Errata & Addenda 6 to LOCA Analysis for Peach Bottom Atomic Power Station,Unit 3ML20112B195 |
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Site: |
Peach Bottom ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
11/30/1984 |
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From: |
GENERAL ELECTRIC CO. |
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To: |
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Shared Package |
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ML20112B082 |
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References |
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NEDO-24082-ERR, NEDO-24082-ERR-06, NEDO-24082-ERR-6, NUDOCS 8501100254 |
Download: ML20112B195 (10) |
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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20199E8961997-10-31031 October 1997 Recirc Piping Reanalysis Uniform Support Motion (Reg Guide 1.60 Free-Field Motion & ASME Code Case N-411 Damping) ML20129A4301996-01-0808 January 1996 Core Spray Line Downcomer Repair Seismic Rept Summary for Peach Bottom Atomic Power Station,Unit 2,Mod P00335 ML20129A4101995-12-22022 December 1995 Core Spray Line Downcomer Repair Hardware Stress Assessment Rept for Peach Bottom Atomic Power Station Unit 2,Mod P000335 ML20069M6271994-06-30030 June 1994 End-Of-Cycle Recirculation Pump Trip Analysis for PBAPS Units 2 & 3 ML20128L4351992-11-30030 November 1992 Spent Fuel Storage K 00 Conversion Analyses ML20150E6371988-01-31031 January 1988 Errata to NEDO-24082, LOCA Analysis for Peach Bottom Atomic Power Station Unit 3 ML20151V7881988-01-31031 January 1988 Errata to NEDO-24081, LOCA Analysis for Peach Bottom Atomic Power Station,Unit 2, Replacing Page 4-14 ML20154C2111986-11-30030 November 1986 BWR Owners Group Assessment of ECCS Pressurization in Bwrs ML20137N6551985-11-30030 November 1985 Evaluation of Low Carbon Type 316 Stainless Steel Recirculation Outlet Safe Ends at Peach Bottom Unit 3 ML20112B1951984-11-30030 November 1984 Errata & Addenda 6 to LOCA Analysis for Peach Bottom Atomic Power Station,Unit 3 ML20096H1271984-06-30030 June 1984 Errata to NEDO-24081 LOCA Analysis for Peach Bottom Atomic Power Station Unit 2 ML20096H1141984-06-30030 June 1984 Errata to NEDO-24229-1, Peach Bottom Atomic Power Station Units 2 & 3 Single Loop Operation ML20091J9051984-03-31031 March 1984 Safety Review of Peach Bottom Unit 3 at Core Flow Conditions Above Rated Flow Throughout Cycle 6 ML20064B9971982-10-31031 October 1982 Errata & Addenda Sheet 5 to LOCA Analysis for Peach Bottom Atomic Power Station,Unit 3 ML20053E8921982-05-31031 May 1982 Core Spray Sparger Crack Analysis at Peach Bottom Atomic Power Station,Unit 2. ML20003E1501981-03-31031 March 1981 Errata 4 to LOCA Analysis for Peach Bottom Atomic Power Station Unit 3. ML20003E1481981-02-28028 February 1981 Errata 3 to LOCA Analysis for Peach Bottom Atomic Power Station Unit 3. ML19337B4631980-06-30030 June 1980 Errata & Addenda Sheet 2 to LOCA Analysis for Peach Bottom Atomic Power Station Unit 3. ML19337B4641980-06-30030 June 1980 Addenda 6 to LOCA Analysis for Peach Bottom Atomic Power Station Unit 2. ML19351F3581980-05-31031 May 1980 Single Loop Operation. ML19290E3151980-01-31031 January 1980 Proposed Alternate Absorber Control Blade Test Program, Revision 1,Class 1 ML19290E3221980-01-31031 January 1980 Errata & Addenda Sheet 5,revising Pages 4-11 & 4-12 ML19290E3181979-12-31031 December 1979 Errata & Addenda Sheet 4,revising Pages 4-10,4-11 & 4-12 ML19249D9081979-08-31031 August 1979 Proposed Alternate Absorber Control Blade Test Program. 1998-05-31
[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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- g. 4 NUCLEAR ENERGY BUSINESS OPERATIONS o GENERAL ELECTRIC COMPANY SAN JOSE. CA LIFORNI A 95125 GENER AL $ ELECTRIC APPLICABLE TO:
PUBLICATION NO. NEDO-24082 T.1. E. NO. mT356 , , , _ _ _
TITLE LOCA ANALYSIS FOR PEACH 6 N O.
BOTTOBf AT051IC POWER STATION DATE November 1984 UNIT 3 NOTE: Correctallcopies of the applicable ISSUE DATE OCCCMbOT 1977 publication as specified below.
INSTRUCTIONS PfRAG A P'N L NE) (COR RECTIONS AND ADDITIONS)
- 1. Page v/vi Replace with new page v/vi.
- 2. P' age 3-1/3-2 Replace with new pages 3-1 and 3-2.
- 3. Page 4-3 Replace with new page 4-3
- 4. Page 4-14 Replace with new page 4-14
- 5. Page 4-15/4-16 Replace with new pages 4-15 and 4-16 (Change brackets in right-hand margin indicate areas where report has been revised.)
i 8501100254 PDR ADOCK 85010705000278 PDR 1 of 1 p PAGE l
.'. .. NEDO-24082-LIST OF TABLES
/ Table Title Pg 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 4-3e MAPLHGR Versus Average Planar Exposure 4-11 4-3f MAPLHGR Versus Average Planar Exposure 4-12 4-3g MAPLHGR Versus Average Planar Exposure 4-13 4-3h MAPLHGR Versus Average Planar Exposure 4-14 4-31 MAPLHGR Versus Average Planar Exposure 4-15
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4-3j MAPLHGR Versus' Average Planar Exposure 4-16 v/vi .
