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Category:Letter
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2024-02-05
[Table view]
Category:Licensee Event Report (LER)
MONTHYEAR05000244/LER-2017-0012017-06-16016 June 2017
During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction., LER 17-001-00 for R. E. Ginna re During Surveillance Testing, Lift Pressure Setpoints on Three Main Steam Safety Valves Found Outside Technical Specifications Limits Due to Stiction
05000244/LER-2016-0012016-04-0707 April 2016
Loss of Station Auxiliary Transformer 12A resulting in automatic start of Emergency Diesel Generator A due to undervoltage signals to safeguards buses 14 and 18., LER 16-001-00 for R. E. Ginna Nuclear Power Plant Regarding Loss of Station Auxiliary Transformer 12A Resulting in Automatic Start of Emergency Diesel Generator A due to Undervoltage Signals to Safeguards Buses 14 and 18
ML0509600362004-12-17017 December 2004
Final Precursor Analysis - Ginna Grid Loop
ML0429403762004-10-12012 October 2004
LER 04-S01-00 for R. E. Ginna Regarding Safeguards Event
ML0202800752002-01-22022 January 2002
LER 01-S01-00 for R E Ginna Nuclear Plant Re Safeguards Event
ML18142A8511978-09-14014 September 1978
LER 1978-007-00 for R. E. Ginna, Bus 16 Circuit Breaker for B Emergency Generator
ML18142A8761978-08-0303 August 1978
LER 1978-006-00 for R. E. Ginna, Main Steam Line Snubbers, Positions MS146 Top and Bottom
ML18142A8771978-06-0606 June 1978
LER 1978-007-01 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump
ML18142B2141978-05-0202 May 1978
LER 1978-005-00 for R. E. Ginna, Unplanned Reactivity Insertion of More than 0.5% K/K While Subcritical
ML18142B2131978-03-31031 March 1978
LER 1978-004-00 for R. E. Ginna, Motor Control Center 1C Circuit Breaker to Motor Control Center 1H Trip
ML18142B2171978-02-10010 February 1978
LER 1978-002-00 for R. E. Ginna, Power Range Low Range Trip Set Point Test
ML18142B2191978-02-0808 February 1978
LER 1978-003-00 for R.E. Ginna, B Steam Generator Tube Leak
ML18142B2221977-07-18018 July 1977
LER 1977-008-00 for R.E. Ginna, B Steam Generator Tube Leak
ML18192A0761977-07-0707 July 1977
LER 1977-006-00 for R.E. Ginna, C Charging Pump Varidrive on 6/19/1977
ML18142B2281977-06-0808 June 1977
LER 1977-024-00 for R.E. Ginna, Accumulation of Borated Water Near a Valve in Safety Injection System Piping
ML18142B2291977-05-27027 May 1977
LER 1976-027-03 for R.E. Ginna, Leak in Letdown Diversion Line on 12/16/1976, and LER 1976-030-03 a Mixed Bed Demineralizer Inlet Piping Leak
ML18142B2351977-05-16016 May 1977
LER 1977-003-00 for R.E. Ginna, Abnormal Degradation of Steam Generator Tubes
ML18142B2211977-03-31031 March 1977
LER 1977-007-00 for R.E. Ginna, Bus 14 Breaker for C Safety Injection Pump
ML18142B2381977-01-27027 January 1977
LER 1977-01-00 for R. E. Ginna, Bus 14 Circuit Breaker for C Safety Injection Pump
ML18142B2401977-01-12012 January 1977
LER 1976-030-00 for R.E. Ginna, a Mixed Bed Demineralizer Inlet Piping Leak
ML18142B2431977-01-11011 January 1977
LER 1976-029-00 for R. E. Ginna, Unit 1, Core Quadrant Power Tilt Ratio Calculation in Excess of Limit During Dropped Rod Condition
ML18142B2421977-01-11011 January 1977
LER 1976-028-00 for R. E. Ginna, Unit 1, on Control Rod F-12 Dropping Into Core During Operation at Reduced Load for Condenser Work
ML18142B2441977-01-0404 January 1977
LER 1976-027-00 for R. E. Ginna, Unit 1, Liquid Leak Through Insulation on 2 Letdown Diversion Line
ML18142B2461976-12-0808 December 1976
LER 1976-026-00 for R. E. Ginna, Unit 1, Controller Output for Cv Spray Naoh Valve 836A Was Less than 10 Ma
ML18142B2471976-11-0909 November 1976
LER 1976-025-00 for R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent
ML18142B2491976-10-22022 October 1976
