Similar Documents at Ginna |
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Category:Letter
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R. E. Ginna Nuclear Power Plant Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0029 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
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ML23317A1192023-11-10010 November 2023
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Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans
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ML23158A1952023-08-30030 August 2023
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ML23235A1722023-08-23023 August 2023
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LLC - Material Control and Accounting Program Inspection Report 05000244/2023401 (Cover Letter Only)
IR 05000244/20230022023-08-0303 August 2023
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ML23191A0592023-07-21021 July 2023
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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R. E. Ginna Nuclear Power Plant - Security Baseline Inspection Report 05000244/2023402 (Cover Letter Only)
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Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.
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2022 Annual Radioactive Effluent Release Report and 2022 Annual Radiological Environmental Operating Report
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ML23075A0872023-03-15015 March 2023
R. E. Ginna Nuclear Power Plant - Project Manager Assignment
ML23061A1632023-03-0303 March 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3
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ML22364A0242023-03-0101 March 2023
R. E. Ginna Nuclear Power Plant Issuance of Amendments Nos. 231, 231, 232, 232, and 154 Regarding Adoption of TSTF-246
ML23060A1622023-03-0101 March 2023
R. E. Ginna Nuclear Power Plant, Supplemental Information - Proposed Alternatives Related to the Steam Generators
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Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203
ML23005A1762023-02-23023 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 153 Revise Technical Specifications (TS) for the Spent Fuel Pool Charcoal System and Two (2) TS Administrative Changes
ML23005A1222023-02-22022 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Amendment No 152 Adopt TSTF-315-Revise Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2
RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023
Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators
ML22287A0692023-02-0808 February 2023
R. E. Ginna Station - Forward Fit Analysis (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094)
ML23031A2992023-02-0707 February 2023
R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request
ML23010A0112023-02-0101 February 2023
R. E. Ginna Nuclear Power Plant - Issuance of Relief Request Associated with Inservice Testing of Refueling Water Storage Tank Outlet Value
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Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10
IR 05000244/20223012023-01-20020 January 2023
Initial Operator Licensing Examination Report 05000244/2022301
IR 05000244/20220122023-01-12012 January 2023
LLC - Design Basis Assurance Inspection (Teams) Inspection Report 05000244/2022012
ML22362A0382022-12-28028 December 2022
R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
ML22348A2062022-12-14014 December 2022
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
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Text
v as vs'ess'wUvswsAxslrsw x 'slJ/ Vs( J Xx(eALllil fQRC 1 RIBUTION FOR PART 50 DOCK VIATERIAL (TEMPORARY FORM}
CONTROL NO: &289D FILE lNCXDENZ PEPOI',T I:ILP FROM: Rochester Gas & Elec. Co P GATE OF DOC DATE R EC'D LTR TWX RPT OTHER Rochester, N.Y.
L.D. White Jr. 11-4-75 11-10-75 XXX ORIG CC OTHER SENT AEC PDR XXX TO'=1ame .~EiL1z 30 SENT LOCAL PDR CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
XXX 30 50-244 DESCR IPTION: ENCLOSURES Letter trans the following...... Unusual Event Report ¹, 75-09; on 10-12-75, Concerning Reactor Coolant-131 Equivalent .
GCtiVity e ~ ~ ~ ~ ~ ~
(30 Copies Received)
PLANT NAME: RE Ginna ¹ 1 e
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November," 19 75 ego,,J oo
, C~X Mr. James P. O'Reilly, Director U. 'S. Nuclear 'Regulatory Commission Office of Inspection and Enforcement ',:=,~IT T6 Region I 631 Park Avenue King of Pru ssia, Pennsylvania 19406
Subject:
Unusual Event 75-09, Reactor Coolant Iodine-131 Equivalent Activity R. E. Qinna Nuclear Power Plant, Unit No. 1 Docket No. 50-244
Dear Mr. O'Reilly:
In accordance'with Technical Specifications, Article 6.6.2b, the attached report of Unusual Event 75-09 is hereby submitted. Two additional copies of this letter and the attachment are enclosed.
Very t'ruly yours,
'C~l ~~P L. D. White, Jr.
Attachment cc: Mr. Donald F. Knuth (30)
Mr. William G. McDonald (3)
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L(CENSEE EVENT REPORT CqNTROL BLOCI(: . LEASE PRINT ALL REQUIRED IMFDRIWATIDM) 6 LICENSEE LICENSE FVENT NAME LICENSE NUMSER TYPE TYPE
[oaj N Y R E G 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~03 7 89 14 15 85 36 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT OATE
'IoO~Icom ~PO L L 0 5 0 0 2 4 4 1 0 1 2 7 5 1 1 0 4 7 5 7 8 57 58 59 60 61 68 69 74 75 80 I
EVENT DESCRIPTION
[op~] During startup with reactor critical, reactor coolant temp. over 500 I-, I-131 equivalent 7 8 9 80 activity was reported to be at 5. 43 micro Ci/gm, a degraded condition permitted by 7 89 80 Qp~] limiting conditions for operation. Increased primary coolant sampling was begun with 7 8 9 80 Qpg increasing purification flow to max. The I activity was returned to less than 3 micro Q 7 8 9 80 Qpg Ci/gm in about 9 hrs. (Unusual Event 50-244/75-09) 7 89 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE COOE COMPONENT COOE 5UPPUER MANUFACTURER VGLATION
~or ~RC ~E E U E L X X N W 1 2 0 N 7 8 S 10 11 13 17 43 44 47 48 CAUSE DESCRIPTION tOOI A partial cooldown and subsequent heatup and the accompan in de ressurizin and 7 8 9 80
[opg] pressurizing of the fuel resulted in. the increased reactor coolant I-131 equivalent 7 8 9 80 t11oj activity.
7 89 80 FACILITY METHOO OF STATUS % POWER OTHER STATUS OISCOVERY OISCOVERY OESCRIPTION
[gg ~C ~00 0 NA sampling per startup procedure 7 8 9 10 18 13 44 45 46 30 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q~g 8 8 . NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
[ig ~00 0 ~E NA 7 8 9 O'I 18 13 80 PERSONNEL INJURIES NUMBER OESCRIPTION
[gQ4 ~00 0 NA 7 89 11 13 80 OFFSITE CONSEQUENCES Jig 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIONAL FACTORS 7 89 80 89 7
NAME: Bruce A. Snow PHDNE.7 1 6/546 2700 'xt GPO 661 80 29 1-2 14 667
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