Letter Sequence Meeting |
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MONTHYEARML20137X7791986-02-28028 February 1986 Confirmatory Action Ltr Re 860228 Telcon W/Jw Lynch Outlining Listed Actions to Be Taken to Assure Operability of Reactor Control Room Emergency Ventilation Sys,Per Tech Specs & GDC 19 Project stage: Other ML20141C7141986-03-21021 March 1986 Notice of Deviation from Insp on 860128-30 & 0224-28 Project stage: Other ML20197F2511986-05-0707 May 1986 Forwards Request for Addl Info Re Control Room Habitability. Control Room Ventilation Sys Functioning Inconsistent W/Tmi Action Plan Item III.D.3.4 or Updated FSAR Project stage: RAI ML20198A1351986-05-14014 May 1986 Discusses Insp on 860128-30 & 0224-28 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty.Violation Involves Licensee Failure to Maintain Control Room Emergency Ventilation Sys in Operable Status Project stage: Other ML20198A1601986-05-14014 May 1986 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $80,000.Violation Noted:Control Room Emergency Ventilation Sys Inoperable & Not Independent Due to Excessive Makeup Flow Rate in Train CB-1B Project stage: Other ML20155J9501986-05-19019 May 1986 Forwards Addl Info Re Adequacy of Control Room Emergency Ventilation Sys & Control Room Habitability,Per Tl Chan 860507 Concerns.Complete Reanalysis of NUREG-0737,III.D.3.4 Requirements Will Be Completed Prior to Startup Project stage: Other ML20195F0061986-06-0404 June 1986 Forwards Revised Dose Calculation Analysis & Schedule for Completion of Control Room Emergency Ventilation Sys & Revised CB-1 Action Plan,Per 860528 Request Project stage: Other ML20205T6301986-06-13013 June 1986 Forwards Revised CB-1 Action Plan,Control Room Pressurization Test Results & Summary of Control Bldg HVAC Operation,Per 860609 Telcon Re Control Room Emergency Ventilation Project stage: Other IR 05000344/19860211986-06-13013 June 1986 Insp Rept 50-344/86-21 on 860522-0606.No Violations or Deviations Noted.Major Areas Inspected:Activities Re Periodic Containment Integrated Leak Rate Test,Including Review of Procedures & Personnel Interviews Project stage: Request IR 05000344/19860271986-07-14014 July 1986 Enforcement Conference Rept 50-344/86-27 on 860709.Major Areas Discussed:Apparent Violation Noted During Special Insp of QC Activities (Insp Rept 50-344/86-24) Project stage: Request ML20212K5131986-08-14014 August 1986 Notice of Withdrawal of Portions of 850419 Application for Amend to License NPF-1,revising Tech Specs to Permit Performance of Surveillance Testing of Control Room Emergency Ventilation Sys Project stage: Withdrawal ML20212K5051986-08-14014 August 1986 Forwards Notice of Withdrawal of Portions of 850419 Application for Amend to License NPF-1,per Util 860714 Request Project stage: Withdrawal ML20214Q8211986-09-19019 September 1986 Summary of 860528 Meeting W/Util & Bechtel in Bethesda,Md Re Control Room Emergency Ventilation Sys,Per TMI Action Item III.D.3.4 on Control Room Habitability.List of Attendees Encl Project stage: Meeting ML20215C2151986-09-30030 September 1986 Forwards Revised Toxic Gas Analysis Re NUREG-0737,III.D.3.4, Control Room Habitability, Justifying Deletion of Ammonia & Sulfur Dioxide Detectors.Implementation Plan for Design Changes & Related Info Encl Project stage: Other ML20207C6791986-12-24024 December 1986 Requests Expedited Review & Approval of Control Room Emergency Ventilation Sys (CB-1) Testing Changes Requested in Re TMI Action Item III.D.3.4, Control Room Habitability. Control Room Cooling Design Change Described Project stage: Other 1986-05-07