LER 1976-024-00 for R. E. Ginna, Unit 1, Accumulation of Borated Water Near Valve in Safety Injection System Piping Between Boric Acid Tanks and Safety Injection Pumps
ML18142B2521976-09-14014 September 1976
LER 1976-023-00 for R. E. Ginna, Unit 1, Incorrect Piping Installation for Modification SM 75-9.21
ML18142B2531976-08-19019 August 1976
LER 1976-022-00 for R. E. Ginna, Unit 1, Error in Westinghouse Safety Analysis Methods
ML18142B2571976-08-19019 August 1976
LER 1976-021-00 for R. E. Ginna, Unit 1, D Bank Group 2 Rcc'S G-3 and G-11 Partially Dropped Into Core
ML18142B2761976-07-19019 July 1976
LER 1976-20-00 for R.E. Ginna, a Accumulator Level Below Technical Specification Limit
ML18142B2721976-07-16016 July 1976
LER 1976-19-00 for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor. for R. E. Ginna, Release of Liquid Radioactive Waste Without Continuous Operation of a Gross Activity Monitor
ML18142B2751976-07-16016 July 1976
LER 1976-20-00 for R.E. Ginna, Unit 1, on Completion of Monthly Surveillance Test of 1A Emergency Generator (Eg), Operator Opened Bus 14 Breaker from Eg and Received Diesel Generator Supply Breaker Overcurrent Trip Alarm
ML18142B2741976-07-16016 July 1976
LER 1976-20-00 for R. E. Ginna, on Completion of Monthly Surveillance Test of 1A Emergency Generator (Eg), Operator Opened Bus 14 Breaker from Eg and Received Diesel Generator Supply Breaker Overcurrent Trip Alarm
ML18142B2781976-06-21021 June 1976
R. E. Ginna - Supplemental Report on LER 1976-10-00, R. E. Ginna Plant, Containment Purge Supply Valve Having Excessive Leakage During Testing
ML18142B2801976-06-0404 June 1976
LER 1976-016-00 for R.E. Ginna, Rod Position Deviation Channel Was Found to Be Inoperable
ML18142B2821976-05-24024 May 1976
LER 1976-015-00 for R.E. Ginna, Air Ejector and Blowdown Radiation Monitors Alarmed
ML18142B2841976-05-11011 May 1976
LER 1976-013-00 for R.E. Ginna, Drop of Two Control Rods
ML18142B2851976-05-10010 May 1976
LER 1976-014-00 for R.E. Ginna, N44 Power Range Detector High Voltage Power Supply Failure
ML18142A9761976-04-23023 April 1976
LER 1976-012-00 for R.E. Ginna, Containment Personnel Airlock Handwheel Shaft Seal Excessive Leakage During Testing
ML18142A9791976-03-22022 March 1976
LER 1976-010-00 for R. E. Ginna, Containment Purge Supply Value Excessive Leakage During Testing
ML18142A9781976-03-19019 March 1976
LER 1976-011-00 for R.E. Ginna, Zero Flow Indicated for Cleanup Filtering Path in Charcoal Filter in Control Room Ventilation System
ML18142A9801976-03-12012 March 1976
LER 1978-009-00 for R. E. Ginna, Bus 18 Breaker from a Emergency Generator Overcurrent Relay
ML18142A9811976-03-11011 March 1976
LER 1976-008-00 for R. E. Ginna, Abnormal Degradation of Steam Generator Tubes
ML18142A9831976-02-28028 February 1976
LER 1976-007-00 for R. E. Ginna, Concerning Relay for Train a Containment Isolation and Containment Ventilation Isolation Failure to Latch
ML18143A4971976-02-19019 February 1976
LER 1976-006-00 for R.E. Ginna, Malfunction of Undervoltage Relay During Surveillance Test on 2/6/1976
ML18142B8941976-02-0606 February 1976
LER 1975-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage
ML18142B8931976-02-0606 February 1976
LER 1976-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage
ML18142B8951976-01-26026 January 1976
LER 1975-013-00 for R. E. Ginna, 30 Day, B Steam Generator Tube Degradation
ML18142B8961976-01-0808 January 1976
LER 1975-012-00 for R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak
ML18142B8971976-01-0808 January 1976
LER 1975-012-00 for R. E. Ginna, (30-Day Report), Charging Pump Discharge Drain Line Pinhole Leak
2017-06-16
[Table view] |
Text
NRI DISTRIBUTION FOR PART 50 DO T MATERIAL (TEMPORARY FORiVI)
Pp CONTROL NO:
FILE. INCIDENT REPORT FILE FROM. Rochester Gas and Electr DATE OF DOC DATE R EC'D LTR TWX RPT OTHER Corp Rochester, N..Y.
