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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20087L5711976-02-0202 February 1976 AO 76-3:during Refueling Outage from 751116-760108,nine Valves Exhibited Leak Rate in Excess of 2000 Cc/Minute. Caused by Loose Body to Bonnet Joint.Bolting Tightened ML20087K9381975-03-0808 March 1975 AO 50-266/75-4:on 750226,air Ejector Discharge Gas Monitor R15 Pegged High,Then Dropped Low.Operator Manually Secured RCS Letdown & Went to Auxiliary Bldg to Assist in Locating Suspected Leak ML20087L0911975-02-18018 February 1975 AO 75-3:on 750208,mechanical Latching Mechanism on Redundant Solenoid Trip Vent Valve 2018C on Main Steam Stop Valve a Failed to Unlatch When Solenoid Deenergized.Caused by Improper Rotation of Rollers as Designed ML20087L2091975-01-28028 January 1975 AO 75-1:on 750120,first of 4 Tanks of Sludge Lancing Waste Sampled & Iodine Levels Found Approx 9 Times Max Permissable Concentration.Caused by Fuel Cladding Leaks Plus Small primary-to-secondary Leak in Steam Generator a ML20087L2661974-11-22022 November 1974 Ao:On 741009,while Personnel Exiting Containment Via 66 Ft Level Personnel Airlock,Air Heard Escaping Following Closing of Inner Door.Caused by Open 3/8-inch Valve on Pressure Gauge Instrument Line.Valve Removed.Served No Purpose ML20087L3101974-08-30030 August 1974 Ao:On 740821,recheck of Control Panel Indicated Above Normal Operating Pressure & Water Level Conditions Existed in Blowdown Evaporator.Caused by Steam Leaking at Steam Supply Control Valve ML20087L3191974-08-27027 August 1974 Ao:On 740815,during Monthly Surveillance Test,Steam Generator B Level Channel 472,lo-lo Level Bistable Would Not Trip When Tested.Caused by Failed Silicon Controlled Rectifier.Rectifier Replaced ML20087L3251974-07-22022 July 1974 Ao:On 740711,rereview of Tech Spec Changes Allowed part-length Rods to Be Inserted Not More than 70%.On 740529,part-length Rods Inserted to Max Integral Worth, 82.5% & Remained in That Position Until 740608 ML20087L3441974-06-13013 June 1974 Ao:On 740325,valve Permitting 150 Gallons of Reactor Coolant to Enter Waste Holdup Tank Inadvertently Opened.Caused by Personnel Error.Operator Reprimanded & Reminded That Utmost Care Must Be Exercised on Valve Lineup Operations ML20087L3361974-06-0808 June 1974 Ao:On 740529,minor Leak Discovered in Main Steam Safety Valve & Secondary Side Steam Pressure Substantially Reduced to Reseat Safety Valve & Terminate Minor Leak. Caused by Incorrect Concentration of Borated Water ML20087L5481974-05-14014 May 1974 Ao:On 740509,auxiliary Bldg Stack Monitor R14 Alarmed at Setpoint During Refueling Activities of 4,000 Counts Per Minute Indicating Release of Radioactivity.Caused by Isolation of Vol Control Tank for Venting ML20087L5931974-05-0303 May 1974 Ao:On 740406,during Performance of Containment Isolation Valves Leak Tests,Two second-off Valves from Containment Found to Leak in Excess of 2000 Cc/Minute.Cause Not Stated. Leak Tests Ongoing.Valves Will Be Repaired & Retested ML20087L6031974-04-17017 April 1974 Ao:On 740407,while Running Motor Driven Auxiliary Feed Pump a to Maintain Steam Generator Water Levels,Operator Noted Pump Not Delivering at Adequate Feedwater Flow Rate.Caused by Strainer Fitted in Flanged Position ML20087L6111974-04-11011 April 1974 Ao:On 740404,following Completion of Operations Refueling Tests,Isolation Valves 1AOV-2084 & 1AOV-2083 Closed Automatically on Signal from R-19 Process Monitor,Indicating Liquid W/Radioactivity Above Normal Levels ML20087L6201974-04-0404 April 1974 Ao:On 730329,when Drain Cap Removed from Penetration 32,air Blew Lightly for Several Seconds & Showed No Signs of Diminishing.Caused by Leak of Sensing Line within Penetration Boundary.Line Will Be Repaired ML20087L6261974-02-0606 February 1974 Ao:On 740125,auxiliary Bldg Stack Monitor R-14 Alarmed Indicating Release of Radioactivity.Caused by Increased Pressure Attained in Holdup Tanks & Suction of Waste Gas Compressors ML20087L6971973-11-0303 November 1973 Ao:On 731013,boric Acid Storage Tank B Placed in Svc & Boric Acid Tank a Concentration Known to Have Fallen Below Tech Spec Limit Immediately Prior to Transfer of Tanks. Caused by Two Personnel Errors ML20084A0901973-10-29029 October 1973 Ao:On 730915,following Investigation of Excess Letdown Line Leak,Valve 1MOV-1299 Downstream Seat Protruded from Valve Body & Crack Discovered in Upper Portion of Downstream Seat Ring.Cause Unknown.Vendor Notified of Valve Problem ML20087L6291973-07-16016 July 1973 Ao:On 730708,high Level Alarm on Facade Sump Received in Main Control Room.Caused by Small But Steady Flow Into Sump from Unknown Source.Retransfer of Borated Water from Refueling Water Storage Tank Instigated ML20087L6311973-05-28028 May 1973 Ao:On 730512,to Expedite Shutdown & Draining of Radwaste Sys Waste Evaporator,Operating Personnel Manually Lifted One of Two Evaporator Safety Valves.Following Shutdown,Valve Remained in Raised Condition.Procedure Pbnp 4.17 Expanded ML19317D4661971-08-11011 August 1971 Ao:On 710803,release of Radioactive Liquid Into Sewage Retention Pond Resulted from