Structural Steel Analysis for Limerick Generating Station, Unit 1 Reactor Bldg Elevation 201-Ft Cooling Water HX Area Room 207,Fire Area 41ML20083H971 |
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Limerick ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
12/20/1983 |
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From: |
PROFESSIONAL LOSS CONTROL, INC. |
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To: |
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Shared Package |
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ML20083H823 |
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References |
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NUDOCS 8401090599 |
Download: ML20083H971 (10) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam B110078, Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 11998-12-31031 December 1998 Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 1 ML20236X7641998-07-31031 July 1998 Rev 0 to SIR-98-079, Response to NRC RAI Re RPV Structural Integrity at Lgs,Units 1 & 2 ML20151Z4881998-06-30030 June 1998 GE-NE-B1100786-02, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 2 ML20202B6231998-01-23023 January 1998 Non-proprietary Version of Rev 1 to ER-9605NP, Missile Probability Analysis Methodology for Limerick Generating Station,Units 1 & 2,w/Siemens Retrofit Turbines ML20198B3351997-06-30030 June 1997 Annual 10CFR50.59 & Commitment Rev Rept for 960701-970630, for Limerick Generating Station,Units 1 & 2 ML20135D7721996-04-30030 April 1996 Non-proprietary, Evaluation of Limerick Initial Core Channels for Re-Use on Ex-Shoreham Fuels Bundles ML20101F1901996-02-29029 February 1996 Evaluation of Limerick Unit-1 Core Shroud Insps (Refuel Outage 6) ML20099L6331995-06-30030 June 1995 Annual 10CFR50.59 & Commitment Rev Rept 940701 - 950630 ML20094H0521995-06-30030 June 1995 Pyrolysis Gas Chromatography Analysis of 21 Thermo-Lag Fire Barrier Samples ML20086B1681995-06-26026 June 1995 Ipeee ML20083K6611995-04-26026 April 1995 Rev a to Upgraded Eals ML20078S3351994-02-10010 February 1994 Evaluation of Abnormal Wear at Limerick ML20059K6261993-10-26026 October 1993 SAR Licensing Rept for Spent Fuel Storage Capacity Expansion,Lgs Units 1 & 2 ML20046B5011993-06-27027 June 1993 Evaluation of Potential Internal Radiation Exposures Associated W/Contamination Events in Handling Traversing In-Core Probe (TIP) Tubing at Limerick Nuclear Generating Station & Recommendations for Evaluation & Control of ... ML20127N8811992-12-31031 December 1992 LLRW Shipment Insp Repts 50-352/PA-92-02 & 50-353/PA-92-02 on 921116-18.No Violations or Deviations Noted.Major Areas Inspected:Licensee LLRW Shipment to Burial Site Including Shipping Documentation,Package Insp & Contamination Surveys ML20113D9801991-11-30030 November 1991 Industry Approach to Seismic Severe Accident Policy Implementation, for Nov 1991 ML20082N0471991-08-28028 August 1991 Annual Plan Mod Rept,Jul 1990 Through June 1991 ML20072R0121991-03-15015 March 1991 Common Plant Summary of ASME Section XI Repairs & Repalcements Completed from 890520-901217,Rept 3 ML20072R0071991-03-14014 March 1991 Common Plant Summary Rept for 890520-901217,Periodic Insp Rept 3 ML20066K7201991-01-31031 January 1991 Simulator Certification Submittal, Providing Supporting Info to Form NRC-474 ML20055J3291990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20042E0901990-03-31031 March 1990 Description of Limerick Inadvertent Spray Actuation Analysis. ML20246A8511989-08-15015 August 1989 Common Plant Summary of ASME Section XI Repairs or Replacements from 870901-890519,Rept 2 ML20248A0261989-06-30030 June 1989 Rev 1 to Response to NRC Bulletin 88-05 for Limerick Generating Station,Unit 2 ML20247J0521989-05-31031 May 1989 Vol Ii,Book 1 to Limerick Generating Station,Unit 2 Independent Design & Const Assessment, Hazards Program Evaluation Suppl ML20245A0801989-04-30030 April 1989 Vol II of Book 1 to Independent Design & Const Assessment, Design