L.D White Jr 8-22-75 8-26-75 TO: ORIG CC OTHER SENT AEC PDR Mr James P.O'Reilly not sigHed SENT LOCAL PDR CLASS UNC LASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
50<<244 DESCRIPTION: ENCLOSURES:
Ltr trans the following: Abnormal Occurrence'f75-13 on 8-15-75'.
concer'ning the transfer of r'efueling water to containment basement ~
', ~ ~ ~
PLANT NAME FOR ACTION/INFORMATION >V ~8"-"26"-75 JGB BUTLER (L) SCHWENCER (L) ZIEMANN (L) ~
REGAN (E)
W/ Copies W/ Copies Ml/ Copies W/ Copies CL~RK (I.) STOLZ (L) DICKFR (E) LEAR (L)
W/ Copies Ml/ Copies W/ Copies W/ Copies PARR (L) VASSALLO (L) KNIGHTON (E) SPELS W/ Copies W Copies Ml/ Copies Ml/ Copies KNIEL (L) RPLE (I ) YOUNGBLOOD (E}
Ml/ Copies opies W/ Copies W/ Copies INTERNAL DISTRIBUTION TECH R EVI EW DENTON LIC ASST A/T I ND
~NRC PDR ~SCHROEDER "-'GR IMES R. DIGGS ILI BRAITMAN OGC, ROOMi P-50GA ~ACCARY GAMMILL H. GEARIN (L) SALTZMAN GOS" ICK/STAF F KNIGHT KASTNFR E. GOULBOURNE (L) MELTZ ~
~CASE PAW! ICKI BALLARD P. KREUTZER (E)
GIAMBUSSO SHAO SPANGLER J. LEE (L) PLANS BOYD "~~ STE LLO M. RUSHBROOK (L) IViCDONALD MOOR E,(L) ~"-~ HOUSTON E NVI RO S. RFED (E) CHAPMAN.
