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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20216C4581998-02-27027 February 1998
Response to NRC Demand for Info (NRC OI Rept 1-95-050)
ML20203L1931998-02-25025 February 1998
Duke Energy Corp,Duke Engineering & Svcs,Inc,Yankee Atomic Small Break LOCA Technical Review Rept
ML20203L2451998-02-23023 February 1998
Assessment Rept of Engineering & Technical Work Process Utilized at De&S Bolton Ofc
ML20203L1621998-02-18018 February 1998
Rept of Root Cause Assessment Review
ML20203L2691998-02-16016 February 1998
Duke Engineering & Svcs Assessment Process Review Rept
ML20056H1741993-06-10010 June 1993
Preliminary Assessment of Potential Human Exposures to Routine Tritium Emissions from Yankee Atomic Electric Co Nuclear Power Facility Located Near Rowe,Ma
ML20062H1981990-11-30030 November 1990
Plant Specific Fast Neutron Exposure Evaluations for First 20 Operating Fuel Cycles of Yankee Rowe Reactor
ML20055E1591990-07-31031 July 1990
Reactor Pressure Vessel Evaluation Rept
ML20055G6801990-07-31031 July 1990
Yankee Plant Small Break LOCA Analysis
ML20055J3221990-07-25025 July 1990
Decommissioning Funding Assurance Rept & Certification
ML20155G6101988-09-30030 September 1988
App a Rev 1 to Incore Detection Sys Analysis
ML20155G6661988-06-0303 June 1988
Reanalysis of 1984 Eddy Current Data for Steam Generators 3 & 4, Supplemental Rept
ML20151H9581988-04-30030 April 1988
CASMO-3G Validation
ML20148Q9031988-03-31031 March 1988
Incore Detection Sys Analysis
ML20151A3711988-03-31031 March 1988
Cask Drop Analysis Yankee Nuclear Power Station Spent Fuel Pool
ML20148G5431988-01-15015 January 1988
Nonproprietary Mods to Critical Flow Model in RELAP5YA
ML20234F0851987-12-30030 December 1987
Revised Summary Evaluation of Reactor Pressure Vessel/ Neutron Shield Tank Seismic Response & Amplified Response Spectra Generation
ML20147B3151987-11-30030 November 1987
Rev to Yankee Atomic Electric Co Reflood Heat Transfer Correlation
ML20149L5461987-10-31031 October 1987
Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45
ML20235P2761987-10-0101 October 1987
Reg Guide 1.97 Nuclear Instrumentation Analysis
ML20239A0921987-09-30030 September 1987
Assessment of Benefits & Potential Impacts of Proposed Change to Expiration Date of Plant Ol
ML20206D5711987-03-27027 March 1987
Vapor Container Seismic Evaluation Soil Bearing Capacity Analysis
ML20203N5641986-09-30030 September 1986
Rev 0 to Leak-Before-Break Evaluation for 5-Inch Diameter Bypass Lines at Yankee Nuclear Power Station
ML20212P8421986-08-22022 August 1986
Auxiliary Power Sys Voltage Study for Yankee Nuclear Power Station
ML20137B0181985-09-19019 September 1985
Fire Water Tank Seismic Analysis for Yankee Nuclear Power Station
ML20133P8401985-08-0606 August 1985
Refueling Cavity Water Seal Evaluation
ML20133B5081985-08-0101 August 1985
Dcrdr Summary Rept for Yankee Nuclear Power Station
ML20214E5211985-01-31031 January 1985
Assessment of Structural Seismic Design Adequacy of Yankee Nuclear Power Station
ML20138L1881984-09-30030 September 1984
Tornado Cost-Benefit Analysis for Proposed Backfits of Yankee Nuclear Power Station
ML20212M8411981-03-31031 March 1981
Analysis of Fast Neutron Flux Levels & End-of-Life Exposure for Yankee Rowe Reactor Pressure Vessel
ML20132A8621979-08-21021 August 1979