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20199E1051999-01-13013 January 1999 Summary of 981119 Meeting with Util to Discuss Pge Preliminary Plans for Final Site Radiation Surveys at Trojan Nuclear Plant.List of Attendees Encl ML20198B7641998-12-16016 December 1998 Summary of 981119 Meeting with Util & NRC Re Issues Pertaining to Portland General Electric ISFSI Emergency Plan.Attendance List Encl ML20155C5561998-10-28028 October 1998 Summary of 981008 Meeting with Portland General Electric in Rockville,Md Re Util 10CFR72 License Application.Attendance List,Agenda & Slide Presentation Matl,Encl NUREG-0782, Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl1998-06-16016 June 1998 Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl ML20141H7051997-05-19019 May 1997 Summary of 970508 Meeting W/Util Mgt to Provide Info to NRC Re Decommissioning Plans for Plant.List of Meeting Attendees Encl ML20129E2231996-09-24024 September 1996 Summary of 960911 Meeting W/Licensee in Washington,Dc Re Plant SFP Debris Recovery Program.List of Attendees & Copy of Licensees Handout Encl ML20129G2581996-04-11011 April 1996 Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo) ML20059F2621994-01-10010 January 1994 Summary of 931130 Meeting W/Util at Plant to Discuss Variety of Topics Related to Efforts by Licensee to Decommission Facility ML20058B5681993-11-18018 November 1993 Trip Rept of 931102 Meeting Between NRC & Util Re Planned Research on naturally-aged Cables from Plant ML20055G9391990-07-19019 July 1990 Summary of 900612 Meeting W/Util Re Reactor Protection Sys Walkdown Results & Proposed Mods.List of Attendees & Handouts Encl ML20196C2491988-11-30030 November 1988 Summary of 881110 Meeting W/Util & B&W to Discuss Use of B&W Mfg Fuel at Facility.Handouts from Meeting & List of Attendees Encl ML20155B8231988-09-20020 September 1988 Summary of Operating Reactors Events Meeting 88-37 on 880920.Info Encl Includes rept-to-date of long-term Followup Assignments & Summary of Reactor Scrams ML20196L2221988-06-23023 June 1988 Summary of 880531 Meeting on Pressurizer Surge Line Movement & Pipe Whip Restraint Program.List of Attendees & Presentation Handouts Encl ML20196F9951988-02-24024 February 1988 Partially Withheld Trip Rept of 880209-11 Mgt Team Visit to Region V & San Onofre & Trojan Sites Re Integrated Assessment of Mgt Effectiveness Associated W/Regionalized NRR & NMSS Programs ML20148H6621988-01-15015 January 1988 Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl ML20235R3671987-09-30030 September 1987 Summary of 870820 Meeting W/Util Re Adequacy of Support Design Verification.List of Attendees Encl ML20235G8061987-09-25025 September 1987 Summary of 870715 Meeting W/Util,Bechtel & Gao Re Main Steam Support Adequacy & Main Feedwater Pipe Thinning.List of Attendees & Util Presentation Encl ML20237J6311987-08-13013 August 1987 Trip Rept of 870722-23 Site Visit to Gather First Hand Info Re Main Feedwater Line Pipe Wall Thinning Problem,Review Licensee Pipe Wall Thinning Monitoring Program & Evaluate Results of Licensee Failure Analysis ML20236L3451987-07-30030 July 1987 Summary of 870617 Meeting W/Util,Bechtel & Impell Re Results of Analyses Concerning Accumulator Fill Line Failure,Main Feedwater Failure & Main Steam Line Thin Wall at Plant.List of Attendees & Viewgraphs Encl ML20245B9271987-06-25025 June 1987 Summary of 870317-18 Meeting at Facility Re SPDS & Dcrdr. Dcrdr Discussions Centered on Certain Human Engineering Deficiencies Whose Resolution Required Addl Info &/Or in-plant Verification ML20215J2291987-06-22022 June 1987 Summary of Meeting W/Util on 870408 in Bethsda,Md Re Technical Issues Related to Util Amend Request for F* Steam Generator Tube Plugging Criteria.Attendees List & Meeting Viewgraphs Encl ML20204E4951987-03-19019 March 1987 Summary of Operating Reactor Events Meeting 87-07 on 870316. List of Attendees,Events Discussed & Significant Elements of Events Presented & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl ML20214P8971986-11-25025 November 1986 Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl ML20210L7201986-09-24024 September 1986 Summary of 860529 Meeting W/Util in Bethesda,Md Re Inoperable Steam Generator Hydraulic Snubbers Relationship to Restrained Thermal Growth of Rcs.Supporting Info Encl ML20214Q8211986-09-19019 September 1986 Summary of 860528 Meeting W/Util & Bechtel in Bethesda,Md Re Control Room Emergency Ventilation Sys,Per TMI Action Item III.D.3.4 on Control Room Habitability.List of Attendees Encl ML20203N0411986-09-18018 