DEYOUNG (L) "'"'OVAK MULLER M. SERVICE (L) DUBF (Ltr)
SKOVHOI T (L) ~ROSS DICKER HSHEPPARD (L) E. COUPE GOLLER (L) (Ltr) ~ IPPOLITO KNIG HTON M: SLATER (E) PETERSON P. COLLINS /TEDESCO YOUNGBLOOD H. SMITH (I.} HARTFIELD (2)
DENISE J. COLLINS REGAN S. TEETS (L) n KLECKER REG OPR LAINAS P ROJ EC1 LD R G. WILLIAMS(E) EISENHUr WFlIi E 5 REGION (2) BENAROYA V, Wll SON (L) 'WIGG)NTOiU
~ . ~'IPC/P (3) ~VO L LME R HAR LESS, R. INGRAM (L) ~ F. WILLIA~IS STEELE M, DUNCAN ~
DISTRIBUTION HA'XTFRNAL LOCAL PDR Lynons, N,Y, and Rochester, N Y~
~1 1 IC (ABERNATHY) (1)(2)(10) NATIONALLABS 1 PD R-SAN/LA/NY
~1 NSIC (BUCHANAN) 1 W. PENNINGTON, Rm E-201 GT 1 OROOKHAVEN iUAT LAB 1 ASLO 1 CONSULTANTS 1 G. ULR IKSON, ORNL AGMED (RUTH GUSSMAN)
~- 1 Newton Anderson ACRS SEiiT TO LIC ASST SEND ONLY TEN DAY REPORTS NF WMARK/BLUME/AGBABIAN 1 Rm B-127 GT 1 J. D. RUNKLES, Rm E-201 GT
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ROCHESTER GAS AND EL,ECTRIC CORPORATIOH o 85'AST AVENUE, ROCHESTER, M.Y. 14649 I.roN D. ivlfITE> JB, Il.hfi'iqOHE VICE PACSIDCtiT inc~ ceae vie 5.46-2700 August 22, 1975 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 'i) c 631 Park Avenue King of Prussia, Pennsylvania 19406 Wry )(
Subject:
Abnormal Occurrence 75-13, Transfer of refueling water to containment basement R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244
Dear Mr. O'Reilly:
In accordance with Technical Specifications, Article 6.6.2a, the attached report of Abnormal Occurrence 75-13 is hereby submitted. Two additional copies of this letter and the attachment are enclosed.
Very truly yours,
~idler d~,
L. D. White, P Jr.
~-
Attachment cc: Mr. Donald P. Knuth (40)
Mr. William G; McDonald '(1) ~
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~UGLY hg75
- ,g; UCENSEE EVENT REPCI(ITe CONTROL 8LOCK
- (PLEASE PRIF4T ALL REQUIRED INFORMATIDN)
LICENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPF Qg09 N Y R E C' 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~0 '1 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE
~o< coNT ~DI T L 0 5 0 0 2 4 4 0 8 1 5 7 5, 0 8 2 2 7 5 7 8 57 58 59 60 61 68 69 74 75 60 EVENT DESCRIPTION
~02 Durin erformance of eriodic test PT-2. 3 Safe uard Valve eration a flow ath 7 8 9 80
[oD3] from refueling water storage tank RWST to containment sum B was inadvertentl esta 7 89 80 t00j4 lished and containment'integrity requirement was violated. Upon receipt of alarms and 7 8 9 80
[oa~l evaluating indications, operator immediately secured flow path. A similar ocCIIrrence, 7 0 9 7
Jog 0 S which did not involve containment inte rit, was re orted as AO 75-10.
80 SYSTEM CAUSE PRME Abnormal Occurrence 50-244 75-13) 80 COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER 'L00LATIDN Q<zj ~SP ~A V A L V E X E H 9 9 9 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION 7
[oaf 8 9 Q erator closed MOV-851B erroneousl reo ened it before the next ste to stroke 80
~09 MOV-850B, and initialed the procedure step "Close MOV-851B" . He noted it was time 7 8 9 80
~10 for his hourly readings and turned to the Head Control (cont'd. on attached sheet) 7 89 80 STATUS 'OWER FACILITY, OTHER STATUS METHOD OF DISCOVERY Qg 7 8 9 E ~io o 10 12 13 NA 44 a
DISCOVERY DESCRIPTION Operator observations after alarms FORM OF 45 46 ACTNITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q~g H z NA NA 7 8 9 10 11 44 45 00 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q~jo ~00 0 E NA 7 8 9 11 1'2 13, 80 PERSONNEL INJURIES NUMBER DESCRIPTION
[g09 7
~00 0 11 12 NA 80 OFFSITE CONSEQUENCES Qs]
7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION
[ice] H 7 89 10 80 PUBLiCITY 7 0 9 ADDITIONAL FACTORS Q~g Following evaluation of conditions it was learned that containment integrity requiremen 7 8 9 Qqg] was violated for approximately 3 minutes, and approximately(cont'd.on attached sheet) 7 09 00 NAIViE: Bruce A. Snow PHDNEI 7 16 546 2700, ext ~ 29 1-2 14 QI'i1 011 A*'l
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-Licensee Event R~~or 2.
50-&$ 4/75-13 Cause Descri tio'n cont'd.
