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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML17059A3611994-07-0606 July 1994 Emergency Action Level Verification & Validation Rept. ML17311A0181994-05-13013 May 1994 New York State EAL Upgrade Project Verification & Validation Rept. ML20196D3011988-10-31031 October 1988 Reactor Vessel Matl Surveillance Program for Indian Point Unit 2 Analysis of Capsule V ML20155H2541988-09-30030 September 1988 Rev 2 to Indian Point Unit 2 (NRC Bulletin 88-008 Thermal Stresses in Piping Connected to RCS) Indentification of Unisolable Piping & Determination of Insp Locations ML20153F9161988-04-28028 April 1988 Changes,Tests & Experiments - 1986 ML20151T4681988-01-31031 January 1988 Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness ML20151U9971986-01-31031 January 1986 Status Rept:Indian Point Special Proceeding Decision CLI-85-06 ML20211G4111985-07-0303 July 1985 Effective Max Beta Energy & Determination of RO-2,2A Response Factors ML20094E0071984-07-26026 July 1984 Addl Info Obtained from Ny State on New York Pirg Petition Which Suppls FEMA Rept to NRC ML20094E0021984-07-26026 July 1984 Evaluation of Addl Issues Raised by NRC Re New York Pirg Petition to Suspend Operation of Indian Point,Units 2 & 3 ML20024B3061983-04-30030 April 1983 Determining Portion of Regulatory Burden on Indian Point 3 Capital & O&M Expenditures 1976 - 1986:10-Yr Cost Projection Also Included. ML20065J6771982-09-14014 September 1982 Testing & Repair of Siren Portion of Alert & Notification Sys for Indian Point Nuclear Power Generating Plant ML1003215451981-10-31031 October 1981 Evaluation of Indian Point Station Unit No 2. ML0934307941981-10-31031 October 1981 Evaluation of Indian Point 3 Nuclear Power Plant. ML20063G0531981-10-26026 October 1981 Evaluation of Prompt Alerting Sys for Indian Point Nuclear Power Station. NUREG/CR-2655, Evaluation of Prompt Notification Sys... & NUREG/CR-2654, Procedures for Analyzing Effectiveness for Alerting Public Encl ML20003C1221981-01-31031 January 1981 Feasibility Study for Mod of Containment Cooling Sys. ML19340E7091980-11-30030 November 1980 Technical Evaluation of the Susceptibility of Safety- Related Sys to Flooding Caused by Failure of Noncategory I Sys for Indian Point 2. ML1002718271980-09-30030 September 1980 Thermal - Radiation Matls Application Data. One Oversize Drawing Encl.Aperture Card Is Available in PDR ML19331B8381980-08-31031 August 1980 Compliance Study in Response to NRC 800211 Confirmatory Order Re Ucs Petition to Suspend Operation.Demonstrates Methods by Which Safety Rules & Regulations Are Implemented. Financial & Reporting Requirements Not Addressed ML19305A7421979-09-28028 September 1979 Safety Evaluation Re Changes to Tech Specs for Mgt Titles ML1009802731979-01-31031 January 1979 Support Sys Redesign for Piping Runs on North Half of Containment. ML1002002351978-12-31031 December 1978 Evaluation of ECCS Per 10CFR50.46 & App K of 10CFR50. Describes Major Reactor Coolant Sys Pipe Ruptures on Westinghouse Model ML1009802761978-04-30030 April 1978 Rept 03-00101,Revision 0,Piping Sys Hydraulic Shock Suppressor Removal Study, & Rept 03-00102,Revision 0, Piping Sys Hydraulic Shock Suppressor Analysis for Removal. ML20079N3161977-07-31031 July 1977 Near-Field Effects of Once-Through Cooling Sys Operation on Hudson River Biota ML1002002391977-06-30030 June 1977 Reactor Vessel Material Surveillance Program,Analysis of Capsule T Submitted in Support of Amend 1 to Application for Amend to License DPR-26.Vessel Matl Surveillance Capsule Was Tested & Evaluated ML20084B1221973-03-30030 March 1973 Review of Replies to AEC Questions by Con Ed on Indian Point Unit 2 Safety & Relief Valve Installation Reanalysis ML20084B2751972-10-11011 October 1972 Investigation & Consequences of Steam Generator Nozzle Debris Plug Assembly Being Inadvertently Left In-Place During Operation of Rcs 1994-07-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H8501999-10-14014 October 1999 Safety Evaluation Supporting Amend 197 to License DPR-64 ML20206U2551999-02-0909 February 1999 Safety Evaluation Supporting Amend 187 to License DPR-64 ML20236Y1571998-08-0303 August 1998 Part 21 Rept Re ASTM A351,GR. CF8 Matl at Indian Point Being Out of Specifications in Molybdenum & Chromium.Cause & Corrective Actions Are Not Stated ML20236V4281998-07-13013 July 1998 Safety Evaluation of TRs WCAP-14333P & WCAP-14334NP, PRA of RPS & ESFAS Test Times & Completion Times. Repts Acceptable ML20236T5511998-06-24024 June 1998 Consolidated Edison Co of Ny,Indian Point Unit 2,Drill Scenario Number 1998C ML20248B2371998-03-31031 March 1998 Revised Monthly Operating Rept for March 1998 for Indian Point Station Unit 2 ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML1005008001997-02-28028 February 1997 Conditional Extension of Rod Misalignment TS for Indian Point 3. ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20096E5101995-12-31031 December 1995 Resubmitted Rev 13 to QA Program ML17059A3611994-07-0606 July 1994 Emergency Action Level Verification & Validation Rept. ML17311A0181994-05-13013 May 1994 New York State EAL Upgrade Project Verification & Validation Rept. ML20029C7801994-03-31031 March 1994 Monthly Operating Rept for Mar 1994 for Indian Point Unit 1. W/940415 Ltr ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20062J2281993-07-23023 July 1993 Consolidated Edison Co of Ny Indian Point Unit 2,Drill Scenario 1993 ML20118A2681992-12-31031 December 1992 Consolidated Edison Co of Ny Indian Point,Unit 2 Exercise Scenario,1992 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20096H2301992-05-21021 May 1992 Special Rept:On 920504,south Side Lower Electrical Tunnel Detection Sys 8 Taken Out of Svc for Mod to Reposition Detection Sys Run of Conduit.Detection Sys Declared Operable on 920520 After Mod Completed & Sys Retested ML20079F9181991-05-31031 May 1991 Structural Evaluation of Indian Point,Units 2 & 3 Pressurizer Surge Lines,Considering Effects of Thermal Stratification ML20059E9461990-08-31031 August 1990 Nonproprietary Rev 2 to Indian Point 2 Tube Fatigue Reevaluation ML20059G2011990-07-31031 July 1990 Final Rept on Steam Generator Insp, Repair & Restoration Efforts During 1990 Midcycle Insp ML20058K4151990-06-30030 June 1990 Steam Generator Insp,Repair & Restoration Program Presentation to Nrc ML20058K4121990-06-30030 June 1990 Status Rept,Indian Point Unit 2 Mid-Cycle Steam Generator Insp Presentation to Nrc ML20043A4891990-05-30030 May 1990 Nonproprietary Indian Point Unit 2 Steam Generator Insp, Repair & Restoration Program. ML20042F1441989-12-31031 December 1989 New York Power Authority Annual Rept for 1989. W/900430 Ltr ML19332B9371989-11-30030 November 1989 Nonproprietary Info Presented to NRC Re Indian Point Unit 2 Steam Generator Secondary Side Loose Objects. ML19332D6661989-10-31031 October 1989 Nonproprietary Rev 2 to Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage. ML20247J8161989-07-31031 July 1989 Safety Evaluation for UHS Temp Increase to 95 F at Indian Point Unit 3 ML20248B3171989-06-30030 June 1989 Rev 1 to Nonproprietary WCAP-12294, Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept,Spring 1989 Outage ML20248D3631989-06-30030 June 1989 Rev 1,to Indian Point Unit 3 Reactor Vessel Fluence & Ref Temp PTS Evaluations ML20247N5331989-05-31031 May 1989 Nonproprietary Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage ML20247J8071989-05-31031 May 1989 Containment Margin Improvement Analysis for Indian Point Unit 3 ML20247G5171989-04-30030 April 1989 Monthly Maint Category I Rept Pages from Monthly Operating Rept for Apr 1989 for Indian Point ML20244C3311989-04-10010 April 1989 Safety Evaluation Supporting Amend 137 to License DPR-26 ML20248F4211989-03-31031 March 1989 NSSS Stretch Rating-3,083.4 Mwt Licensing Rept ML20235V5931989-03-0202 March 1989 Special Rept:During Cycle 6/7 Refueling Outage Scheduled from Feb-May 1989,openings Will Be Made in Plant Penetration Fire Barriers in Order to Install Various Mods. Fire Watches Posted & Fire Detection Tests Completed ML20248F3001988-12-31031 December 1988 10CFR50.59(b) Rept of Changes,Tests & Experiments Completed in 1988 ML20246E2711988-12-31031 December 1988 Con Edison 1988 Annual Rept ML20196D3011988-10-31031 October 1988 Reactor Vessel Matl Surveillance Program for Indian Point Unit 2 Analysis of Capsule V ML20155H2541988-09-30030 September 1988 Rev 2 to Indian Point Unit 2 (NRC Bulletin 88-008 Thermal Stresses in Piping Connected to RCS) Indentification of Unisolable Piping & Determination of Insp Locations ML20154M5661988-08-31031 August 1988 Monthly Operating Rept for Aug 1988 for Indian Point Station Unit 2 ML20154M5691988-07-31031 July 1988 Revised Page to Monthly Operating Rept for Jul 1988 for Indian Point Station Unit 2 ML20151N7881988-07-31031 July 1988 Rev 1 to Charpy Toughness & Brittle Transition Temp Characterization of HAZ High Hardness Zone of Indian Point Unit 2 Steam Generator Girth Weld by Gleeble Weld Thermal Cycle Simulation ML20006B4741988-05-31031 May 1988 Nonproprietary Indian Point Unit 2 Evaluation for Tube Vibration Induced Fatigue. ML20151N7821988-05-31031 May 1988 Fracture Sensitivity Study of Girth Weld 6 Repaired Configuration,Indian Point Unit 2 ML20153F9161988-04-28028 April 1988 Changes,Tests & Experiments - 1986 ML20151T4681988-01-31031 January 1988 Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness 1999-02-09
