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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000244/LER-1976-024, Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking1977-06-0808 June 1977 Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking 05000244/LER-1976-027, Updated LER 76-027/03O-1:on 761216,liquid Noticed Coming Through Insulation on 2-inch Letdown Diversion Line.Caused by Pinhole Leak in Socket Weld Between Pipe & Elbow.Section Line Replaced1977-05-27027 May 1977 Updated LER 76-027/03O-1:on 761216,liquid Noticed Coming Through Insulation on 2-inch Letdown Diversion Line.Caused by Pinhole Leak in Socket Weld Between Pipe & Elbow.Section Line Replaced 05000244/LER-1976-007, Revised LER 76-07/30:on 760207,relays for Train a Containment Isolation & Ventilation Isolation Failed to Latch.Caused by MG-6 Relays Having Improper Latch Screw Factory Adjustment1977-05-25025 May 1977 Revised LER 76-07/30:on 760207,relays for Train a Containment Isolation & Ventilation Isolation Failed to Latch.Caused by MG-6 Relays Having Improper Latch Screw Factory Adjustment 05000244/LER-1976-014, Updated LER 76-014/03O-1:on 760412,N44 Power Range Detector High Voltage Power Supply Failed.Caused by Defective Modular Block Part IV-101.Power Supply Recalibr1976-10-20020 October 1976 Updated LER 76-014/03O-1:on 760412,N44 Power Range Detector High Voltage Power Supply Failed.Caused by Defective Modular Block Part IV-101.Power Supply Recalibr 1977-06-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17265A7601999-10-0505 October 1999 Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis ML17265A7621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With 991008 Ltr ML17265A7531999-09-23023 September 1999 Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped ML17265A7541999-09-22022 September 1999 LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr ML17265A7471999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr ML17265A7431999-08-24024 August 1999 LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed ML17265A7341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr ML17265A7291999-07-29029 July 1999 Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent ML17265A7181999-07-23023 July 1999 LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians ML17265A7081999-07-22022 July 1999 LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored ML17265A7131999-07-22022 July 1999 Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521 ML17265A7031999-07-19019 July 1999 LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr ML17265A7211999-07-19019 July 1999 ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp. ML17265A7021999-07-15015 July 1999 LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr ML17265A7661999-06-30030 June 1999 1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With 991020 Ltr ML17265A7011999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr ML17265A6851999-06-21021 June 1999 LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr ML17265A6761999-06-16016 June 1999 Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis ML17265A6661999-06-0202 June 1999 LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr ML17265A6681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr ML17265A6651999-05-27027 May 1999 Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001 ML17309A6541999-05-27027 May 1999 LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr ML17265A6631999-05-24024 May 1999 LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved ML17265A6601999-05-21021 May 1999 LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr ML17265A6591999-05-17017 May 1999 Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested ML17265A6441999-05-13013 May 1999 LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr ML17265A6431999-05-12012 May 1999 LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed ML17265A6381999-05-0707 May 1999 Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG ML17265A6391999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr ML17265A6361999-04-23023 April 1999 Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001 ML17265A6301999-04-18018 April 1999 Rev 1 to Cycle 28 COLR for Re Ginna Npp. ML17265A6251999-04-15015 April 1999 Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment ML17265A6551999-04-0909 April 1999 Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open ML17265A6291999-03-31031 March 1999 Rev 0 to Cycle 28 COLR for Re Ginna Npp. ML17265A6241999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr ML17265A6141999-03-31031 March 1999 LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr ML17265A6131999-03-29029 March 1999 LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr ML17265A6061999-03-24024 March 1999 LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp ML17265A5661999-03-0101 March 1999 Rev 26 to QA Program for Station Operation. ML17265A5961999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr ML17265A5371999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr ML17265A5951998-12-31031 December 1998 Rg&E 1998 Annual Rept. ML17265A5001998-12-21021 December 1998 Rev 26 to QA Program for Station Operation. ML17265A4951998-12-21021 December 1998 LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr ML17265A4931998-12-17017 December 1998 LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery ML17265A4761998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr ML17265A4691998-11-25025 November 1998 LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR ML17265A4531998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr ML17265A4271998-10-0505 October 1998 LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr ML17265A4291998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr 1999-09-30
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LER-2076-024, Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking |
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2442076024R00 - NRC Website |
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iUi'NSEIS" $NT"iiNP CONTROL BLOCK:I l l I I I I. [ PLEA .E P. TINT ALL CEZullE']INFCRM AT1o?
