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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20196J4111999-06-30030 June 1999 Summary of 990524 Meeting with Util in Rockville,Md to Discuss Technical Issues Re Proposed Rerack of Spent Fuel Pool at Plants.List of Attendees & Handouts Encl ML20217H8081998-03-31031 March 1998 Summary of 980306 Meeting W/Util in Rockville,Md Re Status of Licensing Issues for Byron Station,Units 1 & 2 & Braidwood Station,Units 1 & 2.List of Attendees Encl ML20211P3421997-09-23023 September 1997 Summary of 970904 Meeting W/Commonwealth Edison Co in Rockville,Md Re Methodology for Calculating Radiation Doses in Control Room & at Eab & LPZ in Event of MSB Outside Containment.List of Attendees & Licensee Presentation Encl ML20210Q1281997-08-25025 August 1997 Summary of 970723 Meeting W/Util in Rockville,Md Re Util Assessment of Spring 1997 Eddy Current Insp of Plant SG Tubes.List of Attendees & Handouts Presented Encl ML20141F3641997-06-27027 June 1997 Summary of 970430 Meeting W/Licensee in Rockville,Md to Discuss Various Aspects of SG Eddy Current Insp Conducted at Plants During Spring 1997 Refueling Outage.List of Attendees & Licensee Handouts Encl ML20138L0741997-02-18018 February 1997 Summary of 970123 Meeting W/Commonwealth Edison Co to Discuss Plant Amend Request to Convert Current TSs ML20134M3841997-02-13013 February 1997 Summary of 970128 Meeting W/Util to Discuss Program to Dispose of Weapons Grade Pu Through Use as Mixed Oxide Fuel. List of Attendees & Matl Used in Presentation Encl ML20134G7011997-02-0707 February 1997 Summary of 970122 Meeting W/Util Re Program for Replacement of SG at Licensee Facilities.List of Attendees & Matl Used in Presentation Encl ML20133J0641997-01-13013 January 1997 Summary of 960821 Meeting W/Comed to Discuss Status of SG Replacement Program W/Nrc Staff.List of Attendees & Util Presentation Encl ML20149M3131996-12-10010 December 1996 Summary of 961114 Meeting W/Representives of CE in Rockville,Md to Discuss Status of Ongoing Braidwood,Unit 1, SG Tube Insp.List of Attendees & Slides Encl ML20129F9431996-10-25025 October 1996 Summary of 961004 Meeting W/Representatives of CE in Rockville,Md to Discuss Technical Basis for Licensee Pending Proposal to Delete Braidwood Unit 1 mid-cycle SG Eddy Current Insp.List of Attendees & Matls Discussed Encl ML20129G8501996-07-0505 July 1996 Summary of ACRS Joint Subcommittee Matl & Metallurgy & Severe Accidents Meeting on 960603-04 to Gather Info on Status of Activities Associated W/Development of Proposed Rule Re SG Integrity ML20149D6051993-09-15015 September 1993 Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues ML20029B3591991-02-26026 February 1991 Summary of 910205 Meeting W/Util Re Generic Licensing Issues & Plant Specific Concerns.Agenda & List of Attendees Encl ML20011F6111990-02-28028 February 1990 Summary of Operating Reactors Events Meeting 90-05 on 900228 ML20006E7251990-02-12012 February 1990 Summary of Operating Reactors Events Meeting 90-03 on 900207.List of Attendees & Viewgraphs Encl ML20005E8421989-12-27027 December 1989 Summary of Operating Reactor Events Meeting 89-045 on 891227.List of Attendees & Significant Elements Discussed Encl ML20005D8121989-12-18018 December 1989 Summary of Operating Reactors Events Meeting 89-044 on 891213.List of Attendees & Viewgraphs Encl ML19332G0601989-12-0707 December 1989 Summary of Operating Reactors Events Meeting 89-43 on 891206.On 891128,high Cycle Fatigue Failure of Master Connecting Rod Assembly Occurred at South Texas,Unit 2.RHR Leakage Noted on 891201 at Braidwood,Unit 1 ML20005D6871989-12-0101 December 1989 Summary of Operating Reactors Events Meeting 