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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
, . _ _ _ _ _ _ _ - ._ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _____
NUCLEAR ENERGY BUSINESS OPEaATIONS o GENERAL ELECTRIC COMPANY SAN JOSE, CALIFORNIA 95125 GENERAL $ ELECTRIC APPLICABLE TO:
NEDO-21696 PUBLICATION NO.
77NED148 ERRATA And ' ADDENDA T. i. E. NO.
LOSS-OF-COOLANT ACCIDENT 5HEET TITLE 3 N O.
ANALYSIS REPORT FOR PILGRIM DATE October 1983 NUCLEAR POWER STATION August 1977 NOTE: Correctallcopies of the applicable 1SSUE DATE publication as specified below.
REFERENCES INSTRUCTIONS ITEM (SECTION, PAGE PAR AGR APH, LINE) (CORRECTIONS AND ADDITIONS) 01 Page 1-1 Replace with new page 1-1.
NOTE: Changes are indicated by vertical bar in the right-hand margin.
j 8401090554 831228 PAGE 1 of 1 PDR ADOCK 05000293 P pop l .
4hm. s.
NED0-21696
- 1. INTRODUCTION j- The purpose of this document is to provide the results of the loss-of-coolant accident (LOCA) analysis for the Pilgrim Nuclear Power Station (Pilgrim). r The analysis was performed using approved General Electric (GE) calculational l
l models.
l This reanalysis of the plant LOCA is provided in accordance with the NRC l
requirement (Reference .1) and to demonstrate conformance with the ECCS acceptance criteria of 10CFR50.46. The objective of the LOCA analysis con-l tained herein is to provide assurance that the most limiting break size.
- break location, and single failure combination has been considered for the plant. The required documentation for demonstrating that these objectives have been satisfied is given in Reference 2. The documentatior. contained in this report is intended to satisfy these requirements.
The general description of the LOCA evaluation codels is contained in Reference 3. Recently approved model changes (Reference 4) are described in
' References 5 and 6. These model changes are employed in the new REFLOOD and CHASTE computer codes which have been used in this analysis. In addition, a model which takes into accouct the effects of drilling alternate flow path holes in the lower tieplate of the fuel bundle and the use of such fuel bundles in a full or partial core loading is described in References 7, 8, and 9. This model was also approved in Reference 4. Also included in the reanalysis are current values for input parameters based on the LOCA analysis reverification program being carried out by GE. The specific changes as applied to Pilgrim are discussed in more detail in later sections of this document. The MAPLHGR values for the non-barrier fuel are applicable to barrier fuel of the same type.
Plants are separated into groups for the purpose of LOCA analysis (Reference 10). Within each plant group there will be a single lead plant analysis which provides the basis for the selection of the most limiting break size yielding the highest peak cladding temperature (PCT). Also, the lead plant analysis provides an expanded documentation base to provide added insight into evaluation of the details of particular phenomena. The remainder of 1-1
NED0-21696
- h. . .
the plants in that group will have non-lead plant analyses referenced to the lead plant analysis. This document contains the non-3ead plant analysis for Pilgrim which is a BWR/3 in the BWR/4 with loop selection logic group of plants and is consistent with the requirements outlined in Raference 2.
I The same models and computer codes are used to evaluate all plants. Changes to these models will cause changes in phenomenological responses that are similar within any given plant group. The difference in input paramenters are not expected to result in significantly different results for the plants within a given group. Emergency core cooling system (ECCS) and geometric differences between plant groups may result in different responses for -
different groups but within any group the responses will be similar. Input changes have been made in the new analysis which are essentially an upgrading of the input paramenters to the computer codes. Thus, the lead plant concept is still valid for this evaluation.
e 1-2
_ _