Overflow of Unit 2 Facade Sump During Filling Operation.Caused by Problems W/Facade Drain 1976-02-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 ML20151W4221998-05-31031 May 1998 Corrected Page to MOR for May 1998 for Pbnp Unit 2 NPL-98-0481, Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4011998-04-30030 April 1998 Corrected Page to MOR for April 1998 for Pbnp Unit 2 NPL-98-0356, Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20216D7071998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3981998-03-31031 March 1998 Corrected Page to MOR for March for Pbnp Unit 2 NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant NPL-98-0159, Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3891998-02-28028 February 1998 Corrected Page to MOR for Feb 1998 for Pbnp Unit 2 ML20216D7121998-02-28028 February 1998 Revised Corrected MOR for Feb 1998 for Point Beach Nuclear Plant,Unit 2 NPL-98-0084, Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 1999-09-30
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h 0 Wisconsin Electnc eaata couesur 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201 May 28, 197_3 ' ~ N Mr. John F. O' Leary, Director <f[p'. o, -
N Directorate of Licensing Q 4 (/ , ,
U. S. Atomic Energy Commission '//
Washington, D. C. 20545 48/ffy/ ' < ,
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Dear Mr. O' Leary:
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' 9, (;.,N / ,/,,, 4 g DOCFET NOS. 50-266 AND 50-301 ,
' g[p POINT BEACH NUCLEAR PLANT 'v ' ice UNSCHEDULED RELEAS.E OF RADIOACTIVITY This is to report the details of an abnormal occurrence at Point Beach Nuclear Plant as defined by Section 15.1.a.C of It j) the Technical Specifications. This written report, in accord-ance with Section 15.6.6.A.2 of the Technical Specifications,
) follows a telephone report made on the incident to Mr. K. Baker of Region III Regulatory Operations on May 23, 1973, as required by Section 15.6.6.A.1 of the Technical Specifications.
On Saturday, May 12, 1973, the new radwaste system waste evaporator at Point Beach was shut down for modification and adjustment following a test run. To expedite the shutdown and
]y draining of the evaporator, operating personnel chose to break vacuum in the evaporator by manually lifting one of two evapora-
-TJ tor safety valves. To free himself for other work during the a
vacuum breaking operation, the operator then placed a wrench to f e}d ps prop up the safety valve lifting arm; thus keeping the valve disc lifted approximately 7/8 inch off its seat.
Following the shutdown of the evaporator, the safety valve remained in the raised condition. No written or verbal report of the valve's disposition was passed to the succeeding shift opera-tors.
The waste evaporator was restarted on May 22, 1973, for Difficulty was experienced in raising evapora-further testing.
tor steam pressilre to the required 35 psig and a subsequent inves-tigation determined that a safety valve was in a propped open con-dition, permitting slightly radioactive steam to exit via the unmonitored discharge pipe. The wrench prop was removed and the safety valve,Eas reseated tightly, stopping the leakage.
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May 28, 1973
. Mr. John F. O' Leary An examination of water inventory following the event indicated that approxinately 90 gallons of slightly tritiated water had discharged via the safety valve during the two hour operation of the evaporator. An estimated 50 gallons of this total condensed on the walls of the discharge pipe and drained, as per design, to the Unit 2 facade drain well. After routine sampling, this liquid was pumped to the plant retention pond following the issuance of a standard discharge permit by the Chemistry and Health Physics Group. ,
By deduction, the remaining 40 gallons of water was dis-charged as steam to the atmosphere via the unmonitored stack.
The sampling of the air in the immediate area of the safety valve and condensate from the st,eam vapor indicated that it contained no detectable levels of beta-gamma, gamma, air par-ticulate, airborne iodine, or gaseous activity. Tritium was detected and the following table is drawn up to indicate its significance:
Calculated Concentration Permissible MPC at Site Boundary At Site Boundary Actual Discharge (uCi/cc) (uci/cc) (uCi) 3H 1.7 x 10-12 2 x 10-7 8.18 x 103 (over two hour period)
The table shows that the discharge was well below permitted levels and did not constitute a hazard to the health and safety of the public.
To prevent a recurrence of this incident, the existing Administrative Procedure PBNP 4.17 " Lifted Wires, Jumpers and Bypasses", which requires personnel to complete a log sheet when }i '
actions described in its title are to be implemented, will be expanded to require documentation of any unusual disposition of plant equipment not covered by standard operating or maintenance proceedures.
Very truly yours,
-- l Sol Burstein Senior Vice President cc: Mr. Boyce H. Grier, Regional Director Directorate of Regulatory Operations, Region III 9
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