September 1986 Summary of 860513-14 Meetings W/Util at Site & in Portland, or Re Current Licensing Activities & to Meet W/Plant & Corporate Staff as Result of Appointment of New NRC Plant Manager.Attendees List Encl ML20210S2271986-05-15015 May 1986 Trip Rept of 860510-11 Site Visit to Participate in Licensee Cold Walkdown of Reactor Coolant Loop Piping & Components, Including Supports,To Assess Whether Cause of LER 85-013, Rev 1 Determined ML20154N8751986-03-12012 March 1986 Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20154C9931986-02-24024 February 1986 Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl ML20151Y0031986-01-29029 January 1986 Summary of 860108-09 Meetings W/Util in Bethesda,Md Re Current Licensing Activities & Reestablishment of Compatible Priorities & Schedules Since NRR Reorganization.Attendee List Encl ML20137M6361986-01-14014 January 1986 Summary of 851126 Meeting W/Util at Site Re Five Requested Exemptions from Specific Requirements of Section Iii.G of App R (Fire Protection).List of Attendees & Request for Info Encl ML20141F0461985-12-30030 December 1985 Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl ML20137X5091985-11-29029 November 1985 Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl ML20136C5141985-11-11011 November 1985 Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl IA-85-353, Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl1985-07-15015 July 1985 Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl ML20134A5161985-07-15015 July 1985 Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl ML20126L2331981-05-0101 May 1981 Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation ML20062J7361980-10-20020 October 1980 Summary of 800930 Meeting W/Util & Westinghouse Re Lab Examination Results for Steam Generator Row 1 U-bend Tube Samples Removed from Plant ML20125C1751979-12-19019 December 1979 Summary of 791205-06 Meeting W/Util & Bechtel Re Discussion of LER 79-15 Wherein Certain Problems W/Masonry Block Walls & Support Reactions of Equipment/Piping Attached Thereto Were Identified ML20245C3211977-07-11011 July 1977 Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls ML20196H3251976-06-29029 June 1976 Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl 1999-01-13
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20199E1051999-01-13013 January 1999 Summary of 981119 Meeting with Util to Discuss Pge Preliminary Plans for Final Site Radiation Surveys at Trojan Nuclear Plant.List of Attendees Encl ML20198B7641998-12-16016 December 1998 Summary of 981119 Meeting with Util & NRC Re Issues Pertaining to Portland General Electric ISFSI Emergency Plan.Attendance List Encl ML20155C5561998-10-28028 October 1998 Summary of 981008 Meeting with Portland General Electric in Rockville,Md Re Util 10CFR72 License Application.Attendance List,Agenda & Slide Presentation Matl,Encl NUREG-0782, Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl1998-06-16016 June 1998 Summary of 980318 Meeting W/Portland General Electric Re Util Plans for Disposal of Trojan Reactor Vessel.List of Attendees & Copy of Util Matls,Encl ML20141H7051997-05-19019 May 1997 Summary of 970508 Meeting W/Util Mgt to Provide Info to NRC Re Decommissioning Plans for Plant.List of Meeting Attendees Encl ML20129E2231996-09-24024 September 1996 Summary of 960911 Meeting W/Licensee in Washington,Dc Re Plant SFP Debris Recovery Program.List of Attendees & Copy of Licensees Handout Encl ML20129G2581996-04-11011 April 1996 Summary of ACRS Fire Protection Subcommittee Meeting on 960229 in Rockville,Md to Gather Info Re Probabilistic Risk Assessment (PRA) Model for Evaluating Fire Risk During self-induced Station Blackout (Sisbo) ML20059F2621994-01-10010 January 1994 Summary of 931130 Meeting W/Util at Plant to Discuss Variety of Topics Related to Efforts by Licensee to Decommission Facility ML20055G9391990-07-19019 July 1990 Summary of 900612 Meeting W/Util Re Reactor Protection Sys Walkdown Results & Proposed Mods.List of Attendees & Handouts Encl ML20196C2491988-11-30030 November 1988 