Structural Steel Analysis for Limerick Generating Station, Unit 1 Reactor Bldg Elevation 177-Ft RHR HX & Pump Room - Room 102,Fire Area 32ML20083J026 |
Person / Time |
---|
Site: |
Limerick |
---|
Issue date: |
12/20/1983 |
---|
From: |
PROFESSIONAL LOSS CONTROL, INC. |
---|
To: |
|
---|
Shared Package |
---|
ML20083H823 |
List: |
---|
References |
---|
NUDOCS 8401090637 |
Download: ML20083J026 (7) |
|
|
---|
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 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 ML20245A0951989-04-30030 April 1989 Vol I of Book 1 to Independent Design & Const Assessment, Assessment Summary ML20245A0801989-04-30030 April 1989 Vol II of Book 1 to Independent Design & Const Assessment, Design Assessment ML20246P5671989-03-22022 March 1989 Safety Evaluation of Limerick 1,Cycle 3 Revised Core Loading Pattern ML20235Y3811989-02-28028 February 1989 Rev 11 to Design Assessment Rept ML20235Z5981989-02-28028 February 1989 Extension of Equipment Qualification Programs to Limerick Generating Station Unit 2 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 ML20098E9061984-09-30030 September 1984 Rev 10 to Design Assessment Rept ML20129D7351984-09-30030 September 1984 Evaluation of Feedwater Containment Isolation Check Valves for Hypothetical Pipe Rupture Condition for Limerick Generating Station 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] |
Text
r 'o '
\ (([ Professional Loss Control, Inc.
i f
i I
J 1
STRUCTURAL STEEL ANALYSIS for LIMERICK GENERATING STATION Unit 1 Reactor Building El. 177' RHR Heat Exchanger and Pump Room - Room 102 Fire Area 32 December 20, 1983 9401090637 840104 PDR ADOCK 05000352 E PDR P O. Box 446 e Oak Ridge, Tennessee 37830 * (615) 482-3541
- '_ ~~.~ _ _. . . . _ . _. - -
'i 8
LIMERICK GENERATING STATION
- 1. AREA DESCRIPTION The area under consideration is the RHR Heat Exchanger and Pump Room, Room
- 102, on the 177' elevation of the Unit 1 Reactor Building (Fire Area 32) j (see Attachment A for sketch of area). The bounding walls of the area are j- of reinforced concrete construction with an average thickness of 3 ft.
8 The total surface area for heat transfer is 7848 ft2 (see Attachment A for calculation of areas).
d
- 2. COMBUSTIBLE LOADING Combustible loading in the area consists of 72 gallons of lubricating oil contained in the RHR pump motors. For the analysis this quantity was doubled to account for possible maintenace activities in the area. There are two cable trays in the room - one located along the east wall, the other along the west wall. The total surface area of the cable trays is 52 ft2 with an average combustible loading of 1.'i lbs/ft2 of cable tray surface. ,
l
- 3. VENTILATION PARAMETERS -
There are four doors which enter the area. Two watertight doors measuring 3' wide by 5'10" high enter the area on the 177' elevation and two steam-tight doors measuring 3' wide by 7' high enter the area on the 201' eleva-tion.
- 4. CASES EXAMINED Two cases were examined, each assuming a lube oil fire involving 144 gal-lons of lubricating oil. Case number one assumed the lube oil fire with one
-steamtight door open and case number two assumed both steamtight doors open.
- 5. RESULTS Case number one considered only one 3' x 7' door open which corresponds to
, a ventilation controlled haat output of 4504 kW. At this heat output the
} fire would consume the 144 gallons of lube oil in 85 minutes. The gas temperature at this time would be 664*F, which is below the critical temperature of the structural steel (see Attachment B).
1 l .- - ..
The ventilation controlled burning rate of 4504 kW is equivalent to the heat output from a pool fire with an area of 14 ft2 (pool diameter of approximately 4 ft). In order to assess the effect of the plume of heated gases above the pool fire on the structural steel supporting the intermedi-ate grating at the 201' elevation, Hesketad's relations will be used:
l Virtual point source determination:
Zo = -1.020 + .083 0 4 = 1.09 m Plure temperature at bottom of structural steel supporting intermediate grating.
