ML18017B307
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| ML18017B307 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/05/1981 |
| From: | MCDUFFIE M A CAROLINA POWER & LIGHT CO. |
| To: | OREILLY J P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-80-21, NUDOCS 8101210217 | |
| Download: ML18017B307 (3) | |
Similar Documents at Harris | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARHNP-99-156, Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools C & D in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration1999-10-15015 October 1999
[Table view]Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools C & D in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration HNP-99-153, Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon1999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon IR 05000400/19990071999-10-0707 October 1999 Informs That NRC Region 2 Will Conduct Triennial Fire Protection Baseline Insp 50-400/99-07 at Harris Facility on 991101-05.Insp Objection Will Be to Evaluate Fire Protection Program Implementation HNP-99-148, Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld1999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8951999-10-0404 October 1999 Forwards SE Accepting Util 961118,970314,980612 & 990528 Responses to GL 96-05, Periodic Verification of Design- Basis Capability of Safety-Related Motor-Operated Valves ML14181A4641999-10-0404 October 1999 Discusses Compeletion of Licensing Action for GL 98-01.Staff Reviewed Util Response & Has Concluded That All Requested Info Has Been Provided ML18017A8991999-10-0404 October 1999 Forwards SE Accepting Licensee 990401 Submittal of Rev 99-1 to Harris Nuclear Plant EALs for NRC Review & Approval IAW 10CFR50,App E ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program HNP-99-142, Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves1999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves ML20216G3501999-09-29029 September 1999 Confirms Conversations Re NRC Staff Voluntary Response to Orange County Discovery Requests.Staff Will Voluntarily Answer Discovery Requests & Will Not Waive Any Objection or Privilege Under NRC Regulations.Related Correspondence ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence HNP-99-145, Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii)1999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A9031999-09-23023 September 1999 Forwards Insp Rept 50-400/99-05 on 990718-0828.No Violations Noted.Insp Covered Periodic Resident Insps & Scheduled Public Radiation Safety Insp ML18017A9021999-09-23023 September 1999 Informs That NRC Has Noted That Third Quarter 1999 Performance Indicator Data,Reported in July 1999,showed White PI for Unplanned Scrams Per 7,000 Critical Hours ML18017A8851999-09-22022 September 1999 Concludes That Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of HNP SG Internals in Compliance with Licensing Bases for HNP HNP-99-143, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations ML18017A9071999-09-20020 September 1999 Forwards Insp Rept 50-400/99-11 on 990719-23 & 0802-06.No Violations Noted.Insp Found That Engineering Activites Supported Safe & Reliable Operation of Sys ML18017A8841999-09-20020 September 1999 Forwards RAI Re Licensee Request for Amend to Increase Sf Service.Mutually Agreeable Target Date of 991029 for Response Was Established HNP-99-140, Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) HNP-99-127, Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety HNP-99-129, Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity1999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity HNP-99-136, Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS1999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML14314A7771999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Slide Presentations & List of Questions Received from Participants Encl HNP-99-130, Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided1999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided ML18017A8481999-08-19019 August 1999 Advises That Info Contained in Encl 3 to Plant Ltr Serial: HNP-99-112, Info Supporting HNP Responses to NRC Rai,Dtd 990616, Will Be Withheld from Public Disclosure HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8441999-08-12012 August 1999 Forwards Insp Rept 50-400/99-04 on 990530-0717.Three NCVs Noted HNP-99-128, Corrects Statement Made in ,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment1999-08-10010 August 1999 Corrects Statement Made in ,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment HNP-99-163, Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl1999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0541999-08-0505 August 1999 Forwards RAI Re Licensee 981223 Request for Amend to Revise Plant TS 5.6, Fuel Storage, to Increase Sf Storage Capacity by Placing Sf Pools C & D in Service ML18016B0551999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 05000400/LER-1999-006-01, Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS1999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements HNP-99-116, Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed1999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed HNP-99-119, Informs That in Ltr CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 19981999-07-30030 July 1999 Informs That in Ltr CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 HNP-99-113, Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 9909301999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 HNP-99-114, Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP1999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP HNP-99-104, Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl1999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML18016A9971999-06-30030 June 1999 Discusses Closure of Review of Response to GL 92-01,rev 1, Suppl 1, Rv Structural Integrity. Info Revised & Being Released as Rvid Version 2.Info Posted on Listed Website. Recommends Info Be Reviewed ML18016B0021999-06-28028 June 1999 Forwards Insp Rept 50-400/99-03 on 990425-0529.Violation Being Treated as non-cited Violation ML18016A9981999-06-23023 June 1999 Responds to to Dk Rathbun Requesting That NRC Look Into Situation at Shearon Harris Nuclear Power Plant Described in from H Jaffe Raising Concerns About Proposal by Util to Increase Sf Storage Capacity at Plant ML20212H7741999-06-23023 June 1999 Responds to Re Petition Filed by Orange County Board of Commissioners Re Proposed Expansion of Sf Storage Capacity at Shearon Harris Npp.Public Meeting Will Be Held at Later Date.With Certificate of Svc.Served on 990624 ML18016A9921999-06-18018 June 1999 Forwards SER Accepting Util 980127 Relief Request 2RG-008 Related to Snubber Inservice Insp Requirements for Shearon Harris Nuclear Plant Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year Insp Interval ML18016A9881999-06-16016 June 1999 Forwards Request for Addl Info Re Amend Request to Increase Fuel Storage Capacity at Shearon Harris Nuclear Power Plant ML18016A9961999-06-16016 June 1999 Informs of NRC Plan to Hold Public Meeting on 990713 to Discuss Pilot Program for New Regulatory Oversight Process Conducted at Harris HNP-99-094, Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration1999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration HNP-99-103, Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated1999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9741999-06-0303 June 1999 Informs That Nrc,With Assistance from Ferc,Will Conduct Insp of Auxiliary Reservoir Dam at Plant on 990728.Purposes of Insp Is to Confirm That Dam Conforms with Design Documents & Capable of Safely Performing Design Functions HNP-99-091, Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs1999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs 1999-09-08 Category:INCOMING CORRESPONDENCE MONTHYEARHNP-99-156, Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools C & D in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration1999-10-15015 October 1999
[Table view]Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools C & D in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration HNP-99-153, Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon1999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon HNP-99-148, Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld1999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also HNP-99-142, Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves1999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence HNP-99-145, Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii)1999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) HNP-99-143, Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations HNP-99-140, Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) HNP-99-127, Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety1999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety HNP-99-129, Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity1999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity HNP-99-136, Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS1999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS HNP-99-130, Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided1999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 HNP-99-128, Corrects Statement Made in ,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment1999-08-10010 August 1999 Corrects Statement Made in ,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment HNP-99-163, Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl1999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl 05000400/LER-1999-006-01, Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS1999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements HNP-99-119, Informs That in Ltr CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 19981999-07-30030 July 1999 Informs That in Ltr CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 HNP-99-116, Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed1999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed HNP-99-113, Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 9909301999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 HNP-99-114, Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP1999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP HNP-99-104, Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl1999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl HNP-99-094, Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration1999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service, .Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration HNP-99-103, Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated1999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 HNP-99-091, Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs1999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re CPL Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation HNP-99-087, Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend1999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend HNP-99-088, Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.461999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 HNP-99-085, Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6)1999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 HNP-99-084, Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) HNP-99-060, Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant1999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant HNP-99-069, Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping1999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping HNP-99-074, Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp1999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld HNP-99-076, Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6)1999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) HNP-99-070, Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC1999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC HNP-99-072, Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6)1999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) HNP-99-067, Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change1999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change HNP-99-065, Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl1999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl HNP-99-058, Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl1999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl HNP-99-059, Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld1999-04-0505 April 1999 Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld HNP-99-024, Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings1999-04-0101 April 1999 Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings HNP-99-051, Responds to NRC Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 9902191999-03-31031 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 990219 HNP-99-034, Forwards Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept, IAW 10CFR55.45(b)(5)(ii). NRC Form 474 & Required Info Re Simulator Performance Test Results & Schedules Also Encl1999-03-19019 March 1999 Forwards Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept, IAW 10CFR55.45(b)(5)(ii). NRC Form 474 & Required Info Re Simulator Performance Test Results & Schedules Also Encl HNP-99-053, Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC1999-03-19019 March 1999 Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC ML18016A8691999-03-18018 March 1999 Forwards Resolution Adopted by Lee County,North Carolina Board of Commissioners Re Proposed Expansion of high-level Radioactive Waste Storage Facilities at Carolina Power & Light Shearon Harris Nuclear Power Plant HNP-99-032, Forwards Proprietary & non-proprietary Version of Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFPs C & D. Repts Are Reissued to Reflect Reduction in Proprietary Info.Proprietary Info Withheld1999-03-15015 March 1999 Forwards Proprietary & non-proprietary Version of Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFPs C & D. Repts Are Reissued to Reflect Reduction in Proprietary Info.Proprietary Info Withheld HNP-99-017, Informs NRC of Mod to Commitment for Hnp,Re Comprehensive Review of Implementation of TS Sr.Upon Completion of Listed Reviews,Surveillance Procedure Review Project Will Be Considered Complete1999-03-15015 March 1999 Informs NRC of Mod to Commitment for Hnp,Re Comprehensive Review of Implementation of TS Sr.Upon Completion of Listed Reviews,Surveillance Procedure Review Project Will Be Considered Complete 1999-09-08 Category:UTILITY TO NRC MONTHYEARML20059L0911990-09-12012 September 1990
[Table view]Confirms That Fee Electronically Transferred to Dept of Treasury for Payment of NRC Review Fees ML18009A6581990-09-11011 September 1990 Submits Addl Info Re Use of Hafnium Control Rods at Facility.All Rods Will Be Removed During Spring 1991 Outage ML20059H4181990-09-0606 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/90-13.Corrective Action:Changes to EST-717 in Area of Power Normalization Under Study for Past Several Months ML20059D3511990-08-30030 August 1990 Forwards Decommissioning Financial Assurance Certification Rept Submitted by North Carolina Eastern Municipal Power Agency ML17348B4941990-08-30030 August 1990 Forwards Semiannual 10CFR26 fitness-for-duty Program Data for 900103-0630.Mgt Decision Made to Utilize Alcohol Breath Instruments as Screening Devices for Unscheduled Work Call Outs in Determining fitness-for-duty ML18009A6261990-08-10010 August 1990 Informs That Action Committed to in Response to Generic Ltr 88-14, Instrument Air Supply Sys, Completed ML18009A6241990-08-0303 August 1990 Forwards Addl Info Re Operator