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LER-1997-006, 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 |
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CATEGORY 1 REGULATO INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9802170127 DOC.DATE: 98/02/06 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.PAME-AUTHOR AFFILIATION MECREDl',R.C.
Rochester Gas S Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT: Forwards LER 97-006-00,which requires rept of, "Any Operation or Condition Prohibited by Plants TS."
LER being submitted.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR
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ENCL i
SIZE:
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 05000244'ECIPIENT ID CODE/NAME PD1-1 PD COPIES RECIPIENT LTTR ENCL "
ID CODE/NAME 1
1 VISSING,G.
COPIES LTTR ENCL 1
1 INTERNAL: AE B
ILE CENTER EBB 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
2 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HZCB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB LITCO BRYCE, J H NOAC QUEENER,DS NUDOCS FULL TXT 1
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NOTE TO ALL "RIDS" RECIPZENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPZES RECEZVED 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
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AND r
ROCIIESTER GASANDELECTRIC CORPORATION
~ 89EASTAVENUE, ROCHESTER, N Y. Id5-'9 OUI
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AREA COD 715 8/5=7M
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I ROBERT C. MECREDY Vice President Nvcteor Operotions U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy S. Vissing Project Directorate I-1 Washington, D.C. 20555 February 6, 1998
Subject:
LER 97-006, Revision 1, Verification of Boron Concentration Not Performed Due to Misinterpretation of Event Sequence, Resulted in 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 97-006 (Revision
- 1) is hereby submitted.
This revision clarifies the role of Operations as part of the cause, and includes additional corrective actions that address this cause.
This event has in no way affected the public's health and safety.
Very truly yours, Robert C. Mecredy xc:
Mr. Guy S. Vissing (Mail Stop 14B2)
PWR Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector 9802%70%27 5000244 pgp gQQCK 0 8
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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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