LOCA Analysis Rept for Pilgrim Nuclear Power Station. Errata & Addenda SheetsML20040G819 |
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Pilgrim |
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Issue date: |
11/30/1981 |
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From: |
GENERAL ELECTRIC CO. |
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To: |
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Shared Package |
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ML20040G814 |
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References |
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77NED148, NEDO-21696-ERR, NUDOCS 8202160505 |
Download: ML20040G819 (6) |
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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
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NUCLEAR ENERGY BUSINESS GROUP
- GENER AL ELECTRIC COMPANY SAN JOSE, CALIFORNI A 95125 G EN ER AL $ ELECTRIC APPLICABLE TO:
~
PUBLICATION NO 771ED148 ERRATA And ADDENDA T. I. E. NO.
SHEET TITLE LOSS-OF-COOLANT ACCIDENT "O'
ANALYSIS REPORT FOR PILGRIM DATE November 1981 NUCLEAR POWER STATION NOTE: Correctallcopies of the applicable sSSUE DATE AUWS publication as specified below.
REFERENCES ON, A INSTRUCTIONS ITEM pjSEC g pH L NE) (CORRECTIONS AND ADDITIONS) 01 Page 4-5 Replace with new page 4-5.
02 Page A-3 Replace with new page A-3.
03 Page A-7 Replace with new page A-7.
NOTE: changes are indicated by vertical bar in the right-hand margin.
PAGE l Of l 8202160505 820208 PDR ADOCK 05000293 P PDR
NEDO-21696 Table 2
SUMMARY
OF BREAK SPECTRUM RESULTS e Break Size Core-Wide e Location Peak Local Metal-Water e Single Failure PCT ('F) Oxidation (%) Reaction (%)
e 4.34 ft 2136(1) 2.3 0.14 e Recirc Suction e LPCI Injection Valve
- 1. PCT from CIMSTE P
4- 5
, . o 6
NEDO-21696 Table 3 LOCA ANALYSIS FIGURE
SUMMARY
- NON-LEAD PLAirr Large Break Methods Maximum Suction Break LBA (LPCI Injection Valve Failure)
(4.34 ft2)
Water Level Inside Shroud 1 and Reactor Vessel Pressure Peak Cladding Temperature 2 Heat Transfer Coefficient 3 Core Average Inlet Flow 4 Minimum Critical Power Ratio 5 Peak Cladding Temperature of 2 the Highest Powered Plane Experiencing Boiling Transition Variation with Break Area of 6 Time for Which Hot Node Remains Uncovered 4-6
J .
NED0-21696 the depressurization rate was found to be negligible in the pre-vious section. The results of CHASTE calculations show that the l DBA remains the limiting break.
l A.4.2 Small Break Analysis Break sizes smaller than 1.0 ft2 are not limiting as snown in the comparison of the uncovered times in Table A-2. All breaks in Table A-2 have an uncovered time which is equal to or less than the 154 second uncovered time for the DBA, except for the 0.100 ft2 break. For all these breaks (except the 0.100 ft2, which is described later) the Peak Cladding Temperature (PCT) will be less than the 2200 0F calculated for the DBA, because the time of hot node uncovery decreases with decreasing break size, and the decay heat decreases with increasing break size, and the decay heat decreases with increasing time. Thus the 0 900 ft2 break will have a lower PCT than the DBA, even though both breaks have equal uncovered tbnes, because the 0 900 ft2 break has an uncovery time of 71 seconds, which is much later than the DBA uncovery time of 20.6 seconds. The decay heat at 71 seconds is less than at 20.6 seconds, so the heatup in the uncovered period for the 0.900 ft2 break is less than the heat-up for the DBA.
For the 0.100 ft2 break, which has an uncovered time only 3 seconds more than the DBA, the PCT is calculated by the small break model to be less than 17000F, A .S Conclusions Using the DBA as the limiting break, a bounding analysis was performed with the CHASTE code. The results of the calculations show that for each of the fuel types, a MAPLHGR multiplier which is independent of exposure must be applied to the MAPLHGR values given in Section 4 of this report . These MAPLHGR multipliers are given in Table A-3 The use of these multipliers conservatively determines the MAPLHGR required to keep the PCT below 2200cF for the DBA, with no credit assumed for core spray heat transfer. Break spectrum summary results applicable to the "no core spray" analysis are given in Table A-4.
A-3
s:
NEDO-21696 The calculations described in this Appendix were performed at the request of the Boston Edison Company (BECO) in order to support BECO's proposal to return to service taking no credit for core spray heat transfer. The technical justification for such calculations has been presented in this Appendix. However, General Electric considers the assumption of no core spray heat transfer credit to be excessively conservative, based on the calculations which support the continued structural integrity of the core spray spargers (presented in Reference A-1) and the many recognized conservatisms in the current LOCA models.
A.6 References A-1 Supplement 1 to Supplemental Reload Licensing Submittal for Pilgrim Nuclear Power Station Unit 1 Reload 4, NEDO-24224-1 Supplement 1, March 1980.
l l
f A-4
.4 .
NEDO-21696 Table A-3 MAPLHGR Multipliers Assuming No Core Spray Heat Transfer Credit Fuel Type Core Flow 2 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 Table A-4
SUMMARY
OF BREAK SPECTRUM RESULTS(
e Break Size Core-Wide e Location Peak Local Metal-Water e Single Failure PCT (OF) Oxidation (%) Reaction (%)
e 4.34 ft 2200 2.5 0.17 e Recirc Suction e LPCI Injection Valve (1)With no core spray heat transfer credit.
A-7
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