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| | number = ML20244C821 | | | number = ML20244C821 |
| | issue date = 12/18/1967 | | | issue date = 12/18/1967 |
| | title = Comments on Util Fsar.Dtd June 1967 & Amend 3 Dtd 670714 | | | title = Comments on Util Fsar.Dtd June 1967 & Amend 3 |
| | author name = | | | author name = |
| | author affiliation = COMMERCE, DEPT. OF | | | author affiliation = COMMERCE, DEPT. OF |
Line 12: |
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| | case reference number = FOIA-89-101, FOIA-89-114 | | | case reference number = FOIA-89-101, FOIA-89-114 |
| | document report number = NUDOCS 8904200431 | | | document report number = NUDOCS 8904200431 |
| | | title reference date = Dtd 670714 |
| | package number = ML17055E652 | | | package number = ML17055E652 |
| | document type = GENERAL EXTERNAL TECHNICAL REPORTS, TEXT-SAFETY REPORT | | | document type = GENERAL EXTERNAL TECHNICAL REPORTS, TEXT-SAFETY REPORT |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20205L0541999-04-0101 April 1999 Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis ML17059C5501999-01-31031 January 1999 Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept. 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) ML20198B4991998-05-15015 May 1998 Non-proprietary Replacement Pages for Attachment F to Which Proposed to Change TS 5.5, Storage of Unirradiated & Sf 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 ML18040A3301998-02-28028 February 1998 Rev 0 to Technical Rept 97181-TR-03, EPR Testing of Boat Samples from Core Shroud Vertical Welds V-9 & V-10 at NMP Unit 1. ML17059B9051998-02-28028 February 1998 NMP Unit 1 Boat Samples Analyses Part Iii:Tension Tests, RDD:98:55863-004-000:01 ML17059B9061998-02-28028 February 1998 Non-proprietary Rev 0 to GE-NE-523-B13-01869-113NP, Assessment of Crack Growth Rates Applicable to NMP Unit 1 Vertical Weld Indications. ML17059B9071998-02-28028 February 1998 Rev 0 to Technical Rept 97181-TR-02,Vol 1 to Interpretive Metallurgical Rept on Core Shroud Vertical Weld Boat Samples from NMP Unit 1. ML20217F1201997-09-30030 September 1997 Rev 1 to Boat Sample Analyses at NMP Unit 1 ML17059B6771997-08-11011 August 1997 Rev 0 to Evaluation of Overlay for RWCU Weld 33-FW-22. ML17059B5901997-06-30030 June 1997 Rev 0 to Metallurgical Evaluation of Failed Shroud Tie Rod Lower Spring Contact Wedge Latches, for June 1997 ML17059B4861997-04-30030 April 1997 Non-proprietary Rev 0 to GE-NE-523-B13-01869-043, Assessment of Vertical Weld Cracking on NMP1 Shroud. ML17059B4881997-04-30030 April 1997 Non-proprietary Rev 0 to Gene B13-01739-40, Shroud Repair Anomalies NMP1,RF014. ML17059B5111997-04-30030 April 1997 Non-proprietary Version of Rev 1 to GE-NE-523-B13-01869-043, Assessment of Vertical Weld Cracking on NMP1 Shroud. ML17059B4891997-04-30030 April 1997 Non-proprietary Rev 0 to Gene B13-01739-22, Design Rept for Improved Shroud Repair Lower Support Latches. ML17059B5071997-04-30030 April 1997 Final Rept, Analysis of Nine Mile Point Unit 1 Shroud Weld V9 & Weld V10 Cracking. ML17059B4931997-04-0303 April 1997 Core Shroud Cracking Evaluation. ML17059B2411996-08-13013 August 1996 NMP-1 Core Shroud Repair Mod Summary Rept. ML17059B2441996-08-13013 August 1996 Non Proprietary Version of Suppl 1 NMP-1 Seismic Analysis, Core Shroud Repair Mod. ML17059B2421996-08-13013 August 1996 Suppl 4 NMP-1 Shroud Repair Hardware Stress Analysis. ML17059B2431996-08-0909 August 1996 Rev 4 to Stabilizer Installation. ML18040A1801996-08-0101 