Action Times Assumed in Steam Generator Tube Rupture Analyses for Plant,Per 900712 Telcon ML18009A6081990-07-31031 July 1990 Forwards Plan for Shearon Harris Nuclear Power Plant Emergency Exercise - 900919, Per NRC Request.W/O Encl ML20055J4171990-07-30030 July 1990 Forwards Rev 5 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20055F9431990-07-12012 July 1990 Advises That Stated Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900711 for Payment of Operator License Exam Fees for Listed Insp Invoices ML18009A5991990-07-0606 July 1990 Comments on Electrical Distribution Sys Functional Insp Rept 50-400/90-200 on 900212-0316.Seismic Qualification Package Subsequently Upgraded to Include Qualification Info Based on Receipt of Part 21 from Transamerica Delaval ML18009A5851990-06-28028 June 1990 Advises That Emergency Preparedness Exercise Scheduled on 900919.Exercise Will Consist of Simulated Accident at Plant Site & Will Involve Planned Response Actions.Objectives to Be Fulfilled Encl ML20034D0051990-05-31031 May 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/90-06.Corrective Action:Leak Rate Test Performed Satisfactorily on Valve 1SP-916 After Omission of Test Discovered ML18009A5621990-05-30030 May 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/90-06.Corrective Actions:Procedures OST-1008 & OST-1108 Revised to Delete Stroke Testing of Valve 1ST-359 on Quarterly Basis ML18009A5141990-05-0303 May 1990 Forwards Eddy Current Exam CP&L Shearon Harris Nuclear Power Plant Steam Generators A,B & C, Providing Results of Inservice Insps Performed During Plant Second Refueling Outage in Oct 1989 ML18009A4941990-04-26026 April 1990 Forwards Radiological Environ Operating Rept,1989, Radiological Environ Operating Rept,Vol II,Jan-June 1989, Sample Analyses Data & Radiological Environ Operating Rept,Vol III,Jul-Dec 1989,Sample Analyses Data ML18009A5031990-04-25025 April 1990 Submits Suppl 2 to Relief Request R2-001 Re Plant 10-yr Inservice Insp Plan,Per 880129 Request ML18009A4841990-04-24024 April 1990 Forwards Corrected Bases marked-up Page to 900226 Tech Spec Change Request Re Surveillance Intervals ML18009A4911990-04-24024 April 1990 Forwards Addl Info Re Proposed Wakesouth Regional Airport to Be Located Near Facility,Per 900411 Request.Info Previously Provided to NRC During 900320 & 23 Telcons ML18009A4251990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule Based on Guidelines Provided in NUMARC 87-00, Guidelines & Technical Bases for NUMARC Initiatives.... No Changes to Previous Calculations Necessary & One Deviation Noted ML18009A4231990-03-29029 March 1990 Suppls Response to NRC Re Violations Noted in Insp Rept 50-400/89-23.Corrective Actions:Surveys Performed to Determined Extent & Level of Contamination & Personnel Involved Decontaminated ML18009A4121990-03-23023 March 1990 Forwards Rev 17 to PLP-201, Emergency Plan & Fission Product Barrier Analysis.Rev to Emergency Plan Incorporates Comments Received During Recent Licensed Operator Requalification Training in Emergency Plan Procedures ML18009A4111990-03-23023 March 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/90-02.Corrective Actions:Personnel Involved W/ Quadrant Power Tilt Ratio Calculations & Operability Determination Counseled ML18009A4151990-03-22022 March 1990 Responds to NRC SALP Rept for Jul 1988 - Nov 1989.Contrary to Statement in Rept Significant Amount of Refresher Training Was Conducted During SALP Assessment Period Including Termination & Splicing & Motor & Bus Relays ML18009A4081990-03-19019 March 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/90-01.Corrective Actions:All Calibr Required by Tech Specs for Power Range Nuclear Instrumentation Satisfactorily Completed ML18022A7891990-03-0909 March 1990 Forwards Vols 1 & 2 of Inservice Insp Summary 1st Interval 1st Period,2nd Refueling Outage Completed 891222 ML18022A7881990-03-0606 March 1990 Confirms Understanding of Status of NRC Activities Re Proposed Wakesouth Regional Airport Located Near Plant Site. Pending Issues Should Be Resolved by 900331 to Enable Util to Complete Negotiations W/Airport Authority ML20033E0991990-03-0505 March 1990 Forwards Response to NRC Re Regulatory Effectiveness Review.Encl Withheld (Ref 10CFR73.21) ML18022A7851990-03-0202 March 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/89-34.Corrective Actions:Valve SI-332 Closed & Gravity Drain Path Isolated & Shift Foreman Required to Review MMM-012 Re Priority/Emergency Maint Work Control ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML18022A7721990-02-26026 February 1990 Forwards Application for Amend to License NPF-63,revising Tech Spec Surveillance 4.0.2 to Permit Surveillances to Be Extended Up to 25% of Specified Interval & Removing 3.25 Limitation from Spec,Per Generic Ltr 89-14 ML18022A7701990-02-14014 February 1990 Notifies of Issuance of Renewal of NPDES Permit for Plant. Permit Encl ML18009A3831990-02-0909 February 1990 Responds to Re Violation Noted in Insp Rept 50-400/89-35.Corrective Actions:Valves ICS-775 & ICS-776 Added to Inservice Insp Program for Back Seat & Full Flow Testing & ICS-525 Revised to Satisfy Tech Spec Requirements ML18009A3751990-02-0101 February 1990 Forwards Retyped Tech Spec Pages Re 890630 Application for Amend to License NPF-63 