89-042 on 891129.List of Attendees & Viewgraphs Encl ML19332D2821989-11-16016 November 1989 Summary of Operating Reactors Events Meeting 89-040 on 891115 ML19327C0541989-11-0202 November 1989 Summary of 891019 Meeting W/Sys Energy Resources,Inc, Louisiana Power & Light & Arkansas Power & Light Re Antitrust Concerns W/Consolidation of Operations Under Entergy Operations,Inc.List of Attendees & Viewgraphs Encl ML19325E8981989-11-0101 November 1989 Summary of Operating Reactors Events Meeting 89-38 on 891101 to Brief Senior Managers from Nrr,Aeod,Res,Region Ofc & Commission on Selected Events That Occurred Since 891018 Meeting.List of Attendees Encl ML19325E1761989-10-24024 October 1989 Summary of Operating Reactors Events Meeting 89-37 on 891018.List of Attendees & Events Briefing Encl ML19325D9211989-10-19019 October 1989 Summary of 891012 Meeting W/Sys Energy Resources,Inc, Arkansas Power & Light,Inc & Louisiana Power & Light,Inc at NRC Headquarters to Discuss Consolidation of Operations Under Entergy Operations,Inc.List of Attendees Encl ML20247R0161989-09-21021 September 1989 Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20245G5421989-08-0303 August 1989 Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl ML20248B5171989-08-0303 August 1989 Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl ML20246P7771989-07-13013 July 1989 Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl ML18153B7971989-07-0606 July 1989 Summary of 890612 Meeting W/Util in Rockville,Md Re Plant Configuration Mgt Program.Informs That Goal of Program Is to Confirm That as-built Plants in Conformance W/Licensing Design Basis as Described in FSAR ML20246F8691989-06-22022 June 1989 Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2 ML20245G6411989-06-15015 June 1989 Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram ML20245F2221989-06-0808 June 1989 Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl ML20245A3851989-05-30030 May 1989 Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl ML20247M7961989-05-24024 May 1989 Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247J6991989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl ML20247J7051989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy ML20247D3441989-05-16016 May 1989 Summary of Operating Reactors Events Meeting 89-19 on 890510.List of Attendees,Events Discussed & Significant Elements of Events & Rept of long-term Followup Assignments & Summary of Scrams for Wk Ending 890507 Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20246L7281989-05-0505 May 1989 Summary of 890503 Meeting W/Util in Rockville,Md Re Containment Vessel Structural Integrity Tech Specs for Plants.List of Attendees & Licensee Presentation Encl ML20246C3261989-05-0404 May 1989 Summary of Operating Reactors Events Meeting 89-18 on 890503 ML18153B7071989-05-0404 May 1989 Summary of 890419 Meeting W/Util in Rockville,Md Re Followup on NRC Bulletin 80-11, Masonry Wall Design. NRC Requested Documentation of as-built Boundary Conditions, Available Conservatisms & Field Verifications ML20246B5161989-04-28028 April 1989 Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts Encl ML18153B6791989-04-11011 April 1989 Summary of 890330 Meeting W/Util in Rockville,Md Re Util Overall long-term Improvement Plan to Enhance Plant Operations ML20248K3761989-04-10010 April 1989 Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl 1999-06-30
[Table view] Category:TRIP REPORTS
