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Errata & Addenda to LOCA Analysis Rept for Pilgrim Nuclear Power Station| ML20214Q200 |
| Person / Time |
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| Site: |
Pilgrim |
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| Issue date: |
08/31/1986 |
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| From: |
GENERAL ELECTRIC CO. |
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| To: |
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| Shared Package |
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| ML20214Q102 |
List: |
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| References |
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| 77NED148, NEDO-21696-ERR, NEDO-21696-ERR-04, NEDO-21696-ERR-4, NUDOCS 8706040280 |
| Download: ML20214Q200 (8) |
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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20214Q2221986-10-31031 October 1986
Errata & Addenda to LOCA Analysis Rept for Pilgrim Nuclear Power Station
ML20214R9111986-09-30030 September 1986
Evaluation of HPCI & RCIC Operability Requirements at Low Vessel Pressure for Pilgrim Nuclear Power Station
ML20214Q2001986-08-31031 August 1986
Errata & Addenda to LOCA Analysis Rept for Pilgrim Nuclear Power Station
ML20044G1351986-07-31031 July 1986
Evaluation of Effect on Plant Operation of MSIV Low Turbine Inlet Pressure Isolation Setpoint Change at Pilgrim Nuclear Power Plant.
ML20044G1401986-05-31031 May 1986
Safety Evaluation of MSIV Low Turbine Inlet Pressure Isolation Setpoint Change for Pilgrim Nuclear Power Plant.
ML20099J7151984-09-30030 September 1984
Rev 1 to Nonproprietary Conceptual Design for Pilgrim Nuclear Power Station Emergency & Plant Info Computer (EPIC) Safety Parameter Display Sys (Spds)
ML20108B7931984-09-30030 September 1984
Recirculation Nozzle Repair Program & Hydrogen Water Chemistry Matls Qualification
ML20214Q1821984-09-11011 September 1984
LOCA Analysis Update
ML20083H9181983-10-31031 October 1983
Errata & Addenda to NEDO-21696, LOCA Analysis Rept for Pilgrim Nuclear Power Station
ML20087L0971983-09-30030 September 1983
Suppl 1 to Safety Review of Pilgrim Nuclear Power Station Unit 1 at Core Flow Conditions Above Rated Flow for End-of- Cycle 6
ML20087L0931983-08-31031 August 1983
Safety Review of Pilgrim Nuclear Power Station,Unit 1 at Core Flow Conditions Above Rated Flow Throughout Cycle 6
ML20071N6821982-09-30030 September 1982
GE BWR Extended Load Line Limit Analysis for Pilgrim Nuclear Power Station Unit 1 Cycle 6
ML20073A1491982-06-30030 June 1982
GE BWR Increased Safety/Relief Valve Simmer Margin Analysis for Pilgrim Nuclear Power Station Unit 1
ML20040G8191981-11-30030 November 1981
LOCA Analysis Rept for Pilgrim Nuclear Power Station. Errata & Addenda Sheets
ML20010H9241981-08-31031 August 1981
Supplemental Reload Licensing Submittal for Pilgrim Nuclear Power Station Unit 1,Reload 5.
ML19347F3181980-06-30030 June 1980
Single Loop Operation.
ML20099K3081976-01-31031 January 1976
Suppl to Pilgrim Nuclear Power Station Unit 1 Amend for Single Loop Operation W/Bypass Holes Plugged
ML20099K1161975-10-31031 October 1975
License Amend for Single-Loop Operation
ML20216B6311971-03-0909 March 1971
Analytical Rept for Pilgrim Reactor Vessel
1986-09-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3021999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Pilgrim Nuclear Station.With
ML20212C2921999-09-16016 September 1999
SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station
ML20216F3511999-09-0808 September 1999
ISI Summary Rept for Refuel Outage 12 at Pnps
ML20216E6881999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Pilgrim Nuclear Power Station.With
ML20210R3401999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Pilgrim Nuclear Power Station.With
ML20209C4731999-07-0707 July 1999
Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co
ML20209H8251999-07-0101 July 1999
Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station
ML20209E6191999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Pilgrim Nuclear Power Station.With
ML20196H2451999-06-29029 June 1999
SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation
ML20209A8901999-06-28028 June 1999
SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i)
ML20209B9861999-06-23023 June 1999
Rev 13A to Pilgrim Nuclear Power Station COLR for Cycle 13
ML20217N9061999-06-21021 June 1999
Rept of Changes,Tests & Experiments for Period of 970422-990621
ML20195K3431999-06-15015 June 1999
Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant
ML20195G8231999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Pnps.With
ML20207E7471999-05-27027 May 1999
Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35
ML20206M1971999-05-11011 May 1999
SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant
ML20206J6611999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Pilgrim Nuclear Power Station.With
ML20205L0221999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Pilgrim Nuclear Power Station.With
ML20207J5471999-03-0909 March 1999
Training Simulator,1999 4-Yr Certification Rept
ML20207F9401999-03-0101 March 1999
Long Term Program Semi-Annual Rept for Pilgrim Nuclear Power Station
