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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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Text
PHILADELPHIA GEAR CORPORATION KING OF, PRUSSIA, PENNA. 19406 LIMITORQUE VALVE CONTROL
'ADDENDUM NUMBER NI TEST OF LIMITORQUE VALVE,OPERATOR TO MEET GENERAL REQUIREMENTS OF AN, ELECTRIC VALVE ACTUATOR IN NUCLEAR REACTOR CONTAINMENT ENVIRONMENT REPORT OF JANUARY 2, 1969 A. SHOCK Sc VIBRATION TEST B. TEST OF LIMIT SWITCH NITH MATERIAL CHANGE APRIL 29, 1969
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A. SHOCK AND VIBRATION TEST=
', Y The L'imitorque Operator size SMB-0 with a 15 foot pound, 3 phase, 60 cycle, 440 volt motor, nameplate order 5338164 was shipped to Lockheed Electronics Company environmental labratory and tested on March 10, 1969.
Test Procedure The. test specimen was secured to a vibration machine and subjected to- five cycles of vibration in both the vertical axis and the horizontal axis. Each cycle consisted of two minutes of vibration at a frequency of thirty-five (35) cps and an acceleration level of three (3) "G's", followed by one minute of no vibration.
Vibration scans were also conducted in both axis of vibration between five to thirty-five cps to determine the presence of any
'I resonances.
Visual inspections for evidence of any external physical damage were conducted throughout the vibration testing. The vibration test was completed with no visual evidence of any external physi-cal damage. No resonances were detected du'ring the vibration scans.
The above is included in Lockheed Electronics Company Test Report
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Page April 29, 1969 The previous shock and vibration test of a Limitorque Operator was extended to '1 6 and 25 cps. The above test extended the level to 3 G's at 35 cps.
B. 'EST OF GEARED LIMIT SNITCH NITH MATERIAL CHANGE:
On, the previous test of a Limitorque Operator as submitted January 2, 1969, a failure occurred due to the action of the chemical spray on the material of the gear frame of the geared limit, switch. Thi,s caused the premature, fa ilure of the geared limit switch. The gear frame material has been changed as prev-iously recommended and an additional test of this revised geared limit switch ha's been conducted at The Franklin Institute Research Labratories in Philadelphia, Pennsylvania on April 9 through April 16, 1969. The geared limit switch was placed in the same environmental chamber as the previous test and was used in conjunction with starting and stopping an electric motor also in the test chamber. The environment consisted of a seven day test wherein the geared limit switch was exposed to high steam pres'sure, temperature and chemical environment similar to the previous test.
The new geared limit switch successfully completed the test with no sign of wear or deterioration due to the steam pressure,
0' Page 29, 1969 temperature or chemical environment. The test was completely satisfactory in every respect.
CONCLUSION:
The material change of the geared limit switch has been noted and will be included on all Limitorque Operators subjected to this environmental condition when specified.
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This information is submitted as an addendum to our Test Report dated January 2, l969.
Very truly you s, Edward F. Lawson Sales Manager Limitorque Division EFL/s 1s