August 1996 Rev 5 to Reactor. Drawings Encl ML17059B1221996-04-29029 April 1996 Nonproprietary Core Shroud Repair 270 Degree Tie Rod Assembly Assessment. ML17059B0091995-11-29029 November 1995 NMP Unit 2 Safety Evaluation Summary Rept. ML18040A1671995-09-29029 September 1995 NMP Nine Mile Point Unit 1 Nuclear Power Station Rept of RPV FW & CRD Return Line Nozzle Exams Performed for NUREG-0619...at Culmination of Refueling Outage 13 Which Ended on 950404. ML17059B0181995-01-20020 January 1995 Feedwater Nozzle Analysis. ML18040A1621995-01-16016 January 1995 Rev 2 to 25A5583, Shroud Repair Hardware. ML17059A5781994-12-31031 December 1994 Non-proprietary Version of Final Rept Plant-Specific Charpy Shift Model for Nine Mile Point Unit 1. ML17059A5041994-12-31031 December 1994 Unit 2 Safety Evaluation Summary Rept 1994. ML18040A2971994-10-31031 October 1994 Final Rept Entitled Fracture Mechanics Assessment of Nine Mile Point Unit 1 Shroud H4 Weld. ML18040A2271994-08-19019 August 1994 Nuclear Engineering Rept, Nine Mile Point Unit 1 Shroud Cracking Safety Assessment for GL 94-03. ML17059A3611994-07-0606 July 1994 Emergency Action Level Verification & Validation Rept. ML17059A3531994-06-10010 June 1994 Ny State EAL Upgrade Project Nine Mile Point Unit 1 EAL Generation Package. ML17059A3551994-06-10010 June 1994 Eals. ML17311A0181994-05-13013 May 1994 New York State EAL Upgrade Project Verification & Validation Rept. ML17059A3401994-04-30030 April 1994 Rev 0 to Nine Mile Point Unit 1 Feedwater Nozzle Fatigue Evaluation. ML17059A3411994-04-30030 April 1994 Rev 0 to Nine Mile Point Unit 1 CRD Return Nozzle Fatigue Evaluation. ML17059A0881993-12-31031 December 1993 Safety Evaluation Summary Rept 1993. ML17059A0311993-08-31031 August 1993 Elastic Plastic Fracture Mechanics Assessment...Nine Mile Point,Unit 1:Response to NRC RAI Re GL 92-01 ML18038A7381993-03-17017 March 1993 Upper Shelf Energy Uncertainty Analysis for Nine Mile Point Unit 1 Beltline Welds Final Rept ML18038A7351993-02-22022 February 1993 Final Rept, Elastic-Plastic Fracture Mechanics Assessment of Nine Mile Point Unit 1 Beltline Plates for Service Level C & D Loadings. ML18038A7361993-02-19019 February 1993 Beltline Plate Orientation Determination, Final Rept ML18037A0831992-12-16016 December 1992 Elastic-Plastic Fracture Mechanics Assessment of Nine Mile Point Unit 1 Beltline Plates for Svc Level a & B Loadings. ML18038A7261992-11-19019 November 1992 Technical Response to SE by NRR Related to Proposed Deferment of Torus Mods, Nmp,Nmpns,Unit 1 Docket 50-220 ML17056C1091992-10-29029 October 1992 NMP Unit 2 Safety Evaluation Summary Rept. ML18038A7141992-10-16016 October 1992 Final Rept Entitled, Elastic-Plastic Fracture Mechanics Assessment of Nine Mile Point Unit 1 Beltline Plates for Service Level a & B Loadings. ML18038A5181992-06-12012 June 1992 Response to GL 92-01 for Nine Mile Point Unit 1. ML17056B4781991-12-31031 December 1991 Unit 2 Safety Evaluation Rept 1991. ML18038A3741991-09-0909 September 1991 Rev 1 to Root Cause Rept for Exide UPS 1A,B,C,D & G Trip Event of 910813. Electrical Fault on B Phase Main step-up Transformer Occurred Due to Improper Design.Logic Power Supply for Subj UPS Units to Be Modified 1999-04-01
[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
[Table view] |
Text
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i Comments on
, Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation l ,
Final Safety Analysis Report, Dated June 1967
- and Amendment #3 Dated July 14, 1967 .
