data, etc.). (Section 1.2.4)
(3) Provide user documentation for the Fox 3 that is sufficient for the novice or infrequent user and make this documentation available in the TSC at all time (Section 1.2.4)
=.
_-
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, , .
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'(4) Where possible, provide alerting functions for plant f parameters. correlated to.EAL (Section 1.2.5) ~
'
(5).'To the maximum extent possible, prepare c . pre-calculated graphs. and charts to minimize calculational time during-accident transient (Section 1.2.5)
-(6) EPIP S01-VIII-40.100.could be improved in_the
.following areas:
'
-(i) Include references to related procedures or helpful sources.of information (e.g.,
- S0123-III-8.8, " Alternate Methods of Post-Accident Sampling, and-SONGS 1 Emergency
'
Calculation Manual").
(ii) List' Attachment 4, " Determination of Source Term Based on Main Steam Line Monitor Reading-24 Hours After Shutdown", in the table of content (iii) Include a description of Attachment 4, and instruction on when it should be used, in the-body of the procedur (iv) Correct Section C.2.which lists-the order of
accuracy for monitors / methods to be used to calculate-source terms and make it consistent:
with the note on Attachment I and Section of S023-VIII-40.10 .
1.3- Functional Capability
'1. Operations and Control Room Support ,
The functional: capability of the TSC was' evaluated by presenting an.NRC' developed accident scenario to key
'
members of the licensee's staff normally assigned to the TSC during an emergency.: Licensee personnel responded to
the~ postulated circumstances by describing their actions, and demonstrating how the equipment and supplies available in the.TSC would be used. The evaluation demonstrate that the TSC would be adequately staffed and capable of performing its as' signed function "
.
1. Onshift Dose Assessment During the appraisal, a_ walk-through demonstration of th TSC functions and capabilities was conducted. The walk-
.through scenario was based on a loss of all offsite power and the accident sequence was allowed to progress to the point of significant fuel damage (1-10%). As,a part of this walk-through, source term generation, manual dose
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'as essment',.and computerized dose assessment were
' demonstrated. Source terms.and dose assessments were calculated for containment leakage conditions and fo releases through the. plant stack using real-time
. meteorology. TSC personnel demonstrated the ability ~to perform these calculations' in a timely and accurate-manne During the walk-through, members of the TSC technical team performing source ~ term calculations were observed using calculational worksheets and information which did not appear .to originate from a station procedure or documen Discussions with licensee personnel determined that the binder containing these aids, called the SONGS 1 Emergency Calculational Manual, was compiled by station chemistry-personnel as a tool for the TSC technical team. The inspector was informed that the manual was an uncontrolled document, not subject to periodic review and update, and not covered during trainin . Conclusion Based on the findings in Section 1.3, this portion of the licensee's program meets the ' requirements of Supplement I to NUREG-0737. However, the following items are suggested for improving your. program: Make-the SONGS 1 Emergency Calculational Manual part of the controlled TSCLdocumentation and ensure that it is periodically reviewed and update . Include instruction on the contents and use of the SONGS 1 Emergency Calculational Manual in trainin . Ensure that other appropriate documents reference the SONGS-1 Emergency Calculational Manual (e.g.,.
'
~
Chemistry Leader's Manual, Health Physics (HP).
Leader's Manual, 501-VIII-40.100).
L 2.0 Operations Support Center-(OSC)
2.1 Physical Facilities
>
2. Design, Location, and Habitability The SONGS Unit 1 OSC is located on the second floor (35 foot. level) of the new Unit 1 Control and Administration Building. It should be noted that this is~a new location for the Unit 1 OSC. The new OSC was addressed in Details Section 3 of Inspection Report Numbers 50-206/86-01, 50-361/86-01, and 50-362/86-01. The OSC is adequate in size and layout to support its intended function. The OSC does not have any special shielding or ventilation system;
'
'
however, provisions, including procedures and
. .
