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Category:Letter
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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
"-- I <Tvii"(DOMTFlLECOP;," .--
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ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 EAST AVENUE, ROCHESTER, H.Y. 14649 I ECIN D. WHITE. JR. TELEPIIDNE VICE PRESIDENT ARE* CDDE 7III 546-2700 August 3, 1978 C
Ci>
jr I Mr. Boyce H. Grier, Director I CA U. S. Nuclear Regulatory Commission C Al A7 =
CID Office of Inspection and Enforcement R Region I Dl CA I
631 Park Avenue King of Prussia, Pennsylvania 19406
Subject:
LER 78-006/03L-O, Main steam line snubbers, positions MS146 top and bottom R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244
Dear Mr. Grier:
In accordance with Technical Specifications, Article 6.9.2.b. (2) operation in a degraded mode permitted by a limiting condition for operation, the attached report of Reportable Occurrence 78-006, 30-day, is hereby sub-mitted. Two additional copies of this letter and the attachment are enclosed.
Very truly yours, L. D. White, Jr.
Attachment cc: Director, IE, Washington (30)
Mr. William G. McDonald (3) 782230094'
~ '4 Y t 1
't II
NRC FORM 366 U. S. NUCI.EAR REGULATORY COMMISSION (7-77l P LlCENSEE EVENT REPORT (CAR 1192 & 1196)
. CONTROL BLOCK: (PI.EASE PRINT OR TYPE ALL REQUIRED INFORIVIATION)
I 6
~01 7 8 9 N Y R LICENSEE CODE E G 1 14 Qz 0 0 0 0 0 0 LICENSE NUMBER 0 - 0 0 25 Qz 26 4 1 1 LICENSE TYPE 1 1 30 QE~ 57 CAT 58 QE CON'T KDD8 7
soUROE MLO 60 61 0 5 0 0 0 DOCKET NUMBER 2 4 4 68 7
69 0 7 1 EVENT DATE 3 7 8 74 B 0 75 8 0 3 REPORT DATE 7 8 80 Q
EVENT DESCRIPTION AND PROBABL.E CONSEQUENCES QIO
~o2 During snubber inspection position MS146 (bottom) was found with low accumulator
~o3 level ~ After adding'nd later reche cking level, snubber unit a long withI unit in position MS 146 (top) were replaced for maintenance. When tested both units failed to lock up in compres sion and tension modes ~ (T ~ S ~ 3 ~ 13 ~ 1) ~
~OB
~DB 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENTCODE SUBCODE SUBCODE
~OB ~HB 9 10 QTT E Q2 UBQ>> S U P 0 R T QQ UDQ'9 UZ Q'9 7 8 11 12 13 18 19 20 SEOUENTIAL OCCURRENCE REPORT REVISION LERIRO I EVENT YEAR REPORT NO.
U CODE TYPE NO.
Q17 REPoRT I
L
~~q 21 22 23
~oo 24 9
26 U~
27 M~
28 29 UL 30 LJ 31 Uo 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP, COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER UCOTR U<OER 33 34 UOzo 35 UZO 36 37 0 0 0 0 40 MNOzz 41 UYO24 42 UAO29 43 44 B 2 0 9 47 Qze CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o Constant movement of pipe resulted in check valve failure and wear on accumulator tube, piston, piston shaft and shaft seal on each unit. Top unit had broken spring.
Both units are Bergen-Paterson model HSSA-30. They were replaced with tested 3 spares . Inspection of snubbers will be as dictated in schedule given in Technical 4 Specifications.
