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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20199J6981997-11-11011 November 1997 Rev 2 to 10CFR50.59 Review for Jet Pump Thermal Sleeve Cracking ML20202H1231997-09-30030 September 1997 Small Project Joint Permit Application & Attachments for PECO Energy Co,Peach Bottom Atomic Power Station,Rock Run Creek Low Flow Crossing, to Satisfy PA Dept of Environ Protection & Us Army Corps of Engineers ML20129E8711996-09-26026 September 1996 Rev 0 to 10CFR50.59 Review for NCR Pb 96-03414,Core Spray T-Box Cracks for Peach Bottom Atomic Power Station,Unit 2 ML20117E6351996-05-31031 May 1996 Seismic Evaluation Rept for Pbaps ML20117E6321996-05-31031 May 1996 USI A-46 Relay Evaluation Rept for PBAPS Units 2 & 3 ML20117E6251996-05-31031 May 1996 Seismic Safe Shutdown Equipment List for PBAPS Units 2 & 3 ML20129A4511996-01-11011 January 1996 Core Spray Sparger Downcomer Modification ML20129A4731995-12-11011 December 1995 Fabrication of Core Spray Line Downcomer Clamp ML20092M8921995-09-30030 September 1995 Shroud Vertical Team Weld Evaluation ML20098B1141995-09-30030 September 1995 Evaluation of Peach Bottom Unit 3 Core Spray Line ML20098B1211995-09-30030 September 1995 Residual Stress Analysis of Peach Bottom Unit 3 Core Spray Pipe to Sleeve Fillet Weld ML20092J8151995-09-15015 September 1995 Core Spray Line Tee-Box Analysis Rept for Peach Bottom Atomic Power Station Unit 3 ML20094H0521995-06-30030 June 1995 Pyrolysis Gas Chromatography Analysis of 21 Thermo-Lag Fire Barrier Samples ML20092K9871995-06-13013 June 1995 Rev 3 to Shroud Stabilizer Hardware ML20083K6611995-04-26026 April 1995 Rev a to Upgraded Eals ML20077M0861995-01-31031 January 1995 Nonproprietary TS Improvement Analysis for RPS for PBAPS, Units 2 & 3 ML20077M0951995-01-31031 January 1995 Nonproprietary TS Improvement Analysis for ECCS Actuation Instrumentation for Pbaps,Units 2 & 3 ML20073J7501994-09-30030 September 1994 Shroud Mechnical Repair Program,Peach Bottom Shroud & Shroud Repair Hardware Stress Analysis ML20079S0911994-09-29029 September 1994 Rev 0 to Application of Screening Criteria ML20073J7411994-09-24024 September 1994 Rev 0 to Stress Rept 25A5607, Shroud Stabilizers ML20072P5791994-08-26026 August 1994 Power System Harmonic Study for Peach Bottom Nuclear Power Plant, Final Rept ML20072L9631993-12-13013 December 1993 Evaluation & Screening Criteria for Peach Bottom Unit-2 Shroud ML20064K4291993-12-0303 December 1993 Evaluation & Screening Criteria for Peach Bottom Unit 3 Shroud Indications ML20059L1391993-11-30030 November 1993 Core Spray Crack Analysis for Peach Bottom Unit 3 ML20059G0901993-10-27027 October 1993 Evaluation & Screening Criteria for Peach Bottom Unit-3 Shroud Indications ML20149G0401993-05-30030 May 1993 Fatigue Evaluation of Peach Bottom II & III Reactor Vessels ML20118A3641992-08-26026 August 1992 Vols 1 & 2 of Individual Plant Exam,Peach Bottom Atomic Power Station Units 2 & 3 ML20073E5881991-04-30030 April 1991 Revised Station Blackout Analysis ML20073D0221991-04-30030 April 1991 Full Structural Weld Overlay Design for Peach Bottom Unit 2 RWCU Weld 12-I-1D ML20067E5071991-02-0808 February 1991 Simulator Performance Rept. W/Two Oversize Drawings ML20067E5051991-02-0808 February 1991 Simulator Performance Rept. W/Two Oversize Drawings ML20067E5091991-01-28028 January 1991 Malfunction Causes & Effects ML20055J3271990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20055J3231990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20055J3291990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML18095A3791990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20044H3281990-02-23023 February 1990 Rev a to 30-Month Stability Spec for Rosemount Models 1152, 1153 & 1154 Pressure Transmitters ML20247N3951989-05-16016 May 1989 Methods for Performing BWR Reload Safety Evaluations ML20236A8501989-01-31031 January 1989 Voltage Regulation Study ML20236A8351989-01-31031 January 1989 Rev 1 to Peach Bottom Atomic Power Station Units 2 & 3, Verification of Calculated Auxiliary Distribution Sys Voltages by Test ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20151M5501988-07-15015 July 1988 Security Problem Root Cause