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instrumentation, have been made to monitor habitability.in
'
'the'0SC. If radiological or other conditions necessitate
"
the abandonment of>the Unit 1 OSC, the Units 2/3~0SC.has
<
been designated as the; alternate'0S , .-
_
,
._2; ^ Equipment and Supplies The' equipment and supplies provided in the Unit 1 OSC are
-
'the same as those provided in the Units 2/3 OSC. This matter was evaluated during the Units 2/3 ERF Appraisal _
conducted in March, 1984, and the findings were documented in Section 3.1.2 of inspection report numbers 50-361/84-08 and 50-362/84-07. This portion of the previous inspection was not duplicated, however, the appraisal team verified that the appropriate items were in plac . Communications The communication systems utilized in the Unit 1 OSC are
~
the same as those used in the Units 2/3 OSC. This area was evaluated during the Units 2/3 ERF Appraisal and the findings were documented in Section 3.1.3 of inspection report numbers 50-361/84-08 and 50-362/84-07. ~This portion of the previous inspection was not duplicate . conclusion Based on'the findings in Section 2.1, this portion of'the licensee's program meets the requirements of Supplement I to KUREG-073 .2 Functional Capability 2. Staffing and Activation
.
The Unit 1 OSC functions in the same manner as the Units 2/3 OSC. Personnel staffing, organization and activation are the same. This a.rea was evaluated during the Units
-
2/3 ERF appraisal and the findings were documented in
, Sections 3.2.1 and 3.2.2 of inspection report numbers-50-361/84-08 and 50-362/84-07. This portion of the
previous inspection was not duplicate .
2. Conclusion
'
, Based on the findings in Section 2.2, this portion of the (
<
licensee's program meets the requirements of Supplement 1 to NUREG-073 .0 - Exit Interview
~'
'An exit interview was held with the licensee on July 25, 1986, for the
'
purpose of discussing the preliminary findings of the appraisal. Those
~
licensee personnel who attended the meeting have been identified in
?
.
'
17 -
,> l Attachment'A to this report. The licensee was informed that no
- significant deficiencies or violations of NRC requirements were identified during the appraisal. - The NRC Team Leader addressed each of the open items and improvement items described in the body of this repor ,
,
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ATTACHMENT A-
'
. . Persons Contacted
'*L~. Bennett; Nuclear Safety and Licensing Enginee'r
- Bray, Health Physics Enginee *J. Brooks, Health Physics Engineer K.. Brooks,' Foreman, Health. Physics,-Unit 1 R. Bush, Senior Training' Consultant-(Non-SCE)
G.'Buxton, Station Engineer C. Chiu, Assistant Manager, Station Technical D. Duran, Health Physics Engineer ,
D. Eckhart, Station Engineer J. Firoved, Emergency Preparedness Engineer
,
.K..Flynn, Station Engineer-
'T.~ Head, Computer Engineer-
- Helm,. Effluent Engineer M.'Herschthal, Station Engineer S. Hetrick, Station Engineer
- S. Hunn,- Supervisor, . Corporate Document Management (Operations)
~
.
- J. Ibarra, Nuclect Safety and Licensing Engineer T. Jackson, Instrument and Contro1' Engineer P. Knapp, Manager, Health Physics J. Kroeger, Nuclear Training Instructor
- A.'Llorens, Nuclear. Safety and Licensing Engineer J. Madigan,: Supervisor, Health Physics, Unit 1 A. Melville, Supervisor, Corporate Document Management
.R. Messeder, Health Physics Engineer S. Olofsson, Associate Emergency Preparedness Specialist
- J. Reilly, Manager, Station Technical
- R. Rice, Project Engineer-
' S. Schifield, Health Physics Ecgineer M. Tomlinsen, Computer Operato .J. Vandenbroek, Station Engineer J. Walderhaug, Computer Engineer R. Waldo, Supervisor, Computers -
- H. Wharton,' Deputy Station' Manager
- Denotes those present at the exit interview on July 25, 198 Perscas Present at July 25, 1986, Exit Interview Only R. Beatty, Liaison,' Station Security C. Bostrom, Administrator,. Health Physics / Chemistry Training C. Couser, Compliance. Engineer
- -
D. Dack, Quality Assurance Engineer P. Dooley, Supervisor, Emergency Planning H. Morgan, Station Manager J. Rainsberry, Supervising Engineer R.-Reed, Associate Emergency Planning Specialist
_
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_ _ _ _ _- _ _ _ ___._. __
. . .. . . . .. . - -. . . ~ . . - . . - . -
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R. Reiss,-Quality' Assurance Engineer G. Robinson, Supervisor, Security Operations
~ R. Santosuosso, Assistant Manager, Maintenance'
D.-Schone, Manager, Site Quality Assurance
.
B. Smith, Supervisor, Facility Planning J. Yann, Manager, Nuclear Project Engineering i
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