Assessment ML20245A0951989-04-30030 April 1989 Vol I of Book 1 to Independent Design & Const Assessment, Assessment Summary ML20245A1031989-04-30030 April 1989 Vol II to Books 2,3 & 4 to Independent Design & Const Assessment,Design Observation Repts,DOR-001 to DOR-118 ML20246P5671989-03-22022 March 1989 Safety Evaluation of Limerick 1,Cycle 3 Revised Core Loading Pattern ML20235Z5981989-02-28028 February 1989 Extension of Equipment Qualification Programs to Limerick Generating Station Unit 2 ML20235Y3811989-02-28028 February 1989 Rev 11 to Design Assessment Rept ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20148R7511988-03-0808 March 1988 Readiness Program Assessment for Limerick 2 ML20236V6631987-08-31031 August 1987 Summary of ASME Section XI Repairs & Replacements Completed from 840928-870831,Rept 1 ML20153G3091986-02-24024 February 1986 Summary of Validation Program for Spds ML20129C3861985-06-30030 June 1985 Control Room Design Review Supplemental Rept 2 to Final Rept of June 1984 ML20112E4491985-02-11011 February 1985 BNL Technical Review Rept & Handwritten Notes of 850121-25 Insp ML20083L7691984-12-31031 December 1984 Descriptive Rept of Archeological Investigation for 220-60 Transmission Line Right-of-Way in Association W/Limerick Nuclear Generating Station,Montgomery & Chester Counties, Pa ML20083L7901984-12-31031 December 1984 Descriptive Rept of Archeological Investigation for 220-61 Transmission Line Right-of-Way in Association W/Limerick Nuclear Generating Station,Montgomery & Chester Counties, Pa ML20107G6421984-10-31031 October 1984 Control Room Design Review, Final Rept,Suppl 1 ML20129D7351984-09-30030 September 1984 Evaluation of Feedwater Containment Isolation Check Valves for Hypothetical Pipe Rupture Condition for Limerick Generating Station ML20098E9061984-09-30030 September 1984 Rev 10 to Design Assessment Rept ML20093C9921984-09-17017 September 1984 Independent Design Review of Limerick Generating Station 1, Core Spray Sys, Bimonthly Status Rept 8 for Period Ending 840915.Related Correspondence ML20096C7651984-08-31031 August 1984 Environ Qualification Rept ML20095A6021984-08-0909 August 1984 Rev 0 to Raceway Separation Criteria. Raceway Separation Test Program Discussion Encl ML20093N6651984-07-31031 July 1984 Nonproprietary Rev 9 to Vol 1 of Design Assessment Rept ML20095D3101984-06-30030 June 1984 Rev 3 to Final Rept Overhead Handling Sys Review ML20092K9461984-06-30030 June 1984 Control Room Design Review,Final Rept 1999-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Lgs,Units 1 & 2. with ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 ML20212A4481999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With ML20211E9891999-08-20020 August 1999 LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5 ML20210L7051999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.With ML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20209D7741999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam ML20195G4651999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Lgs,Units 1 & 2 ML20209D7791999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Limerick Generating Station,Units 1 & 2 ML20195B3021999-05-0606 May 1999 Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6 ML20206N2901999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Limerick Generating Station,Units 1 & 2.With ML20195G4761999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Lgs,Units 1 & 2 ML20206D8971999-04-22022 April 1999 Rev 2 to PECO-COLR-L1R7, COLR for Lgs,Unit 2 Reload 7, Cycle 8 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205N9311999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Limerick Generating Station,Units 1 & 2.With ML20204G9851999-03-11011 March 1999 Safety Evaluation Re Revised Emergency Action Levels for Limerick Generating Station,Units 1 & 2 ML20207J7461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Limerick,Units 1 & 2.With ML20199G2371999-01-31031 January 1999 Rev 0 to