7 8 9 80 FACILITY ~3P METHOD OF STATUS 'YQ POWER OTHER STATUS QP DISCOVERY DISCOVERY DESCRIPTION Q32 1 9 E Q29 ~10 0 Q29 NA UBQET Surveillance of enubbere 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q36
~6 7 8 9 Z Q33 ~ZQ34 10 44 45 NA 80 PERSONNEL EXPOSURES NUIABER TYPE DESCRIPTION
~17 [~00 0 QET UZQEE NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41
~l8 ~00 0 Q49 NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION
~IB1 (~zQ42 NA 7 8 9 10 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q46 L~JQ44 NA 8 9 10 68 69 80 NAME OF PREPARER S. Spector PHQNE.716/546-2700, ext. 291-215
+ ur. (iq/e I DS REGULATORY I NFOR 'TION DISTRIBUTION SYSTEM ( >
DISTRIBUTION FOR INCOMING MATERIAL 0-244 DOCDATE: 06/06/78 REC:
NRC GRIER B H ORG: WHITE L D ROCHESTER GAS 8c ELEC 'ATE RCVD: 06/12/7 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING SUPPLEMENTAL LICENSEE EVENT REPT (RO 50-244/77-'007> ON 06/29/77 CONCERNING DURING TEST C SI PUMP FAILED TO START FROM BUS 14 BREAKER ON 2 I
ATTEMPTS.
PLANT NAME: RE GINNA UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS
'-'(DISTRIBUTION CODE A002) %I FOR ACTION: BR F ORB02 BC~~W/4 ENCL INTERNAL: 4+W/ENCL NRC PDR+4W/ENCL I 8 E~~W/2 ENCL MIPC++W/3 ENCL I 5 C SYSTEMS BR44W/ENCL EMERGENCY PLAN BR++W/ENCL NOVAK/CHECK++A/ENCL EEB~~W/ENCL AD FOR ENG44W/ENCL PLANT SYSTEMS BR~%W/ENCL HANAUER+4W/ENCL 'AD FOR PLANT SYSTEMS>>W/ENCL AD FOR OPER TECH44W/ENCL REACTOR SAFETY BR<4W/ENCL ENGINEERING BR++M/ENCL VOLLMER/BUNCH+~W/ENCL KREGER/J. COLL I NS4 4 W/ENCL POWER SYS BR4%W/ENCL K SEYFRIT/IE+~W/ENCL EXTERNAL: LPDR S ROCHESTER NY4+W/ENCL T I C+4 W/ENCL NS IC++W/ENCL ACRS CAT B++W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 781650068 SIZE-. 1P+iP THE END
NRC 3031305 006 UNITED STATES NUCLEAR REGULATORY COMMI DDC DAILY ACCESSION LIST 05/04/78 FILE LEVELS... DOC. DA'TE ma~w~w~wwm~w~~mmmww~ww~~wwma~~~~~~~~
STN 50 484 NORTHERN STATES POWER.'COMPANY TYRONE Pi...
50 02/22/78 ACCESSION NBR! 77346 0280 NBR:
484 DOCUMENT TYPE: MEMO FICHE NBR !
C DOCUMENT SIZE. 1 p NOTARIZED!
DOCKET DATE: LPDR:
REPORT NBR!
RECP! CARLSON R T RECP AFFI4 ORG! REINMUTH 'G W INSPECTIONS'TASK ORG AFF ILI SUBJECT! "SNUPPS" 50 04/20/78 ACCESSION NBR! 78118 0200 'TASK NBR:
484 DOCUMENT TYPE,; L'ETTER 'FICHE NBR !
'C DACUMFNT SIZE! 2P . NOTARIZED:
DOCKET DATE! 04/21/78 LPDR!
RFPORT NBR!
RECP! SMITH I W RECP AFFIL KORNBLITH L ANDERSON G C ORG'EWIS S H ORG AFF ILI
SUBJECT:
RESPONSE TO THE BOARD'S MEMO 8, ORD BY 04/21'/78 THEIR VIEWS ON "WHETHE, CONSIDERATIONS Li IF SOr WHAT SCHE CONSIDERING THE REMANDED MATTERS."
50 04/21/78 ACCESS IQN NRR! 78121 0006 TASK NBR:
484 DQCUMFNT TYPE! OTHERS FICHE NBR C DOCUMghlT SIZE: bP+2P NOTARIZED:
DOCKET DATE: 04/24/78 L'PDR!
RFPORT NBR:
RECP! RECP AFF IL ORG! CHARNOFF ORG AFF ILI BAXTER T SUBJECT! PERMITTEES'EGATIVE RESPONSE TO A WHETHER MA'TTERS 'REMANDED TO ASLB C APPL'ICAhlT S MN "CORP ~ TO WI SUBSID I'F SVC.
