LER-1981-005, Forwards LER 81-005/03L-0 |
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Wisconsin Electnc eowra couesur 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201 June 5, 1981 Mr. J. G. Keppler, Regional Director Office of Inspection and Enforcement, Region III U. S. NUCLEAR REGULATORY COMMISSION 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT 1 LICENSEE EVENT REPORT NO. 81-005/03L-0 Enclosed is Licensee Event Report No. 81-005/03L-0 (a 30-day report) with an attachment which provides a description of an event reportable in accordance with Technical Specification 15.6.9.2.B.2, " Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shut-down required by a limiting condition for operation."
Very truly yours, C. W. Fay,' Director Nuclear Power Department Enclosure Copy to NRC Resident Inspector 8107140366 810702 PDR ADOCK 05000 8
JUL-6 1981
NRC h ORM $
U. S. NUCLEAR H E GULAT ORY COMMISSION 87-771 LICENSEE EVENT REPORT
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60 69 DOCK ET NUMBER 68 69 EVENT DATE 74 75 R E POR T D AT E 80 EVENT DESCRIPTION AND PROBABLE CONSECUENCES h l0l2llOn 5-15-81 annual TS testina revealed that the contrni rnnm omorgoney 1
10 l 3 l j filtration system, common to both units, was not operating within TS,
I lSection 15. 3.12. 2. C, limits.
Thus, the subject system was deemed in-I o,
goperable by TS definition.
This condition placed the plant in a degradecl o 3 j o is i Imode of operation allowed by the TS.
The event had no effect on the
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lpublic health and safety as the system would have operated, although at I a y l o is i la lower than design flow rate, to filtrate the control room atmosphere.J DE CODE
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_ EVENT YE AR REPORT NO.
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33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS li l 0 l [The low system flowrates were caused by an improperly bal anced backara f t I l damper located at the W14A fan discharae and an improper setting of 4-ho_J i i
- balancing dkmper located just upstream of the systems roughing fil te rs. l
,,,., g,The dampers were readj usted.
The system was retested and found to cer-1 i, i, i iform satisfactorily and was returned to service on 5-20-81.
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DiSCOvERv DESCRIPTION
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PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
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C. W.
Fay PHONE:
NAME OF PREPARER
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ATTACHMENT TO LICENSEE EVENT REPORT NO. 81-005/03L-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 1 Docket No. 50-266 On May 15, 1981, at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, during Technical Specification ventilation system performance testing, it was discovered that the fans of the control room emergency filtration system, common to both units, were not operating within plus or minus 10 percent of their designed flow rates as required by Technical Specification, Section 15.3.12.2.C.
Thus, the control room emergency filtration system was deemed inoperable by Technical Specification definition.
This condition placed the plant in a degraded mode of operation allowed by the Technical Specifications.
The event had no effect on the public health and safety as the system would have operated to filter, although at a lower flowrate than originally designed, the control room a tmosphere.
In addition, the forced air breathing apparatus was available to the control room personnel to mitigate the consequences of airborne radioisotope contamination of the control room atmosphere.
The overall system flowrate was 3600 scfm while operating on fan W14A, and 4300 scfm while operating on fan W14B.
The system design flowrate is 4950 scfm.
The low system flowrate, while operating with fan W14A, was caused by an improperly balanced backdraft damper located just downstream of the fan discharge, and an improperly adjusted balancing damper located just upstream of the system's roughing filters.
The low system flowrate, while operating with fan W14B, was caused by the improperly adjusted balancing damper located just upstream of the system's roughing filters.
The backdraft damper was rebalanced and the balancing damper was reset.
The system was retested, and found to perform satisfactorily.
The system was returned to service at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on May 20, 1981.