Assessment of Effect of Increased Fuel Rod Fill Gas Pressure on Core 14 ECCS Performance Analysis
ML20148G9291976-09-30030 September 1976
App C,Addl LOCA Analysis W/Revised Upper Hemispherical Head Temp
ML20148E9731975-12-11011 December 1975
Energy Absorption by Size 14 Figure 607 Valve Seat & Disk at Yankee Rowe
ML20148E9681975-08-13013 August 1975
Disk Velocity at Impact W/Seat for Line Break at Upstream Side of Size 14 Figure 607 Non-Return Valve
1998-02-27
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217C1311999-10-0808 October 1999
Safety Evaluation Supporting Amend 153 to License DPR-3
ML20211J5111999-08-31031 August 1999
Rev 29 to Yankee Decommissioning QA Program
ML20211J3361999-08-27027 August 1999
Safety Evaluation Supporting Amend 152 to License DPR-3
ML20209D5391999-06-22022 June 1999
Rev 29 to Yaec Decommissioning QA Program
ML20207F9491999-03-0505 March 1999
Safety Evaluation Supporting Amend 151 to License DPR-3
ML20202H5871999-02-0303 February 1999
Safety Evaluation Supporting Amend 150 to License DPR-3
ML20154P9691998-10-16016 October 1998
Rev 28 to Yankee Atomic Electric Co Decommissioning QA Program
ML20249A7901998-06-17017 June 1998
Safety Evaluation Supporting Amend 149 to License DPR-3
ML20216C4581998-02-27027 February 1998
Response to NRC Demand for Info (NRC OI Rept 1-95-050)
ML20203L1931998-02-25025 February 1998
Duke Energy Corp,Duke Engineering & Svcs,Inc,Yankee Atomic Small Break LOCA Technical Review Rept
ML20203L2451998-02-23023 February 1998
Assessment Rept of Engineering & Technical Work Process Utilized at De&S Bolton Ofc
ML20203L1621998-02-18018 February 1998
Rept of Root Cause Assessment Review
ML20203L2691998-02-16016 February 1998
Duke Engineering & Svcs Assessment Process Review Rept
ML20199B4601998-01-20020 January 1998
Special Rept:On 980105,meteorological Monnitoring Instrumentation for Air Temp Delta T Inoperable for More than 7 Days.Caused by Breakdown in Wiring Between Junction Box at 199 Foot Level.Wiring Replaced
ML20203J3001997-12-31031 December 1997
Ynps 1997 Annual Rept
ML20217N0981997-08-21021 August 1997
LER 97-S02-00:on 970725,discovered Uncontrolled Safeguards Documents.Caused by Personnel Error.Matls Retrieved & Stored in Safeguards Repositories
ML20210H0991997-08-0707 August 1997
LER 97-S01-00:on 970709,potential Compromise of Safeguards Info Occurred.Caused by Human error.Stand-alone Personal Computer & Printer Not Connected to Network,Have Been Located within Text Graphics Svc Dept
ML20149K7781997-07-24024 July 1997
Special Rept:On 970520 & 0714,air Temp Delta T Channel Indicated Temp Difference Between Top & Bottom of Meteorological Tower.Caused by Reversed Input Wiring to Channel.Restored Air Temp Delta T Channel Operability
ML20141E4671997-05-30030 May 1997
Rev 28 to Operational QA Program
ML20135C8461996-12-31031 December 1996
Yankee Nuclear Power Station 1996 Annual Rept
ML20132G6771996-12-20020 December 1996
Rev 27 to YOQAP-I-A, Operational QA Program
ML20058N4771993-12-20020 December 1993
Rev 0.0 to Yankee Nuclear Power Station Decommissioning Plan
ML20059K8491993-12-15015 December 1993
Clarifications to Pages 2,41,43 & 44 of 44 in Section I, Organization of YOQAP-I-A,Rev 24, Operational QA Program
ML20059C5011993-10-29029 October 1993
Special Rept:On 931019,meteorological Instrumentation Channel for Delta T Declared Inoperable.Caused by Ceased Aspirator Motor Located at Top of Tower.Motor Replaced