Summary of 881110 Meeting W/Util & B&W to Discuss Use of B&W Mfg Fuel at Facility.Handouts from Meeting & List of Attendees Encl ML20155B8231988-09-20020 September 1988 Summary of Operating Reactors Events Meeting 88-37 on 880920.Info Encl Includes rept-to-date of long-term Followup Assignments & Summary of Reactor Scrams ML20196L2221988-06-23023 June 1988 Summary of 880531 Meeting on Pressurizer Surge Line Movement & Pipe Whip Restraint Program.List of Attendees & Presentation Handouts Encl ML20148H6621988-01-15015 January 1988 Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl ML20235R3671987-09-30030 September 1987 Summary of 870820 Meeting W/Util Re Adequacy of Support Design Verification.List of Attendees Encl ML20235G8061987-09-25025 September 1987 Summary of 870715 Meeting W/Util,Bechtel & Gao Re Main Steam Support Adequacy & Main Feedwater Pipe Thinning.List of Attendees & Util Presentation Encl ML20236L3451987-07-30030 July 1987 Summary of 870617 Meeting W/Util,Bechtel & Impell Re Results of Analyses Concerning Accumulator Fill Line Failure,Main Feedwater Failure & Main Steam Line Thin Wall at Plant.List of Attendees & Viewgraphs Encl ML20245B9271987-06-25025 June 1987 Summary of 870317-18 Meeting at Facility Re SPDS & Dcrdr. Dcrdr Discussions Centered on Certain Human Engineering Deficiencies Whose Resolution Required Addl Info &/Or in-plant Verification ML20215J2291987-06-22022 June 1987 Summary of Meeting W/Util on 870408 in Bethsda,Md Re Technical Issues Related to Util Amend Request for F* Steam Generator Tube Plugging Criteria.Attendees List & Meeting Viewgraphs Encl ML20204E4951987-03-19019 March 1987 Summary of Operating Reactor Events Meeting 87-07 on 870316. List of Attendees,Events Discussed & Significant Elements of Events Presented & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl ML20214P8971986-11-25025 November 1986 Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl ML20210L7201986-09-24024 September 1986 Summary of 860529 Meeting W/Util in Bethesda,Md Re Inoperable Steam Generator Hydraulic Snubbers Relationship to Restrained Thermal Growth of Rcs.Supporting Info Encl ML20214Q8211986-09-19019 September 1986 Summary of 860528 Meeting W/Util & Bechtel in Bethesda,Md Re Control Room Emergency Ventilation Sys,Per TMI Action Item III.D.3.4 on Control Room Habitability.List of Attendees Encl ML20203N0411986-09-18018 September 1986 Summary of 860513-14 Meetings W/Util at Site & in Portland, or Re Current Licensing Activities & to Meet W/Plant & Corporate Staff as Result of Appointment of New NRC Plant Manager.Attendees List Encl ML20154N8751986-03-12012 March 1986 Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20154C9931986-02-24024 February 1986 Summary of Operating Reactors Event Meeting 86-04 on 860210.List of Attendees,Briefing & Reactor Scram Summaries Encl ML20151Y0031986-01-29029 January 1986 Summary of 860108-09 Meetings W/Util in Bethesda,Md Re Current Licensing Activities & Reestablishment of Compatible Priorities & Schedules Since NRR Reorganization.Attendee List Encl ML20137M6361986-01-14014 January 1986 Summary of 851126 Meeting W/Util at Site Re Five Requested Exemptions from Specific Requirements of Section Iii.G of App R (Fire Protection).List of Attendees & Request for Info Encl ML20141F0461985-12-30030 December 1985 Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl ML20137X5091985-11-29029 November 1985 Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl ML20136C5141985-11-11011 November 1985 Summary of Operating Reactors Event Meeting 85-21 on 851028.List of Attendees,Events Discussed & Completion Dates Assigned Encl ML20134A5161985-07-15015 July 1985 Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl IA-85-353, Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl1985-07-15015 July 1985 Summary of 840223 Meeting W/Util Re Spirit Lake Blockage & Flooding Potential.List of Attendees & Viewgraphs Encl ML20126L2331981-05-0101 May 1981 Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation ML20062J7361980-10-20020 October 1980 Summary of 800930 Meeting W/Util & Westinghouse Re Lab Examination Results for Steam Generator Row 1 U-bend Tube Samples Removed from Plant ML20125C1751979-12-19019 December 1979 Summary of 791205-06 Meeting W/Util & Bechtel Re Discussion of LER 79-15 Wherein Certain Problems W/Masonry Block Walls & Support Reactions of Equipment/Piping Attached Thereto Were Identified ML20245C3211977-07-11011 July 1977 Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls ML20196H3251976-06-29029 June 1976 Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl 1999-01-13
