|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML17146B1741999-08-0303 August 1999 GL 96-06 Risk Assessment for Sses. ML20195B2381999-03-31031 March 1999 Redacted Version for 10CFR2.790 Request for Decommissioning Status Rept for Sses,Units 1 & 2 ML20217Q4891998-04-21021 April 1998 Rev 1 to Draft LDCN 2482, FSAR Chapter 13.4 & FSAR Chapter 17.2 Changes to Support ITS Implementation ML20155F7661996-07-25025 July 1996 Partially Deleted Job Number 739619-96, Investigation of E Diesel Breaker Misalignment ML20155F7491996-07-24024 July 1996 Independent Safety Evaluation Svcs Project Rept 3-96, Investigation of E Diesel Generator In-Operability Event ML17164A6631995-04-11011 April 1995 Impact of Extending T-10 AOT from 3 to 7 Days. ML18026A5351994-10-31031 October 1994 SSES Unit 1 & 2 MSIV Leakage Alternate Treatment Method Seismic Evaluation. W/One Oversize Drawing ML17158A1631993-12-0909 December 1993 Remote Indication of Spent Fuel Pool Level & Temperature. ML18026A4281993-08-16016 August 1993 PP&L Response to NRC Concerns Re Loss of Spent Fuel Pool Cooling Following Loca,Sses,Units 1 & 2. ML17157C1421992-10-21021 October 1992 Engineering Assessment of Fuel Pool Cooling Piping EDR-G20020. ML17157C1401992-08-31031 August 1992 Review of Fuel Pool Cooling During Postulated Off-Normal & Accident Events SSES Units 1 & 2. ML17157C1411992-08-31031 August 1992 Loss of Fuel Pool Cooling Event Evaluation. ML20082C4941992-08-14014 August 1992 Evaluation of Unit 1 & Unit 2 Derating of Power Cables in Raceways Wrapped W/Thermo-Lag Matl ML17157C1381992-07-27027 July 1992 Safety Consequences of Boiling Spent Fuel Pool at Susquehanna Steam Electric Station. ML17157B0971990-11-0505 November 1990 COTTAP-2,Rev 1 Theory & Input Description Manual. ML20065L6651990-10-31031 October 1990 Environ Qualification Analysis of 250 Volt DC Limitorque Motor Operators for Valves Located Outside Containment of Susquehanna Steam Electric Station ML17157A4211990-08-31031 August 1990 Analysis of Pitting Corrosion Failures in ESW Sys RHR Lube Oil Coolers & RCIC Pump Room Unit Coolers at Susquehanna Steam Electric Station. ML17157A2171990-05-0303 May 1990 Rev 1 to SEA-EE-183, Evaluation of Unit 1 Computer Class 1E - Non-Class 1E Interfaces. ML17157A2191990-05-0303 May 1990 Rev 1 to SEA-EE-184, Evaluation of Unit 1 Annunciator Class 1E - Non-Class 1E Interfaces. ML17157A2201990-05-0303 May 1990 Rev 1 to SEA-EE-226, Evaluation of Welded Shut Class 1E Limitorque Limit Switches Used for Unit 2 Computer Inputs. ML17157A2221990-04-17017 April 1990 Rev 0 to SEA-EE-235, Evaluation of Potential High Voltage Sources Into Unit 1 & 2 Computers. ML17157A2211990-04-12012 April 1990 Rev 0 to SEA-EE-231, Evaluation of Welded Contacts of Class 1E Circuit Breaker Auxiliary Switches & Limit Switches Used for Unit 2 & Common Annunciator Inputs. ML20005F9831990-01-0505 January 1990 Rev 0 to Analysis of B & C 1989 Diesels Failure. ML20235Z1801989-01-31031 January 1989 Rev 2 to Pennsylvania Power & Light Co Approach to Risk Mgt & Risk Assessment ML17156A6921988-07-31031 July 1988 CRD Housing Cap Screw Corrosion. ML17146B0951987-11-30030 November 1987 Rev 1 to Susquehanna Unit 2 Cycle 3 Reload Analysis Design & Safety Analyses. ML17146B0941987-11-30030 November 1987 Rev 1 to Susquehanna Unit 2 Cycle 3 Plant Transient Analysis. ML18040A8521987-08-31031 August 1987 Suppl 4 to Evaluation of Selected Fire Door & Door Frame Assemblies, Technical Rept ML17146B0101987-05-31031 May 1987 Suppl 3 to Evaluation of Selected Fire Door Frame Assemblies, Technical Rept ML17146B0091986-06-30030 June 1986 Suppl 2 to Evaluation of Selected Fire