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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
ML20117E6251996-05-31031 May 1996
Seismic Safe Shutdown Equipment List for PBAPS Units 2 & 3
ML20117E6321996-05-31031 May 1996
USI A-46 Relay Evaluation Rept for PBAPS Units 2 & 3
ML20117E6351996-05-31031 May 1996
Seismic Evaluation Rept for Pbaps
ML20129A4511996-01-11011 January 1996
Core Spray Sparger Downcomer Modification
ML20129A4731995-12-11011 December 1995
Fabrication of Core Spray Line Downcomer Clamp
ML20098B1211995-09-30030 September 1995
Residual Stress Analysis of Peach Bottom Unit 3 Core Spray Pipe to Sleeve Fillet Weld
ML20098B1141995-09-30030 September 1995
Evaluation of Peach Bottom Unit 3 Core Spray Line
ML20092M8921995-09-30030 September 1995
Shroud Vertical Team Weld Evaluation
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
ML20077M0951995-01-31031 January 1995
Nonproprietary TS Improvement Analysis for ECCS Actuation Instrumentation for Pbaps,Units 2 & 3
ML20077M0861995-01-31031 January 1995
Nonproprietary TS Improvement Analysis for RPS 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
ML20073D0221991-04-30030 April 1991
Full Structural Weld Overlay Design for Peach Bottom Unit 2 RWCU Weld 12-I-1D
ML20073E5881991-04-30030 April 1991
Revised Station Blackout Analysis
ML20055J3231990-07-20020 July 1990
Decommissioning Rept of Philadelphia Electric Co
ML20055J3291990-07-20020 July 1990
Decommissioning Rept of Philadelphia Electric Co
ML20055J3271990-07-20020 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
ML20236J7141987-10-28028 October 1987
Commitment to Exellence Action Plan Status Rept
ML20235H5601987-09-0909 September 1987
Methods for Performing BWR Sys Transient Analysis
ML20236D1271987-09-0303 September 1987
Rev 0 to Safety Evaluation for Mod 2085,Peach Bottom Unit 3
ML20236K6081987-07-15015 July 1987
Rev 1 to Evaluation of Insulated Blind Barrel Splices on Dual Voltage Motors in Limitorque Actuators
1998-12-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 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
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
ML20212D1281999-09-17017 September 1999
Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11
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
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
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
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
ML20199E3471998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With
ML20205K0381998-12-31031 December 1998
PECO Energy 1998 Annual Rept. with
ML20206P1651998-12-31031 December 1998
Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection
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
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
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
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
ML20153B9651998-09-14014 September 1998
Safety Evaluation Supporting Amend 9 to License DPR-12
ML20151Y2901998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with
ML20238F2661998-08-24024 August 1998
Safety Evaluation Supporting Amend 222 to License DPR-44
ML20237B9531998-08-10010 August 1998
Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3
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
ML20237A5351998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3
ML20236R8281998-07-15015 July 1998
Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II)
ML20236M3471998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3
ML20249C4791998-06-0202 June 1998
Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12
ML20248F4781998-06-0101 June 1998
Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos
ML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML20248M3001998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3
ML20247N5351998-05-11011 May 1998
SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3
ML20249C4751998-05-0707 May 1998
Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12
ML20247G0721998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3
1999-09-30
[Table view] |
Text
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ERRATA And ADDENDA
- r. E no. 77nn3ss SHEET 737tg LOCA Analysis for Peach 7
Bottom APS Unit 2 Novebu 19M NO TE: Correct all copies of the applicable uS5uE D ATE DeCe~ bet 197I pJblication as spectfied below.
REFERENCES ITE M O A E pjSEC 9gc A t E) (COR RECT NS AN ADDITIONS)
- 1. Page v/vi Replace with revised page v/vi.
- 2. Page 3-1/3-2 Replace with revised page 3-1/3-2.
- 3. Page 4-3 Replace with revised page 4-3.
- 4. Page 4-11 Replace with revised page 4-11.
- 5. Page 4-12 Replace with revised page 4-12.
- 6. Page 4-13/4-14 Add new page 4-13/4-14.
(Change bars in right-hand margin indicate where report has been revised.)
l 1
PAGE 1 8202230300 820219 PDR ADOCK 05000277 P PDR
~
LIST OF TABLES Table Title Py 3-1 Significant Input Parameters to the Loss-of-Coolant Accident Analysis 3-1 4-1 Summary of Results 4-5 4-2 LOCA Analysis Figure Summary 4-6 4-3a MAPLHGR Versus Average Planar Exposure 4-7 4-3b MAPLHGR Versus Average Planar Exposure 4-8.
4-3c MAPLHGR Versus Average Planar Exposure 4-9 4-3d ~ MAPLHGR Versus Average Planar Exposure 4-10 MAPLHGR Versus Average Planar Exposure 4-11 4-3e 4-3f MAPLHCR Versus Average Planar Exposure 4-11 4-3g MAPLHGR Versus Average Planar Exposure . 4-12, 4-3h MAPLHGR Versus Average Planar Exposure- 4-12 4-31 MAPLHGR Versus Average Planar Exposure 4-13/4-14 v/vi
a .
- 3. INPUT TO ANALYSIS A list of the significant plant input parameters to the LOCA analysis is presented in Table 3-1.
