LER-1996-007, Forwards LER 96-007-01,IAW 10CFR50.73.Listed Item Represents New Commitment Made in Ltr |
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far 3f 9 0$ f 76f f UTILITIES August 8.1997 NO-971062 Document Control Desk U. S. Nuclear Regulatory Commission hiail Station PI 37 Washington, D. C. 20555-0001
Subject:
Duane Arnold linergy Center Docket No: 50 331 Op. License No: DPR-49 Licensec !! vent Report #96 007-01 File:
A-118a
Dear Sir:
Please find the attached subject Licensee Event Report Supplement submitted in accordance with 10CFR50.73. The following item represents the new commitment made in this letter:
The effectiveness of previous improvements in the test methodology for the Main Steam Safety Valves will be reviewed aller receipt of the Refueling Outage 15 test results. This action will be completed by July 31,1998.
Sincerely,
/
e rt '
Gary Van Middlesworth Plant hianager - Nuclear cc:
Mr. A. Bill Beach Regional Administrator Region til U. S. Nuclear Regulatory Commission 801 Warrenville Road Lisle,IL 60532 NRC Resident inspector - DAliC kh,k ll hhhhll [DOCUJ 9708200045 9700d$ '
PDR ADOCK 05000331 S
PDR an seg onsu,t,es comper
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| 05000331/LER-1996-001, :on 960325,determined That Degradation in Scram Insertion Times Occurred.Caused by Adhesion Between Viton SSPV Exhaust Valve Diaphragm & SSPV Seat.Replaced Viton SSPV Diaphragms W/Buna-N |
- on 960325,determined That Degradation in Scram Insertion Times Occurred.Caused by Adhesion Between Viton SSPV Exhaust Valve Diaphragm & SSPV Seat.Replaced Viton SSPV Diaphragms W/Buna-N
| | | 05000331/LER-1996-002-01, :on 960408,PCIS Half Group III Isolation Occurred Due to Blown Fuse During Maint.Fuse Was Replaced & Radiation Monitor Was Tested |
- on 960408,PCIS Half Group III Isolation Occurred Due to Blown Fuse During Maint.Fuse Was Replaced & Radiation Monitor Was Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000331/LER-1996-002, :on 960408,PCIS Half Group III Isolation Occurred Due to Blown Fuse During Maint.Reviewed Event W/ Maint Technicians to Reinforce Need to Secure Loose Cables During Maint Activities |
- on 960408,PCIS Half Group III Isolation Occurred Due to Blown Fuse During Maint.Reviewed Event W/ Maint Technicians to Reinforce Need to Secure Loose Cables During Maint Activities
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2) | | 05000331/LER-1996-003, :on 960716,PCIS Groups 1-5 Isolations Occurred. Caused by Electrical Protection Assembly Breaker Trip Undervoltage.Placed Bus on Alternate Power Supply & Reset Isolations & Half Scram |
- on 960716,PCIS Groups 1-5 Isolations Occurred. Caused by Electrical Protection Assembly Breaker Trip Undervoltage.Placed Bus on Alternate Power Supply & Reset Isolations & Half Scram
| 10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000331/LER-1996-004, :on 961008,HPCI Sys Isolation Occurred Due to Misplaced Relay Block During Testing.Hga & Hfa Relays Were Labeled to Indicate Contact Locations |
- on 961008,HPCI Sys Isolation Occurred Due to Misplaced Relay Block During Testing.Hga & Hfa Relays Were Labeled to Indicate Contact Locations
| 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)(x) | | 05000331/LER-1996-005, :on 961020,PCIS Groups 3 & 5 Isolations Occurred Due to Temporary Power Connections to Istrument Ac. Temporary Power Cart That Was Also Connected to 1BR8601 Was Removed |
- on 961020,PCIS Groups 3 & 5 Isolations Occurred Due to Temporary Power Connections to Istrument Ac. Temporary Power Cart That Was Also Connected to 1BR8601 Was Removed
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000331/LER-1996-005-01, :on 961020,PCIS Groups 3 & 5 Isolations Occurred Due to Temporary Power Connections to Instrument Ac.Temporary Power Cart Was Removed from Breaker That Was Also Supplying Power to 1Y2A |
- on 961020,PCIS Groups 3 & 5 Isolations Occurred Due to Temporary Power Connections to Instrument Ac.Temporary Power Cart Was Removed from Breaker That Was Also Supplying Power to 1Y2A
| 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) | | 05000331/LER-1996-006, :on 961026,non-conservative APRM 15% Scram Setpoint Occurred Due to Inadequate Procedures.Oss Immediately Halted Core Alterations & Verified That All CR Were Fully Inserted |
- on 961026,non-conservative APRM 15% Scram Setpoint Occurred Due to Inadequate Procedures.Oss Immediately Halted Core Alterations & Verified That All CR Were Fully Inserted
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2) | | 05000331/LER-1996-007-01, Forwards LER 96-007-01,IAW 10CFR50.73.Listed Item Represents New Commitment Made in Ltr | Forwards LER 96-007-01,IAW 10CFR50.73.Listed Item Represents New Commitment Made in Ltr | | | 05000331/LER-1996-007, :on 961203,three MSRVs & One MSSV Failed to Meet TS Setpoints.Caused by Insufficient Tolerance Associated W/Relief Valve Setpoint Acceptance Criteria.Out of Tolerance MSRVs & MSSV Were Restored to within TS LSSS |
- on 961203,three MSRVs & One MSSV Failed to Meet TS Setpoints.Caused by Insufficient Tolerance Associated W/Relief Valve Setpoint Acceptance Criteria.Out of Tolerance MSRVs & MSSV Were Restored to within TS LSSS
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2) |
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