MONTHYEARML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20154L1661988-05-10010 May 1988 Trip Rept of 880412-15 Mgt Team Visit to Plant Sites,Two Matls Licensees & Region I Ofcs.List of Team Members & Summary of Observations & Perceptions from Visit Encl.Info Deleted 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 ML20151W0041987-03-12012 March 1987 Submits After Trip Rept ML20147E8911986-08-20020 August 1986 Trip Rept of 860721-25 Visit to Plant to Observe INPO Accreditation Team Evaluation of Six Training Programs, Including Instrumentation & Control Technician,Mechanical Maint & Electrical Maint.List of Team Members Encl ML20213F8661986-07-31031 July 1986 Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl IA-86-778, Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl1986-07-31031 July 1986 Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl ML20206J6561986-06-23023 June 1986 Trip Rept of 860612 Training Session in Lacey,Wa Re Federal Radiological Emergency Response Plans & Meeting W/Utils & State of Wa Concerning Potential Emergency Preparedness Issues.Attendees Listed & Training Agenda Encl ML20244D8391986-05-0707 May 1986 Trip Rept of 860415 Site Visit Re Demonstration for Ultrasonic Exam Procedure of Statically Cast Stainless Steel Primary Loop Welds.Issue of Preservice Ultrasonic Exam of Welds Resolved.Trip Repts by Inel & Bnwl Encl ML20244D8401986-04-22022 April 1986 Trip Rept of 860415 Site Visit Re Demonstration of Ultrasonic Exams Performed on Cast Stainless Steel Primary Piping Welds.Exam Procedure Appears to Meet or Exceed ASME Code Requirements.Written Procedure Not Available ML20154L9181986-03-0606 March 1986 Trip Rept of 851021-24 Site Visits Re Wrong Unit/Wrong Train Events to Determine Whether Simple,Low Cost Improvements Can Be Identified & Implemented ML20237C9681986-02-19019 February 1986 Trip Rept of Attendance at State of Il 860213 Meeting Re Training Session on NRC Incident Response Program & NRC Participation in 860408 Plant Emergency Exercise.List of Attendees & Partial Agenda Encl ML20141H8551986-01-10010 January 1986 Trip Rept of 851112-15 Site Visits Re Wrong Unit/Wrong Train Events.Visit Conducted as Part of short-term Effort to Determine If Low Cost Improvements Can Be Identified & Implemented to Reduce Frequency of Events ML20138A1201985-09-23023 September 1985 Trip Rept of 850617-20 Site Visits Re Reduction of Wrong Unit/Wrong Train Events at Facilities ML20147E2301985-06-0303 June 1985 Trip Rept of 850420-22 Visit to Port Gibson,Ms,To Participate in Field Test of Draft Training Review Criteria & Procedures at Plant.Nrc Teams Observed Licensed Operator & Nonlicensed Operator Training ML20133B8781985-03-15015 March 1985 Trip Rept of 850315 Site Visit Re Presentation of Licenses to Senior Reactor Operators & Reactor Operators.Subjs Discussed During Visit Stated ML20133B8521985-02-26026 February 1985 Trip Rept of 850207-08 Site Visit Re Status of Licensee Performance Enhancement Program & Status of Action Plan Being Used to Improve Overall Training Effort ML20136F6871985-02-0505 February 1985 Trip Rept of 841203-07 Visit to Bechtel in Norwalk,Ca Re Structural Engineering Design Audit Based on Util 841031 Submittal of Design Rept.List of Attendees,Agenda & Addl Info Required for Satisfactory Question Response Encl ML20199G3181985-01-15015 January 1985 Trip Rept of 841114-16 Site Visit Re Meetings W/Qa/Qc Inspectors to Emphasize That All Safety Issues Must Be Resolved Before Units Can Be Licensed ML20147E0431985-01-10010 January 1985 Trip Rept of 850930-1004 Observation of INPO Accreditation Team Evaluation of Plant Training Programs,Including Licensed Reactor Operator,Nonlicensed Operator & Shift Technical Adviser.Inpo Evaluation Team Member List Encl ML20237D0071985-01-10010 January 1985 Trip Rept of 871112-15 Visit to Sites to Determine Whether Simple,Low Cost Improvements Can Be Identified & Implemented to Reduce Frequency