Door & Door Frame Assemblies, Technical Rept ML18040B1191985-08-31031 August 1985 Suppl 1 to Evaluation of Selected Fire Door & Door Frame Assemblies. ML18040B1291985-04-17017 April 1985 Fact-Finding Rept on Air Duct Penetrations Through 1 H Fire Resistive Wall Assembly. ML20102C2131985-03-0101 March 1985 Detailed Control Room Design Review Supplementary Summary Rept ML18040A7861985-01-31031 January 1985 Evaluation of Selected Fire Door & Door Frame Assemblies, Technical Rept ML20092J2391984-06-0606 June 1984 Investigation of Unit 2 Power Transient of 840528. Related Info Encl ML20091B3401984-02-10010 February 1984 Reactor Mode Switch Functional Testing & Wear Characteristics Evaluation, Final Rept ML18040B0231983-09-0909 September 1983 Rev 4 to Equipment Qualification Rept. ML20023D1651983-04-29029 April 1983 Reactor Mode Switch Failure Modes & Mechanisms, Final Rept ML18031A4071982-10-27027 October 1982 Addendum to Final Rept Independent Design Review- Susquehanna Steam Electric Station. ML17139B0421982-08-24024 August 1982 Suppl to Investigation of Unit 1 Small Piping Sys Design Installation & Insp Program Adequacy & Implementation. Viewgraphs Encl ML17139B0401982-08-23023 August 1982 Investigation of Unit 1 Small Piping Sys Design Installation & Insp Program Adequacy & Implementation. ML18031A3861982-07-23023 July 1982 Pool Swell Forcing Functions for Mark II Wetwell-to-Drywell Vacuum Breakers. ML20050C2991982-04-30030 April 1982 Design Assessment Rept, Vol 2,Revision 6 ML17139B8881982-03-31031 March 1982 App D to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Commonality Diagrams. ML17139B8851982-03-31031 March 1982 Rev 1 to Control Sys Power Supply & Sensor Malfunction Study. ML17139B8901982-03-31031 March 1982 App E to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Failure Modes & Effects Analysis. ML17139B8911982-03-31031 March 1982 App F to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Malfunction Analysis Tables. ML18040B0271982-03-31031 March 1982 App C to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Control Sys Identification Diagrams. W/Five Oversize Diagrams.Aperture Cards Are Available in PDR ML18040A7091982-03-31031 March 1982 App B to Rev 1 to Control Sys Power Supply & Sensor Malfunction Study, Control Sys & Safety Functions. 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML17146B1741999-08-0303 August 1999 GL 96-06 Risk Assessment for Sses. ML20206D3331999-04-27027 April 1999 SER of Individual Plant Examination of External Events Submittal on Susquehanna Steam Electric Station,Units 1 & 2. Staff Notes That Licensee IPEEE Complete with Regard to Info Requested by Suppl 4 to GL 88-20 ML20195B2381999-03-31031 March 1999 Redacted Version for 10CFR2.790 Request for Decommissioning Status Rept for Sses,Units 1 & 2 ML17164A8451998-10-31031 October 1998 SSES Unit 1 Tenth Refueling & Insp Outage ISI Outage Summary Rept. ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20217Q4891998-04-21021 April 1998 Rev 1 to Draft LDCN 2482, FSAR Chapter 13.4 & FSAR Chapter 17.2 Changes to Support ITS Implementation ML18026A4931998-03-30030 March 1998 LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement ML18026A5401998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Susquehanna Steam Electric Station.W/980313 Ltr ML18026A4891997-11-17017 November 1997 LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed ML18017A2921997-10-28028 October 1997 1997 Nrc/Fema Observed Exercise. ML17158C1861997-06-0505 June 1997 Proceedings of Intl Topical Meeting on Advanced Reactors Safety Vol II, on 970601-05 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML18026A4781997-03-28028 March 1997 Rev 1 to Application of Anfb to ATRIUM-10 for Susquehanna Reloads. ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20155F7661996-07-25025 July 1996 Partially Deleted Job Number 739619-96, Investigation of E Diesel Breaker Misalignment ML20155F7491996-07-24024 July 1996 Independent Safety Evaluation Svcs Project Rept 3-96, Investigation of E Diesel Generator In-Operability Event ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs ML18026A5961996-01-0202 January 1996 LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr ML18017A0511995-11-30030 November 1995 Monthly Operating Repts for Nov 1995 for SSES Units 1 & 2. W/951215 Ltr ML20092H7641995-08-31031 August 1995 Monthly Operating Repts for Aug 1995 for Susquehanna Ses ML17158A8771995-08-15015 August 1995 Exercise Manual. ML17158A8061995-07-14014 July 1995 Books 1 & 2 of ISI Outage Summary Rept SSES Unit 1 8th Refuel Outage. ML18017A0461995-07-0707 July 1995 LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation ML17164A6631995-04-11011 April 1995 Impact of Extending T-10 AOT from 3 to 7 Days. ML17164A5871995-01-31031 January 1995 Monthly Operating Repts for Jan 1995 for Susquehanna Ses ML18026A5351994-10-31031 October 1994 SSES Unit 1 & 2 MSIV Leakage Alternate Treatment Method Seismic Evaluation. W/One Oversize Drawing ML17158A4821994-08-23023 August 1994 ISI Outage Summary Rept Unit 2 6th Refueling Outage, Books 1 & 2 of 2 ML17158A2391994-04-0505 April 1994 Books 1 & 2 of SSES Unit 1 Seventh Refueling & Insp Outage ISI Outage Summary Rept. ML18017A2701993-12-31031 December 1993 PP&L Annual Rept 1993. ML17158A2651993-12-31031 December 1993 Allegheny Electric Cooperative,Inc Annual Rept 1993. ML17158A1631993-12-0909 December 1993 Remote Indication of Spent Fuel Pool Level & Temperature. ML18026A4281993-08-16016 August 1993 PP&L Response to NRC Concerns Re Loss of Spent Fuel Pool Cooling Following Loca,Sses,Units 1 & 2. ML18026A4261993-06-0909 June 1993 LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr ML17157C2441993-02-28028 February 1993 Monthly Operating Rept for Feb 1993 for Susquehanna Steam Electric Station,Units 1 & 2 ML18017A2031993-02-0101 February 1993 Books 1 & 2 of Unit 2 Fifth Refueling & Insp Outage,Isi Outage Summary Rept. ML20044C2741993-01-31031 January 1993 Corrected Monthly Operating Rept for Jan 1993 for Susquehanna Steam Electric Station,Unit 2,consisting of Info on Unit Shutdowns & Power Reductions ML17157C3691992-12-31031 December 1992 PP&L Annual Rept 1992. ML20056C3941992-12-31031 December 1992 Allegheny Electric Cooperative,Inc Annual Rept 1992 ML18017A0421992-12-14014 December 1992 Suppl to 921127 Part 21 Rept Re High Air Concentration in Reactor Bldg Making Area Uninhabitable for Retrieving Air Filters,Per NUREG-0737,Item II.F.1.Util Current Position Re Fuel Pool Cooling Issues Contrary to Reg Guide 1.3 ML18026A2481992-11-27027 November 1992 Part 21 Rept Re Substantial Safety Hazard in Design of Facility for Loss of Normal Spent Fuel Pool Cooling ML18026A4231992-11-17017 November 1992 LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr ML17157C1421992-10-21021 October 1992 Engineering Assessment of Fuel Pool Cooling Piping EDR-G20020. ML17157C1411992-08-31031 August 1992 Loss of Fuel Pool Cooling Event Evaluation. ML17157C1401992-08-31031 August 1992 Review of Fuel Pool Cooling During Postulated Off-Normal & Accident Events SSES Units 1 & 2. ML20082C4941992-08-14014 August 1992 Evaluation of Unit 1 & Unit 2 Derating of Power Cables in Raceways Wrapped W/Thermo-Lag Matl ML17157C1381992-07-27027 July 1992 Safety Consequences of Boiling Spent Fuel Pool at Susquehanna Steam Electric Station. ML17157B9331992-07-24024 July 1992 Sixth Refueling & Insp Outage Inservice Insp Outage Summary Rept, Books 1 & 2 ML20097D4681991-12-31031 December 1991 Pennsylvania Power & Light Company,1991 Annual Rept ML18017A0391991-07-26026 July 1991 LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr 1999-09-30
