:on 970107,missed Security Test/Insp Occurred. Caused by Cognitive Personnel Error.Individual Involved Counseled & Security Testing/Insp Tracking Process Enhanced| ML20133Q420 |
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| Site: |
San Onofre  |
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| Issue date: |
01/20/1997 |
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| From: |
Krieger R SOUTHERN CALIFORNIA EDISON CO. |
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| To: |
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| References |
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| LER-97-001, LER-97-1, NUDOCS 9701280102 |
| Download: ML20133Q420 (2) |
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text
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VTM k
50Vili[RN CAllFORNIA R. W. Krieger ED
'{
Mce Pmsident Nudear Generation An LDISON INTLltNATIO%AL Company January 20, 1997 U.
S. Nuclear Regulatory Commission i
Attention: Document Control Desk Washington, D.
C.
20555
Subject:
Docket Nos. 50-206, 50-361 and 50-362 14-Day Report Licensee Event Report No.97-001 San Onofre Nuclear Generating Station, Units 1, 2 and 3 l
This submittal provides a written follow-up 14-day report required by Unit 2/3 License' Condition 2.G using the Licensee Event Report (LER) format as required by Unit 1 License Condition 2.D.
The reported condition, missed testing / inspection of security systems, affected neither the health nor the safety of plant personnel or the public.
Sincerely, k
s 1
l
Enclosure:
LER No.97-001 cc:
L.
J.
Callan, Regional Administrator, NRC Region IV T.
P. Gwynn, Director, Division of Reactor Safety, NRC Region IV K.
E.
Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV J. A.
Sloan, NRC Senior Resident Inspector, San Onofre Units 2 &3 L.
C.
Carson, NRC Project Manager, San Onofre Unit 1 M.
B.
Fields, NRC Project Manager, San Onofre Units 2 and 3 Institute of Nuclear Power Operations (INPO) 9701200102 970120 P
gdh DR ADOCK 0500 6
g P. O. Ilox 128 San Clememe, CA 92674 714-it46255 I'ax 714 368-6183
)
I a
LICENSEE EVENT REPORT (LER)
Facility Name (1)
Docket Number (2)
Piiae v3)
SAN ONOFRE NUCLEAR CEhERATING STATION. UNIT 1 015101010121016 1
of 0
1 Title (4)
Missed Security Test / Inspection l
EVENT DATE (5)
LER NUMBER (6)
REPORT DATE (7)
OTHER FACILITIES INVOLVED (8)
Month Day Year Year
/// Sequential
/// Revision Month Day Year Facility Names Docket NLaber(s)
///
Ntaber
///
Number SONGS. UW1T 2 01 51 01 01 01 31 61 1 0l1 01 7 917 917 010l1 010 011 210 917 SONCS. UNIT 3 01 51 01 01 01 31 61 2 OPLRAllNG THlh kEPORT'IS WUBM TTED' PURSUANT'TO 'HE'REuulREMLNTS OF 10CFR MODE (9) 0 (Chock one or more of the followina) (11) 20.402(b) 73.71(b)
POWER 20.405(a)(1)(1) 20.405(c) 50.73(a)(2)(iv) 73.71(c)
LEVEL 20.405(a)(1)(ll) 50.36(c)(1) 50.73(a)(2)(v) other (Specify in 50.36(c)(2)
(101 01 010 20.405(a)(1)(lii) 50.73(a)(2)(1) 50.73(a)(2)(vil)
.n 50.73(a)(2)(viii)(A)
Abstract below and
//////////i//////////////
20.405(a)(1)(iv) 50.73(a)(2)(ll) 50.73(a)(2)(viii)(B) in text)
/////////////////////////
20.405(a)(1)(v) 50.73(a)(2)(lii) 50.73(a)(2)(x)
Unit 1 License 2.0
/////////////////////////
UnitsE&3, License 2.G
/////////////////////////
LICENSEE CONTACT FOR THIS LER (12)
Name iElEPHONE NUMBER AREA CODE R. W. Krieaer. Vice President. Nuclear Generation 71114 316181-l6121515 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THlh REPORT'(13s CAUbE SYSTEM COMPONENT MANUFAC.
REPORTABLE ///////
CAUSE
SYSTEM COMPONENT MANUFAC-REPORTABLE
//////
TURER TO NPRDS
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TURER TO NPRDS
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l l I l 1 l l
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l l l 1 l l l
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l l 1 l l l l
///////
I l I I I I l J/////
$UPPLEMENTAL'REPOR' EXPECTED L14)
Month Day Year I
Expected Submission Yes (if ves. comotete EXPECTED SUBMfSSION DATE) xx ND l
l l
e On 1/7/97, with Unit 1 permanently shutdown, Unit 2 shutdown for refueling and Unit 3 at 100% power, a review of security system [IA] records revealed that three (3) of twenty (20) E-field sectors had not been tested within the 92 days required by the physical security plan (PSP).
