Similar Documents at Maine Yankee |
|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20234F2361987-06-26026 June 1987
Special Rept:Cardox Sys Inoperable for 26 Days Due to Failed Relay in Cable Vault Zone Discovered on 870519.Fire Watch Established.Replacement Relay Installed & Tested on 870611. Cardox Sys Functionally Tested on 870613
ML20214V7971986-09-0808 September 1986
Ro:On 860810,plant Tripped Due to Low Steam Generator Level Following Loss of Static Inverter.On 860811,dose Equivalent I-131 Activity Exceeded 1.0 Uci/G.Dose Equivalent Iodine Activity & Plant Operating Characteristics Encl
ML20212C6381986-07-15015 July 1986
Ro:On 860612,plant Tripped When Excess Flow Check Valve Inadvertently Closed.Dose Equivalent Iodine (Dei) Activity Also Exceeded 1 Uci/G.Dei Activity & Plant Operating Characteristics Presented in Tables 1 & 2,respectively
ML20198R3051986-05-20020 May 1986
Ro:On 860416,dose Equivalent I-131 Activity Exceeded 1.0 Uci/G & Remained Above Level All Day.Letdown Flow Increased Upon Reactor Shut Down in Order to Increase Coolant Cleanup & Reduce I-131 Level
ML20210U8781986-05-14014 May 1986
Ro:On 860429,Mensor High Precision Quartz Manometer,Which Provides Containment Pressure Info to Plant Computer,Failed. Mensor Repaired & Returned to Svc.Alternate Calculations Will Continue
ML20155A8591986-03-24024 March 1986
Ro:On 860222,dose Equivalent Iodine (I-131) Levels Exceeded 1 Uci/G for 7.5 H After Unit Shutdown on 860221 to Repair Hydrogen Leak in turbine-generator Unit.Peak Activity Spike 1.96 Was Uci/G.Cause Not Stated
ML20126L7811981-06-0303 June 1981
Ro:On 810603,at Completion of Fuel Handling Activities & W/ Greater than 23 Ft of Water in Reactor Cavity,Svc Water Cooling to Secondary Component Coolers Interrupted for Approx 30 Minutes.No Significant Increase in Temp
ML20126B4341980-01-30030 January 1980
RO 80-001/01T:during Review of Steam Line Break Analysis, Incorrect Assumption Utilized in Zero or Low Power Steam Line Break Analysis Discovered.Cause Unstated.Necessary Mods to Be Implemented Prior to Startup
1987-06-26
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20211M4841999-08-31031 August 1999
Replacement Pages 2-48,2-49 & 2-50 to Rev 14 of Defueled Sar
ML20211D7111999-08-0909 August 1999
Rev 17 to Maine Yankee Defueled Safety Analysis Rept (Dsar)
ML20196K4821999-07-0606 July 1999
Safety Evaluation Concluding That Because of Permanently Shutdown & Defueled Status of Myaps Facility,Confirmatory Orders No Longer Necessary for Safe Operation or Maint of Plant
ML20206H1611999-05-0505 May 1999
Safety Evaluation Supporting Amend 164 to License DPR-36
ML20206G5731999-05-0303 May 1999
Safety Evaluation Supporting Amend 163 to License DPR-36
ML20205D5261999-03-26026 March 1999
SER Accepting Util Rev 1 to CFH Training & Retraining Program for Maine Yankee.Rev 1 to CFH Training & Retraining Program Consistent with Current Licensing Practice for Facilities Undergoing Decommissioning
ML20204C4631999-03-16016 March 1999
Safety Evaluation Supporting Amend 162 to License DPR-36
ML20206D7491998-12-31031 December 1998
Co Annual Financial Rept for 1998. with
ML20155G9591998-11-0303 November 1998
Rev 1 to Post-Shutdown Decommissioning Activities Rept
ML20155D8651998-10-28028 October 1998
Public Version of, Maine Yankee Emergency Preparedness Exercise
ML20197C8231998-09-0303 September 1998
Safety Evaluation Supporting Request for Exemption from Certain Requirements of 10CFR50.54(q),10CFR50.47(b) & (C) & App E to 10CFR50 Re Emergency Planning
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML20236X1751998-08-0303 August 1998
Rev 16 to Defueled Sar
ML20236U8451998-07-24024 July 1998
Safety Evaluation Accepting Rev 14 to Maine Yankee Atomic Power Co Operational QA Program
ML20248D3011998-05-26026 May 1998
Rev 14,page 16 of 17,Section II of QA Program
ML20247J0211998-05-11011 May 1998
Revised Page 16 of 17 of Section II of QA Program,Rev 14
ML20247D3451998-05-0606 May 1998
Rev 15 to Defueled SAR, Replacing List of Effective Pages
ML20217J9811998-04-28028 April 1998
Part 21 Rept Re Incorrect Description of Drift Specification for Model 1154,gauge Pressure Transmitters,Range Code 0 in Manual Man 4514,Dec 1992.Cause Indeterminate.Will Issue & Include Errata Sheets in All Future Shipments to Users
ML20217H5241998-03-30030 March 1998
Safety Evaluation Supporting Amend 161 to License DPR-36
ML20217D9691998-02-28028 February 1998
Monthly Operating Rept for Feb 1998 for Maine Yankee.W/
ML20216D7681998-02-25025 February 1998
Rept to Duke Engineering & Services,Inc,On Allegations of Willfulness Related to Us NRC 971219 Demand for Info
ML20203A3011998-01-31031 January 1998
Monthly Operating Rept for Jan 1998 for Maine Yankee
ML20202F3771998-01-31031 January 1998
Annual Rept of Facility Changes & Relief & Safety Valve Failures & Challenges
ML20202E0541998-01-30030 January 1998
Rev 14 to Myaps Defueled Safety Analysis Rept
ML20199K3211998-01-27027 January 1998
Rev 13 to Maine Yankee Atomic Power Co,Qa Program
ML20199K3471998-01-22022 January 1998
Rev 14 to Maine Yankee Atomic Power Co QA Program
ML20199C2281997-12-31031 December 1997
Monthly Operating Rept for Dec 1997 for Maine Yankee