1 6 UCENSE NuveE A PE YFE
, N ME oi l Nl Y l Rl E lGl 1l l Ol 0 l-l 0 l0 l 0 l 0 l 0 l-l 0 l 0 l l 4 l 1 l 1l 1l1l l0l1l 32 7 89 . 14 15 25 26 30 31
" REPORT CATE CATEGORY T7PY ONHCE
- OoCrET NuvetA ' EvtNT DATE E] con t i57 I I lo_l Lt_.1 101 s 101-1012 I 4 I 4 I 1110 f 0181716 I I Ol 6101817 ! e 7 8 58 59 60 61 = 68 69 74 75 E EVENT OEsCA:PTON -
f5[ij l During normal operations an auxiliar/ operator found an accumulation of borated water e
7 89 03 I near a valve in the Safety Injection System piping between the Boric Acid Tanks and E
7 09 Q l Safety Injection Pumps. Further investigation revealed a leak in a section of 8" E 7 53 9
@ l Schedule 10 stainless steel pipe between valves 826A and 826B. ~ The unit was taken E 7 89 oo l to cold shutdown as recommended by PORC. Leaks were (cont'd. on attached sheet) 6 7 89 pqug t CCct COMPONENT CODE
' C SER vcLATON E ISIFI [FJ 7 89 10 11 l el t le i Eix I xl 12 17 LN_j 43 44 lKI0l5l5l 47
[N_j 48 CAUSE OEsCAiPTION
] l As a result of metallurgical analysis and metallographic examinations, chloride stress b-7U9
{] l corrosion cracking is believed to be the cause of the leaks. As the investigation con-7 89 E
] l tinued, further information was submitted in a supplemental (cont'd. on attached sheet i
'stANs' % POWE A OTHER STATUS OSCOVERY OrSCOVEAY DESCA.PT:CN d [ E_j l1l0 l 0] l NA l [b_j l By operator 7 8 9 10 12 13 44 45 46 E.
A LE OF E AMOUNT OF ACTMTV LOCAT:ON CF AELEISE 1? l2l [e jASE l NA l 44 l
45 NA E.
7 8 9 10 11 PERSONNEL EXPOSURES NUWEA TYPE DESCALPTON M l0l0l0l [c] l NA 12 13 6, 7 89 11 PEAsONNEL lNJUA:Es
- NuvetA CESCA.PTON t .1 l0 l 0 l 0] l NA 7 89 11 12 c<
OFFsfTE CONsEOUENCEs is l NA 7 89 c.
Loss OR OAMAGE TO FAC!UTY Yvrf O(SCAIPTCN i yl See Event Description S;
7 89 10 PuBLCITY 37 l Press release on October 8,1976 7 89 El ADOITICNAL FACTOAs 8304070133 770608 PDR ADOCK 05000244 1e l NA g PDR 7 89 BC 19 l .
' Licensee Event Repo.s o '
o
. . Reportqble Occurrence 50-244/76-24 Event Description (cont'd.)
found in two sections of pipe, and 11guld penetrant and ultrasonic examina-tion of 75 welds and the piping associat4d with those welds 16 the boric acid tank outlet piping rev,ealed five other sections of pipe of fittings with indications. All seven of these components of the piping system containing leaks or indications were replaced. (Reportable Occurrence 76-24).
Cause Description (cont'd.) ,
report, dated February 10, 1977, which supported this conclusion, and pro-vided the corrective action performed and being considered. The supplemental report also described our December 21, 1976 response to IE Circular 76-06 which stated that during the 1977 refueling and maintenance out, age additional testing and examination would be performed on piping and selected welds in the containment spray and safety injection systems.