NEDO-32645, Limerick Generating Station,Units 1 & 2 SRV Setpoint Tolerance Relaxation Licensing Rept ML20199L5301999-01-19019 January 1999 Special Rept:On 981214,seismic Monitor Was Declared Inoperable.Caused by Spectral Analyzer Not Running.Attempted to Reboot Sys & Then Sent Spectral Analyzer to Vendor for Analysis & Rework.Upgraded Sys Will Be Operable by 990331 B110078, Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 11998-12-31031 December 1998 Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 1 ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20199F9611998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Limerick Generating Station.With ML20198C7151998-12-10010 December 1998 Rev 1 to COLR for LGS Unit 1,Reload 7,Cycle 8 ML20198A3871998-12-10010 December 1998 Safety Evaluation Supporting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20206N4061998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Limerick Generating Station,Units 1 & 2.With ML20199E3281998-11-23023 November 1998 Rev 2 to PECO-COLR-L2R4, COLR for Lgs,Unit 2,Reload 4,Cycle 5 ML20195C9771998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Limerick Generating Station,Units 1 & 2.With ML20154H5691998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Limerick Generating Station,Units 1 & 2.With ML20151X3511998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Limerick Generating Station Units 1 & 2.With ML20237F0291998-08-27027 August 1998 Special Suppl Rept:On 960425,one Loose Part Detection Sys (Lpds) Was Identified to Be Inoperable.Initially Reported on 960531.Caused by Loose Parts Detector Module.Repairs Performed & Intermittent Ground No Longer Present ML20237D1041998-08-17017 August 1998 Books 1 & 2 of LGS Unit 1 Summary Rept for 960301-980521 Periodic ISI Rept 7 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20236X7641998-07-31031 July 1998 Rev 0 to SIR-98-079, Response to NRC RAI Re RPV Structural Integrity at Lgs,Units 1 & 2 ML20237B4711998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Limerick Generating Station,Units 1 & 2 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 ML20151Z4881998-06-30030 June 1998 GE-NE-B1100786-02, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 2 ML20236P9781998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Limerick Generating Station,Units 1 & 2 ML20196K1801998-06-30030 June 1998 Annual 10CFR50.59 & Commitment Rev Rept for 970701-980630 for Lgs,Units 1 & 2. with ML20249B3501998-06-11011 June 1998 Rev 1 to PECO-COLR-L2R4, COLR for LGS Unit 2 Reload 4,Cycle 5 ML20249A5331998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Limerick Units 1 & 2 ML20247M7071998-05-14014 May 1998 Safety Evaluation Supporting Amend 128 to License NPF-39 ML20217Q5101998-05-0404 May 1998 Safety Evaluation Supporting Amend 127 to License NPF-39 ML20247H5071998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Limerick Generating Station ML20216F3601998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Limerick Generating Station,Units 1 & 2 ML20217M0791998-03-31031 March 1998 Safety Evaluation Supporting Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216F9471998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Limerick Generating Station,Units 1 & 2 ML20216F3471998-02-28028 February 1998 Revised Monthly Operating Rept for Feb 1998 for Limerick Genrating Station,Unit 1 1999-09-30
[Table view] |
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(([ Professional Loss Control, Inc.
STRUCTURAL STEEL ANALYSIS for LIMERICK GENERATING STATION Unit 1 Reactor Building El. 201' Cooling Water HX Area Room 207 Fi,re Area 41 l
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December 20, 1983 l
l 8401090599 840104 PDR ADOCK 05000352 E PDR l
P. O. Box 446
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LIMERICK GENERATING STATION
- 1. AREA DESCRIPTION The area under consideration is the Cooling Water Heat Exchanger Area Room 207 on the 201' elevation of the Unit 1 Reactor Building (Fire Area 41).
