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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML17059B5131997-04-30030 April 1997 Non-proprietary Version of Rev 1 to Shroud Repair Anomalies NMP Unit 1,RF014. ML17059B5121997-04-30030 April 1997 Non-proprietary Version of Rev 1 to Design Rept for Improved Shroud Repair Lower Support Latches. ML18040A1551995-02-24024 February 1995 Suppl 1 to GE-NE-B13-01739-04, Nine Mile Unit 1 Shroud. ML17059A5221994-11-0404 November 1994 Structural Evaluation & Justification of Nine Mile Point 1 Core Shroud for Continued Operation. ML20077M5181994-09-13013 September 1994 Fatigue Evaluation Power Uprate Operating Conditions, Rev 1 ML18038A4011988-01-29029 January 1988 Mark I Torus Shell & Vent Sys Thickness Requirements for Nine Mile Point Unit 1 Nuclear Station. Viewgraphs & Agenda Encl ML18038A7581987-09-30030 September 1987 Nonproprietary Suppl 1 to Nine Mile Point Unit 1 Safer/ CORECOOL/GESTR-LOCA,LOCA Accident Analysis. ML20237D8291987-06-30030 June 1987 Nonproprietary Nine Mile Point Unit 1 SAFER/CORECOOL/GESTR- LOCA LOCA Accident Analysis ML17053A7581979-06-28028 June 1979 Extended Load Line Limit Analysis,License Amend Submittal (Cycle 6). ML20062D3961977-06-24024 June 1977 RWR-1tm Radwaste Vol Reduction Sys. Describes RWR-1tm Vol Reduction Sys for Appl to Radioactive Waste Produced at Nuc Elec Generating Station Utilizing Fluidized Bed to Calcine Liquids & Incinerate Solids ML17053A8581969-04-29029 April 1969 Addendum I to Test Rept of Limitorque Valve Actuator in Nuclear Reactor Containment Environ,Prepared by Philadelpha Gear Corp.Forwarding Ltr Encl ML17053A8571968-11-30030 November 1968 Rept Re Limitorque Valve Operator Test Under Simulated Reactor Containment post-accident Steam & Chemical.Prepared for Philadelphia Gear Corp 1997-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With ML20216J9251999-09-30030 September 1999 Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With ML20209D0291999-07-0202 July 1999 Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709 ML20210B9081999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With ML20209F8811999-06-0808 June 1999 Rev 1 to NMP Unit 1 COLR for Cycle 14 ML20207G2261999-06-0707 June 1999 SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1 ML20196E2111999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Nmp,Unit 1.With ML20207B0241999-05-18018 May 1999 Safety Evaluation of Topical Rept TR-107285, BWR Vessel & Intervals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996.Rept Acceptable ML20206U5351999-05-17017 May 1999 SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2 ML20196L2301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Nmp,Unit 1.With ML20205L0541999-04-0101 April 1999 Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis ML20205S5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for NMP Unit 1.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207G2671999-03-0101 March 1999 Special Rept:On 990315,Nine Mile Point,Unit 1 Declared Number 12 Containment Hydrogen Monitoring Sys Inoperable. Caused by Degraded Encapsulated Reed Switch within Flow Switch FS-201.2-1495.Technicians Replaced Flow Switch ML20204C9971999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Nine Mile Point,Unit 1.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML17059C5501999-01-31031 January 1999 Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept. ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20199K9331998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20210R8441998-12-31031 December 1998 1998 Annual Rept for Energy East ML20206P2391998-12-31031 December 1998 Special Rept:On 981222,operators Removed non-TS Channel 12 Drywell Pressure Recorder & Associated TS Pressure Indicator from Svc.Caused by Intermittent Measuring Cable Connection in non-TS Recorder Circuitry.Replaced Cable ML20206P2421998-12-30030 December 1998 Special Rept:On 981219,number 12 Hydrogen Monitoring Sys (Hms) Was Declared Inoperable When Operators Closed Valve 201.2-601.Caused by Indeterminate Failure of Valve 201.2-71. Supplemental Rept Will Be Submitted After Valve Is Repaired ML20198M3571998-12-23023 December 1998 Special Rept:On 981210,operators Declared Number 11 Inoperable,Due to Failure of CR Chart Recorder.Caused by Inverter Board in Power Supply Circuitry of Recorder Due to Component Aging.Maint Personnel Replaced Failed Inverter ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With ML20155E2001998-11-0202 November 1998 Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation ML20195J4141998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20154D8401998-10-0505 October 1998 Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs ML20154P1821998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20153B2001998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Nmpns,Unit 1.With ML20237C6351998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20236T5911998-07-20020 July 1998 LER 98-S01-00:on 980618,security Force Member Left Nine Mile Point,Unit 2 Vehicle Gate Unattended Without Ensuring,Gate Alarm Had Been Reactivated.Caused by Inadequate Work Practice.Vehicle Gate Alarm Was Activated ML18040A3491998-07-0202 July 1998 LER 98-017-00:on 980602,control Room Ventilation Sys Was Declared Inoperable.Caused by Original Design Deficiency. Mod Designed,Tested & Implemented Prior to Startup from RF06 to Correct Design deficiency.W/980702 Ltr ML20236Q1701998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Nine Mile Point Nuclear Station,Unit 1 ML17059C1011998-06-24024 June 1998 LER 98-014-00:on 980525,noted Differences Between Actual Valve Weights & Weights Shown on Engineering Drawings.Caused by Vendor Failing to Provide Accurate Valve Weights.Revised Valve Drawings & Associated Calculation,Per 10CFR21 ML20151P1751998-06-16016 June 1998 Rev 0 to SIR-98-067, Evaluation of NMP Unit 2 Feedwater Nozzle-to-Safe End Weld Butter Indication (Weld 2RPV-KB20, N4D) ML18040A3451998-06-0404 June 1998 LER 98-004-01:on 980302,TS Required LSFT of Level 8 Trip of Main Turbine Was Missed.Caused by Knowledge Deficiency of EHC Sys.Revised Applicable LSFT Procedures Prior to Refueling Outage 6.W/980604 Ltr ML20249B4971998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20198B4991998-05-15015 May 1998 Non-proprietary Replacement Pages for Attachment F to Which Proposed to Change TS 5.5, Storage of Unirradiated & Sf ML20247R1141998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20217B0621998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Nine Mile Point Nuclear Station,Unit 1 ML17059C1681998-03-19019 March 1998 Revised Niagara Mohawk Powerchoice Settlement Document for NMPC PSC Case Numbers 94-E-0098 & 94-E-0099, Vols 1 & 2 ML20217F4341998-03-19019 March 1998 SER Related to Proposed Restructuring New York State Electric & Gas Corp,Nine Mile Point Nuclear Station,Unit 2 ML17059B9051998-02-28028 February 1998 NMP Unit 1 Boat Samples Analyses Part Iii:Tension Tests, RDD:98:55863-004-000:01 1999-09-30
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NEDO-31446-1 Supplement 1 Class I September 1987 SUPPLEMENT 1 TO NINE MILE POINT UNIT 1 SAFER/CORECOOL/GESTR-LOCA LOSS-OF-COOLANT ACCIDENT ANALYSIS P. Wei W. A. Zarbis Approved:
J S. Charnley, Manage uel Licensing Approved:
L. D. Noble, Manager Reload Nuclear Engineering-1 NUCLEAR ENERGY BUSINESS OPERATIONS ~ GENERAL ELECTRIC COMPANY SAN JOSE. CALIFORNIA 95125 GENERAL ELECTRIC 8712290226 87i2i8 PDR ADOCK 05000220
.P ; PDR
~E NEDO-31446-1 CLASS I'ISCLAIMER OF RESPONSIBILITY This document was prepared by or for the General Electric Company.
