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Category:Letter
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R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 155 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1
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ML23060A1622023-03-0101 March 2023
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Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators
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R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request
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Initial Operator Licensing Examination Report 05000244/2022301
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R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
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Re. Ginna Nuclear Power Plant - Annual Commitment Change Notification
RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022
Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator
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
~ U.S. NUCLEAR REGULATORY COMMISSION DOCKET NUMBER FILE NUMBER NRC DISTRI8UTION FDR PART 50 DOCKET MATERIAL INCIDENT REPORT FROM:ROCHESTER GAS & ELEC. CORP. DATE OF J.P.O'REXLLY, DOCUMENT'ATE ROCHESTER, N.Y.
'L.D. WHITE, JR. ~ RECEIVED Q LETTE R ONOTOAIZED PROP INPUT FOAM NUMBER OF COPIES RECEIVED QOAIGINAL EBUNCLASSIFIED K)CO> Y DESCAIPTION ENCLOSURE 1'TR'RANS THE FOLLOWXNG UBDATE LICENSEE EVENT REPORT /f 76-27, 30 DAY ON 12/16/76 CONCERNING LIQUID COMING THROUGH INSULA ION ON 2" LE'ZDOWN DIVERSION LINE.......
I:. ~
UPDATE LICENSEE EVQP REPORT 1/ 76-30, 30 DAY ON (1P) . 12/17/76. CONCERNIg+LXQUPJ"%EARP, FROM THE "A" MIXED. BED SEMINERAL'IZQR I%K'ET~~QIg M k4I II';I)K:
PLANT NAME' E GINNA 4/
I" SAB NOTE ~ IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/Jo COLLINS FOR ACTION/INFOFIMATI ON
'RANCH CHIEF!
W 3 CYS FOR ACTION LIC, ASST'!
W /CYS ACRS / CYS 14Ch5%NG S NT INTERNAL DISTRI BUTION
'NRC PDR MIPC
~ SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES BUTLER IIANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS EANAL DISTRIBUTION CON OL NUMBER LPDR:
TIC:
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'iI'4'"7/ "'"PW Pi i't.i<IL'/74Ii W'"W ROCHESTER GAS AND ELECTRIC CORPORATlON 89 EAST AVENUE, ROCHESTER,, N.Y. 14649 LEON D. WHITE. JR. TCLCPNONC VICC PACSIDCNT iPCi CONC TIO 54G 2700 May 27, 1977 r
Mr. James P O'Reilly, Director
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8 > ge 'Ctt U. S. Nuclear Regulatory Commis%%8 g UN 2 3977~
Office of inspection and Enforcement Region I
'EI re' ~I g..S. IIIIC'C">RUU5h5kV
>Ncll54rtbe 63 1 Park Avenue King of Prussia, Pennsylvania 19406
Subject:
Supplemental reports on Reportable Occurrences:
76-27 (30-day report) Leak in letdown diversion line 76-30 (30-day report) "A" mixed bed demineralizer inlet piping leak R. E. Qinna Nuclear Power Plant, Unit No. 1 Docket No. 50-244
Dear Mr. O'Reilly:
The purpose of this letter is to provide you with corrected component manufacturer information in connection with the subject reports which were submitted January 4 and January 12, 1977 respectively. The attached update reports LER 76-27/30 and LER 76-30/30 provide this information.
Two additional copies of this letter and the attachments are enclosed to conform to the original submittal of LER 76-27/3L and LER 76-30/3L.
Very truly yours, L. D. White Jr.
cc: Dr. Ernst Volgenau (30)
Mr. William G. McDonald (3)
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LER 76-27/30 Update Report Previous Report Date 1/4/77 CONTROL BLOCK:
Q.IOENSEE EVENT REPORT
+
fPLEASE PAINT ALL REQVIREO IiNFORIViATION)
LICENSEE UCENSE EVENT NAME UCENSE NUMBER TYPE TYPE
[op~j N Y R B G 1 0 0 0 0 0 0 0 0 0 O 1 1 1' ~03
~
7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE 0
7
[oO~]corn 8 57 58 0
59 L
60 61 0 5 0 2 4 4 68 69 1 2 1 6 7 6 74 '50 5 2 7 7 7 80 EVENT DESCRIPTION gg During normal rounds operator noticed liquid coming through insulation on 2" letdown 7 8 9 80 tOQ3) diversion line ~ Upon return to steady state letdown condition, line was isolated ~
7 89 80 (Reportable Occurrence 76-27, 30-day) .