The bounding walls of the area are of reinforced concrete construction with an average thickness of 3 ft. The total surface area for hest transfer is 8985 ft2 (see Attachment A for sketch and calculation of surface areas).
- 2. COMBUSTIBLE LOADING Combustible loading in this area consists of cable insulation located in cable trays. The total surface area of cable trays is 702 ft2 with an average combustible loading of 3.5 los/ft2 of cable tray surface area.
There are no combustible liquids in this area.
- 3. VENTILATION PARAMETERS There are two doors which enter this area. Both measure 3' wide by 7' nigh.
One door is located in the east wall and the other is located in the west wall and enters stair No. 2.
- 4. CASES EXAMINEn Two cases were examined, each assuming that all the cable trays in the area were burning simultaneously. Case number one assumed one door open while case number two assumed both doors open.
- 5. RESULTS Case number one assumed all cables burning simultaneously witn one 3' x 7' door open. This resulted in a ventilation controlled fire with a burning rate of 4504 kW and a duration of 90 minutes. The gas temperature at this time would be 601*F which is below the critical temperature of the struc-tural steel (see Attachment B).
Case number two assumed all cables burning simultaneously witn both 3' x 7' doors open. This resulted in a ventilation controlled fire with a burning rate of 9008 kW and a duration of 45 minutes. The gas temperature at this time would be 820 F which is below the critical temperature of the struc-tural steel (see Attachment 3).
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The position of cable trays relative to structural members were examined throughout the area in' order to assess the potential for localized heating.
Cable tray 10CQA is located within 12 inches of member types W27X84, W21X44, W18X40 and W27X102.
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Attachment C Contains the results 'of Calculations performed to determine the response of the structural steel members to localized heating. Tnese calculations are conservative because they assume that the entire lengtn of the structural steel member is subjected to a temperature of 1300*F when',
- in actuality, only a small section of the steel would be subjected to
' localized heating. As can be seen from the results, none of the members exceeded the single point failure temperature of 1300*F during the 35 minute exposure period (time required for tray to burn to completion),
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Unit 1 Reactor Building El. 201' Cooling Water heat Exchanger Area Room 207 Surface Area Calculation Wall s North wall (95' x 15') 1425 ft2 East wall (132' x 15') 1980 ft2 South wall (33' x 15') 495 ft2 West wall (105' x 15') 1575 ft2 5475 ft' Ceiling Area 1 (12' x 48') 576 ft2 Area 2 (19' x 11') 209 ft2 Area 3 (29' x 74') - (18' x 8') 2002 ft2 Area 4 1/2(48')(32') 768 ft2 3 55 ft' Total Surface Area for Heat Transfer 9030 ft2 s
ATTACHMENT A
bnSt i4UMSER 1 BUILDING: UNIT 1 REACTOR BUILDING ELEVATION AND AREA DESCRIPTION: 201' COOLING WATER HX AREA ROOM 207 CASE DESCRIPTION: ONE DOOR OPEN ALL CABLES BURNING