Assessment ML20147A7971988-02-23023 February 1988 Root Cause Investigation of Shutdown Cooling Isolations Peach Bottom Atomic Power Station ML20148H1211988-01-15015 January 1988 Rev 0 to Peach Bottom Atomic Power Station,Units 2 & 3, Response to IE Bulletin 85-003 ML20149D6981988-01-13013 January 1988 Methods for Performing BWR Steady-State Reactor Physics Analyses ML20196K0311987-12-31031 December 1987 1987 Annual Plant Mod Rept,Per 10CFR50.59 ML20236V3311987-11-20020 November 1987 SAR for Peach Bottom Atomic Power Station Spds 1998-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000278/LER-1999-005-03, :on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With1999-10-20020 October 1999
- on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With
ML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 05000278/LER-1999-004-03, :on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held1999-10-0101 October 1999
- on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held
ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML15112A7681999-09-20020 September 1999 SER Accepting Revision 25 of Pump & Valve Inservice Testing Program,Third 10-year Interval for Plant,Units 1,2 & 3 ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 05000278/LER-1999-003-03, :on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With1999-09-13013 September 1999
- on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With
ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with 05000277/LER-1999-005-01, :on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With1999-07-16016 July 1999
- on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With
ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with 05000278/LER-1999-002-02, :on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With1999-05-0606 May 1999
- on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With
ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 05000278/LER-1999-001-03, :on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments1999-04-0808 April 1999
- on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments
ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With 05000278/LER-1998-009-01, :on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with1999-01-20020 January 1999
- on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with
ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with 05000277/LER-1998-008-01, :on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With1998-12-30030 December 1998
- on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With
05000277/LER-1998-007-02, :on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With1998-12-0404 December 1998
- on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With
ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with 05000278/LER-1998-005-03, :on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With1998-11-20020 November 1998
- on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With
ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 05000277/LER-1998-006-02, :on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With1998-10-0909 October 1998
- on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With
ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with 05000278/LER-1998-004-03, :on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc1998-09-18018 September 1998
- on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc
05000277/LER-1998-005-02, :on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made1998-09-18018 September 1998
- on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made
ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 1999-09-30
[Table view] |
Text
.-
ArrkamtwT 3 O
l PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 i
MARK I LONG TERM PROGRAM PLANT UNIQUE ANALYSIS DOCKET NUMBERS: 50-277 AND 50-278 PREPARED FOR PHILADELPHIA ELECTRIC COMPANY 1
BECHTEL POWER CORPORATION SAN FRANCISCO, CALIFORNIA REVISION 1 AUGUST 1983 gggeggggg9,gggggg, p
PDR
- _ ~ _. _ _ _ - _ -.. - _ _.
]
i Table 7-1 J
VENT SYSTEM FREQUENCIES i
1 l
Mode Frequency (liz)
I i
.j i
I 1
8.03 i
1 l
2 11.02 r
1 1
4 3
11.07 l
{
4 13.31
[
r 4
5 13.64 6
13.87 7
14.16 8
14.47 9
14.87 i
l 10 17.09 1
w.
