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Category:Letter
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Initial Operator Licensing Examination Report 05000244/2022301
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Re. Ginna Nuclear Power Plant - Annual Commitment Change Notification
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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
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NR STRIBUTION FOR PART 50 DOCK MATERIAL (TEMPORARY FORM)
CONTROL NO:
FI LE. INCIDENT REPORTs 'FIL'E' ROM: Rochester Gas 6, El.ec. Co DATE OF DOC DATE REC'D LTR TWX RPT OTHER Roches ter, No Y, 4-7>>75 4-16-75 TO: ORIG CC OTHER SENT AEC PDR James P. O'Rbilly 1sSigned SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO XX DESCRIPTION: ENCLOSURES:
Le"ttei "trans" the folloM':ng... Abno'r, Occurr. 8 751"-07 , on 3 '24-'75, con-cerning degradation of steam Generator Tub es ~ ~ ~ o
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ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, LEON O. WHITE, JR. TELEPHONE VICE PRE8IDENT AREA CODE Tld 546-2700 April 7, 1975 cpQ
~rqLO DO '~T,O u~
Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission ij "V- EQ j>> /
Office of Inspection and Enforcement Region I ~s'6oo gsu g(o8c (- )(jpCP'"
DosLoI 631 Park Avenue King of Prussia, Pennsylvania 19406
Subject:
Abnormal Occurrence 75-07, Abnormal degradation of steam Generator Tubes 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 75-07 is hereby submitted. Two additional copies of this letter and the attachment are enclosed. '
more detailed report is being prepared and a copy will be forwarded upon completion.
Very truly yours, r ~
L. D. Whi, Jr.
Attachment cc: Mr. Donald F. Knuth (40)
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LICENSEE EVENT REPORT CONTROL BLOCK: (PLEASE PRINT ALL REQUIRED INFDRMATIDN) 1 UCEN SEE UCENSE EVENT NAME LICENSE NUMBER TYPE TYPE
[oaj N Y R 2 GI 0 0 0 0 0 0 0 0 0 4 I 1 I I ~01 7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE OOCKET NUMBER EVENT OATE REPORT OATE
[on~]coo7 ~MI T L. 0 5 0 0 2 4 4 3 2 4 7 5 0 4 0 7 7 5 7 8 57 58 59 60 61 68 69 74 75 80 I
EVENT DESCRIPTION
[oO~] During eddy current ins pection of Steam Generator (SG) tubes results. showed 10 "A" SG 7 8 9 80 hot leg tubes and 12 "B" SG hot leg tubes with wall thinning of 50% or reater Tube ~
7 8'9 80 Qp~] thinning in the "A" SG was previously reported, AQR 74-02, on 2/19/74 with a follow-7 8 9 80 Qpg up report on 3/21/74. The above tubes are to be plugged. (Abnormal Occurrence 7 8 9 80 Qpg 50 244/75 07) 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COBE CODE COMPONENT COOE SUPPLER MANUFACTURER VCIATION
~CI B H T B X C H ~N W 1 2 0 ~N 7 8 9 10 11 12 17 43 44 x 47 48 CAUSE DESCRIPTION
[ops] Local corrosion of tube QD surface is believed to have been caused by phosphate 7 8 9 80
[oO~] residue not removed on change to AVT chem. control. SG descri tive data and 7 8 9 80
~10 measures to prevent recurrence are on attached page.
7 89 FACIUTY METHOO OF 80 STATUS POWER OTHER STATUS DISCOVERY OISCOVERY OESCRIPTION Pig a ~00 0 N/A eddy current test of tubes 7 8 9 10 12 13 44 45 46 80 FORM OF AMOUNT OF ACTIVITY LOCATION OF RELEASE N/A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION Pg~oo 7 89 o B 12 13 NA 11 80 PERSONNEL INJURIES NUMBER OESCRIPTION
(+4 ~0o o N/A 7 89 11 12 80 OFFSITE CONSEQUENCES N/A 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION P N/A 7 89 10 80 PUBLICITY 7 89 80 ADDITIONAL FACTORS
~18 Shell side sludge removal was done 3/74 and ll/74. An AVT S. G. chem. control 7 89 80
~19 program, was started ll/74 and adherence to this has been good to date.
7 89 80 NAME: L. D. White, Jr. PHDNE, 7 1 6/546-2700, ext. 2420 GPO 861 667
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Licensee Event Report 2.
50-244/75-07 Steam Generator Descri tive Data:
The steam generators are Westinghouse series 44, using Inconel series 600 tubes, size 0. 875" OD, with . 050" walls.
Measures to Prevent Recurrence:
- a. The shell side of the tube sheets will be cleaned using a high pressure water lance against attack which may be due to any remaining phosphates or caustics contained in sludge.
- b. For further information on the tube degradation mechanism, at least two
<ub~-.tube-ends are to be extracted from the steam generators.
- c. A series of mechanical modifications is being considered to decrease the area of the tube sheet which is susceptible to low flow conditions and s ludge buildup.
- d. A high blowdown rate during varying steam generator conditions will be continued to minimize dissolved and suspended solids, consistent with recommended all volatile treatment (AVT) steam generator chemistry control.
- e. In the event that sludge accumulation continues to be observed in future shutdowns, additional lancings may be considered to lower residual phosphate levels in the steam generators.
0 I