Because this condition was not in conformance with the PSP, Edison i
made the required 24-hour report on 1/7/97 (NRC Log No. 31553).
Due to this discovery, Edison reviewed other Station records and, on 1/9/97, concluded the December monthly inspection for active Vehicle Barrier System bollards had not been completed on time.
Edison made a similar 24-hour report on 1/10/97 (NRC Log No. 31569). As required by Condition 2.D of the Unit 1 Possession Only License, and Condition 2.G of the Units 2 and 3 Facility Operating Licenses, this 14-day follow-up report is provided for both occurrences.
These occurrences were caused by cognitive personnel error. The individual responsible for security system tests / inspections failed to ensure they were completed as required.
Edison implemented the required compensatory actions pending test / inspection completion.
The E-field tests were successfully completed on 1/8/97; the active bollards inspections were successfully completed on 1/9/97 Edison confirmed the affected systems were i
always operable or the required compensatory actions were in place.
Consequently, these occurrences had no safety significance. Edison counseled the individual involved and will enhance the security testing / inspection tracking process.
LER 1-96-002 reported a missed inspection of security tamper switches.
That event was caused by inadequate ccmmunication when capturing inspection requirements for a newly installed security system, a cause not present for the events reported herein.
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| | | Reporting criterion |
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| 05000361/LER-1997-001-01, Forwards Ltr Provided LER 97-001-01 for Occurences Involving Surveillance Testing & Implementation of New Standard TSs Re San Onofre Nuclear Generating Station,Units 2 & 3 | Forwards Ltr Provided LER 97-001-01 for Occurences Involving Surveillance Testing & Implementation of New Standard TSs Re San Onofre Nuclear Generating Station,Units 2 & 3 | | | 05000206/LER-1997-001-02, Forwards LER 97-001-02 Re Missed Testing/Insp of Security Sys.Util Has Noted That Counselling of Individual Was Inadvertently Not Completed & LER Is Being Revised, Accordingly | Forwards LER 97-001-02 Re Missed Testing/Insp of Security Sys.Util Has Noted That Counselling of Individual Was Inadvertently Not Completed & LER Is Being Revised, Accordingly | | | 05000206/LER-1997-001, :on 970107,missed Security Test/Insp Occurred. Caused by Cognitive Personnel Error.Individual Involved Counseled & Security Testing/Insp Tracking Process Enhanced |
- on 970107,missed Security Test/Insp Occurred. Caused by Cognitive Personnel Error.Individual Involved Counseled & Security Testing/Insp Tracking Process Enhanced
| 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) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000362/LER-1997-001-02, :on 970412,four Out of Five RCS Nozzles Leaked During Plant Operation & Fifth Suspected of Leaking.Caused by Crack Through Nozzle in Heat Affected Zone of Partial Penetration Weld.Completed Required Welding |
- on 970412,four Out of Five RCS Nozzles Leaked During Plant Operation & Fifth Suspected of Leaking.Caused by Crack Through Nozzle in Heat Affected Zone of Partial Penetration Weld.Completed Required Welding
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000206/LER-1997-002-02, :on 971027,discovered That Single Copy of Security Contingency Plan Was Missing.Cause Indeterminate. Revised LER Will Be Submitted by 971219 to Provide Results of Investigation |
- on 971027,discovered That Single Copy of Security Contingency Plan Was Missing.Cause Indeterminate. Revised LER Will Be Submitted by 971219 to Provide Results of Investigation
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(iii) | | 05000361/LER-1997-002, :on 970128,increase in Pressurizer Level Occurred Due to Valve Alignment Error.Npeo Was Temporarily Removed from Duties & Counseled by Mgt |
- on 970128,increase in Pressurizer Level Occurred Due to Valve Alignment Error.Npeo Was Temporarily Removed from Duties & Counseled by Mgt
| 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) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000362/LER-1997-002-01, :on 970703,RCS Leakage Occurred in Instrument Thermowell Nozzles.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Matls.Replaced Outer Half of Nozzles W/Inconel 690 Matl |
- on 970703,RCS Leakage Occurred in Instrument Thermowell Nozzles.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Matls.Replaced Outer Half of Nozzles W/Inconel 690 Matl