[Table view] |
Text
TECHNICAL REPORT EVALUATION OF SELECTED FIRE DOOR AND DOOR FRAME ASSEMBLIES (SUPPLEMENT 3) by, Chr istopher A. Spencer Prepared for Pennsylvania Power and Light Company Susquehanna Steam Electric Station Route 11 Salem Township, Pennsylvania 15635 May 1987 Reviewed by:
W. F. Shield, Assistant Manager Materials Section (Codes/Ratings)
FMRC Approved by:
P. H. Dobson oui ~ Senior Engineet 87 i 0>303b3;,.:
. hooey.;"0 05000387 PORE I FMRC PDR Factory NIIItual Research 1161 Boston-Providence Turnpike Norwood. Massachusetts 02062
0' ~ k tFACTORY MUTUAL RESEARCH t
CORPORATION TABLE OF CONTENTS Section Title ~Pa e TABLE OF CONTENTS i
SUMMARY
AND, CONCLUSIONS iii I INTRODUCTION 1 II FIRE DOOR AND FRAME EVALUATION 2 III RECOMMENDATIONS 5
FACTORY MUTUAL RESEARCH CORPORATION
SUMMARY
AND CONCLUSIONS An evaluation of selected fire doors and frames protecting safety related ar eas was conducted for the Pennsylvania Power and Light Co. (PPQ.) at Susquehanna Steam Electric Station, Units 1 & 2. The purpose of the evaluation was to examine certain unlabeled or modified doors and frames, compar e them with labeled units and render an opinion on their expected fire resistance.
This evaluation was requested by PPAL as a supplement to the original evaluation contained in a Factory Mutual report dated January 1985, Supplement 1 dated August 1985 and Supplement 2 dated June 1986.
The following conclusions were reached:
- 1. All frames examined may be expected to provide 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire resistance subJect to the completion of Recomendations 1 and 2 noted in this report.
'74M
- 2. Door 115 on Level 779 had a 1-1/2 hour label attached. The door may be expected to provide that level of protection.
- 3. Door 175 on Level 676 had a 1-1/2 hour label attached. The door may be expected to provide that level of protection.
- 4. Door 408 on Level 719 may be expected to provide 1-1/2 hours fire resistance;
- 5. Door 531 on Level 749 may be expected to provide 1-1/2 hours fire resistance subject to replacement of the missing silencer s and installation of a 16 ga. cover plate over the hole which was provided to receive an electromagnetic switch mechanism.
- 6. The active leaf of Door 712 on Level 799 has been sprung at the top and should be replaced.
~ W ~
FACTORY MUTUAL RESEARCH CORPORATION INTRODUCTION The plant was visited on April 9, 1987 by W. F. Shield and C. A. Spencer of FMRC. We were accompanied'by Mr. S. Davis of PAL. Five doors and frames were examined during this visit. The assemblies were located in Unit 1 and 2 Reactor Buildings and the Control Building.
Mr. C. A. Spencer is a Registered Professional Engineer in fire protection with 17 years'xperience at Factory Mutual. Mr. Spencer has been involved in field and plan review evaluation of fire walls and fire rated assemblies and is now involved in testing and evaluation of fire resistance of building materials and fire rated assemblies.
FACTORY MUTUAL RESEARCH CORPORATION FIRE DOOR AND FRAME EVALUATION Two labeled fire doors and frames, and three unlabeled fire doors and frames, were examined during this visit to the Susquehanna Steam Electric Station at the request of the Pennsylvania Power and Light Company (PPLu.).