of Wrong Unit/Wrong Train Events ML20209D3321984-09-21021 September 1984 Trip Rept of 840816-22 Visits to Lasl & Plant Re DHR & Unresolved Safety Issue A-45 ML20136F1681984-08-31031 August 1984 Trip Rept of 840621-22 Site Visits to Examine Clastic Dikes of Coastal Plain ML20136F1281984-08-0707 August 1984 Trip Rept of 840724 Site Visit Re Radiation Protection Facilities.Attendee List Encl ML20133B9461984-07-0505 July 1984 Trip Rept of 840703 Site Visit Re Training Organization & Programs.Program Not Implemented Due to Lack of Senior Mgt Support ML20127B5101984-04-13013 April 1984 Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed IA-85-160, Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed1984-04-13013 April 1984 Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed ML20149B6101984-03-28028 March 1984 Trip Rept of 840323 Visit to INPO to Respond to INPO Concerns Re Training & Qualifications Rulemaking Package (SECY-84-76).Accreditation Team Rept on McGuire Station Read & Questions Answered ML20115A0941984-02-0909 February 1984 Trip Rept of 830124-25 Site Visit Re Control Room Habitability.Hvac Sys Generic General Concerns & Overall Perspective Addressed ML20138M9741983-12-20020 December 1983 Trip Rept of 831129-30 Site Visit Statistical Analysis of Backfit Insp Program ML20132B6931983-11-21021 November 1983 Trip Rept of 831104-05 Site Visit & Meeting to Formulate Final Objectives,Guidance & Schedule for Initial full-scale Exercise ML20080D2771983-10-31031 October 1983 Trip Rept of 830622-24 Caseload Forecast Panel Site Visit Re Plant Status Review.Projected Fuel Load Date Comparisons Listed ML20080D2631983-10-31031 October 1983 Draft Trip Rept of Caseload Forecast Panel 830222-24 Site Visits Re Const Progress Review & Estimating Resource Needs for Licensing Activities ML20209C3391983-08-0808 August 1983 Trip Rept of Attendance at 830727 Meeting in San Francisco, CA Between Idvp & Util Re Status of Closure Efforts on Open Items in Idvp Final Rept.Projected Date for Issuance of Idvp Final Rept Suppl Is mid-Sept 1983 ML20080D2971983-07-27027 July 1983 Summary of 830622-24 Caseload Forecast Panel Site Visit Re Plant Status Review ML20151H8231983-07-26026 July 1983 Trip Rept of 830712 & 15 Site Visit Re Fire Protection Site Audit.List of Agreements & Concerns Discussed Encl ML20209C3101983-07-25025 July 1983 Trip Rept of 830607 Visit to San Francisco,Ca to Observe Test Program Developed by Util & Bechtel.Program Was to Determine Statistically Spot Weld Capacity of Superstrut Matl Installed at Plant ML20209C2311983-06-30030 June 1983 Trip Rept of Attendance at 830512 Technical Interchange Meeting W/Util & Independent Verification Program Staff Re Containment & Turbine Bldgs & Control Room.Attendee List Encl ML20209C1171983-04-29029 April 1983 Trip Rept of 830425 Visit to Bechtel in Gaithersburg,Md to Review Grand Gulf Cable Tray Support Calculations for Use in Resolution of Allegation Concerning Superstrut Spot Welds at Diablo Canyon ML20080D2551983-03-18018 March 1983 Marked-up Draft Summary of Trip Rept of Caseload Forecast Panel 830222-24 Meetings Re Const Progress Review & Mgt Decision on Allocation of Staff Resources During Licensing Review ML20205T5371983-02-15015 February 1983 Trip Rept of 830126 Meeting in Bethesda to Discuss Question of Corrective Actions to Be Required of Util Re Finding of Uncertified QC Inspectors at Site ML20209B9941983-02-14014 February 1983 Trip Rept of 830126 Meeting W/Rl Cloud & Assoc in Berkeley, CA to Clarify Items Re Interim Technical Rept (Itr) 12, Independent Design Verification Program (Idvp) - Piping & Itr 17, Idvp - Piping,Addl Samples ML20209B8411983-01-10010 January 1983 Trip Rept of 