ML20056H1741993-06-10010 June 1993
Preliminary Assessment of Potential Human Exposures to Routine Tritium Emissions from Yankee Atomic Electric Co Nuclear Power Facility Located Near Rowe,Ma
ML20237F1671993-02-19019 February 1993
Safety Evaluation Supporting Amend 147 to License DPR-3
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
ML20198D2481992-05-13013 May 1992
Yankee Nuclear Power Station Certified Fuel Handler Initial Certification Program
ML20198D2541992-05-13013 May 1992
Yankee Nuclear Power Station Certified Fuel Handler Recertification Program
ML20062H1981990-11-30030 November 1990
Plant Specific Fast Neutron Exposure Evaluations for First 20 Operating Fuel Cycles of Yankee Rowe Reactor
ML20058H2841990-11-0303 November 1990
Special Rept:On 901101,control Rod 24 Found Disconnected from Drive Shaft.Drive Shaft Latching Will Be Initiated
ML20058F2201990-11-0202 November 1990
Safety Evaluation Accepting Util Response to Generic Ltr 83-28 Re post-trip Review - Data & Info Capability
ML20062E8331990-10-31031 October 1990
Monthly Operating Rept for Oct 1990 for Yankee Atomic Power Station
ML20058G1471990-10-31031 October 1990
Vol 2 to Star Methodology Application for PWRs Control Rod Ejection Main Steam Line Break
ML20058C4061990-10-22022 October 1990
Safety Evaluation Supporting Amend 137 to License DPR-3
ML20062B6751990-09-30030 September 1990
Monthly Operating Rept for Yankee Atomic Power Station for Sept 1990
ML20059G2411990-09-0606 September 1990
Safety Evaluation Supporting Amend 135 to License DPR-3
ML20059E3071990-08-31031 August 1990
Safety Assessment of Yaec 1735, Reactor Pressure Vessel Evaluation Rept for Yankee Nuclear Power Station. Detailed Plan of Action W/Listed Elements Requested within 60 Days After Restart to Demonstrate Ability to Operate Longer
ML20059E8001990-08-31031 August 1990
Monthly Operating Rept for Aug 1990 for Yankee Atomic Power Station
ML20058P7841990-08-14014 August 1990
Part 21 Rept Re Misapplication of Fluorolube FS-5 Oil in Main Steam Line Pressure Gauges.All Four Indicators Replaced W/Spare Gauges Which Utilize High Temp Silicone Oil
ML20058N6581990-08-13013 August 1990
Special Rept Re Diesel Fire Pump & Tank Inoperable for Greater than Seven Days for Draining,Cleaning & Insp.During Period Redundant Pumping Capacity Available Via Two Remaining Electric Driven Fire Pumps
ML20058L6651990-08-0202 August 1990
Safety Evaluation Supporting Amend 134 to License DPR-3
ML20058L0321990-08-0202 August 1990
Safety Evaluation Supporting Amend 133 to License DPR-3
ML20056A1961990-08-0101 August 1990
Special Rept:Two Fire Pumps Inoperable at Same Time.Caused by Necessity to Accomplish Surveillance to Verify Capability to Start Pump on Emergency Diesel Generator 3 & Planned 18-month Insp of Diesel Per Tech Specs
ML20055G6801990-07-31031 July 1990
Yankee Plant Small Break LOCA Analysis
ML20055E1591990-07-31031 July 1990
Reactor Pressure Vessel Evaluation Rept
ML20055G7011990-07-31031 July 1990
Yankee Nuclear Power Station Core 21 Performance Analysis
ML20055J3221990-07-25025 July 1990
Decommissioning Funding Assurance Rept & Certification
ML20055G7051990-07-19019 July 1990
Rev 0 to Yankee Cycle 21 Core Operating Limits Rept
ML20055F6751990-06-30030 June 1990
Monthly Operating Rept for June 1990 for Yankee Atomic Power Station
1999-08-31
[Table view] |
Text
., '. .
