LER-1998-002, Forwards LER 98-002-01,per 10CFR50.73.Revised LER Describes Change in Planned Corrective Actions for Ssps Testing Deficiency |
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CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9805050225 DOC.DATE: 98/04/30 NOTARIZED: NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION ROBINSON,W.R.
Carolina Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards LER 98-002-01,per 10CFR50.73.Revised LER describes change in planned corrective actions for SSPS testing deficiency.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL i
SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
DOCKET ¹ 05000400 NOTES:Application for permit renewal filed.
05000400 E RECIPIENT ID CODE/NAME PD2-1 PD INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC, POORE, W.
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1 RECIPZENT ID CODE/NAME FLANDERS,S AEOD RAB R
NRR/DE/EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2 FILE 01 LITCO BRYCE,J H NOAC QUEENER,DS" NUDOCS FULL TXT COPIES LTTR ENCL 1
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NOTE.TO ALL "RIDS" RECIPIENTS:
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 25 ENCL 25
Carolina Power & Light Company PO Box 165 New Hill NC 27562 William R. Robinson Vice President Harris Nuclear Plant APR 3 O 1998 U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555 Serial: HNP-98-067 10CFR50.73 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 DOCKET NO. 50-400 LICENSE NO. NPF-63 LICENSEE EVENT REPORT 98-002-01 Sir or Madam:
In accordance with 10CFR50.73, the enclosed revision to Licensee Event Report (LER)98-002 is submitted.
This revision describes a change in planned corrective actions for the Solid State Protection System testing deficiency.
Sincerely, MV Enclosure c:
Mr. J. B. Brady (HNP Senior NRC Resident)
Mr. L. A. Reyes (NRC Regional Administrator, Region II)
Mr. S. C. Flanders (NRC - NRR Project Manager) 9805050225 980430 PDR ADQCK 05000400 S
PDR 5413 Shearon Harris Road New Hill NC Tel 919 362.2502 fax 919 362.2095
U. S. Nuclear Regulatory Commission Document Control Desk / HNP-98-067 Page 2 of 2 bcc:
Ms. D. B. Alexander Mr. R. W. Baylor Mr. T. C. Bell Mr. H. K. Chernoff (RNP)
Mr. B. H. Clark Mr. W. F. Conway Mr. G. W. Davis Mr. W. J. Dorman (BNP)
Ms. J. P. Gawron (BNP)
Mr. H. W. Habermeyer Mr. K. N. Harris Mr.'W. J. Hindman Ms. C. W. Hobbs (HEEC)
Mr. W. D. Johnson Mr. R. M. Krich Mr. M. B. Keef.(HEEC)
Ms. W. C. Langston Mr. C. W. Martin (BNP)
Mr. R. D. Martin Mr. J. W. McKay Mr. B. A. Meyer Mr. P. M. Odom (RNP)
Mr. W. R. Robinson Mr. R. F. Saunders Mr. F. E. Strehle Mr. J. M. Taylor Mr. D. L. Tibbius Mr. C. A. VanDenburgh Mr. R. L. Warden (RNP)
HNP Real Time Training INPO Harris Licensing File Nuclear Records
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| 05000400/LER-1998-001, :on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01 |
- on 980109,potential Condition Outside Design Basis Related to Instrument Air Sys Leak Causing SG pre- Heater Bypass Isolation Valves to Be Inoperable Was Noted. Caused by Inadequate Design Control.Generated Jco 98-01
| 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)(iii)
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(a)(2) | | 05000400/LER-1998-002, :on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive |
- on 980121,determined Ssps (P-11 Permissive) Testing Deficiency.Caused by Inadequate Review of Initial Ts.Will Revise & Perform Surveillance Test Procedures to Verify Operability of P-11 Permissive
| 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) | | 05000400/LER-1998-002-01, Forwards LER 98-002-01,per 10CFR50.73.Revised LER Describes Change in Planned Corrective Actions for Ssps Testing Deficiency | Forwards LER 98-002-01,per 10CFR50.73.Revised LER Describes Change in Planned Corrective Actions for Ssps Testing Deficiency | | | 05000400/LER-1998-003, :on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures Revised |
- on 980129,failure to Perform Shutdown Margin Calculation Required by TS Surveillance Requirements Occurred.Caused by Ambiguity in TS 3.1.3.1.c.Procedures Revised
| 10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(viii)
10 CFR 50.73(e)(2)
10 CFR 50.73(e)(2)(iii) | | 05000400/LER-1998-004, :on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor |
- on 980313,identified Design Deficiency Re Potential Runout of Tdafwp.Caused by Inadequate Original AFW Sys Design.Operability Evaluation Was Completed on 980313 & Addl Engineering Analysis Was Performed by Vendor
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2) | | 05000400/LER-1998-004-01, Forwards LER 98-004-01 Re Design Deficiency Concerning Potential Runout Condition Occurring with Tbafp During Certain Accident Scenarios.Rev Includes Results of Subsequent Testing by Vendor | Forwards LER 98-004-01 Re Design Deficiency Concerning Potential Runout Condition Occurring with Tbafp During Certain Accident Scenarios.Rev Includes Results of Subsequent Testing by Vendor | | | 05000400/LER-1998-005, :on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim Manner |
- on 980420,TS Verbatim non-compliance Was Determined.Caused by Misinterpretation of TS Requirements. Issued Memo to Reemphasize Need to Comply W/Literal Meaning of TS Requirements in Verbatim Manner
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
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) | | 05000400/LER-1998-006, :on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling Each |
- on 980508,failure to Perform Insp & Preventive Maint on MCCB as Required by TS Was Noted.Caused by Inadequate Sps.Tested 9 Pressurizer Heater Bank Breakers by Cycling Each
| 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) | | 05000400/LER-1998-007, :on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With |
- on 981023,turbine Control Anomaly Caused Manual Rt.Caused by Failure to Incorporate Verbal Vendor Guidance in Operating Procedures.Addl Vendor Guidance Will Be Verified & Added to Procedures.With
| 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)(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) |
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