ML20207H5451999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Pilgrim Nuclear Power Station.With
ML20196E2151998-12-31031 December 1998
1998 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept.With
ML20206Q2741998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Pilgrim Nuclear Power Station.With
ML20197J3591998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Pilgrim Nuclear Power Station.With
ML20195C9951998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Pilgrim Nuclear Power Station.With
ML20154K0721998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Pilgrim Nuclear Power Station.With
ML20153D3901998-09-22022 September 1998
Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station
ML20197C5011998-09-0404 September 1998
Rev 12C,Pages 4 & 5 to Pilgrim Nuclear Power Station Colr
ML20197C5471998-08-31031 August 1998
Rev 12C to Pilgrim Nuclear Power Station Colr
ML20151W8231998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Pilgrim Nuclear Power Station.With
ML20237E2251998-08-26026 August 1998
Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station
ML20237A9941998-07-31031 July 1998
Monthly Operating Rept for Pilgrim Nuclear Power Station
ML20236U8201998-07-13013 July 1998
Rev 12B to Pilgrim Nuclear Power Station COLR (Cycle 12)
ML20236P0151998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Pilgrim Nuclear Power Station
ML20249A3741998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Pilgrim Nuclear Power Station.W/Undated Ltr
ML20247H2081998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Pilgrim Nuclear Power Station
ML20207B7601998-03-31031 March 1998
Final Rept, Pilgrim Nuclear Power Station Site-Specific Offsite Radiological Emergency Preparedenss Prompt Alert & Notification System Quality Assurance Verification, Prepared for FEMA
ML20216G3911998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Pilgrim Nuclear Power Station
ML20216J3741998-03-19019 March 1998
Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B
ML20248L2241998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Pilgrim Nuclear Station
ML20202G5251998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for Pilgrim Nuclear Power Station
ML20236M8511997-12-31031 December 1997
1997 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept
ML20198L7701997-12-31031 December 1997
Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station
ML20203D6101997-11-30030 November 1997
Monthly Operating Rept for Nov 1997 for Pilgrim Nuclear Power Station
ML20202D5761997-11-0808 November 1997
1997 Evaluated Exercise
BECO-LTR-97-111, Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station1997-10-31031 October 1997
Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station
ML20217D6431997-10-0101 October 1997
Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim
ML20217H5621997-09-30030 September 1997
Monthly Operating Rept for Sept 1997 for Pilgrim Nuclear Power Station
ML20216J4131997-08-31031 August 1997
Monthly Operating Rept for Aug 1997 for Pilgrim Nuclear Power Station
ML20210J3321997-07-31031 July 1997
Monthly Operating Rept for Jul 1997 for Pilgrim Nuclear Power Station
1999-09-08
[Table view] |
Text
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1 NUCLEAR ENERdY SUSINESS OPER ATl!NS e GENERAL ELECTRIC COMPANY SAN JOSE CAUFORNIA 96125 GENER AL $ ELECTRIC APM.lCA8LE TO:
PutuCATioN No.
"E -216<>6 77NED148 ERRATA And ADDENDA T. i. E. =0.
ET TITu TASS-OF-COOLANT ACCIDENT g_ 4 ANALYSIS REPORT 70R PILCRIM August 1986 OATE NUPTIAR POWER STATION AUGUST 1977 Nom Cms #ewimo% app # cable issut DATE publication a specified below.
REFERENCES INSTRUCTIONS ITEM ($EcTION. PAG E PA A AG R APH. UN E) (CORRECTIONS AND ADDITIONS)
- 1. Page iv Replace with new page iv
- 2. Page 3-1 Replace with new page 3-1 -
- 3. Page 4-3 Replace with new page 4-3
- 4. Page 4-13 Add new page 4-13
- 5. Page A-7 Replace with new page A-7 Note: Changes are indicated by a vertical bar in the right-hand margin. -
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e t
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8706040280 870522 PDR ADOCK 05000293 PDR P
PAGE I Of 1
, NEDO-21696 .
9
't TABLE OF CONTENTS
.E* E *.
- 1. INTRODUCTION 1-1
- 2. LEAD PLANT SELECTION 2-1
- 3. INPUT TO ANALYSIS 3-1
- 4. LOCA ANALYSIS COMPUTER CODES 4-1 4.1 Results of the LAMB Analysis 4-1 4.2 Results of the SCAT Analysis 4-1 4.3 Results of the SAFE Analysis 4-1 4.4 Results of REFLOOD Analysis 4-2 4.5 Results of the CHASTE Analysis 4-3 4.6 Methods 4-4
- 5. DESCRIP* ION OF MODEL AND INPUT CHANGES 5-1
- 6. CONCLUSIONS 6-1
- 7. REFERENCES 7-1
, APPENDIX A - Loss-of-Coolant Accident Analysis with A-1 No Core Spray Heat Transfer Credit iii
NEDO-21696 LIST OF TABLES #
Table Title Page 1 Significant Input Parameters to the Loss-of-Coolant Accident 3-1 2 Summary of Break Spectrum Results 4-5 3 LOCA Analysis Figure Summary - Non-Lead Plant 4-6 4A MAPLHGR Versus Average Planar Exposure 4-7 4B MAPLHGR Versus Average Planar Exposure 4-8 4C MAPLHGR Versus Average Planar Exposure 4-9 4D MAPLHGR Versus Average Planar Exposure 4-10 4E MAPLHGR Versus Average Planar Exposure 4-11 4F MAPLHGR Versus Average Planar Exposure 4-12 4G MAPLHGR Versus Average Planar Exposure 4-13 l l
l iv
i NEDO-21696 8
r
- 3. INPUT TO ANALYSIS A list of the significant plant input parameters to the LOCA analysis is presented in Table 1.