2.1 FIRE DOOR FRAMES All.frames examined were found to be fabricated in accordance with the American National Standards Institute, Standard A155.1, and may be expected to provide 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire resistance subJect'o completion of Recommendations 1 and 2.
2.2 FIRE DOORS Two labeled doors with modifications were examined and three unlabeled doors were compared to labeled fire doors to obta'in an estimated fire-resistance rating.
2.2. 1 Labeled Fire Doors with Modifications Labeled doors with modifications were examined to determine whether the door would still be expected to provide the level of fire resistance indicated on the label.
Door 115-g g999~.>.gd Door 115 (Elevation 779, Reactor Building, Unit 2) had a 1-1/2 hour label attached. This door had been modified by addition of an electromagnetic card reading device. Examination indicates this door may be expected to provide 1-1/2 hours fire resistance. (Note: The report of the original fire door evaluation dated January 1985 referenced a Door No. 115 on Elevation 670 of Reactor Building, Unit 1. This is not the same door.)
Door 175 Door 175 (Elevation 676, Control Structure, Lunch Room C-109) had a 1-1/2 hour label attached. This door had been modified by addition of a 10 in x 10 in wired glass light (Model T4G manufactured by Leslie Locke Inc ,
Atlanta, Georgia). Examination indicates that since this is within the
t FACTORY MUTUAL RESEARCH l
CORPORATION maximum exposed glass area allowed by National Fire Protection Association, NFPA 80, Standard for Fire Doors and Windows, this door may be expected to provide 1-1/2 hours fire resistance.
2.2.2 Unlabeled Fire Doors Unlabeled fire doors were examined by comparing their construction features with labeled doors.
Door 408 Door 408 (Elevation 719, Reactor Building, Unit 2) had no label. This
'A~ ~-L -8~
door was compared to Door 115'Mith the, following results:
- a. Both doors are the same size.
- b. Both doors have vertical internal stiffeners at approximately 6 in.
on center.
- c. Face sheet thickness (18 ga'.) and hinge reinforcement (16 ga.) were-the same on both doors.
- d. Both doors have mineral wool insulation in the cavity.
- e. Door 408 has a latch throw of 1/2 in. compared to 5/8 in. for 9m~ a-c -rt'T Door 115." However, this satisfies the minimum latch throw requirement specified in NFPA 80 for a 1-1/2 hour door.
Based on the above observations, it is concluded that Door 408 would have an expected rating of 1-1/2 hours.
Door 531 Door 531 (Elevation 749, Reactor Building, Unit 1) had no label. This Qe n4 door was compared with Door 115 41th the following results:
- a. Both doors had the same dimensions.
- b. Both doors have vertical internal stiffeners at approximately 6 in.
on center as determined using a stethoscope.
c~ Face sheet thickness ( 18 ga.) and hinge reinforcement ( 16 ga.) were the same on both doors as determined using a specially adapted micrometer.
- d. Both doors have latch throws of 5/8 in.
- e. Both doors have mineral wool insulation in the cavity.
FACTORY MUTUAL RESEARCH CORPORATION It is concluded that Door No. 531 would have an expected rating of 1-1/2 hours subject to completion of the recommended improvements in Section III of this report.
Door 712 An examination of Door 712 (Elevation 799, Reactor Building, Unit 1) showed that the active leaf of this pair of doors had been sprung at the top edge and should be replaced.
FACTORY, MUTUAL RESEARCH CORPORATION I II RECOMMENDATIONS The silencers missing from the frame of Door 531 should be replaced.
The opening in the frame of Door 531 which was intended to receive an electromagnetic switch mechanism for a card reader, should be covered with a 16 ga. cover plate.
The active leaf of Door 712, which has been sprung at the top, should be replaced with a labeled 1-1/2 hour rated fire door.
DEVIATION REQUEST NP. 3 SUSQUEHANNA STEAM ELECTRIC STATION - UNITS I 5 2 FIRE PROTECTION PROGRAM - CONCERN ¹I DOCKETS NO. 50-387 50-388 APPENDIX A - DEVIATION REQUESTS DEVIATION REQUEST NO. 3 ATTACHMENT 5