|
---|
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
, _ --- - -_- - ..._ _ . . . . . _ . . _ . _ . _ . _ _ - _ _ _ -- -_ _ . _ -
i
}(( Professional Loss Control, Inc.
STRUCTURAL STEEL ANALYSIS for LIMERICK ATOMIC GENERATING STATION Unit 1 Reactor Building, El. 253' General Floor Area
.. . Fire Area 45A November 1, 1983 Of[30fgjos --
eBR .
r 7922 West Chester Pike
- Upper Darby, Pa. 19082 * (215) 853-1700
r LIMERICK GENERATING STATION
- 1. AREA DESCRIPTION l The area under consideration is the general floor area on the 253' ele-
.vation of the Unit 1 Reactor Building (Fire Area 4EA). The heaviest combustible loading encountered on this elevation is found in the CRD Hydraulic Equipment Area and Neutron Monitoring System Area. The area of heaviest combustible loading is bounded by column lines 19.4 & 23 and J & Fa (see Attachment A for a sketch of the area under considera-tion). The total surface area for heat transfer is approximately 11,774 ft .2 The bounding walls are constructed of reinforced concrete with an average thickness of 1.5 ft.
- 2. COMBUSTIBLE LOADING The heaviest concentration of cabling found within this area was along the east wall. The average combustible loading of the cable trays in this area is 4.7 lbs/ft2 of tray surface area. There are no combustible liquids in this area. Enclosed combustibles are not included in the combustible loading.-
- 3. VENTILATION PARAMETERS The area under consideration is open .to the remainder of this elevation on its south side. This opening is approximately 28.5 ft. wide and 29 ft. high.
- 4. CASES EXAMINED A spreading cable fire was assumed to originate in the area of heaviest cable concentration in order to present the worst case. The fire is assumed to start at a point source and spread horizontally along the cable trays in each direction at a rate of 10 feet per hour. The fire will spread north and south along the east wall and westward a distance of 8 feet in each direction along the cable trays before the original point source dies out after 47 minutes. A maximum s'urface area of 386 ft2 of cable trays (see Attachment B for a list of trays) will be involved at any one time, which corresponds to a hea't output of 6816 kW. This heat output is assumed constant throughout the fire duration.
The actual heat output as the fire spreads out of the area originally involved would be less since the quantity of cabling involved at any one time would be less.
1
--- - - . - . . _ . , . . . - . . . . - . _ . - . _ . . _ . . . . . ~ - - . . - . . . . . . . - - . . . - . . - -
- 5. RESULTS The fire duration was taken to be 180 minutes and the fire temperature reached after 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> was 940*F which is below the critical temperature for the structural steel (see Attachment C for results of analysis).
Since the- fire is assumed to occur in the area of heaviest combustible loading, the results are considered to be representative for the entire general floor area on the 253' elevation of the Reactor Building.
The positions of cable trays relative to structural steel members were examined throughout the 253' elevation of the Reactor Building in order to assess the potential for localized heating. Cable tray 1AGY05 is located 12" below the bottom of a girder type G-52 (54WF366).
Attachment D contains the results of calculations performed to deter-mine the response of the girder to localized heating. These calcula-tions are conservative because they assume that the entire length of the girder is subjected to a temperature of 1500*F when in actuality only a small section of the steel would be subjected to localized heat-ing. As can be seen from the results, the girder does not reach its single point failure temperature of 1300*F during the 50 minute expo-sure period (time required for a tray to burn to completion).
t #
2
a l, '\,
'i
,e.l
'~'
i ui d- !
.M '
9 N- ' n , '
, .-' g \ @. 1 ,h!:M
, . I
~'
h l 1 i N l8 I l
\ / I 8
,,\
% W ,.-
r 6 .
/ k{ *$
- l. rf .,
' y
?'
L n l 4
Unit 1 Reactor Enclosure 253' El.
Surface Area Calculation Walls North wall above Neutron Mon. (18' x 19') 342 ft2 North wall. Neut. Mon. to Stairway (35'x28.5') 997.5 ft2 North wall stairwell (8'x28.5')-(3'x7') 207 ft2 East wall (67' x 28.5') 1909.5 ft2 Column North & South Faces East Wall (16'x28.5') 456 ft2 Drywell Access Wall (16' x 28.5') 456 ft2 Drywell wall above Neutron Mon. . (22'x19') 418 ft2 Drywell wall from Neut. Mon to Access (49' x 28.5') 1396.5 ft2 Neutron Monitoring Walls (63' x 9.5') - (3' x 7') 577.5 ft2 6969 ft2 I'
ATTACHMENT A .
