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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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Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators
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R. E. Ginna Station - Forward Fit Analysis (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094)
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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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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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ROCKIEST'M'AS ANN ELECYREC CORMRAT!oil e 89 FAST AVEhfQE, ROCHESTER. IZ.Y. l4649
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a+a~ cosa ~re 546-Z'YoO Gin+a Station February 28, 1976
% ~ James P. O'Really'.
~] g5 S. Nuclear RegmatorT Ccmission Mrectorate o Rep~tozy Operations Region 1 631 Park A~-cnue King of'russia, Penn~1venia 3.9406 SubJect: Bcportab3.e Occurrence f76-99: A>nor~ DegraCation of Stea-Generator Toocs D ar Pm. O'Heil+:
This is to confer. g phone call to Pz. John?fannon, on ."-e a=:- 2":, 975, to report Abnorma1 Occu rance F76-08 et Ginna Station.
A program o plaxmM eddy current: e-azu9.n~ ion ~~ conduct.eR on both 1o.-.p "A" an4 "8 steam generators at the Ginna Sta ion Wcn Feb~ary 3.5th to February 27, 1976, durS.ng, +he pr ese" re~~eling turbine ~~tenaace outage. ~s programs sp cH'S.e6 eum~nations at ~03 %R to detect aa6 casure ym'antis.i tube Cef'ects anl at 2$ KiK to provMe a profile of slv8gc deposits.
r I 100 percent Snipe tion of both steam generators {hot and cold. legs) <em a rforxetX. As a result of this effort, 39 t..bes frere ep3.os"very pluge6 in the "A" stean gener*%or ad@ 2 in the "8" team gewera o=. These ubes had.
cxh"-bitc8 tvhe mal). 6etcriorat~on in c-.xcess o 40 percent.
Very trav yours, Cha-1es Z. Pla" Superint enQent CEP ig cc Bz. G. Z. Svez<hout,~ RGF Cog.
Hr. T. B. Wite, Jr.MM Corp.
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o 89 EAST AYEHVE, ROCHESTER, H.Y. 14504
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.'r. Jm.cs Pi D'Reilly U~ 8. nuclear !eguXatory Comkssion Mrectoratc af Regulatory Qperations Region 1 63E Park Ave.
FATE@ of Prfzesia, Pennsylvania l94OS REiiCT: Pepartable Occurrcace -'76-3.1 Contro1 Ra".~ Charcoal Hlter Beeper Xaproperly Positioned Bear 4 O'Peilly-This S.s tc cuba.:i~ ay phoae call to Yg. Bat @vis on Parch 8, 1976, to redo t e $ aprop"r pooktioning of one af the Wo doers for the contxoL -om charcoal fil,ter cysts .
Rhino.conductin. a Qev check on the control room chercoaL filter svstc on 3-9-76, i.t ~as discovered that one o+ the ceo darmere air Qaw turovgh. the charcoaE filters curing thar. controls 25" of t>e controE a radiation r racy "as Kn t.".c v-.
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positian. Xnis condition alEo ed one of the taro ca=pere to always be closed so &at the rccircu2ation of 257, of the contra1 mm air Garo"gx the charcoal filter ~as aot
)ossibEce 4
1 troub1e card @as ismc8 ace carl= ia being done toady to co rect the probXm.
Ve~ tMlp ) ovrs, CnarEcs E. Platt Su per intendant
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{P-76 I 50-244 FILE NUMBER PJRC DISTRIBUTION FDR PART 50 DOCKET,:MATERIAL INCIDENT REPORT DATE OF DOCUMENT TO: J.P. O'ei ly 1 Rochester Gas 5 Elec. Corp. 3-1-76 Rochester, N.Y.
DATE RECEIVED L.O. White, Jr, 3-6-76 C3NOTORIZEO PROP INPUT FORM NUMBER OF COPIES RECEIVED C3LETTE R C3ORIGINAL 8 UNC LASS IF I E D SCOPY DESCRIPTION ENCLOSURE Ltr. trans the following....... Reportable Occurrence ¹ 76-07, on 2-7-76, Concerning Relays for Train "A" Containment isolation ans containment'Ventilation. isolation failure to latch..;-.
(1 Cy. Recieved)
PLANT NAME: RE Ginna ¹ 1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J COLLINS SAFETY FOR ACTION/INFORMATION ENVIRO NCH CHIEF:
>l 4 CYS FOR ACTION C ASST:
M/ 'CYS S 16 CYS SSXXIXNG/ ENT TO LA INTERNAL D IST Rl BUTION F LE E 2 OEDER/IPPOLITO AK CHECK ME K E ESCO MACCA 0
LMER BUNG E E OL NS EXTERNAL DISTRIBUTION CONTROL NUMBER R: e e C
2239 NRC FORM 195 {2.761
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., 0 e 1~ ~ E ~ i I mls waafs l 51AIC r~OCII ESTER C;AS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 Lf.ON D. WHITE. JR. TCLCt'HONK YICF. PRCSIDCNT ~ac* cooc via 546 2700 March 1, 1976,. g
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gyves $ 76 Mr. James P. O'Reilly, Director jg U. S. Nuclear Regulatory'ommission i'
P Office of Inspection and Enforcement ,
Region I .