- o***x**********************x*****x************xxxx***********x***x****
CEILING / WALL CEILING / WALL Ao Ho Aw Q THICKNESS MATER I AL (ft) (ft2) (ft) (ft2) (kW)
- x**xxxxxx**********xxx**xxx*******xx*******xx**xx*xxxxx**
3.0 CONCRETE 21.0 7.0 9030 4504 FIRE IS FUEL CONTROLLED FIRE DURATION GAS TEMPER ATUR$
(nin) (deg,F) 5 197 10 249 15 288 20 322 25 351 30 378 35 402 40 425 45 446 50
- 466 55 486 60 504 65 522 70 539 75 555 80 571 05 586 90 601 ATTACHMENT S
' CASE' NUMBER: 2 BUILDING: UNIT 1 REACTOR BUILDING
. ELEVATION AND AREA DESCRIPTION: 201' COOLING WATER HX AREA ROOM 207 CASE DESCRIPTION: TWO DOORS OPEN ALL CABLES BURNING en**********************************************************************
CEILING / WALL -CEILING / WALL Ao Ho Aw Q THICKNEES MATERIAL (ft) (ft2) (ft) (ft2)
- n**********r*************************************x**************x(*kW) 3.0 CONCRETE 42.0 7.0 9030 9000 FIRE IS FUEL CONTROLLED
. FIRE DURATION GAS TEMPERATURE (nin) (deg.F) 5 322 10 425 15 504 20 571 25 630 30 683 -
35 732 40 778 45 820 i 4
l ATTACHMENT S
s CASE. NUMBER: 1 BUILDING: UNIT 1 REACTOR BUILDING ELEVATION AND AREA DESCRIPTION: 201' COOLING WATER HX AREA ROOM 207 CASE DESCRIPTION: LOCALIZED HEATING OF MEMBER TYPE W10x40 EFFECTS OF LOCAL HEATING ON STRUCTURAL STEEL FIRE TEMPERATURE (deg. F): 1300 WEIGHT OF STEEL MEMBER (1bs./ft): 40 SURFACE OF STEEL MEMBER HEATED (sq.ft./ft): 4.38 TIME STEEL TEMPERATURE (min) (deg.F) 5.00 601 10.00 903 15.00 1075 20.00 1172 25.00 1227 30.00 1259 35.00 1277 e
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ATTACHMENT C
CASE NUMBER: 2 BUILDING: UNIT 1 REACTOR BUILDING ELEVATION AND AREA DESCRIPTION: 201' COOLING WATER HX AREA ROOM 207 CASE DESCRIPTION: LOCALIZED HEATING OF MEMBER TYPE U21x44 EFFECTS OF LOCAL HEATING ON STRUCTUR AL STEEL FIRE TEMPERATURE (deg. F): 1300 WEIGHT OF STEEL MEMBER (1bs./ft): 44 SURFACE OF STEEL MEMBER HEATED (sq.ft./ft): 4.94 TIME STEEL TEMPERATURE (min) (deg.F) 5.00 614 10 .00 910 15.00 1008 20.00 1102 25.00 1234 30.00 1263 35.00 1280 l
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ATTACHMENT C
CASE NUMBER: 3 BUILDING: UNIT 1 REACTOR BUILDING ELEVATION AND AREA DESCRIPTION: 201' COOLING WATER HX AREA ROOH 207 CASE DESCRIPTION: LOCALIZED HEATING OF MEMBER TYPE W27x84 EFFECTS OF LOCAL HEATING ON STRUCTURAL STEEL FIRE TEMPERATURE (deg. F): 1300 l WEIGHT OF STEEL MEMBER (1bs./ft): 84
' SURFACE OF STEEL MEMBER HEATED (sq.ft./ft): 6.70 TIME STEEL TEMPERATURE (min) (deg.F) 5.00 461 10.00 728 15.00 911 20.00 1035 25.00 1119
- 30.00 1177 35.00 1216 r
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ATTACHMENT C
CASE NUMBER 4 DUILDING: UNIT 1 REACTOR BUILDING ELEVATION'AND AREA DESCRIPTION: 201' COOLING WATER HX AREA ROOM 207 CASE DESCRIPTION: LOCALIZED HEATING OF MEMBER TYPE W27x102 EFFECTS OF LOCAL HEATING ON STRUCTURAL STEEL FIRE TEMPER ATURE (deg . F): 1300 WEIGHT OF STEEL MEMBER (1bs./ft): 102 SURFACE OF STEEL MEMBER HEATED (sq.ft./ft): 6.05
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TIME STEEL TEMPERATURE (min) (deg,F) 5.00 395 10.00 635 15.00 811 20.00 941 25.00 1036 30.00 1106 35.00 1158 ATTACHMENT C