L :_= === _= _ - _ _ - . - - - - - - - - - - - - -
Ceiling Area 1 (27' x 11') 297 ft2 Area 2 1/2(27' x 41') - 240 ft2 313.5 2 Area 3 (46' x 74') 3404ft{t Area 4 1/2(22' x 6') - 21 ft2 45 ft2 Area 5 -
4' x 61') 244 ft2 Area 6 4' x 4') 16 ft2 Area 7- 4' x 42') 168 ft2
-Area 8 21' x 12') 252 ft2 Area 9 1/2(11' x 12') 66 ft2 4805.5 ft2 Total Surface Area for Heat Transfer = 11,774 ft2 0
ATTACHMENT A
tu.-..-..-...-.-...-. . . - - ~ .. .. - -. - - - - _ - ..- - - - . .
The following cable trays are present in the area defined for the source fire and all of the trays are assumed to be burning simultaneously:
Surface Tray No. Width (in}, Length (ft) Area (ft21 1DCPA79 24" 2' 4 10CAA74 24" 16' 32 10CVA72 24" 5' 10 10CBA72 24" 10' 20 10CQA21 24" 12' 24 11CCA21 24" 16' 32 10CZA21 24" 9.5' 19 10CPA74 24" 7' 14 1CDPA75,76,78 24" 5' 10 1DCQA76 24" 11' 22 11CLA74 24" 11' 22 10CDA74 24" 11' 22 10lYA74 24" 11' 22 10CZA74 24" 8' 16 11CCA74 24" 8' 16 10CBA74 24" 8' 16 10CDB13 24" 11.5' 23
'~
101YB13 24" 15' 30 10CDB12 24" 8' 16 101YB12 24" 8' 16
, 386 ft2 Average Combustible Loading per Tray Surface Area = 4.7 lb/ft2 Fire Duration for Free Burning Cablg Tray Fire =
4.7 lb/ft 4 01 lb = 47 minutes ft'/ min Heat output with all trays in source fire area (above) burning simultaneously:
386 ft2 _ x 190 kW/m2 = 6816 kW 10.76 ft4/m' ATTACHMENT B
[djd.yy'7-' , ' ' '*'; '
f _ -
', CASE ANUMBEft 1,, .1 BUILDING: ' REACTOR ENCLOSURE UNIT 1 ELEVATION AND AREA DESCRIPTION: 253'EL. NORTHEAST CORNER TASE : DESCRIPTION : .
SPREADING CABLE FIRE
'. .c x x
- x x x *-x x xa: y x x x x x x *
- x x x x x x x x x x x x x x
,v ,
CEILING / WALL CEILING / WALL Ao Ho Aw Q THICKNESS MATERIAL (ft) (ft2) (ft) (ft2) (kW) 0"c a u x x x
- x x r t-x x x x x x x-x x r x x -x x x x x
1.5 CONCRETE U26 27 11774 6816 b
FIRE IS FUEL CONTROLLED FIRE DURATION GAS TEff ER ATURE (Min) (deg.F) 10 277 20 362 30 427 40 402 50 530 60 573 70 614
~
80 6b1 90 606 o
e 100 719 110 751 120 701 130 010 140 830 150 065 160 891 170 916 100 940 s
. e
- W .
s ,
I '::t ATTACHMENT C
.y. i
= . s e
.yyk &
>> 1
.. 'i .
g., *
,, Y.
'e . .
5' Q . :
.; ; ; , J ' .';: ' . tr -
. m :.,:- w- . ,a
y ..- ,
e,-- , s .; . w .t.z . . -
.r n s , t*
. CASE. NUMBER 1 .
, 'BUILDINGV UNIT 1 REACTOR BUILDINC ELEVATION AND AREA DESCRIPTION: 253' GENER AL FLOOR AREA CASE. DESCRIPTION: LOCALIZED HEATING OF MEMBER TYPE G-52 (54WF366)
. q-
' ~
=4 *e ,
. [,,4:'.j " EFFECTS OF LOCAL HEATING ON STRUCTURAL STEEL
, ,a ' ., y (g v *.
' FIRE TEMPERATURE (deg. F): 1500 WEIGHT OF STEEL MEMBER (lbs./ft): 366 SURFACE OF STEEL MEMBER HEATED (sq .f t ./f t ): 13.30 TIME STEEL TEMISERATURE
. (Min) (dog.F) 5.00 274 10.00 450 15.00 600 20.00 729 25.00 040 30.00 935 35.00 1016 1005 40.00 45.00 1145 50.00 1196 4
0 e
k e
e a 9 4
e b
4 4 g y'
sq** ATTACHMENT D h ,
O $ t
-wg ,- --_