4 t
b i
l i
1 T1002677-DIS 7-17 4
I
... _ _ _ -. _ _.., -- - -_..._,-.,._. _ ~,.. - -.. - - _ -. -. _ _. _. - - -. _ - - - - _ _... -,. _ _ -. _. _..,... _... _ _... _ -.
Table 7 2 RESS EvhLUATION AT KEY LOCATIONS SERVICE LEVEL A
[ VENT HEADER SUPPORT C. BAY l
IIST DOWNCOMER 3RD DOWNCOMER PAIR 2ND DO OMER PAIR Y
] [(;
i i
'e s
7,' -
(
C VENT PIPE Calculated Allowable 9I SI Location Stress Type oci)
(ksi)
Fatio lO Intersection between P
28.33 37.70 0.75 header and D/C 1 (A)
P
+Pb+Q 50.26 58.00 0.87 l
Intersection between P
8.01 37.70 0.21 header and D/C 3 (B)
P
+Pb+Q 38.30 58.00 0.66 Intersection between P
10.37 29.00 0.36 b
header and vent (C)
P
+Pb+Q 10.64 58.00 0.18 Main vent (D)
P 3.14 19.30 0.16 g
P
+P 3.34 29.00 0.12 b
P
+Pb+Q 3.68 58.00 0.06 lhader between D/C 1 P
10.08 19.30 0.52 ond D/C 2 (E)
P
+P 13.76 37.70 0.36 b
P
+Pb+Q 23.20 58.00 0.40 0
T1002677-DIS 7-18
Table 6-3 DESIGN CASE TORUS PRESSURES AND FREQUENCY RANGES
- Peak Pressure Frequency Range Load Case (psid)
(Hz)
A1.1 6.67 4.09 to 8.49 A3.1 6.67 4.09 to 8.49 A1.3 6.51 4.11 to 8.18 A1.2/A2.2/A3.2 7.53 6.25 to 11.63 C3.1 6.67 3.80 to 10.18 C3.2 7.53 5.31 to 13.49
- Calibration and multiple valve factors not included.
T1002677-DIS 6-29
(
Table 6-4 TORUS FRCQUENCIES Frequency (Hz)
No.
Dry Structure Coupled Structure 1
17.35 14.28 2
17.90 15.08 3
22.41 15.75 4
22.53 16.27 S
23.15 17.58 6
23.48 17.93 7
27.02 18.19 l
8 27.56 20.35 9
28.68 20.78 10 29.70 21.32 O
T1002677-DIS 6-30
.~.;
=.-.-- ~
1 flow rate.
Each of the three phases imparts distinctly chara<<aristic f
- (
dynamic pressures on the shell.
The origin and methods of calculating plant unique loads are discussed in detail in the LDR.
The plant unique I
loads are summarized here.
6.2.2.1 Pool Swell Loads l
During a postulated LOCA, the torus shell is subjected to two types of i
pressure transients:
(1) submerged pressure transients caused by the downward pressure of water on the wetted area of the torus shell and (2)
I torus air space pressure transients caused by compression of the air space above the pool surface.
i j
The definition of these two types of torus shell pressure transients was based on test data obtained from the Quarter Scale Test Facility (QSTF) and the 1/12 Scale Test Facility.
The methodology used for applying the test i
data to this analysis is described in Reference 11.
Plant unique test data and test results for specific loading conditions are contained in Reference l
18.
The test results were based on a two-dimensional model.
Additional margins were incorporated to account for three-dimensional effects.
These j
adjustments to the test results were based on empirical scale factors.
I Different scale factors were applied to the download phase and the upload phase of the transient.
I 6.2.2.2 Submerged Pressure Transients The basis for the definition of submerged torus shell loads is the " average submerged pressure." The average submerged pressure is the " base" pressure used in determining the pressure history at any submerged point in the torus shell. This is plant unique and is based on QSTF and 1/12-scale test 4
results.