821202 Meeting W/Teledyne Engineering Svcs, Bechtel,Bnwl,Norton,Burke,Berry & French,Util,State of CA, Hhb & Urs/Blume to Discuss Listed Portions of Independent Design Verification Program ML20070V1351982-12-20020 December 1982 Trip Rept of 820913-17 Visit to Facility to Review Seismic & Dynamic Qualification Methods,Procedures & Results for safety-related Mechanical & Electrical Equipment & Observe Field Installation of Equipment ML20209B7941982-11-30030 November 1982 Trip Rept for 821112 Info Exchange Meeting Between Teledyne Engineering Svcs & Util in Waltham,Ma to Review Corrective Action Plans for Annulus Structure ML20209B7801982-10-28028 October 1982 Trip Rept of 820920-23 Visit to Site & Escondido,Ca Re NRC & Us Coastal Engineering Research Hydrologic Engineering Review Comments on Breakwater/Intake Structure Repts for Jul 1982 ML20134B4611982-09-16016 September 1982 Trip Rept of 820830-31 Visit to Bechtel,Norwalk,Ca to Observe Region IV Insp Concerning Effectiveness of Util/ Bechtel Processing of Field Change Notices for Facility Const.Supporting Documentation Encl ML20083L8031982-09-0202 September 1982 Trip Rept of 820813 Site Visit Re Replacement of Recirculation Sys Piping ML20069D1861982-08-30030 August 1982 Trip Rept of 820915-18 Seismic Qualification Review Team Site Visit Re Performance of Plant Site Review for Selected safety-related,mechanical & Electrical Equipment.Revision to Site Visit Rept Encl.W/O Encl ML20080D6561982-08-19019 August 1982 Trip Rept of Caseload Forecast Panel 820811-13 Site Visits Re Status of Const & Preoperational Testing Evaluation. Related Info Encl 1989-08-24
[Table view] |
Text
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'o UNITED STATES
!%(,',%,I NUCLEAR REGULATORY COMMISSION
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W ASHINGTON. D. C. 20565 E 2 6 B83 MEMORANDUM FOR: Victor Benaroya, Chief Chemical Engineering Branch Division of Engineering THRU:
Robert Ferguson, Section Leader Chemical Engineering Branch Division of Engineering FROM:
Dennis Kubicki Chemical Engineering Branch Division of Engineering
SUBJECT:
TRIP REPORT:
FIRE PROTECTION SITE AUDIT - BYRON STATION UNITS 1 AND.t Plant Name:
Byron Station Units 1 and 2 Docket Numbers:
50-454 and 50-455 Licensing Stage: OL Responsible Branch:
LB -1; L. 01shan, PM Chen.ical Engineering Branch Reviewer:
D. J. Kubicki Between July 12 and 15,1983, we conducted our fire protection site audit at the Byron Station, Units 1 and 2.
A representative of our con-sultant, Gage Babcok & Associates, participated.
As a result of the audit, we reached several agreements regarding the adequacy of the fire protection program.
In addition, we expressed a number of concerns / questions pertaining to previous applicant commitments; the justification for particular fire protection designs; and tne degree of compliance with our fire protection criteria.
A summary of these issues is enclosed.
The applicant agreed to respond to our concerns.
M >1:~L Dennis Kubicki Chemical Engineering Branch Division of Engineering
Enclosure:
As stated
Contact:
D. Kubicki cc:
See next page O
ala g 3080 40619 Y
"A*-
Victor Benaroya cc:
R. Vollmer W. Johnston R. Ferguson T. Wambach R. Eberly S. Pawlicki T. Sullivan
- 0. Parr J. Wermiel J. Taylor C. Norelius, Region III D. Eisenhut T. Novak B. J. Youngblood L. 01shan F. Rosa M. Srinivasan R. Wessman R. Barnes (GBA) l t
9 1
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Enclosure Chemical Engineering Branch / Fire Protection Section Byron Station, Units 1 and 2 Docket Nos. 50-454 and 50-455 Introduction Between July 12 and 15, 1983, we conducted our fire protection site audit at the Byron Station, Units 1 and 2.