631 Park Avenue King of Prussia, Pennsylvania 19406 Subject. Reportable Occurrence 76-07 (30-day report), Relays for Train "A" containment isolation and containment ventilation Ssolation failure to latch.
R. E; Ginna Nuclear Power Plant,'nit No. 1 Docket No. 50-244
Dear Mr. O'ei) 3y:
In accordance with Technical Specifications, Article 6.9.2b, the attached report of Reportable Occurrence 76-07, 30-day, is hereby submitted. Two additional copies of this letter and the attachment are enclosed.
Very truly yours,
~PA.
L. D. White, Jr.
Attachment cc: Mr. Ernst Volgenau (30)
Mr. William G. McDonald (3)
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Ill:ENSEE EVENT REPDRi U i C CONTROL BLOCK: fPLEABE PRINT ALL REQUIRED INFORMATION) 1 6 LrCENSEE LICENSE EVENT NAME LrCENSE NUMBER TYPE TYPE 0 0 ~03
[OD1] N Y R E G 1
'5+0 0 0 0 0 0 0 6 1 1 1 1
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7 89 14 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE
~01 coNT L ~L 0 6 0 0 2 4 4 0 2 0 7 7 6 0 3 0 1 ~/6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION Jog urin valve ali nment verifica'tion followin manual containment isolation'I and con-7,8 9 80
'[QQ3] ainment ventilation isolation (CVI) in preparation for ILRT, sump A discharge AOV had 7 89 80 tppj4 ot closed. Investigation revealed that MG-6 relays in "A" safeguards train for CI and 7 8 9 80 Qpg CVI would not latch and would drop back on release of pushbutton. Train "B" functioned 7 S 9 80 Qpg properly. There has been no previous failure of this (cont'd. under Additional Pactors) 7 8d9 PRME
'80 SYSTEM CAUSE COMPONENT "
COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER VIDLATON
~os ~IB 8 S'10 B R B L A Y X 17
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48 7 11 12 CAUSE DESCRIPTION Qpg estinghouse Electric Corp. type MG-6 relays, style 289B363All, 125 VDC, were found 7 8 9 80 Qpg ith improper latch screw factory adjustment. Removed relays were adjusted and stored s Srs spares. Remaining MG-6 relays in safeguard racks will be checked during safe-
~10 uard functional test durin this refuelin outa e.
7 89 METrIDD 0F 80 FACIUTY STATUS POWER OTHER STATUS DISCOVERY OSCOVERY DESCRIPTION Q~g ~H ~oo o NA NA 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF riELEASE AMDUNT 0F AOTrvITY LOCATION OF RELEASE K~I ' L~l NA NA 7 8 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q~g ~00 0 ~B NA 7 8 9 11 12 13 80 PERS'ONNEL INJURIES 7 89 11 12 80 OFFSITE CONSEQUENCES NA 7 89 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g 7 89 10 PUBLICITY NA 7 '89 00 ADDITIONAL FACTORS
[118] (cont'd. from Event Description) t pe. Identical replacement rela s from ori inal s a~re 7 89 80 parts inventory were adjusted, tested, installed and retested satisfactorily by qualified Q~g .est ersonnel. Re ortable Occurrence 76-07 .30-da .
7 89 80 E. Clair Edgar PHQNE. 716/546-2700, ext. 29 1-223 GFO ae>. BRZ
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&is is~~~jrm.~-pha~.cal3. to ~. Joy n Fmmoa-. 4%is .~ingto. give him information on ReportabLe Occurrence 176-05
.ressurimtion of the contain=ent for the c ont aizment integrated
-.est began at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on Saturday Feb 7. The 35 psig pr essure ~as =
y",
stablished at 0890 hours0.0103 days <br />0.247 hours <br />0.00147 weeks <br />3.38645e-4 months <br /> on Sunday Februa 8 19>6 ~ ter aai 35 psig pressure for approxkmteXy five ho urs r it becee apparent t'h totters vase-'gj
.xcessa~ve eakage thronglr'everaL c &trat,Dns ~ Furt oar investigation g
.ounce the c~nents that were responsible for the excessive leak r~e to he=
{3.) Containment Purge Supp+ Valve InsS.de Contain=ent (2) Contaixunent'urge Exhaust VaIves (3) Motor Operated Valves $ 813 h RGL< Reactor SnopoM Cooling . ,tg qf",,
Check Valve P'1713 KS.trodden supp~ to h tReeacror Coolant Dtvdn,'~.- "
Tank ~+r~i
.-ate. test MXU. 'be resmed as soon as repairs are cmpleted
'a'ez g t.rd23r pours y Canaries K'. P3att"p Superintendent v, S
.rP/Qg G- Z- Smethomt BQK Corp L. D <<ai e BM:- Corp .
Sweet HGRZ Corp- C- V J.art3.i 3 BG'
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