ML20217R2301997-12-31031 December 1997
Myap Annual Financial Rept for 1997
ML20203F8551997-11-30030 November 1997
Monthly Operating Rept for Nov 1997 for Maine Yankee
ML20202D3181997-11-26026 November 1997
Safety Evaluation Supporting Amend 160 to License DPR-36
ML20198R6371997-11-0606 November 1997
Yankee Mutual Assistance Agreement
ML20155G9511997-10-31031 October 1997
Rev 1 to M01-1258-002, Decommissioning Cost Analysis for Myaps
ML20198P9431997-10-31031 October 1997
Monthly Operating Rept for Oct 1997 for Maine Yankee
ML20217K5191997-10-24024 October 1997
Part 21 Rept Re Five Valves That May Have Defect Related to Possible Crack within Forging Wall at Die Flash Line.Caused by Less than Optimal Forging Temperatures.Newer Temperature Monitoring Devices at Forging Area Heating Ovens Procured
ML20211N0571997-10-0707 October 1997
Revised Pages to Jul/Aug 1994 SG Insp Summary Rept
ML20198K0201997-09-30030 September 1997
Monthly Operating Rept for Sept 1997 for Maine Yankee
ML20199H1861997-09-25025 September 1997
Rev 12 to Maine Yankee Atomic Power Co,Qa Program
ML20217A9251997-08-31031 August 1997
Monthly Operating Rept for Aug 1997 for Maine Yankee
ML20217R1051997-08-27027 August 1997
Myaps Post Shutdown Decommissioning Activities Rept
ML20216F1511997-08-0808 August 1997
Safety Evaluation Supporting Amend 159 to License DPR-36
ML20210M4451997-07-31031 July 1997
Monthly Operating Rept for July 1997 for Myaps
ML20151M1351997-07-21021 July 1997
Rev 0 to Technical Evaluation 172-97, Cable Separation Safety Assessment Rept
ML20141H2691997-06-30030 June 1997
Monthly Operating Rept for June 1997 for Maine Yankee
ML20141B9951997-05-31031 May 1997
Monthly Operating Rept for May 1997 for Maine Yankee.W/
ML20141G6511997-05-19019 May 1997
Safety Evaluation Supporting Amend 158 to License DPR-36
ML20138G3541997-05-0202 May 1997
Safety Evaluation Supporting Amend 157 to License DPR-36
ML20141G2871997-04-30030 April 1997
Monthly Operating Rept for Apr 1997 for Maine Yankee
ML20137Z1971997-04-14014 April 1997
Forwards to Commission Results of Staff Evaluation of Performance of Licensees W/Ownership Structure Similar to Plant
ML20137N7541997-03-31031 March 1997
Rev 11 to Operational Quality Assurance Program
ML20138B1491997-03-31031 March 1997
Monthly Operating Rept for Mar 1997 for Maine Yankee
1999-08-09
[Table view] |
Text
_ _ - - - - - - .
F E
MAIRE HARHEE ATOMIOPOWER00MPARUe ,vaugr,y,?n", o",lg6 (207) 623-3521 May 14, 1986 O MN-86-63 GDH-86-113 Region I United States Nuclear Regulatory Commission Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Thomas E. Murley, Regional Administrator
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) Maine Yankee Final Safety Analysis Report, Section 5.2.4
Subject:
Containment Height of Air Monitoring System Gentlemen:
Maine Yankee Atomic Power Company hereby submits the following report in accordance with Technical Specification 3.11.G.I.
At 0704 hours0.00815 days <br />0.196 hours <br />0.00116 weeks <br />2.67872e-4 months <br /> on Tuesday, April 29, 1986, the plant's Mensor high precision quartz manometer, which provides containment pressure information to ,
the plant computer, failed. The pressure input is utilized to calculate the l weight of air within the sealed containment, and the calculated value is j trended for an added measure of assurance of leak-tightness of the l containment. The containment's integrity is primarily assured by the I automatic isolation features and administrative controls in place generally . l for U.S. plants of this type. l Since discovery of the Mensor quartz manometer failure on April 30th, Operations Department personnel have been performing hand calculations of containment weight of air once per shift with pressure values obtained from a locally read barometer. Additionally, the wide range containment pressure i sensor has been substituted for the Mensor quartz manometer in the computer calculation. The results of the hand calculation and the revised computer calculation are both being used for trending in accordance with Technical Specification 3.11 in the same way the Mensor calculation is normally used.
The alternative calculations are not quite as accurate, however, giving day-to-day fluctuations in calculated air weight about two and one-half times the Mensor based daily fluctuations.
7573L-SEN < )_
8606100001 860514 . I PDR ADOCK 05000309 i g S PDR l l
j MAINE YANKEE ATOMIC POWER COMPANY United States Nuclear Regulatory Commission Page Two Attention: Dr. Thomas E. Murley, Regional Administrator MN-86-63 The necessary parts to repair the Mensor quartz manometer were received on May 7, 1986. The Mensor has been repaired, calibrated, and returned to service. Alternative calculations will continue, however, for ten days to ensure the Mensor is fully operational.
He trust this information is satisfactory. Please contact us should you have any questions regarding this matter.
Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY
.jp6 wl$
G. D. Whittier, Manager Nuclear Engineering and Licensing GCH/bjp cc: Mr. Ashok C. Thadani Mr. Pat Sears Mr. Cornelius F. Holden We 7573L-SEN