(
SUPPLEMENTAL REPORT REANALYSIS OF 1984 EDDY CURRENT DATA FOR STEAM GENERATORS NO. 3 AND NO. 4 9
Prepared by:____ l 1 D. F. May
_ /_9_[_[_
Date Nuclear Engineer Reviewed ane # l Approved by [___ u_ /______ _ _h,d_kh____
R. A. Mello Date Technical Director 8806200047 880607 PDR ADOCK 05000029 l
Q DCD t _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _
4 Introduction This Special Report is a result of the review: of previous inservice inspection data for steam generators (S/G) No. 3 and No. 4 performed in May and June of 1987 and is intended to supplement the 1984 report, "Steam Generator Inservice Inspection Results" (Reference 1). During the 1987 ;
inspection, results of previous inspections done in 1985 for S/G No. 1 and in 1984 for S/G's No. 3 and No. 4 were re- l evaluated due to discrepancies found during a review of the 1984 eddy current data for S/G No. 2.
References
- 1. Steam Generator Inservice Inspection Results, May 1984, FYR 85-61
- 2. Steam Generator No. 2 Inservice Inspection Results, June 1988, FYR 88-79
- 3. Zetec report. "Assessment of Data Interpretation Techniques", dated July 16, 1987.
- 4. LER 87-006, "Defective Tubes Missed During 1984 Steam Generator Eddy Current Examination". FYR 87-69 dated July 2, 1987 S. Memorandum from C.G.Garrow to D.A.Maidrand, "Evaluation of the Potential 10 CFR Part 21 - Zetec Steam Generator Evaluation", dated September 29, 1987 Results Discussion As a result of this re-evaluation 18 tubes were plugged in S/G No. 3 and 16 tubes in S/G No. 4 in May and June of 1987.
No additional tubes were plugged in S/G No. 1. Tables I and II list the location and percent of wall thickness penetration for each imperfection found in the re-evaluation.
Imperfections listed in these tables include those that l either differed significantly from, or were not included in, the 1984 report results.
The failure to detect defective tubes during the 1984 inspection has been attributed to the improvements in eddy current inspection and evaluation techniques and also to the lack of a secondary review of the eddy current data (Reference 4). An evaluation (Reference 5) conducted after the E/C testing concluded the deviations experienced during the 1984 inspection were not reportable under 10 CFR Part 21.
Corrective actions were provided in Reference 4.
i
6.w.
TABLE I - STEAM GENERATOR NO. 3 INSPECTION RESULTS (based on review of old data)
Row Column % Degradation Location of Degradation Plugged D 019 38 TTS-CL+0000.3 YES D 042 38 TTS-CL+0002.3 YES 47 TTS-CL+0001.4 ---