During the 1977 refueling and mainten.Ince outage the boric acid storage tank outlet piping was modified to eliminate all inaccessible portions. The exam-inations and testing consisted of the following:
- 1. Nine welds in the Boric Acid Piping were ultrasonically examined. As this included the remaining two welds which were previously inaccessible, all the welds of the heat traced boric acid supply piping to the safety injection pumps have been ultrasonically examined.
- 2. Five welds in the Containment Spray Pump Discharge piping inside con-tainment were ultrasonically examined.
- 3. The Boric Acid Piping to the Safety Injection Pumps and the containment spray pump suction piping was hydrostatically tested to 280 psig (mini-
- mum). .
- 4. The containment spray pumps discharge piping was.hydrostatically tested to 380 psig (minimum).
- 5. The Safety Injection Pumps Discharge Piping was hydrostatically tested to 1880 psig (minimum).
- 6. The Spray Additive Tank was pressure tested, using a nitrogen medium, to 375 psig (minimum). ,
All welds and piping inspected and tested as listed above were found to be acceptable. The welds and piping in the Safety Injection and Containment Spray Systems will continue to be examined in accordance with the require-ments of the Ginna Station Inservice Inspection Program to assure the continued integrity of these systems.
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ROCHESTER GA$ AND ELECTRIC CORPORATION e 89 EAST AVENUE, ROCHESTER, N.Y.14649 ft.cpac ,
LEON O WHITE. JR. e aan. con t.* 5.:6 2700 vica cas e.oene I ro' /
June 8,1977 [- ~
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bhfb Ji.t /t.J
'Is I\
SEP291977
Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission '2 "*5'To30[s T*M
' x Office of Inspection and Enforcement N Region I 4
631 Park Avenue King of Prussia, Pennsylvania 19406 .
Subject:
Supplemental repcrt on Reportable Occurrence 76-24, leaks in schedule 10 boric acid piping R. E. Ginna Nuclecc Power Plant, Unit No.1 Docket No. 50-244
Dear Mr. O'Reilly:
In a supplemental report dated February'10,1977 on the subject Reportable Occurrence it was stated that during the 1977 refueling and maintenance outage additional testing and examinations would be performed on piping and selected welds in the safety injection and containment spray systems . The attached update report LER 76-24/10 provides the results of this investigation.
Two additional copies of this letter and the attachment are enclosed to conform to the original sub*nittal of LER 76-24/1T.
Very truly yours,
- p. .
L. D. White , Jr.
cc: Dr. Ernst Volgenau (40)
Mr. William G. Mcdonald (3) -
l l
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05000244/LER-1976-007, Revised LER 76-07/30:on 760207,relays for Train a Containment Isolation & Ventilation Isolation Failed to Latch.Caused by MG-6 Relays Having Improper Latch Screw Factory Adjustment | Revised LER 76-07/30:on 760207,relays for Train a Containment Isolation & Ventilation Isolation Failed to Latch.Caused by MG-6 Relays Having Improper Latch Screw Factory Adjustment | | 05000244/LER-1976-014, Updated LER 76-014/03O-1:on 760412,N44 Power Range Detector High Voltage Power Supply Failed.Caused by Defective Modular Block Part IV-101.Power Supply Recalibr | Updated LER 76-014/03O-1:on 760412,N44 Power Range Detector High Voltage Power Supply Failed.Caused by Defective Modular Block Part IV-101.Power Supply Recalibr | | 05000244/LER-1976-024, Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking | Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking | | 05000244/LER-1976-027, Updated LER 76-027/03O-1:on 761216,liquid Noticed Coming Through Insulation on 2-inch Letdown Diversion Line.Caused by Pinhole Leak in Socket Weld Between Pipe & Elbow.Section Line Replaced | Updated LER 76-027/03O-1:on 761216,liquid Noticed Coming Through Insulation on 2-inch Letdown Diversion Line.Caused by Pinhole Leak in Socket Weld Between Pipe & Elbow.Section Line Replaced | |
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