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. TESTING AND REPAIR of the SIREN PORTION OF THE ALERT AND NOTIFICATION SYSTEM for the INDIAN POINT NUCLEAR POWER GENERATING PLANT September 14, 1982 l
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I"8210060148 820915 l PDR ADOCK 05000247
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on March 3, 1982, a drill was held to test the Indian Point emergency preparedness procedures which had been established by the Power Authority and Consolidated Edison in conjunction with Various County and state organizations. The cirens were tested as part of this drill.
The siren system covers parts of four Counties, namely, Westchester, Rockland, Putnam and Orange, with 43, 24, 9 and 12 sirens in each of those Counties, respectively. Operation of the sirens is by radio control based on transmission of coded radio signals in each of the four Counties. The Westchester and Orange County installations operate on a high-band, and the Rockland and Putnam County systems operate on a low band. The high band systems .for Westchester *and Orange Counties are a digital system which allows both the growl signal and the alert signal for each individual siren to be transmitted from the County EOC. The growl signal from the EOC operates the receiver, decoder and control equipment at a designated siren to l allow the siren to op, erat.e for about five seconds and is i intended for test purposes only. The actual alert signal is !
approximately three minutes in duration. In Orange County the I control equipment is located in the EOC in Goshen, and in f Westchester, the control equipment is located in the County l Parkway Police Headquarters in Hawthorne. The equipment for the other two Counties, Putnam, and Rockland is a low-band system l and is also operated from the County EOC's.
The March 3rd exercise indicated that some of the sirens had not been heard by residents living near those sirens. The utilities jointly conducted a complete re-test on the sirens. By -
completion of the testing program, all of the inoperative sirens had been repaired and were functional. The corrections were i accomplished prior to June 1, 1982. I The re-test activity was organized by Power Authority and Con Edison. The tests included: circuit parameters such as received signal strength, receiver sensitivity and circuit voltages; they also included functional tests of controls, siren rotation, growl and alert functions; an( components such as fuses, counters and relays.
! Based on a survey conducted by the utilities, of all the 88 sirens tested on March 3rd, 1982 sixty eight were reported to have been heard. Nine were reported as not having been heard; these have been repaired and the remaining were in remote park locations. Of these eleven remote sirens only six required corrective action. Appendix 'A' provides details for the repairs to this total of 15 sirens. I i
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.The approach for this program, was to correct any observed questionable condation in any siren even though it was not confirmed that the condition could contribute to a malfunction of the siren. These actions included such conditions as crimped
- wire, weather tight fittings and adjustment of thermal relays.
Also as a result of the complete system re-test the analysis shows 15 additional sirens as having had corrections performed on parts that could have precluded operation. Appendix 'B' details the actions taken on these 15 sirens.
It is expected that periodic testing will be conducted in accordance with recommended guidance provided in NUREG 0654 Rev.
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- APPENDZX 'A' and APPENDIX 'B' NOTE: For descriptive purposes the siren system is subdivided into subsystems as follows:
- 1. The Communications subsystem consisting of radio transmitters and receivers, encoders and decoders, antennas and antenna cables.
