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LER-1997-007, Forwards LER 97-007-01,re RT Instrumentation Which Would Have Been in Condition Prohibited by Ts.Rev 1 Corrects Typo on Page 6 & Clarifies Content of Training Which Will Be Conducted |
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CATEGORY 1 REGULATORS INFORMATION DXSTRIBUTXON SYSTEM (RIDS)
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ACCESSION NBR:9802180021 DOC.DATE: 98/02/06 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH..NAYS.
AUTHOR AFFILIATION MECREDY,~.C.
Rochester Gas
&. Electric Corp.
RECXP.NAME RECIPIENT AFFILIATION VISSZNG,G.S.
Document Control Branch (Document Control Desk)
SUBJECT: Forwards LER 97-007-0l,which requires rept of, "Any Operation or Condition Prohibited by Plants TSs."
LER rev being submitted.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR I
ENCL
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SIKE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET I 05000244 1
C 05000244g RECIPIENT ID CODE/NAME PD1-1 PD COPXES RECIPIENT LTTR ENCL ID CODE/NAME 1
1 VISSING,G.
COPXES LTTR ENCL 1
1 INTERNAL:
D PD/RAB ILE CE NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN1 FILE 01
. EXTERNAL: L ST LOBBY WARD NOAC POORE,W.
NRC PDR 2
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1 1
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AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EZB LITCO BRYCE,J H NOAC QUEENER,DS NUDOCS FULL TXT 1
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N NOTE TO ALL "RZDS" RECZPZENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED:
LTTR 24 ENCL 24
AND ROCH STET GASANDEI'ECTRICCORIOR4TION
~ 89EASTAVENIIE ROCHESTER N Y Idrd9DDDI M AREA CODE7ld Sdd RTDD ROBERT C. MECREDY Vice President NucteErr Operations February 6, 1998 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555
Subject:
LER 97-007, Revision 1, Reactor Trip Instrumentation Would Have Been in a Condition Prohibited by Technical Specifications R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Vissing:
In accordance with 10 CFR 50.73, Licensee Event Report System, item (a) (2) (i) (B), which requires a report of, "Any operation or condition prohibited by the plant's Technical Specifications",
the attached Licensee Event Report LER 97-007 (Revision 1) is hereby submitted.
Revision 1 corrects a typographical error on Page 6, and clarifies the content of the training which will be conducted.
This event has in no way affected the public's health and safety.
Very t ly yours,
. Robert C. Mecredy xc:
Mr. Guy S. Vissing (Mail Stop 14B2)
Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector 9802i80021 98020tct PDR ADOCK 05000244 8
PDR IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII
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| 05000244/LER-1997-001, :on 970131,discovered Service Water Temp Was Less than Specified Value.Caused by non-representative Method of Monitoring.Increased Water Temp in Screenhouse Bay to Greater than 35 Degrees F |
- on 970131,discovered Service Water Temp Was Less than Specified Value.Caused by non-representative Method of Monitoring.Increased Water Temp in Screenhouse Bay to Greater than 35 Degrees F
| 10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(viii) | | 05000244/LER-1997-002, :on 970720,34.5 Kv Offsite Power Circuit 751 Was Lost.Caused by Automatic Actuation of B Emergency DG Due to Undervoltage on Safeguards Buses 16 & 17.Offsite Power Restored to Safeguards Buses 16 & 17 |
- on 970720,34.5 Kv Offsite Power Circuit 751 Was Lost.Caused by Automatic Actuation of B Emergency DG Due to Undervoltage on Safeguards Buses 16 & 17.Offsite Power Restored to Safeguards Buses 16 & 17
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii) | | 05000244/LER-1997-003, :on 970730,bistable Instrument Trip Setpoint Could Have Exceeded Allowable Value.Caused by Insufficient Existing Margin Between Trip Setpoint & Allowable Value. Held Switches in Tripped Configuration |
- on 970730,bistable Instrument Trip Setpoint Could Have Exceeded Allowable Value.Caused by Insufficient Existing Margin Between Trip Setpoint & Allowable Value. Held Switches in Tripped Configuration
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii) | | 05000244/LER-1997-004, :on 971024,radiation Monitor Alarm Were Noted Due to Higher than Normal Radioactive Gas Concentration Resulted in Cvi.New R-12 Alarm Setpoint Was Maintained for Duration of Refueling Outage |
- on 971024,radiation Monitor Alarm Were Noted Due to Higher than Normal Radioactive Gas Concentration Resulted in Cvi.New R-12 Alarm Setpoint Was Maintained for Duration of Refueling Outage
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(viii) | | 05000244/LER-1997-005, :on 971031,undetected Unblocking of SI Actuation Signal Occurred at Low Pressure Condition,Due to Faulty Bistable Which Resulted in Inadvertent SI Actuation Signal.Sias,Ci & CVI Signals Were Reset |
- on 971031,undetected Unblocking of SI Actuation Signal Occurred at Low Pressure Condition,Due to Faulty Bistable Which Resulted in Inadvertent SI Actuation Signal.Sias,Ci & CVI Signals Were Reset
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii) | | 05000244/LER-1997-006-01, Forwards LER 97-006-01,re Verification of B Concentration Which Was Not Performed Due to Misinterpretation of Event Sequence.Rev Clarifies Role of Operations as Part of Cause & Includes Addl CAs That Address Cause | Forwards LER 97-006-01,re Verification of B Concentration Which Was Not Performed Due to Misinterpretation of Event Sequence.Rev Clarifies Role of Operations as Part of Cause & Includes Addl CAs That Address Cause | | | 05000244/LER-1997-006, :on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status |
- on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(e)(2)(ii) | | 05000244/LER-1997-007, :on 971117,reactor Engineer Recognized That Neutron Flux Low Range Trip Circuitry for Channel Was Not in Tripped Condition as Required.Caused by Technical Inadequacies.Channel Defeat Will Be Identified |
- on 971117,reactor Engineer Recognized That Neutron Flux Low Range Trip Circuitry for Channel Was Not in Tripped Condition as Required.Caused by Technical Inadequacies.Channel Defeat Will Be Identified
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii) | | 05000244/LER-1997-007-01, Forwards LER 97-007-01,re RT Instrumentation Which Would Have Been in Condition Prohibited by Ts.Rev 1 Corrects Typo on Page 6 & Clarifies Content of Training Which Will Be Conducted | Forwards LER 97-007-01,re RT Instrumentation Which Would Have Been in Condition Prohibited by Ts.Rev 1 Corrects Typo on Page 6 & Clarifies Content of Training Which Will Be Conducted | | | 05000244/LER-1997-055, Forwards LER 97-055-00 Re Undetected Unblocking of SI Actuation Signal Occurrence While at Low Pressure Condition Due to Faulty Bistable Which Resulted in Inadvertent Safety Injection Actuation | Forwards LER 97-055-00 Re Undetected Unblocking of SI Actuation Signal Occurrence While at Low Pressure Condition Due to Faulty Bistable Which Resulted in Inadvertent Safety Injection Actuation | |
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