A representative of our consultsnt, Gage Babcock and Associates participated.
As a result of the audit, we reached a number of agreements regarding the adequacy of the fire protection program.
In addition, we expressed a number of concerns pertaining to previous applicant commitments; the justification for particula fire protection designs; and the degree of compliance with our fire protection criteria. The agreements and CJn-cerns can be summarized as follows:
Agreements 1.
The applicant has desigied those components required for hot shut-down so that rupture or inadvertent operation of fire suppression systems will not adversaly affect the operability of these compo-nents. Where necessary, apprcpriate protection is provided to pre-vent impingement of water spray on components required for hot shut-down.
Redundant trains of components that are susceptible to damage from water spray are physically separated so that manual fire sup-pression activities will not adversely affect the operability of components not involved in the postulated fire.
j 2.
The imtallation of a third fixed repeater for emergency commu-nications on the roof of the elevator machine room in the Turbine Building provides reasonable assurance that a single fire could not interrupt emergency communications in the plant. This modification complies with Section C.S.g of BTP CHEB 9.5.1.
l 1
2 3.
Because of the complete, area wide, automatic fire detection and suppression systems; the steel pipe construction and the insulation for the cooling water pipes in the diesel generator rooms, a fire in Room 18 will not damage cooling water pipes for both deisel gen-erators before being detected and extinguished.
Therefore, the routing of cooling water lines for diesel generator 1A through the room containing diesel generator 18 is an acceptable deviation from the technical requirements of Section III.G of Appendix R.
4.
With the exception of the two doors identified in item 16 (below),
the non-U.L. labeled doors, identified in Section 2-3 of the appli-cant's. Fire Protection Report, will achieve an equivalent level of safety to labeled fire doors and is, therefore, an acceptable deviation from the technical requirements of Section C.5.a of BTP CMEB 9.5.1.
Concerns The following is a list of fire protection concerns raised during the audit.
1.
In the August 16, 1982 revision to the Fire Protection Report, the applicant committed to seal fire barrier penetrations with material having a fire resistance rating comparable to the ratings of fire j
walls and floor / ceiling assemblies.
This necessitates that seal-int saterial be installed to an appropriate depth consistant with its U.L. listing. We observed that RTV silicon sealant material was installed in the plant in thicknesses greater than the depth 4
of the concrete floor slab.
This configuration does not appear to be consistent with the listing of the material. We are concerned that this sealant material will not be able to withstand anticipated I
fire exposures. The applicant should verify that penetration seals I
featuring silicon foam, as installed in the plant, are equivalent to the rating of the structural assembly.
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' 2.
The following features of the fire protection program were observed to be incomplete:
The installation of penetration seals in fire walls and fire rated floor / ceiling assemblies.
The provision of seismic supports for the hydrogen supply piping routed through tha Aux. Building.
The installation of fire proofing for steel structural elements.
The installation of fire hose nozzles, hose houses and hose-house fire fighting equipment.
The third repeater for the plant emergency communications network.
The 0.5. Y-type sectional control valve at the discharge outlet for the fire pumps to avoid the necessity of shutting off one fire pump in order to test the other.
The applicant should verify that these features of the fire protection program will be completed by fuel load.
3.
To comply with Section C.6.a of BTP CHEB 9.5.1, electrical circuits associated with automatic fire suppression systems, including fire detection circuits, are required to be Class "A" supervised such that system activation is possible automatically under a single break or ground fault condition.
Information was unavailable during the audit to completely verify this design feature in the plant. With the exception of the redundant fire detection systems in the cable spreading rocas, (where activation of either system initiates fire suppression system discharge), the applicant should verify that all circuits associated with automatic fire suppression systems are class "A",
including those circuits from the local fire alarm panels to the suppression system actuating mechanism.
, 4.
In the August 16, 1982 revision to the Fire Protection Report, the applicant committed to comply with Section C.5.d of BTP CMEB 9.5.1 and with Section C.7.b with the exception that an automatic fire suppression system will not be installed in "offices" in the control room complex. We obsevered that the computer related storage area adjacent to the control room is not squipped with an automactic fire suppression system which is not consistent with these commit-ments.