Concerning RCS Pressure Temp Limits ML18009A3701990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 ML18009A3631990-01-26026 January 1990 Responds to NRC Bulletin 88-008, Thermal Stratification in Piping Connected to Rcs. Design Differences That Either Minimize Potential of Occurrence or Enhance Possibility of Detection Should Scenario Be Created at Plant Determined ML18009A3531990-01-25025 January 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Conducted in Oct 1989.Util Believes That Packing Leaks Discovered Are Isolated Failures & That Repair Should Prevent Recurrence ML18009A3501990-01-22022 January 1990 Forwards Revised Tech Spec Table 3.7-6, Area Temp Monitoring, Per 891218 Tech Spec Amend Request ML18022A7591990-01-17017 January 1990 Submits Results of Aircraft Hazards Study Associated W/ Proposed Wakesouth Regional Airport & Facility ML20005G5731990-01-16016 January 1990 Forwards Response to Insp Rept 50-400/89-32.Encl Withheld (Ref 10CFR73.21) ML18009A3351990-01-0505 January 1990 Forwards Rev 16 to Vol 1,Part 2 of Plant Operating Manual PLP-201, Emergency Plan. Revised NUREG-0654 Comparison W/ Plant Emergency Action Level Flow Path Also Encl for Review ML18009A3171989-12-21021 December 1989 Responds to NRC Re Violations Noted in Insp Rept 50-400/89-21.Corrective Actions:Incident Reviewed by Both Plant & Nuclear Engineering Dept Personnel to Avoid Future Miscommunication ML18009A3011989-12-15015 December 1989 Forwards Proprietary WCAP-12403 & Nonproprietary WCAP-12404, LOFTTR2 Analysis for Steam Generator Tube Rupture W/Revised Operator Action Times for Shearon Harris Nuclear Power Plant. WCAP-12403 Withheld (Ref 10CFR2.790(b)(4)) ML18009A3181989-12-15015 December 1989 Forwards Retyped Amend Bar Pages to Tech Spec Table 3.3-3 Re Auxiliary Feedwater Manual Initiation,Per 891026 Application for Amend to License NPF-63 ML18022A7371989-12-13013 December 1989 Forwards Change 3 to Rev 2 to State of Nc Emergency Response Plan in Support of Shearon Harris Nuclear Power Plant, Incorporating Administrative Enhancements. W/One Oversize Encl ML18009A2971989-12-0808 December 1989 Responds to NRC Re Violations Noted in Insp Rept 50-400/89-23.Corrective Action:Min of Four Decontamination Personnel Will Be Assigned 24 H Per Day During Fuel/Cask Handling to Maintain Cleanliness in Fuel Handling Bldg ML18009A2841989-11-30030 November 1989 Forwards Rev 0 to Core Operating Limits Rept in Support of Cycle 3 Operations ML18005B1531989-11-27027 November 1989 Forwards Retyped Amend Bar Pages to 890630 Request for Rev to License NPF-63 Re RCS pressure-temp Limits ML18022A7311989-11-27027 November 1989 Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements ML18005B1511989-11-17017 November 1989 Forwards 15-day Special Rept Identifying Number of Steam Generator Tubes Plugged During Current Inservice Insp Period 1990-09-06 |
Text
CAGE Carolina Power&Light Comparty~~R~~'el%\1 i't i<W~~'January 5, 1981 CF gRN"Ahg Mr.J.P.O'Reilly Region II U.S.Nuclear Regulatory Commission 101 Marietta Street, N.W.Atlanta, Georgia 30303 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NOS 1, 2, 3, AND 4 DOCKET NOS~50 400>>50 401>>50 402>>AND"50 403 IE BULLETIN 80-21
Dear Mr.O'Reilly:
As requested by IE Bulletin 80-21, Carolina Power&Light Company (CPGL)has reviewed the design of the Shearon Harris Nuclear Power Plant (SHNPP)with regard to the use of valve parts cast by Malcolm Foundry Company, Inc.CPSL has determined that active safety related valves which have parts supplied by Malcolm Foundry are used on SHNPP Units 1 and 2.Anchor Darling Valve Company is the only affected valve manufacturer.
Attachment 1 is a compilation of valve parts as well as the valve tag numbers which are used in safety related systems on SHNPP.Anchor Darling is arranging tests to determine that the material in the affected valves is acceptable.
Any valve parts having properties not in accordance with ASTM material specification will be replaced by Anchor Darling.Resolution of this item will be complete before receipt of the facility operating license.If you have any questions on this subject>>please contact our staff.CP&L plans no further response to this bulletin.Yours very truly, M, A.McDuffie Senior Vice President Engineering 6 Construction ONH/d1c (N818)Attachment cc: Director, Division of Reactor Construction Inspection Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission Washington, D.C.20555 h>elml r>pl 7 411 Fayettevilte Street o P.O.Box 1551 o Raleigh, N.C.27602 P 7 ATTACHMENT 1 VALVES WITH MALCOLM FOUNDRY CO MANUFACTURED PARTS A/DV S.O./Item E5796-2 E5796-12 Qty Part Description/Dwg.
No.6 Handwheel D8271 6 Handwheel Insert B50508 8 Handwheel D8268 8 Handwheel Insert B50504 Valve Description 4"900 GTMAN 3" 150 GTMAN Valve No.3AF-V5SA-1 3AF-V6SA-1 3AF-'V7SA-1 3AF-V14SA-1 3AF-V15SA-1 3AF-V16SA-1 3PM-V4SN-1$
2 3PM-VSSN-1$
2 3PM-V26SN-l, 2 3PM-V47SN-1, 2 E5796-14 2 Handwheel D8269 2 Handwheel Insert B50506 4"150 GTMAN 2CT-V59SAB-1,2 E5796-15 E5796-19 E5796-3 6 Handwheel D8269 6 Handwheel Insert B50506 4 Handwheel D8220 4 Valve Yoke 4" 105 GTMAN 8"300 GTMO 6"900 GTMO 3PM-VlSN-1,.
3PM-V109SN-1+2 3PM-V2SN-1, 2 3PM-V3SN-1, 2 2CT-V21SA-l, 2 2CT-V43SB-1, 2 2MS-V8SB-l, 2 2MS-V9SA-1$
2
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