Figure 6-13 shows the plant unique average submerged pressure transient for Peach Bottom Units 2 and 3.
These QSTP average pressures are adjusted by margins based on empirical relations defined in Reference 11.
i I
This additional margin works out to be 21.2% of the net download for the download phase of the transient.
s T1002677-DIS 6-5 7
e aem---
-r.-#
ww y-1 w
=
6.2.2.3 Air Space Pressure Transients The torus air space pressure transients are also based on QSTP tests.
The plant unique pressure transient for this portion of the torus shell is shown in Figtce 6-14.
The magnitude of the QSTF pressure transient for the upload phase was increased by an additional margin of 31.5% of the net upload.
The upload additional margin was applied only to that portion of the transient representing the upload phase, starting from the beginning of the upload phase to the end of the transient.
Figure 6-15 shows the adjusted pressure transients in the wetted surface and air space.
6.2.2.4 CO and Chugging Loads CO and chugging loads are cyclic in nature whereas the pool swell load is a transient. Plant unique CO and chugging loads are defined in the LDR.
6.2.3 SRV Discharge Loads SRV discharge loads on the torus are transient pressures on the submerged portion of the shell. The SRV discharge phenomenon is briefly described in Section 3.
The method of defining the SRV 31scharge load is given in the LDR.
It provides two alternative methods of calculating torus shell loads.
They are:
(a) Calculation of shell pressures using the General Electric program QBUBS (b) Calculation of shell pressures using in-plant SRV test data.
For Peach Bottom, the latter method was used.
A detailed test program was conducted in Peach Bottom Unit 2 after the quenchers were installed. Shell pressures and structural responses were measured.
The General Electric fluid model QBUDS which calculates the torus shell pressures was calibrated to calculate interface shall pressures.
The calibrated progr-was then T1002677-DIS 6-6
f N Table 5-3 GOVERNING LOAD COMBINATIONS FOR VENT HEADER PENETRATION Column No. in Combination Service Table 5-1, No.
Level Load Combinations Ref 14 1
A N+SRV +IBA/SBA (P +T +R ) +0BE 12
+2 A
N+SRV +IBA/SBA (P +T +R ) +CH+OBE 14 g
+ 3*
A N+DBA(R )+PS+0BE 18
+4 A
N+DBA(P +R +T )+CO+0BE 20 3 A 5
C N+SRV +IBA/SBA (P +T +R ) +CH+SSE 15 g
6 C
N+SRV +DBA(R )+PS+SSE 25 s
7 C
N+DBA (P +R +T ) +CO+SSE 27 7 ~)
g
%)
- (a) Evaluation for fatigue and primary plus secondary stress range is not required.
(b) For the pool swell impingement region of the vent system, allowabic stresces may be increased to service Level C.
+ (a) For local membrane stress intensity and priraary membrane plus bending stress intensity, the S values may be increased to 1.3 S,.
/'~'1 t
/'
T1002677-DIS 5-7
Table 5-4 GOVERNING LOAD COMBINATIONS FOR INTERNAL SUPPORTS Column No. in Combination Service Table 5-1, No.