5.
To comply with Section C.6.c of BTP CMEB 9.5.1, interior manual I,ose stations should be installed so as to be able to reach any location that contains, or could present a fire exposure hazard to safety related equipment with at least one effective hose stream.
We observed that because of the present location of manual hose stations, it may not be possible to reach all areas of the computer room and cable riser area on elevation 451 feet.
The applicant shouid conduct a hose stretch test to verify the adequacy of the existing design.
We also observed that because of congested conditions in certain plant areas, such as the cable spreading rooms, it may not be pos-sible to utilize existing manual hose stations because of the in-ability to fully deploy the woven-jacketed fire hose.
In such areas, to comply with Section C.6.c of BTP CMEB 9.5.1, it will be necessary to replace t'te woven-jacketed hose with a hard rubber type.
- 6. In the August 16, 1982 revision to the fire Protection Report, the applicant committed to seal fire barrier penetrations with material having a fire resistance rating comparable to the rating of fire walls and floor / ceiling assemblies.
Information was unavailable during the audit to verify that bus duct penetrations of fire rated assemblies have been sealed internally with an appropriate fire rated material. The applicant should confirm that such penetrations are sealed to maintain the integrity of the barrier.
In additon,
. we observed that fire dampers were installed in a "ganged" configu-ration in several large ventilation openings in fire barriers, such as the diesel generator room exhaust vents.
This arrangement does not appear to be consistent with the listing of the damper.
The applicant should verify thtt the installation of the dampers in a ganged configuration will achieve 6 fire rating equivalent to that of the barriers in which they are installed.
7.
In the August 16, 1982 revision to the Fire Protectior Report, the applicant committed to comply with NFPA Standards 13 and 15 in the design and installation of fixed water extinguishing systems. We observed that manual discharge valves for the water deluge fire suppression systems protecting charcoal filter; would be inaccessible during a fire becausa of their closeness to the filters and the limited access in the area.
This condition appears contrary to the commitment.
8.
To comply with Section C.5.b of BTP CMEB 9.5.1 and Section III.G of Appendix R, structural steel forming a part of or supporting fire barriers should be i,rotected to provide fire resistance equivalent to that required of the barrier.
We observed that in the upper and lower cable penetration areas and in the Auxiliary Building General Floor area, on elevations 346 feet through 426 feet, the structural steel supporting the floors was unprotected.
We are concerned that a fire could cause the collapse of such elements and effect components / cables of redundant shutdown divisions located within the same floor elevation or on vertically adjoining elevations.
The applicant should provide protection for such structural steel commensurate with the fire exposure and the degree of separation between redundant shutdown divisions (see concern in item 18 below).
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We are also concerned that openings in non-fire rated barriers, I
such as equipment batches, removable concrete slabs, and unprotec-i ted stairway openings in the Auxiliary Building General Floor areas would subject redundant shutdown divisions, which are located on different elevations, to less from a single fire.
The applicant should provide fire protection commensurate with the hazard and in accordance with Section C.5.b of our fire protection guidelines or demonstrate that at least one shutdown division would remain free of damage from a vertically propagating fire.
9.
We observed several discrepancies in the description of fire protection features in the applicant's Fire Protection Report from what was observed in the plant.
Such discrepancies include the description of fire proofing for structtral steel, the extent of fire detection in safety related plar.t areas, the nature of fire doors and the lack of a fire hazard's analysis and fire protection for the "Med-Chem" area on elevation 401 feet.
10.
In our Safety Evaluation Report, we stated that an oil collection system for each reactor coolant pump was required in accordance with Section C.7.a of BTP CHEB 1.5.1.
Based on observations of conditions in containment as they pertain to the fire hazard posed by the reactor coolant pumps, our conclusion regarding the need for an RCP oil collection system remains unchanged.
11.