D 041 24 TTS-CL+0001.0 NO C 022 67 TTS-CL+0000.6 YES E O25 42 TTS-CL+0000.5 YES I O20 59 TTS-CL+0000.2 YES I O21 33 TTS-CL+0000.9 NO G O22 25 TTS-HL+0000.9 NO F O22 <20 TTS-CL+0002.8 NO K O26 31 TTS-CL+0000.8 NO G O26 36 TTS-CL+0001.9 YES F O26 24 TTS-CL+0001.3 NO H O24 <20 TTS-HL+0003.3 NO 21 TTS-HL+0000.6 ---
J O24 35 TTS-CL+0001.2 YES K O25 81 TTS-CL+0000.6 YES I O25 69 TTS-CL+0000.4 YES N 028 46 TTS-CL+0001.6 YES J O28 <20 TTS-CL+0001.3 NO K 030 56 TTS-CL+0000.8 YES F 036 <20 TTS-CL+0000.9 NO E 037 <20 TTS-CL+0001.2 NO G 037 26 TTS-HL+0000.7 NO H 037 <20 TTS-CL+0001.1 NO I 038 33 TTS-HL+0001.4 YES l 46 TTS-HL+0001.7 ---
l 48 TTS-CL+0000.8 ---
G 039 24 TTS-CL+0000.4 NO H 039 <20 TTS-CL+0000.8 NO G 041 33 TTS-CL+0001.1 NO H 041 29 TTS-CL+0000.7 NO F 043 25 TTS-CL+0000.8 NO H 043 36 TTS-HL+0002.0 YES I 043 <20 TTS-HL+0001.0 NO DD 035 35 4-AVB+ 0000.0 YES R 047 23 TTS-HL+0000.4 NO BB 047 49 TTS-HL+0000.5 YES H 049 62 TTS-HL+0000.3 YES K 049 (20 TTS-HL+0000.5 NO L 049 23 TTS-HL+0001.2 NO O 049 33 TTS-HL+0000.5 NO AA 050 <20 TTS-HL+0000.5 NO l H 053 <20 TTS-HL+0000.5 NO V 055 <20 TTS-HL+0000.5 NO W 055 27 TTS-HL+0001.7 NO P 056 <20 TTS-HL+0000.6 NO
<20 TTS-HL+0000.8 ~~-
4
~
s ,
TABLE I CONTINUED Row Column % Degradation Location of Degradation Plugged R 057 <20 TTS-HL+0000.4 NO S 057 <20 TTS-HL+0000.4 NO O 058 <20 TTS-HL+0001.3 NO
, I 060 <20 TTS-HL+0000.6 NO E 039 036 TTS-CL+0001.3 YES D 039 036 TTS-CL+0000.8 YES H 035 023 TTS-CL+0001.3 NO F O28 029 TTS-CL+0000.4 NO l
l l
l l
l l
l l
l l
l AVB - Antivibration Bar )
1 CL - Cold Leg j HL - Hot Leg TE - Tube End TTS - Top of Tube Sheet 1
I I
TABLE II - STEAM GENERATOR NO. 4 INSPECTION RESilLTS (Based on review of old data) f Row Column X Degradation Location of Degradation Plugged l
G 048 078 TTS-HL+0001.5 YES P 044 076 TTS-HL+0000.9 YES P 043 054 TTS-HL+0000.9 YES O 043 059 TTS-HL+0001.5 YES D 039 031 TTS-CL+0001.0 NO R 041 <20 TTS-HL+0002.6 NO K 037 077 TTS-HL+0005.6 YES J 035 039 TTS-CL+0001.5 YES O 034 079 TTS-HL+0000.8 YES K 033 <20 TTS-HL+0002.6 NO O 032 081 TTS-HL+0003.0 YES N 031 071 TTS-HL+0003.1 YES P O29 038 TTS-HL+0001.0 YES J O29 027 TTS-HL+0004.2 YES 046 TTS-CL+0001.7 ---
G O29 034 TTS-ru+0001.2 NO H O28 038 TTS CL+0000.3 YES L 028 022 TTd-HL+0002.4 NO P O28 031 TTS-HL+0001.2 NO M O27 031 TTS-CL+0000.6 NO H 018 039 TTS-CL+0000.8 YES H O20 061 TTS-HL+0001.8 YES F O21 026 TTS-CL+0001.6 NO L 022 056 TTS-CL+0000.5 YES J O25 <20 'TS-CL+0000.4 NO H O23 <20 TTS-CL+0002.9 NO L 023 045 TTS-HL+0002.1 YES 050 TTS-CL+0000.6 ---
l l
l AVB - Antivibration Bar 9 l
CL - Cold Leg l HL - Hot Leg TE - Tube End TTS - Top of Tube Sheet
- _ - _ - - - )