Table 1 SIGNIFICANT INPUT PARAMETERS TO THE LOSS-OF-COOLANT ACCIDENT ANALYSIS Plant Parameters:
Core Thermal Power 2037 MWe, which corresponds to 102% of rated core power Vessel Steam Output 8.14 x 106 lbm/h, which corre-sponds to 102% of rated core power ,
VesselSteamDome'kressure 1050 psia Recirculation Line Break 4.34 ft2 (DBA)
Area for Large Breaks - Suction Number of Drilled Bundles 428 Fuel Parameters:
Peak Technical Initial l
Specification Design Minimum Linear Heat Axial Critical i
Fuel Bundle Generation Rate Peaking Power Fuel Type Geometry (kW/ft) Factor Ratio
- A. 8DB219L 8x8 13.4 1.5 1.24 l B. 8DB219H 8x8 13.4 1.5 1.24 C. 8DB262 8x8 13.4 1.5 1.24 D. P8DRB265L 8x8 13.4 1.5 1.24 E. P8DRB282 8x8 13.4 1.5 1.24 F. P8DRB265H 8x8 13.4 1.5 1.24 G. BP8DRB300 8x8 13.4 1.5 1.24 l
\ *To account for the 2% uncertainty in bundle power required by Appendix K, the SCAT calculation is performed with an MCPR of 1.22 (i.e., 1.24 divided by 1.02) for a bundle with an initial MCPR of 1.24.
3-1
t NEDO-21696
- u 4.5 RESULTS OF THE CHASTE ANALYSIS 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 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 accept,ance criteria.
The CHASTE results presented are:
o 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 o 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 2. Table 3 lists the figures provided for this analysis. The MAPLHGR values for each fuel type in the Pilgrim core are presented in Tables 4A through 4G.
l 4-3
NEDO-21696-t 4.6 METHODS 4 In the following sections, it will be useful to refer to the methods used to analyze DBA, large breaks, and small breaks. For jet pump reactors, these are defined as follows: ,
- a. DBA Methods. LAMB / SCAT / SAFE /DBA-REFLOOD/ CHASTE. Lreak size: DBA.
- b. Large Break Methods (LBM). LAMB / SCAT / SAFE /non-DBA REFLOOD/ CHASTE.
Break sizes: 1.0 ft2 < A < DBA.
- c. Small Break Methods (SBM). SAFE /non-DBA REFLOOD. Heat transfer coefficients: nucleate boiling prior to core uncovery, 25 Btu /hr-f t 2 *F after recovery, core spray when appropriate. Peak cladding tenperature and peak local oxidation are calculated in non-DBA-REFLOOD. Break sizes: A < 1.0 ft2, 4
l 1
l 1
1 4-4
', NEDO-21696 u
Table 4G MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Plant: Pilgrim Fuel Type: BP8DRB300 Average Planar Exposure MAPLHGR PCT 0xidation (GWd/MT) (GWd/ST) (kW/ft) (*F) Fraction 0.22 0.2 10.9 2045. 0.018 1.1 1.0 11.0 2038. 0.017
.5.5 5.0 11.4 2041. 0.016 11.0 10.0 12.0 2100. 0.020 16.5 15.0 12.3 2140. 0.022 22.0 20.0 12.1 2134. 0.022 27.6 25.0 11.5 2047. 0.017 38.6 35.0 10.3 1854. 0.008 49.6 45.0 9.1 1704. 0.005 l
l 4-13 i
s NEDO-21696
' f, Table A-3 MAPLHGR Multipliers Assuming No Core Spray Heat Transfer Credit Fuel Type Core Flow > 90% Rated Core Flow < 90% Rated 8DB219L 0.93 0.85 8DB219H 0.93 0.85 8DB262 0.94 0.86 P8DRB265L 0.91 0.84 P8DRB282 0.92 0.85 P8DRB265H 0.90 0.82 BP8DRB300 0.90 0.82 l Table A-4
SUMMARY
OF BREAK SPECTRUM RESULTS(1 e Break Size Core-Wide e Location Peak Local Metal-Water e Sinale Failure PCT ('F) Oxidation (%) Reaction (%)
e 4.34 ft2 2200 2.5 0.17 e Recire Suction e LPCI Injection Valve i
(1)With no core spray heat transfer credit.
A-7