Level Load Combinations Ref 14 1
A N+SRV +IBA (P +T +R ) +CH+0BE 14 2
A N+DBA (R ) +PS+OBE 18 3
A N+DBA (P +T + R ) +CO+0BE 20 4
C N+SRV +IBA(P +T +R )+CH+SSE 15 5
C N+SRV +DBA (R )+PS+SSE 25 6
C N+DBA (P +T +R ) +CO+SSE 27 O
O T1002677-DIS 5-8
i
! f]
ILLUSTRATIONS (Cont'd)
Figure Page 7-7 Vent System Thrust Loads 7-29 7-8 Pool Swell Impact Loading Sequence 7-30 7-9 Typical Local Pressure Transient 7-31 7-10 Finite Element Model of the Vent and 7-32 Ring Header 7-11 Additional Vent System Details 1-33 7-12 Finite Element Model of Downcomers 7-34 7-13 Computer Plot of Vent System 22.5* Finite 7-35 Element Model i
l 7-14 Downcomer CO. Load Application 7-36 7-15 Deformation Due to Unit Vertical Loads 7-37 7-16 Radial Displacement Due to Uniform Internal 7-38 Pressure 7-17 First Mode Shape for Cross Section Through Ring 3 7-39 7-18 Second Mode Shape for Cross Section Through Ring 3 7-40 7-19 Third Mode Shape for Cross Section Through Ring 3 7-41 7-20 First Mode Shape for the Plan View at Downcomer Tips 7-42 7-21 Second Mode Shape for the Plan View at Downcomer Tips 7-43 7-22 Third Mode Shape for the Plan View at Downcomer Tips 7-44 7-23 Principal Stresses at Downcomer/ Vent Header 7-45 Intersection for Pool Swell 7-24 Vent Header Support Outside Column Reaction for 7-46 Pool Swell Loading.
B Plan of Catwalk,_ Monorail, and Spray Header 8-26 8-2 Catwalk Modifications 8 8-3 Monorail and Spray Header Support Modifications 8-28 V
T1002677-DIS xiii'
ILLUSTRATIONS (Cont'd)
Figure Page 8-4 RER Elbow and Support 8-29 8-5 Modifications to HPCI Turbine Exhaust Pipe 8-30 Support 8-6 Modifications to RCIC Turbine Exhaust Pipe 8-31 Support l
8-7 Vacuum Breaker Drain Line Supports 8-32 8-8 Torus Plan Showing Location of Thermowell 8-33 Assembly 8-9 Section and Detail for Thermowell Assembly 8-34 8-10 Modifications to Instrument Air Line 8-35 8-11 Arrangement of Electrical Canister 8-36 O
T1002677-DIS xiv
CONTENTS (Cont'd) i Page 8
STRUCTURAL EVALUATION OF TORUS INTERNAL STRUCTURES 8-1 8.1 Description of Structures and Modifications 8-1 8.2 Loads 8-9 8.3 Allowable Stresses 8-12 8.4 Structural Evaluation 8-15 9
SUMMARY
AND CONCLUSIONS 9-1 REFERENCES R-1 i
t i
i
}
l f
T1002677-DIS ix i
4
ILLUSTRATIONS O
Figure Page 2-1 Peach Bottom Containment Configuration 2-9 2-2 Plan of Torus 2-10 2-3 Cross Section of the Torus 2-11 2-4 Plan of Vent System 2-12 2-5 Plan of Unit 2 Torus Penetrations 2-13 2-6 Plan of Unit 3 Torus Penetrations 2-14 2-7 Return Line Routings Inside Torus 2-15 6-1 Pictorial View of T-Quencher and supports 6-38 6-2 Pictorial View of the Column Tie Down 6-39 6-3 Pictorial View of the Torus Showing Stiffeners 6-40 and Thermowells 6-4 Pictorial View of the Torus Nc:rzle Reinforcement 6-41 6-5 Cross Section Showing Major Modifications 6-42 6-6 Plan of Torus Showing the Location of SRV Quenchers 6-43 6-7 SRV Discharge Lines and Supports Inside Torus 6-44 6-8 T-Quencher Support System 6-45 6-9 Typical Torus Tie Down 6-46 6-10 Shell Stiffeners 6-47 6-11 Typical Nozzle Reinforcement 6-48 6-12 liorizontal Seismic Response Spectrum (OBE) 6-49 6-13 Average submerged Pressure 6-50 6-14 Torus Air Pressure 6-51 6-15 Adjusted Pool Swell Pressure Transients 6-52 6-16 Locations of Pressure Gages 6-53 O
T1002677-DIS x