In the August 16, 1982 revision to the Fire Protection Report, the applicant committed to cogly with NFPA Standard No. 20 regarding the installation of fire pumps. We observed that an unlisted controller has been installed for the electric motor driven fire pump which is not consistent with that comitment, l
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. 12.
In the August 16, 1982 revision to the Fire Protection Report, the applicant committed to comply with Section C.5.d(1), "Control of Combustibles" of BTP CMEB 9.5.1.
In the diesel generator rooms and at the Auxiliary Fuel Pump Room, we observed that curbs were not provided at doorways into these areas and therefore, a potential 1
existed for a diesel fuel fire to propagate through the doorway into adjoining areas.
The applicant should provide curbs at these doorways to be consistent with their comitment.
13.
In the Fire Protection Report, the applicant coanitted to comply with NFPA Standard No.13 in the design of automatic sprinkler i
systems. We observed that the ceiling level sprnklers over the lube oil drain tank were obstructed, which is contrary to that commitment.
- 14. To comply with Section C.5.g(1) of BTP CMEB 9.5.1, fixed self-contained Ifghting consisting of flourescent or sealed beam units with individual 8-hour minimum battery power supplies should be provided in all plant areas that need to be manned for safe shutdown and all routes to these areas.
We observed that the t
Essential Safety Features Switchgear Room has not been provided 4
I with 8-hour battery powered emergency lighting as required. All
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other areas of the plant that are accessed for safe shutdown have been provided with emergency lighting off of individual battery units or the station batteries.
The use of station batteries represents a deviation from our fire protection guidelines.
To be considered acceptable, the applicant would have to demonstrate that a fire in an area containing emergency lighting off of the station batteries would not af fact battery powered emergency lighting in all other plant areas.
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. 15. The August 16, 1982 revision to the Fire Protecton Report identifies equipment located within the Control Room Refrigeration Equipment Dooms being necessary for safe shutdown.
We observed that comporents and cables from both shutdown division are vulnerable to damage from a fire in this room and therefore do not meet the guidelines of Section C.S.b of BTP CME 8 9.5.1.
16.
Labeled fire doors were not provided at the Auxiliary Fuel Pump Room and at the doorway in the fire wall at Column L-11 on elevation 401 feet, as committed to in the Fire Protection Report.
- 17. We observed that, because of the absence of an automatic fire suppression system and the lack of a fire wall between redundant divisions, both RHR pumps and related cabling are vulnerable to a fire located in the containment spray pump area.
To satisfy the guidelines in Section C.5.b of BTP CMEB 9.5.1, the unprotected openings in the wall separating the Division 11 RHR pump room from the containment spray pump area should be protected to prevent the passage of smoke and heat.
- 18. We observed that, because of the absence of automatic fire suppres-sion systems, area-wide smoke detection systems and/or physical sepLration between redundant divisions, both trains of shutdown related cabling and components are vulnerable to damage from a single fire in the following plant areas:
Non segregated bus duct area Aux. electrical equipment room Aux. building general area, Elevation 346 feet Aux. building general area, Elevation 364 feet Aux, building general area, Elevation 401 feet Aux. building general area, Elevation 426 feet Containment.
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s The fire protection for these areas is not in accordance with the guidelines in BTP CMEB 9.5.1 or Section III.G of Appendix R.
Out-side containment, the applicant should completely protect one shut-down division with a one-hour fire rated barrier wherever redundant divisions are located within 20 feet of one another or located more than 20 feet apart but the intervening space contains combustible material.
In addition, complete area-wide fire detection and automatic fire suppressian are required.
Inside containment, the fire protection guidelines of Section C.7.a of BTP CMEB 9.5.1 apply. To facilitate our evaluation of any deviation from our guidelines and to evaluate the adequscy of the applicant's response to Item 8 (above), the applicant j
should provide color coded drawings showing the relative location of redundant shutdown related cables for all fire areas.
NOTE Because no safe shutdown analysis was provided for Unit 2, our evaluation applies only to Unit 1.
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