Operator to ask him to take them. Returning to the procedure he saw that the next step a'fter the last step he had initialed was to open MOV-850B. Upon the opening of MOV-850B with MOV-851B open, flow was established from the RWST to Sump B.
The PORC recommended the following immediate remedial action:
- 1. Make an inspection of containment to evaluate the extent of any possible damage.
- 2. Pump out Sump B and inspect it for any debris, and inspect the Reactor Coolant Drain Tank located there for any possible damage.
- 3. Have health physics personnel evaluate the extent of airborne contamination.
4.. Reprimand the Control Room operator.
Further actions to prevent recurrence recommended by PORC are to change PT-2. 3 to incorporate requ'irements that
- 1. No other activities relative to maintenance or testing may b'e performed
'which may distract Control Room personnel involved in the performance of this test. In the event any emergency and/or unusual conditions develop, the test is to be terminated until such conditions cease to exist.
I
- 2. The Control Room personnel involved in the test will not have simultaneous Control Room responsibilities relative to normal duties and routine operations.
- 3. More definite precautions are to be added to PT-2.3 at the steps concerned involving valves which created the inadvertent flow path.
I Additional Factors cont'd.
k 12,000 gal. of refueling water was transferred to containment. The Technical Specification for RWST inventory was not violated. There were indications that approximately 1 inch of water had been on the floor. No damage to any safe-guards equipment was noted. Processing the developed waste water is being carried out according to normal procedures.
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Before.actually opc atiag the switch to close RDV-85iBB he placebo his ie-itiaXa Q the apace provided oa'tbo proccdura a1'ongside this operatioa He thea.aoticed that it Mne.tire &r hie'to get 'the 14&) Kf geaeratfoa reffdiqys p
cad he meeatarily turaod aul ashad the Read Coatrol Oporator to get the rend-
%age.~.btu" Be.'taraed arouffd to coatkaae,the procechxr'e and ha sap that tha otep"after the 1ast stop that..hi iaitis?ed van to Q~?SV&50B "Ho had ~
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7 II c~l le occurrence:
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1 never:cXoscd: 89V-05XB'e Wcn. ho opcxatcxF the switch to open; 80V-0508-ar ~
path'van open from the, Refueling; Hater Storage TanTic to contaiment Smrp. 9
-Shortly, after this. operation the. htgb XeveX alazsc in Sump 9 sounded in. the .
controL eocene follcrzcd chart Ey aftazwaxIda. by a. high XevaX aXszm. in. Su=p CL Sy the time. the operator rcaXf=cd-. what. hnd happened and .coulct get. l3Ã-85XE closc4 approximatoEy IZ 000 SaXXons of. ReMeing Pater Storage TaaEc water had run'nto Sump 9 avarHcrus6-onto thc containacnt. basement floor, and drained through. tha floor drains ta Sump fL %he appzoxianta tiara. that contcxxcment integrity. van .vfioXatecE ona 3 csinutes Tha PORC.saat. at: ISO, revkccced tha occurrence and made the foXZasring.
rccaumdntions."
(a) IhEce an Knspwtioa.of contatumnnt;.
(b) ReprimancE the contxoX racaa operator (c) Eave the Kcalth Phys%ca perammcE-:take a particuXatn aampXe in the baaeuent of containmant (d) Pump the water fanic Sump PI and ihspect the Sump. 8 area for any debris aud also: inspect CElL Reactor Coolant 9?Sin Tank vhich't@ Xocatcd in.
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iLn. inspection vas made of: containment at. I530 'Xhc: on1y evidence of the water vas several usmXX puddles oK water here and them. on. the floor, Sump B fuXL of.'water and'n indfcation. ia aevaraX- pIacea. that approxfanteZy X~
of water had been. on tha basement. floor She plant. continued operation. at XODX power. aX'I during tha occurrence and no operating problems hnvo been. encounteract since the occurrence CharXeadf Plat t,
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Superintendent. I I I ~
cc Cn Swsrhtoutq RG&E'orp L ",9~ Mhitc Jr~ RG&E Corp J~ F Swaeh'~ RG&R Corp 8 A Sacs RG&K Cozy I
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