i' Prepared by 1
Air Rer wrces Environmental Laboratory Environmental Science Services Administration December 18, 1967 As was the case with the Preliminary Hazards Summary Report, the meteorological analysis in the Final Report is very comprehensive and is particularly useful in estimating atmospheric diffusion in a -
wide variety of realistic meteorological conditions. We agree that the addition of one year of meteorological data since the PHSR shows
? no evidence of any important differences.
( The Turbulence Classes depicted in figures A-4,1 through A-4.7 are
{y similar to the Pasquill Types of atmospheric diffusion rates. For
] , example, Turbulence Class I is similar to Pasquill Type A (strong lapse) and Turbulence Class IV to Pasquill Type F (moderate inversion).
} These are the limiting categories for both classifications. A
' realistic attempt has been made to describe, quantitatively, the
- changes in dispersion parameters such as occur with flow f rom cold .
1 water to hot land (fig.. A-4.7) and flow initially over land for 2 km, j ,
then over water for 21 km, and back over land again (fig. A-4,5) .
i The annual (actually a two-year average) atmospheric dispersion developed f rom on-site meteorological measurements and shown in figures 11-7 and 11-8 are realistic and have been spot-checked for accuracy. The highest long-term off-site dose in these computations j is about 5 x 10"8 sec/m-3 at a distance of 2 km at the northeast
! corner of the site assuming tric effluent is released from a 350-f t I stack. There is a slight discrepancy in figures 11-7 and -8 in that the 10 isopleth is inside the southern site boundary in the first figure and outside in the other.
As noted in Table A-5, credit has been taken for effluent rise above li the stack. With a stack effluent velocity of '55 f t/see and a 30 C 3
temperature excess of stack gas over ambient air, it is obvious that a significant rise will take place, especially at lower wind speeds.
.As reported by Moses [J3 there are many plume rise expressions
(
I ,
9904200431 FOIA 890413 4 PDR PDR i WETTERH89-101
ze >
i .
.c
..d -
,.r.
(
i p 'available in the literature, but he finds it extremely ' difficult to recommend any technique with enthusiasm. He concludes that for large stacks with appreciable buoyancy, such as,the stack under consideration, the Holland equatLon with a correction factor of 3
- , gives the best results. Assuming the variables as listed in Table A-5
- and the corrected Holland equation, an effective stack height of 192 m results for a wind speed of 3 5 m/sec. This compares well with i I the 205 m computed by an entirely different technique in the report.
Our assessment of the maximum downwind ground concentration f rom an i' 3 accidental release of radioactive effluent through the stack would be I the pseudo-fumigation condition described by Van der Hoven [2] in his '
L, figure 3. A reasonable set of parameters in the case might be as i' follows: u = 5 m/sec, effective stack height and depth of mixed layer
= 150 m, oy at 2 km = 100 m (Pasquill Type E). Using the fumigation 1 equation, the resulting ground concentration is 5 x 10-6 sec/m3 If this phenomenon was to happen at 1 km downwind the concentration would be about 1 x 10-5 sec/m3 because of a reduction of cy to 50 m. These values should be considered as an upper limit to possible, short-term -
)
(2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) downwind ground concentrations resulting from an accidental elevated release. These numbers are about a factor of eight higher than listed in Table E-20 of the report, which was detenmined ;
directly f rom' the unidirectional, centerline' concentrations depicted
[4 ( in figures A-4.1 to A-4.7.
References , -
[1] Moses, H., G. H. Strom, and J. E. Carson,1964: Effects of l
meteorological and engineering factors'in stack plume rise.
Nuc. Safety, 6(1), pp. 1-19.
f d [2] Van der Hoven, I.,1967: Atmospheric transport and diffusion at 1 coastal sites. Nuc. Safety, 8(5), pp. 490 499. ,
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