AO 50-29/74-3:on 740627,during Routine Refueling Interval Surveillance Testing,Low Pressure Scram Setpoint Found in Violation of Tech Specs.Caused by Instrumentation Drift. Low Pressure Scram Setpoint Readjusted| ML20148J452 |
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Yankee Rowe |
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| Issue date: |
07/05/1974 |
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| From: |
Autio H
YANKEE ATOMIC ELECTRIC CO. |
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| Shared Package |
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| ML20148J451 |
List: |
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| References |
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| AO-50-29-74-3, NUDOCS 8011240122 |
| Download: ML20148J452 (2) |
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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20148J4521974-07-0505 July 1974
AO 50-29/74-3:on 740627,during Routine Refueling Interval Surveillance Testing,Low Pressure Scram Setpoint Found in Violation of Tech Specs.Caused by Instrumentation Drift. Low Pressure Scram Setpoint Readjusted
ML20148J5791974-03-0808 March 1974
AO 74-1:on 740227,following Routine Sampling,Leak Found at Bonnet Joint of Diaphragm Type Isolation Valve WD-V-634. Caused by Loose Bolting.Bolting Tightened
1974-07-05
[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
ML20198D2541992-05-13013 May 1992
Yankee Nuclear Power Station Certified Fuel Handler Recertification Program
ML20198D2481992-05-13013 May 1992
Yankee Nuclear Power Station Certified Fuel Handler Initial Certification 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
ML20058L0321990-08-0202 August 1990
Safety Evaluation Supporting Amend 133 to License DPR-3
ML20058L6651990-08-0202 August 1990
Safety Evaluation Supporting Amend 134 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
ML20055G7011990-07-31031 July 1990
Yankee Nuclear Power Station Core 21 Performance Analysis
ML20055E1591990-07-31031 July 1990
Reactor Pressure Vessel Evaluation Rept
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
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i
> ABNORYAli 00CURRE!!CE REPORT I $ r i REPORT IrGERi '50-29/7h-3 REPORT DATE: July 5,.'197h ,
OCCURREHCF DATE: ' June 27, 197h FACILITY: Yankee Atomic.' Electric Company,' Rove, Massachusetts' 01367 t
IDE'iTIFICATIO*! 0F OCCURRE"CE: Protective Instrumentation Setpoint-Drift-COUDITIONS PRIOR TO OCCURRENCES: Refueling Shutdown, Shutdown Cooling Systen h Operating, Reactor.. Coolant Tenperature at :
I
'1000F.
~!
' DrCCDv"" 0F OCCURRENCE
_-Durind routine refueling interval surveillance testing of the pressurizer [
rressure channel, the lov pressure scran'setpoint vas. found to be at 1780 psig.
!- This ia a violation of the Technical Specifications Appendix A, Section D.2.d.1. 4 i
and-Table 1 which lists a'nininun setpoint of 1800 psig. s l
DESIT'ATIS" 0F APPARENT CAUSE OF OCCURRF.UCE ,
- i. Inntru entation drift; setpoint too close to the Technical Specificatiens limit.
t
.t A"ALYFIS OF OCCURREMCE The pressurizer pressure channel is one of two channels, the other being the i nain'ecciant pressure channel, capable of serening the reactor-in event of a-low pressure condition. Surveillance testing of the main coolant pressure channa' y 'ormed three weeks earlier showed the low pressure scran setpoint to be .t - * 'inits. Therefore had a low pressure scran condition occurred, 4
the rew n r vould have been scranned prior to exceedinC the Technical Enecification limit. ;
Also, the YAEC Safety Analysis, FHSR Section h00, lists a trip setting of .j
. 1750 psis used during the Transient Analysis. This setting is 21 psi less l
- than the cut-of-tolerance value. It could therefore be concluded that no !
additiene.1' risk to the health and safety of the public vould have occurred
'had the reactor been scra.ned at the out-of-tolerance limit. ~i CORF MT'"JE ACTION
,The11ovE;ressure scran setpoint was readjusted to 1830 psig to allow for .
instrunc:tation drift without exceeding the Technical Specification limit of L1303. 7::ig, i i
FAIL *1?E ItTA
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AEC DISTRIBUTION FOR PART 50 DOCKET MATERIAL b i *
( (TalPORARY FORM) CONTROL NO: 6335 FILE: N/h FRCH: , DATE OF DOC DATE REC'D LTR TWX RPh CTHER Y:nkee Atomic Electric Company Rove, Mass. 01367 ,
Mr. H.A. Autio 7-5-74 7-12-74 X T0g- # [ ORIG CC OTHER SENT AEC PDR XXX j 1 signed SENT LOCAL PER XXX l J.P. O'Reilly f CLASS U:; CLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
l XXX 1 50-29 l DESCRIPTION: ENCLOSU?2S: 1 Ltr trans the following...... Abnormal occu'r rence Report No. 50-29/74-3 l l
concerning.... Protective' Instrumentation Setpoint Drift.....
. (1 cy enc 1 rec'd)
Yankee Rowe -
m pga;T NAME: !
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FOR ACTIO:i/I~7C1"J.TICM 7-12-74 JB
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