7 8 9 80 toom 7 8 9 80 tm 7 8 9 PA VIE 80
. SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER VGIATION
[ocvj ~CG B P I P B X X ~N B 1 3 0 N 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION A pinhole leak was found fn socket weld between pipe and elbow. Weld was built up 7 8 9 80
~09 in area of leak, and a visual inspection performed upon return of system to service ver 7 8 9 80 Q~g ified leak was stopped. This section of line was (cont'd. under Additional Factors) 7 89 80 FACILITY METHOD OF STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION gg8 7 9 B ~io 10 o
12 13 NA 44 b
45 46 0 erator makin rounds FORM OF
. 80 AMOUNT OF ACTIVITY LOCATION OF RELEASE 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7 89 11 12 13 80 PEFISONNEL INJURIES NUMBER DESCRIPTION
~4 ~oo o NA 7 8 9 . 11 12 80 OFFSITE CONSEQUENCES NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION
~16 NA 7 89 10 80 PUBLICITY 7 89 80 ADDITIONAL FACTORS
[J>QB (cont'd. from Cause Description) replaced during refueling shutdown to remove weld 7 89 80 Qg 7 89 which had been leaking. CAR llllwas issued to document this corrective action.
80 NAME: ames Witte/D. Hamelink pgONE', 7 1 6/546-2 700, ext. 29 1 -2 1 5 GPO 661 6 61
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~ l e LER 76-30/30 UDdate Report Previous Report Date 1/12/77 CONTROL BLOCK
~ ICENSEE EVENT REPORT fPLEAGE PRINT ALL RECIUIRED INFORMATION) 1 6 UCENSEE LICENSE EVENT NAME LICENSE NUMBEA TYPE 'TYPE Qg09 N Y R E G 1 0 0 0 0 0 4 LBO~J
~
7 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE AEPOAT DATE
~cl cowl 0 L 0 5 0 0 2 4 4 1 2 1 7 7 0 5 2 7 7 7 7 8 57 58 59 60 61 68 69 74 75 80 I
EVENT DESCRIPTION During normal rounds an operator discovered liquid leaking from the "A" mixed bed 7 8 9 80 demineralizer inlet pipe . (Reportable Occurrence 76-30, 30-day) .
7 09 80 t00j4 7 8 9 80 Jog 7 0 9 80
[0DQ 7 09 PAVE 80 SYSTEM CAUSE COMPONENT COMPONENT MANUFACTUREA
~IB CODE CODE COMPONENT CODE SUPPUER VIOIATKIN tocC>~ILcGCa P I P E x x N B 1 3 0 N 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION Q~g Pinhole leak in weld between pipe and elbow. Hole was ground out and repaired using 7 0 9 80
[pgg] proper welding procedure. The piping was visually inspected for leakage after return 7 8 9 80 Q~g to service. CAR 1114 was issued for this event.
7 89 METHOD OF 80 FACILITY STATUS POWER OTHER STATUS DISCOVERY ~ DISCOVERY DESCRIPTION 7
Eg 0
LEJ 9
~io 10 o
12 13 NA 44 45 b
46 0 erator makin rounds FOAM OF 80 ACTIVITY COATENT AELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Qg H sj NA 7 8 9 10 11 44 45 00 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Pg~oo 7 8 9 o B 12 13 NA 11 80 PERSONNEL INJURIES NUMBER DESCRIPTION fig ~00 0 NA 7 09 ~
11 12 80 OFFSITE CONSEQUENCES Qg NA 7 09 00 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g s 7 09 10 80 PUBLICITY Q~~] ~ e ~ i +II'lI Ej
$ Pl, 7 89 80 ADDITIONAL FACTORS l,lJ ~
NA 7 89 80 7 09 80 NAME: , Dave Hamelink PHDNL.".
7 1 6/5 4 6 2 7 0 0, ex t ~
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