- 2. The siren subsystem consisting of the siren itself, siren / motor couplings, motor, motor circuits, and motor control devices.
- 3. The Power subsystem including transformers, service entrances and interconnecting power lines.
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APPENDIX A .
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TEST DETAILS .
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-1 i. W C ')hliUN ICATIONS SIREN POWER .
- 0. SUBSTYSTEM SUBSYSTEM SUBSYSTEM OTHER
-2 l Returned Rcvr- l l l.
I defective RG-8u 1 I I .
I replaced 1 l l l 1 1 I
-27
-4 6
- l l Counter works on l l l l growl only - 1 I l l Repaired l l 1 I i 1
-56 l Returned revr. l l l l RG-8/u replaced l l . l l Defective l l l 1 1 I I
-58 l l Replaced siren I l l l l 1
-60 l Defective RG-8/u 1 l l l replaced. l l l l , I I I
-61 l Loose antenna l l I l connector. Cable l I l l and Connectors l l l l Replaced. I I l l l 1
- 7 8
- lI I I I I I I I l Starting capacitors l
-84 l l '
l l replaced. l I I I 1 1
- Denotes sirens that functioned properly during retest subsequ,ent to March 3
l APPENDIX A
SIREN COMMUNICATIONS SIREN POWER NO. SUBSTYSTEM SUBSYSTEM SUBSYSTEM OTHER I I I l
-3 l Replaced Revr./ l l l l Decoder Boards l l l l RG-8/u and l l l l Connectors. l l l 1 I I I
-7 l Rewired phono. l Blown 100 A Fuse l l l conn. on Revr Board l l l l 1 1 I
-9 l Defective RG 8/u l l l l Antenna replaced.. l l .- l l 1 1 I
-10 l Defective antenna l l l l connector repaired.l l l l l l 1
-50 l Nrong antenna l l l Corrected I replaced. I ! I bulkhead fitting l l l l problem
-16 Open starter motor winding / siren replaced
APPENDIX B ,
TEST DETAILS .
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SIREN COMMUNICATIONS SIREN POWER NO. SUBSTYSTEM SUBSYSTEM SUBSYSTEM OTHER I I I l- -
-5 l Inadequate signal l l AC Line crimped l l level, installed l l in Service Box l l new Yagi Antenna. l l Transformer 900 ft. l l Replace defective l I from siren, excessive l l Revr. Board & l l voltage drop, trans- l l PG-58/u. l l former relocated. l l l l l
-12 1 Defective RG-8/u l Thermal relay l l I replaced. l tripped.Improperlyl l l l set, reset to 100%l .
l I l l 1
-21 l No center pin on l l ' l l antenna. Defective l l l l RE-8/u replaced. l l l l 1 I i
-24 l l Replaced start l l l l capacitor relay l l 1 I l l
-25 l No received signal l Siren delective-1 l l l l open winding, one l l l l shorted. Thermal l l l l relay reset to l l l l 100%. l l l l l l
! -26 l No center pin on l l l l antenna, antenna l l l l repaired. l l l l l l 1
-30 1 Decoder inoperative l Thermal relay l l l repaired I adjusted to 100% l l 1 l l 1 i
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APPENDIX B TEST DETAILS , .'.
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SIREN COMMUNICATIONS SIREN POWER .
NO. SUBSTYSTEM SUBSYSTEM SUBSYSTEM OTHER ~~
I I I I
-32 l l Thermal relay I l I which tripped l l l l l breaker, at 25% l l l l was reset to 36% l l 1 I I I
-35 1 Defective antenna l Thermal relay l l l
l pin released. I reset to 36%. l l l l l l 1 I i
-39 I Revr. misaligned l l l l and repaired. De- l l l l fective RG-58/u & l Repaired loose l ? I l connectors replacedI splice to motor i l l incorrect antenna l l l l with MWH-150.
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-40 l Defective RG-58/u l l l l replaced. l I l I I I i
-41 l Defective RG-58/u l l l l replaced. l l 1 I . I I I
-49 I l Run capacitors l I l l not connected. I l l I I l
-65 I Defective RG-8/u I I l l replaced. Defcetivel I I l RG-58/u. replaced. l l l l l l 1
-77 l Re-soldered RF plugl l l l on PC Board. Wrong l l l l Antenna replaced. l l 1 I I I I NOTES: 1. After 4/20/82, the fuses were changed routinely to Slow-blow during the retest and maintenance program.
- 2. All thermal relays set to 100% on single phase systems only.
- 3. Af ter 4/5/82 and performance of the initial growl test, al1 antenna cables were routinely replaced.
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