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September 190 1986 Docket No. 50-344 DISTRIBUTION Docket File OGC NRC PDR E. Jordan LICENSEE: Portland General Electric Local PDR B. Grimes PD#3 Rdg. ACRS(10)
FACILITY: Trojan Nuclear Plant S. Varga T. Quay T. Chan J. Hayes
SUBJECT:
MEETING
SUMMARY
REGARDING THE MAY 28, 1986 CONTROL ROOM HABITABILITY MEETING A meeting was held in Bethesda, MD with Portland General Electric Company (PGE) and NRC representative on May 28, 1986 to discuss the Control Room Emergency Ventilation System (CREVS) as it related to Control Room Habitability, TMI Action III.D.3.4. The staff's May 6,1986 request for additional information and PGE's May 19, 1986 response provided the background for discussion. A list of attendees is provided in Enclosure 1.
Discussions rentered around PGE's present and future activities regarding the correction of oeficiencies within the CREVS. Enclosure 2 identifies the major areas of concerns and proposed corrective actions. In cara ction with the corrective actions, the staff requested that PGE provide an update of their CREVS Action Plan (Attachment 2 to their May 19, 1986 respanse) with respect to commitments and schedules, in order for the staff to resolve concerns prior to restart from the 1986 refueling outage.
The NRC staff also requested that PGE provide a revised III.D.3.4 dose calculation utilizing input that was consistent with the implemented and proposed procedural and hardware changes, so that this concern could be resolved prior to restart.
PGE stated that revised Technical Specifications and an evaluation of toxic gas threats on the Control Room would be submitted to the staff by Septcmber 30, 1986. The staff concurred with this schedule.
On June 4, 1986, PGE provided the revised III.D.3.4 dose calculations and update of their CREVS Action Plan. A subsequent telephone conference on June 9,1986 provided additional clarification. These discussions and commitments were formalized in PGE's letter dated June 13, 1986.
DMginal .11gned ty Terence L. Chan, Project Manager Project Directorate #3 Division of PWR Licensing-A
Enclosure:
As stated cc: See next pa'e
- PD#3 . PW CV an TChan s arca 96 9/}]/86 E
/p/86 8609260334 860719 PDR ADOCK 05000344 P PDR
.~
,lk Mr. Bart D. Withers Portland General Eletric Company Trojan Nuclear Plant ec: . .
Senior Resident Inspector U.S. Nuclear Regulatory Commission -
Trojan Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Robert M. Hunt, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 William T. Dixon Oregon Department of Energy Labor and Industries Building Room 111 Salem, Oregon 97310 Regional Administrator, Region V U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 1450 Maria Lane, Suite 210 Walnut Creek, California 94596
o ENCLOSURE 1 LIST OF ATTENDEES -
MAY 28, 1986 CONTROL ROOM HABITABILITY Name Organization T. Quay NRC J. Hayes NRC K. Johnston NRC T. Chan NRC S. Varga NRC R. Jagels Bechtel R. Fosse Bechtel A. Go Bechtel P. Yundt PGE G. Zimmerman PGE D. Kenter PGE 4
ENCLOSURE 2 CONTROL ROOM VENTILATION Major Areas of Concern:
A. Filtered and Unfiltered Inleakage B. Ability to Maintain 1/8" Differential Pressure l
C. Adequate Toxic Gas Protection D. Single Failure Criteria E. Charcoal and Filter Performance F. Control Room Heat Load and Temperature C. Technical 8pecification and Procedure Improvements i
control Room Ventilation Page 1 of 9
A. Filtered and Unfiltered Inleakare Concern / Deficiencies:
- 1. CB-1B makeup flow was 450 cfm vs. 150 cfm. . .