~
Table 3-1 SIGNIFICANT INPUT PARAMETERS TO THE LOSS-OF-COOLANT ACCIDENT ANALYSIS Plant Parameters:
Core Thermal Power 3440 MWt, which corresponds to 105% of rated steam flow Vessel Steam Output 14.05 x 106 lbm/h, which corresponds to 105% of rated steam flow
~
Vessel Steam Dome Pressure 1055 psia Recirculation Line Break Area for farge Breaks - Discharge 1.9 ft 2 DBA)
- Suction 4.1 ft 2 ((DBA)
Number of Drilled Bundles 360 Fuel Farameters:
Peak Technical Initial Specification Design Minimum Lit. ear Heat Axial Critical Fuel Bundle Generation Rate Peaking Power Fuel Type Geometry (kW/ft) Factor Ratio A. IC Type 2 7x7 18.5 1.5 1.2 B. IC Type 3 7x7 18.5 1.5 1.2 C. 8D274L 8x8 13.4 1.4 1.2 D. 8D274H 8x8 13.4 1.4 1.2 E. LTA260 8x8 13.4 1.4 1.2 F. 8DRB284 L 8x8 13.4 1.4 1.2 G. P8DRB284H 8x8 13.4 1.4 1.2 H. P8DRB285 8x8 13.4 1.4 1.2 I. P8DRB299 0x8 13.4 1.4 1.2
- To account for the 2% uncertainty in bundle power required by Appendix K, the SCAT calculation is performed with an MCPR of 1.18 (i.e., 1.2 divided by 1.02) for a bundle with an initial MCPR of 1.20.
3-1/3-2
4.5 RESULTS Or THE CRASTE ANALYSIS e
This code is used, with suitable inputs from the other codes, to calculate the fuel cladding heatup rate, peak cladding temperature, peak local cladding oxidation, and core-wide metal-water reaction for large breaks. The detailed fuel model in CHASTE considers transient gap conductance, clad swelling and rupture, and metal-water reaction.' The empirical core spray heat transfer and channel wetting correlations are built into CRASTE, which solves the transient heat transfer equations for the entire LOCA transient at a single axial plane in a single fuel assembly. Iterative applications of CHASTE determine the maximum permissible planar power where required to satisfy the requirements of 10CFR50.46 acceptance criteria.
The CHASTE results presented are:
e Peak Cladding Temperature versus time e Peak Cladding Temperature versus Break Area e Peak Cladding Temperature and Peak Local Oxidation versus Planar
~
Average Exposure for the most limiting break size e Maximum Average Planar Heat Generation Rate (MAPLHGR) versus Planar Average Exposure for the most limiting break size A summary of the analytical results is given in Table 4-1. Table 4-2 lists the figures provided for this analysis. The MAPLHGR values for each fuel type in the PB-2 core are presented in Tables 4-3a through 4-31. l 4-3
l 1 Table 4-3 e MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Plant: PB-2 Fuel Type: LTA260 Average Planar Exposure MAPLHGR PCT 0xidation (Mwd /c) (kW/ft) (*F) Fraction 200 11.4 1829 0.007 1,000 11.5 1839 0.008 5,000 12.1 1913 0.010 10,000 12.2 1929 0.011 15,000 12.3 1958 0.012 20,000 12.1 1961 6.012 25,000 11.7 1911 0.010 30,000 11.3 1882 0.009 35,000 10.3 1752 0.006 40,000 9.7 1678 0.004 45,000 9.1 1603: 0.003 50,000 8.5 1567 0.002 Table 4-3f MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Fuel Type: SDRB284L l Md Exposure MAPLEGR PCT Oxidation (MVd/t) (kW/fc) ('F) Fraction 200 11.3 1858 0.009 1,000 11.3 1862 0.009 5,000 11.8 1926 0.011 10,000 12.0 1937 0.011 15,000 12.0 1947 0.012 20,000 11.6 1910 0.010 25,000 10.9 1828 0.008 30,000 10.2 1751 0.006 35,000 9.6 1676 0.004 40,000 8.9 1600 0.003 4-11
..).-
c.
3 Table 4-3g i MAPLHGR VERSUS AVERAGE PLGAR EXPOSL%E Fuel Type: P8DRB284H*
Average Planar Exposure MAPLEGR PCT 0xidation
(%'d/t) (kW/ft) (*F) Fraetion 200 11.2 1861 0.003 1,000 11.2 1865 0.008 5,000 11.7 1903 0.010 10,000 12.0 1938 0.011 15,000 12.0 1938 0.011 20,000 11.5 1907 0.011 25,000 10.8 1823 0.007 30,000 10.1 1744 0.005 35,000 9.6 1665 0,004 40,000 9.0 1589 0,003
- Applicable to 80, 100, and 120 mil channels Table 4-3h
' MAPLHCR VERSUS AVERAGE PLANAR EXPOSURE Fuel Type: P8DRB285 Average Planar Exposure MAPLHGR PCT Oxidation ON'd/t) (kW/f t) (DF) Fraction 200 11.0 1826 0.008 1,000 11.1 1836 0.008 5,000 11.9 1924 0',011 10,000 12.2 1948 0.012 15,000 12.1 7043 0.011 20,000 11.7 502 0.010 25,000 11.0 818 0.007 30,000 10.3 1740 0.005 35,000 9.7 1667 o,004 40,000 9.1 1592 0,003 4-12
t' Table 4-31 MAPLEGR VERSUS AVERAGE PLANAR EXPOSURE Plant: PB-2 Fuel Type: P8DRB299 Average Planar Exposure MAPLHGR PCT Oxidation (kW/ft) (*F) Fraction (Mud /t) 200 10.9 1800 0.007 1,000 11.0 1804 0.007 5,000 11.5 1851 0.008 10,000 12.2 1933 0.011 15,000 12.3 1962 0.012 20,000 12.3 1965 0.012 25,000 11.9 1932 0.011 30,000 11.4 1864 0.009 35,000 10.9 1799 0.007 40,000 10.4 1744 0.005 45,000 10.0 1689 0.004 l
l 4-12/4-14 f