Neither the General Electric Company nor any of the contributors to this document:
A. Makes any warranty or representation, express or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of any information disclosed in this docu-ment may not infringe privately omed rights; or B. Assumes any responsibility for liability or damage of any kind which may result from the use of any information disclosed in this document.
0-NEDO-31446-1 CLASS I CONTENTS
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- l. INTRODUCTION AND
SUMMARY
- 2. REFEREN CE APPENDICES A. MAPLHGR Uersus Average Planar Exposure A-1 B. Bundle Description B-1
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NEDO-31446-1 CLASS I
- l. INTRODUCTION AND
SUMMARY
This report contains the maximum average planar linear heat generation rate (MAPLHGR) values for the GE fuel design (GEBXSEB bundle type BD321B) to be loaded into Nine Mile Point Nuclear Generating Station Unit 1.
Appendix A contains summaries of MAPLHGR versus exposure for the BD321B fuel bundle. These MAPLHGRs are determined based on the analyses detailed in Reference l.
Appendix B contains a description of the BD321B fuel type.
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NEDO-31446-1 CLASS I
- 2. REFERENCE
- 1. NEDC-31446P, "Nine Mile Point Unit One SAFER/CORECOOL/GESTR-LOCA Loss-of-Coolant Accident Analysis," June 1987.
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NEDO-31446-1 CLASS I APPENDIX A MAPLHGR* VERSUS AVERAGE PLANAR EXPOSURE Table A-1 MAPLHGRs FOR BUNDLE TYPE BD321B**
FIVE-LOOP OPERATION Plant: NMP-1 Fuel T e: BD321B Average Planar Exposure MAPLHGR*** PCT Local (GWd/MTU) (kW/ft) ('F) Oxidation Fraction 0.22 10.40 2023 <0.150 10.51 2032 <0.150 5.5 11.05 2089 <0.150 11.0 11.59 2154 <0.150 14.0 11.84 2176 <0.150 15.0 11.83 2184 <0.150 16.5 11.40 2118 <0.150 22.0 10.90 2087 0.165 27.5 10.80 2114 0.169 30.0 10.76 2109 0.167 33.0 10.49 2082 0.154 38.5 9.97 2040 0.134 44.0 9.40 1941 0.095
- 50. 0 8.74 1879 0.075
<<One set of MAPLHGRs is conservatively applied to all lattices in the BD321B Bundle.
- <<Lattice definitions appear in Appendix B.
<<<<<<Limited by ECCS considerations for 15 < E < 30 GWd/MTU exposure range.
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NEDO-31446-1 CLASS I Table A-2 MAPLHGR MULTIPLIERS FOR BUNDLE TYPE BD321B*
Four-Loo 0 eration Idle Loo Condition Exposure Ran e MAPLHGR Multi lier Unisolated All Exposures Isolated E < 15 or E > 30 GWd/MTU Isolated 15 < E < 30 GWd/MTU Three-Loo 0 eration Idle Loo Condition Ex osure Ran e MAPLHGR Multi lier Unisolated All Exposures Isolated E < 15 or E > 30 GWd/MTU Isolated 15 < E < 30 GWd/MTV
- Based on the discussion in Reference 1, no MAPLHGR multiplier is required for operation in the Extended Load Line Limit Analysis (ELLLA) region.
A-2
NEDO"31446-1 CLASS I, APPENDIX B BUNDLE DESCRIPTION Table B-l, FUEL BUNDLE INFORMATION FOR BD321B Weight Exposure at Enrichment of U Maximum Max. k-inf.
(Wt. X U-235) ~(k ) k-inf. (GWd/MTU)
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NEDO-31446-1 CLASS I Figure B-l. Enrichment Distribution for the BD321B Fuel Bundle B-2
NEDO-13446-1 CLASS I Figure B-2. Gadolinium Distribution for the BD321B Fuel Bundle B-3
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