- 2. CB-1A cooler duct housing was broken. -
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- 3. Open cooler drain on CB-1.
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- 4. Leakage around doors and penetrations. l
- 5. CB-2 and CB-12 damper leakage.
Conclusions:
The calculated dose that could have been received due to the above deficiencies would have exceeded acceptable levels without using breathing protection or KI tablets.
Corrective Actions:
i
- 1. The outside makeup air flow was adjusted to i 150 cfm. Disassembly and inspection of CB-1A revealed that the makeup flow control damper was rotated 90* from its control handle which accounts for it measuring only 125 cfa. Makeup air will be measured at least every refueling interval.
- 2. The broken CB-1A cooler duct housing was repaired when discovered.
A full inspection of all CB-1 ducting outside the control room will
- be completed at least every refueling interval. ~
- 3. The open drain line was capped when discovered. The drains were separated and valves installed on each line. Automatic drain traps will be installed after startup.
- 4. An extensive inspection of all control room boundary penetrations has been made. Several leak paths were identified which have been fixed.
- 5. Inspection and testing of all control room dampers has been completed. All damper gaskets have been repaired / replaced. The integrity of these dampers will be evaluated at least every refueling outage and a PM program implerented.
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B. Ability to Maintain 1/8" Differential Pressure Concerns / Deficiencies:
- 1. Control pressure was not maintained > 1/8" AP as compared to all
surrounding boundaries.
- 2. Operation of CB-5 on CB-10 effects the ability of CB-1 to' maintain j control room positive pressure.
- 3. CB-1 system was run with the outside makeup dampers closed, and therefore, it was not possible for it to maintain positive pressure.
! 4. Testing has shown that CB-1 system cannot maintain a positive 1/8" pressure with only 150 cfm makeup air.
Conclusions:
I PCs agrees that measures should be taken to ensure a positive pressure j for all control room boundaries (not just the outside), even though not
- required by Technical Specifications. Due to the location of where differential pressure is measured and operation of CB-5 and CB-10 I differential pressure as compared to the outside has not been consistently maintained > 1/8" of water as required by Technical
- specifications.
Corrective Actions:
{ 1. Permanent test instruments have been installed to measure
! differential pressure between the control room and surrounding j boundaries. Testing to ensure 1/8" differential pressure to i surrounding boundaries will be conducted at least every refueling I outage.
- 2. It is intended to implement a design change before startup to automatically trip CB-5 and CB-10 on an automatic start of CB-1. If this design change is not completed before startup, procedures will be implemented to ensure manual tripping until design changes are completed.
- 3. Procedure changes have been implemented to ensure CB-1 dampers open automatically on safety injection signal.
- 4. Design changes will be made before startup to increase the distance between the containment and the location of where makeup air is taken from 64 to 128 feet. This design change will allow increasing i the makeup flow from 150 cfm to 450 efm.
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s l
,~ C. Toxic Gas Protection Concern / Deficiencies:
- 1. Operation of CB-2 and CB-1 during a toxic gas event haf result in l high control room inleakage. ,
! 2. Operation of CB-5 snd CB-10 may result in high control room 1 inleakage.
i
- 3. Operators do not put on masks upon a toxic gas challenge.
- 4. Should ammonia detector be installed?
Conclusions:
i Operation of CB-2, CB-5 and CB-10 fans during a toxic gas event could have permitted more inleakage than if they were secured.
! Corrective Actions:
- 1. ONI-54, "High Toxic Cas concentration", has been revised to require securing CB-2 supply fans and starting CB-1 on recirculation only.
ONI-54 will be revised to require stopping CB-2 recirculation fan.
Differential pressure measurement will be verified at least every refueling outage to ensure there is no excessive differential pressure on any control room boundary.
l 2. ONI-54 will be revised to stop CB-5 and CB-10 on high tqxic gas. A l design change will be implemented to automatically stop these fans. ~
j Test will be conducted as noted above.
1
! 3. ONI-54 requires operator to don self-contained breathing apparatus, but not wear mask until the alarm is confirmed.
- 4. Analysis to determine if ammonia detectors should be installed is being performed.
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D. Ability to Meet sinale Failure Criteria s
Concerns / Deficiencies:
- 1. CB-1A and B cooler drains were cross-connected. , ,
- 2. Control room dampers for CB-2 and CB-12 do not meet single f ailure criteria.