ATo = 9.1[T ,/(gc pf 2 ,,,2)].333 Oc .667 (Z - Zo)-1.67 ATo = 348*K temperature use T = 695"F temperature of fire plume
. i The plume temperature is below the critical temperature of the structural steel.
Case number two considered both 3' x 7' doors open which corresponds to a ventilation controlled burning rate of 9008 kW'. At this heat output the fire would consume the 144 gallons of luue oil in 44 minutes. The gas
- temperature at this time would be 923*F which is below the critical ,
temperature of the structural steel (see Attachment B).
The ventilation controlled burning rate of 9008 kW is equivalent to the heat output from a pool fire with an area of 28 ft2 (pool diameter of approximately 6 ft). In order to assess the effect of the plume of heated gases above the pool fire on the structural steel supporting the intermedi-ate grating at the 201' elevation, Hesketad's relations will be used:
Virtual point source determination:
Zo = -1.020 + .083 0 4 = 1.32 m l Plume temperature at bottom of structural steel supporting intermediate grating.
2 i
l m -
,. -,, - , - -m
c- .
r aTo = 9.1[Tg /(gcp2 j ,2)].333 Oc .667 (Z - Zo)-1.67 i oTo = 597'X temperature rise
~
T = 1194*F temperature of- fire plume l The plume temperature is below the critical temperature of the structural I steel.
i The= plume temperature is below the critical temperature of the structural steel for both cases. It is concluded that there is no problem due to localized heating of the structural steel as a result of the maximum pool fire that can be supported by the available airflow into the room through two open doors.
The cable trays in this area were positioned such that they did not present a localized heating exposure to the structural steel, i
e e
M i
8 3
I i
1 o
i .
I IJnit 1 Reactor Building El. 177' RHR Heat Exchanger and Pump Room 102
! Surface Area Calculation Walls North wall (32' x 40') 1280 ft2 South wall (52' x 40') 2080 ft2 East wall (29' x 40') 1160 ft2 West wall (52' x 40') 2080 ft2 6600 ft2 Ceiling for area is at elevation 217' Ceiling (24' x 52') 1248 ft2 Total Stiface Area for Heat Transfer 7848 ft2 11 ATTACHMENT A l
l i
CASE NUMBER: 1 BUILDING: UNIT 1 REACTOR BUILDING ELEVATION AND AREA DESCRIPTION: 177' RHR HX & PUMP ROOM 102 CASE DESCRIPTION: ONE 3'x7' DOOR OPEN LUBE OIL FIRE cowwwww********************uwwwwwww*************************************
CEILING / WALL CEILING / WALL Ao Ho Aw -
O THICKNESS MATERIAL i (ft) (ft2) (ft) (ft2) (kW)
I nc**********************************************************x***********
3.0 CONCRETE 21.0 7.0 7840 4504 FIRE IS VENTILATION CONTROLLED FIRE DURATION GAS TEMPERATURE (min) (deg F) 5 216 10 275 15 321 -
20 359 25 393 30 424 35 452 40 -
478 45 , 503 50 526 55 548 60 569 65 589 70 609 75 628 80 646 85 664 ATTACHMENT B
~~
.. .. _ _ _ - _ - ~ ~: . . -. _ - _ - _ . _ . _ - - . . - - - - . - . . . -
~. . -
^
CASE NUMBER: 2' BUILDING: UNIT 1 REACTOR BUILDING ELEVATION AND AREA DESCRIPTION: 177' RHR HX & PUMP ROOM 102 CASE DESCRIPTION 1 TWO 3'x7' DOORS OPEN LUBE OIL FIRE L
nuw**************************O******************************************
i
! CEILING / WALL CEILING / WALL - Ao Hc Aw 0
! THICKNESS MATERI AL (ft) (ft2) (ft) (ft2) (kW) f g oc**********************************************************************
3.0 CONCRETE 42.0 7.0 7848 9008 FIRE IS VENTILATION CONTROLLED FIRE DURATION GAS TEMPER ATURE (min) (deg.F) 4 330 8 436 12 517 16 586 20 646 24 701 28
798 36 842 40 884 44 923 l
l l
I l
ATTACHMENT B l- . -_
. _ , . _ _ _ _ _ . _ _