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NED0-24082
- 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 MWe, 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 Large Breaks - Discharge 1.9 f t' (DBA)
- Suction 4.1 ft2 (pgA)
Number of Drilled Bundles 432 Fuel Parameters:
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Table 3-1 continued on Page 3-2.
3-1 ..
g-NED0-24082 .
Table 3-1 (Continued)
Peak Technical Initial.
Specification Design Minimum Linear Heat Axial Critical Fuel Bundle Generation Rate Peaking Power-
' Fuel Type Geometry (kW/ f t) Factor Ratio
- A~. IC Type 2 7x7 18.5 1.5 1.2 B. IC Type 3 7x7 18.5 1.5 1.2
~ ae b ,9 e ,
C. 8D274L 8x8 13.4 1.4 1.2
'D.. 8D274H 8x8 13.4 1.4 1.2 E. -PTA260 8x8 13.4 1.4 1.2 F. .8DRB283 8 x 8R 13.4 1.4 1.2 G. P8DRB284H 8 x 8R 13.4 1.4 1.2
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H. B/P8DRB299 8 x 8R 13.4 1.4 1.2 -
I. P8DQB326LTA 8 x 8R 13.4 1.4 1.2 J. BP8DRB299H 8 x 8R 13.4 1.4 1.2
- To account for the 27. 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.
4 3-2
NEDO-24082 4.5 RESULTS OF THE CHASTE ANALYSIS This code is used, with suitable inputs from the other codes, to calculate the fuel'eladding heatup rate, peak cladding temperature, peak local cladding exidation, 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 reacciaa. The empirical core spray heat transfer and
' channel wetting correlations are built into CHASTE, 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 0xidation 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-3 core are presented in Tables 4-3a through 4-3j.
4-3
4.6 METRODS In the following sections, it will be useful to refer to the methods used to enalyze DBA, large breaks, and small breaks. For jet-pump reactors, these are defined as follows:
- a. DBA Methods. LAMB / S CAT / SAFE / DBA-RFILuvu / CH A STE . Break size: DBA.
- b. Large Break Methods (LBM). LAMB / SCAT / SAFE /non-DBA REFLOOD/ CHASTE.
2 Break sizes: 1.0 ft 1 A < DBA.
- c. Small Break Methods (SBM). SAFE /non-DBA REFLOOD. Heat transfer coefficients: nucleate boiling prior to core uncovery, 25 Btu /hr-ft2 _ .7 after recovery, core spray when appropriate. Peak cladding temperature and peak local oxidation are calculated in non-DBA-REFLOOD. Break sizes A 1 1.0 ft2 4-4
- )
m .- 1 s --
NEDO-24082 !
Table 4-3g MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Plant: PB-3 ,
Fuel Type: P8DRB284H Average' Planar Exposure MAPLHGR PCT 0xidation (mwd /t) (kW/ft) (*F) Fraction 200 11.3 1812 0.007 1,000 11.3 1813 0.007 5,000 11.7 1858 0.008 -
10,000 12.1 1894 0,009 15,000 12.0 1897 L.009 20,000_ 11.6 1858 0.008 25,000 10.9 1777 0.006 30,000 10.2 1700 0.004 35,000 9.6 1630 0.003
. 40,000 9.0 1556 0.002 4-13
. n NEDO-24082 Table 4-3h MAPIRGR VERSUS AVERAGE PLANAR EXPOSURE
- Plant: PB-3 Fuel Type: P8DRB299 and BP8DRB299
.Avarage Planar.
Exposure MAPLHGR PCT Oxidation
' (Wd/t) (kW/ft) (*F) Fraction 200 10.9 1768 0.006 1,000 11.0 1772 0.006 5,000 11.5 1817 0.007 10,000 12.2 1894 0.009 15,000 12.3 1923 0.010 20,000 12.1 1906 0.010 25,000 11.6 1856 0.008 30,000 10.9 1776 0.006 35,000 10.3 1703' O.004 40,000 9.6 1629 0.003 4-14
NEDO-24082 Table 4-31 MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Plant: PB-3 Fuel Type: P8DQB326LTA Average Planar Exposure MAPLHGR PGT 0xidation -
(MWa/t) (kW/ft) (*F) Fraction 200 10.9 1724 0.005 1,000 10.9 1730 0.005 5,000 11.5 1798 0.007 10,000 12.4 1892 0.010 15,000 12.5 1902 0.010 20,000 12.5 1902 0.010 25,000 11.9 1838 0.008 30,000 11.3 1766 0.006 35,000 10.7 1704 0.005 40,000 10.3 1659 0.004 45,000 9.3 1556 0.002 50,000 8.4 1446 0.001 4-15
-)
NEDO-24082 ~
Table 4-3j MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Plant: PB-3 Fuel Type: BP8DRB299H Average Planar Exposure MAPLHGR PCT 0xidation (mwd /t) (kW/ft) ('F) Fraction 200 11.1 1820 0.007 1,000 11.2 1822 0.007 5,000 11.7 1877 0.009
-10,000 12.2 1940 0.011 15,000 12.3 1954 0.012 20,000- 12.0- 1930 0.011
.25,000 11.2' 1843 0.008 30.000 10.5 1767 0.006 i 35,000 9.8 1682 0.004 140,000 9.2 1607 0.003 45,000 8.7 1543 0.002 I'
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