- 3. CB-1 outside makeup damper may not meet single failure criteria.
- 4. High radiation signal should automatically initiate emergency ventilation the same as a safety injection signal.
Conclusion:
The CB-1 system itself meets single failure criteria. Some components that could effect the control room envelope do not meet sig'"
criteria. '7 f ailure Corrective Actions:
- 1. CB-1A and B cooler drains have been separated.
- 2. Installation of two dampers for CB-2 and CB-12 is being evaluated.
- 3. No changes are planned for CB-1.
- 4. Automatic actuation of emergency ventilation on a high radiation signal is being evaluated, but should be considered a back fit.
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1 Control Room Ventilation Page 5 of 9
E. Charcoal Filter performance Concerns / Deficiencies:
- 1. Charcoal testing is not conducted at appropriate toppgratures and relative humidity to ensure 95% removal of methyl radiolodine as assumed in analysis. .
- 2. With a flow of 3.200 cfm i 10% results in residence time < 1/2 second, and therefore, efficiency < 95% removal of methyl radiolodine.
- 3. In-place DOP and freon tests should be based on .05% penetration not 1%.
Conclusion:
Charcoal and filter performance is still being evaluated, but presently it is . felt to be tested conservatively.
Corrective Action:
- 1. Charcoal test requirements will be reviewed and changed to ensure a 95% removal for methyl radiolodine which was assumed in analysis.
Technical specifications will be changed accordingly.
- 2. Actual flow conditions have been about 3,000 cfm. Flows required to ensure removal efficiency of 95% will be evaluated and implemented.
Technical Specifications will be changed accordingly.
- 3. In-place DOP and freon testing being evaluated, but the reason forI this concern is not clear.
l l Control Room Ventilation page 6 of 9 l
F. Control Room Heat Load and Temperature Concerns / Deficiencies:
- 1. Control room equipment is monitored at an incorrect location.
- 2. Heaters should be turned on instead of set at 70% to cycle on as humidity increases above 70%.
Conclusion:
The control room air temperature is being maintained < 110*F as designed and required by Technical Specifications.
Corrective Actions:
- 1. Control room temperatures and heat load are being evaluated, but any changes should be evr.luated under back fit requirements. '
- 2. The basis for turning the heater on during testing (other than drying out the charcoal) is not understood since these are not the conditions during actual operations. This should be evaluated unda back fit requirements.
Control Room Ventilation Page 7 of 9
C. Technical Specifications and Procedures Concerns /Deficiencly:
- 1. Toxic gas monitors and control room ventilation should be operable in all modes.
- 2. Analysis indicates that control room isolates in three seconds at a concentration of 1 ppm. Technical specifications show actuation at i 5 ppm. i
- 3. Several procedural discrepancies have been identified.
Conclusions:
Technical Specifications and procedures can be improved.
Corrective Actions:
- 1. Technical Specification changes will be submitted to be consistent with standard Technical Specifications.
- 2. Technical Specification changes will be submitted to be consistent with analysis.
- 3. All procedural discrepancies will be reviewed and procedures revised.
I i
i DRK:bjp 70133z Control Room Ventilation Page 8 of 9 l
l i
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, CONTROL ROOM HVAC OPgRATION CB-2 CB-2 CB CB-1 ,C4-1 CB-5 Recire M/U 3&4 Fans M/U CB-10 Closed (2)
Normal Operations ON ON ON OFF Red Flagged ON SIS OFF OFF OFF ON Open OFF High Radiation Auto OFF OFF OFF OFF Closed (2) OFF Red Flagged Manual (1) OFF OFF OFF ON Open OFF Toxic Gas Auto ON OFF OFF OFF Closed (2) OFF Red Flagged Manual (1) OFF OFF OFF ON Closed OFF POT-20-1 Test OFF OFF OFF ON Closed OFF Carbon Dry ON ON ON ON Closed ON (1) Manual actions are actions required by ONI-12 or ONI-54.
(2) Damper is normally closed (green light) with control switch red flagged.
This allows damper to auto open when CB-1 starts. If switch is green l flagged, damper will not open when CB-1 starts.
i control Room Veintilation Page 9 of 9 e
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