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| 05000301/LER-1981-001-03, /03L-0:on 810324,steam Generator Loop a Pressure Safeguards Actuation Setpoint Found Below Tech Spec.Caused by Setpoint Drift in Foxboro Model 63U-BC-OHCA-F Bistable. Bistable Replaced | /03L-0:on 810324,steam Generator Loop a Pressure Safeguards Actuation Setpoint Found Below Tech Spec.Caused by Setpoint Drift in Foxboro Model 63U-BC-OHCA-F Bistable. 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Also Forwards Addl Rept on Evaluation of Apr 1981 Eddy Current Insp Results & Eddy Current Insp Maps | | | 05000266/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000266/LER-1981-002-03, /03L-0:on 810113,post Acceptance Review of Annual Test Results from 04-80,for Control Room Emergency Filtration Sys,Showed 1980 Annual Test Incomplete.Caused by Personnel Failing to Determine Sys Velocity & Flow Info | /03L-0:on 810113,post Acceptance Review of Annual Test Results from 04-80,for Control Room Emergency Filtration Sys,Showed 1980 Annual Test Incomplete.Caused by Personnel Failing to Determine Sys Velocity & Flow Info | | | 05000301/LER-1981-002-01, /01T-0:on 810420,leaking Plug Detected in Steam Generator a & Degraded & Defective Tubes Found in Each Steam Generator During Eddy Current Exam of First Support Plate on 810426.Cause Not Stated.Eddy Current Insp Results Encl | /01T-0:on 810420,leaking Plug Detected in Steam Generator a & Degraded & Defective Tubes 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After Surveillance Testing.Valve Repositioned & Locked Open | | | 05000266/LER-1981-006, Forwards LER 81-006/01T-0 | Forwards LER 81-006/01T-0 | | | 05000301/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000301/LER-1981-007-03, /03L-0:on 810902,boric Acid Heat Trace Circuit P131 Found Inoperative.Caused by Failed Fuse Holder.Fuse Holder Replaced & Boric Acid Heat Trace Circuit Returned to Svc | /03L-0:on 810902,boric Acid Heat Trace Circuit P131 Found Inoperative.Caused by Failed Fuse Holder.Fuse Holder Replaced & Boric Acid Heat Trace Circuit Returned to Svc | | | 05000301/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000266/LER-1981-007, Forwards LER 81-007/01T-0 | Forwards LER 81-007/01T-0 | | | 05000266/LER-1981-007-01, /01T-0:on 810626,during Normal Operation,Unit Tripped from Approx 80% Power Due to Loss of Instrument Bus. 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Probably Caused by Dirty Contacts.New Rees Contact Block Installed | | | 05000266/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000266/LER-1981-012, Forwards LER 81-012/01T-0 | Forwards LER 81-012/01T-0 | | | 05000266/LER-1981-012-01, /01T-0:on 810828,control Room Critical Control Power Failure Alarm Annunciated.Caused by Breakers Accidentally Opened by Contractor Personnel Installing Fire Barriers in Control Room.Breakers Closed & Alarm Cleared | /01T-0:on 810828,control Room Critical Control Power Failure Alarm Annunciated.Caused by Breakers Accidentally Opened by Contractor Personnel Installing Fire Barriers in Control Room.Breakers Closed & Alarm Cleared | | | 05000266/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000266/LER-1981-013-03, /03L-0:on 810921,records Revealed That Safeguards Bus Undervoltage Relays Were Not Tested within Required Time Frame.Caused by Earlier than Normal Testing During Annual Diesel Overhaul.Surveillance Callup Modified | /03L-0:on 810921,records Revealed That Safeguards Bus Undervoltage Relays Were Not Tested within Required Time Frame.Caused by Earlier than Normal Testing During Annual Diesel Overhaul.Surveillance Callup Modified | | | 05000266/LER-1981-014, Forwards LER 81-014/01T-1 | Forwards LER 81-014/01T-1 | | | 05000266/LER-1981-014-01, /01T-1:on 811010,while Performing Refueling Leakage Tests of Containment Isolation valves,4-inch Check Valve in Svc Air Supply Found to Have Leakage Exceeding Tech Specs.Caused by Foreign Matl in Internals | /01T-1:on 811010,while Performing Refueling Leakage Tests of Containment Isolation valves,4-inch Check Valve in Svc Air Supply Found to Have Leakage Exceeding Tech Specs.Caused by Foreign Matl in Internals | | | 05000266/LER-1981-015-01, /01T-0:on 811010,during Refueling Outage,High & Low Head Safety Injection Check Valve Leakage Test Indicated Excessive Leakage.Cause Not Stated.Affected Line Flushed & Passed Retest | /01T-0:on 811010,during Refueling Outage,High & Low Head Safety Injection Check Valve Leakage Test Indicated Excessive Leakage.Cause Not Stated.Affected Line Flushed & Passed Retest | | | 05000266/LER-1981-015, Updated LER 81-015/01T-1:on 811010,high & Low Head Safety Injection Check Valve Leakage Test Indicated Leakage in Excess of Acceptable Criteria for 1-853C.Cause Not Stated. Affected Line Flushed & 1-853C Retested | Updated LER 81-015/01T-1:on 811010,high & Low Head Safety Injection Check Valve Leakage Test Indicated Leakage in Excess of Acceptable Criteria for 1-853C.Cause Not Stated. Affected Line Flushed & 1-853C Retested | | | 05000266/LER-1981-016, Forwards LER 81-016/01T-0 | Forwards LER 81-016/01T-0 | | | 05000266/LER-1981-016-01, /01T-0:on 811016,vendor Notified of Unusually High Failure Rate of Westinghouse Nbfd Relays Upon de-energization.Caused by Voltage Spike.Gradual Replacement of Designed Relays or Coils Planned | /01T-0:on 811016,vendor Notified of Unusually High Failure Rate of Westinghouse Nbfd Relays Upon de-energization.Caused by Voltage Spike.Gradual Replacement of Designed Relays or Coils Planned | | | 05000266/LER-1981-017, Forwards LER 81-017/01T-0 | Forwards LER 81-017/01T-0 | | | 05000266/LER-1981-017-01, /01T-0:on 811030,during refueling,10 Tubes in a Steam Generator & 7 Tubes in B Steam Generator Found to Exceed Tech Specs.Caused by Caustic.Crevice Flush Planned Before Startup & Defective Tubes Sleeved | /01T-0:on 811030,during refueling,10 Tubes in a Steam Generator & 7 Tubes in B Steam Generator Found to Exceed Tech Specs.Caused by Caustic.Crevice Flush Planned Before Startup & Defective Tubes Sleeved | |
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