| 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) 10 CFR 50.73(a)(2)(1) | | 05000362/LER-1997-002, Forwards LER 97-002-00 Re Occurrence Involving RCS Pressure Boundary Leakage,Per 10CFR50.73(d) | Forwards LER 97-002-00 Re Occurrence Involving RCS Pressure Boundary Leakage,Per 10CFR50.73(d) | | | 05000206/LER-1997-002, Forwards LER 97-002-00 Re Loss of Single Copy of Security Contingency Plan.Revised LER Will Be Submitted by 971219 After Investigation Into Cause & Development of Corrective Actions | Forwards LER 97-002-00 Re Loss of Single Copy of Security Contingency Plan.Revised LER Will Be Submitted by 971219 After Investigation Into Cause & Development of Corrective Actions | | | 05000206/LER-1997-003-01, :on 970520,SCE Discovered Security Computer Sys Was Out of Svc.Caused by Unit 1 Permanently Shutdown,Unit 2 at 100% Full Power & Unit 3 Shutdown.Computer Sys Was Restored |
- on 970520,SCE Discovered Security Computer Sys Was Out of Svc.Caused by Unit 1 Permanently Shutdown,Unit 2 at 100% Full Power & Unit 3 Shutdown.Computer Sys Was Restored
| | | 05000362/LER-1997-003-01, Forwards LER 97-003-01 Re Out of Tolerance Condition Identified During Testing of Pressurizer Safety Valve Setpoints.Ler Contains No New Commitments | Forwards LER 97-003-01 Re Out of Tolerance Condition Identified During Testing of Pressurizer Safety Valve Setpoints.Ler Contains No New Commitments | | | 05000362/LER-1997-003-02, :on 971218,determined That Pressurizer Safety Valve Setpoints Were Out of Tolerance.Caused by Setpoint Drift.Valves Will Be Disassembled,Inspected,Reassembled & Reset by Proper Personnel |
- on 971218,determined That Pressurizer Safety Valve Setpoints Were Out of Tolerance.Caused by Setpoint Drift.Valves Will Be Disassembled,Inspected,Reassembled & Reset by Proper Personnel
| 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) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1997-003, :on 970225,out of Tolerance Condition Identified During Testing of Pressurizer Safety Valve Setpoints.Caused by Setpoints Drift.Setpoints Bounded by Analysis |
- on 970225,out of Tolerance Condition Identified During Testing of Pressurizer Safety Valve Setpoints.Caused by Setpoints Drift.Setpoints Bounded by Analysis
| 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)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(1) | | 05000206/LER-1997-003, Forwards LER 97-003,providing 30-day follow-up Rept Required by 10CFR73.71(d) for Security Computer Sys Being Inoperable for Few Minutes | Forwards LER 97-003,providing 30-day follow-up Rept Required by 10CFR73.71(d) for Security Computer Sys Being Inoperable for Few Minutes | | | 05000361/LER-1997-004, :on 970303,discovered Steam Leakage from Reactor Coolant Sys Pressurizer Thermowell.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Materials. Removed & Replaced Nozzle W/Inconel 690 |
- on 970303,discovered Steam Leakage from Reactor Coolant Sys Pressurizer Thermowell.Caused by Primary Water Stress Corrosion Cracking of Alloy 600 Type Materials. Removed & Replaced Nozzle W/Inconel 690
| | | 05000362/LER-1997-004, Forwards LER 97-004-00 for Occurrence Involving Typo in Ts. Health & Safety of Public or Plant Personnel Was Not Affected | Forwards LER 97-004-00 for Occurrence Involving Typo in Ts. Health & Safety of Public or Plant Personnel Was Not Affected | | | 05000362/LER-1997-004-01, :on 971205,typo in TS Was Found.Caused by Personnel Error.Tendon Surveillance Procedure Correctly Referenced Tendon 88-154 & Not 38-154 |
- on 971205,typo in TS Was Found.Caused by Personnel Error.Tendon Surveillance Procedure Correctly Referenced Tendon 88-154 & Not 38-154
| 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1997-005, :on 970319,determined That RCS Leakage Was Through Body of Valve Packing Leakoff Plug Caused by Defect. Defective Plug Confirmed to Be Free of Similar Defects, Removed Head & Ground Smooth |
- on 970319,determined That RCS Leakage Was Through Body of Valve Packing Leakoff Plug Caused by Defect. Defective Plug Confirmed to Be Free of Similar Defects, Removed Head & Ground Smooth
| | | 05000361/LER-1997-006, :on 970319,NRC Noted Some Utils Had Not Been Fully Complying W/Requirements of TS Re Surveillance Testing of Electronic Circuits,Per GL 96-01.Specific Cause of Omission Not Known.Procedures Revised |
- on 970319,NRC Noted Some Utils Had Not Been Fully Complying W/Requirements of TS Re Surveillance Testing of Electronic Circuits,Per GL 96-01.Specific Cause of Omission Not Known.Procedures Revised
| 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)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | | 05000361/LER-1997-007-01, Forwards LER 97-007-01,reporting Occurrence Involving Incomplete Surveillance Testing of Radiation Monitors. Neither Health Nor Safety of Plant Personnel or Public Affected by Occurrence | Forwards LER 97-007-01,reporting Occurrence Involving Incomplete Surveillance Testing of Radiation Monitors. Neither Health Nor Safety of Plant Personnel or Public Affected by Occurrence | | | 05000361/LER-1997-007, :on 970403,incomplete Surveillance Testing of Radiation Monitors Occurred.Caused by Cognitive Personnel Error.Procedures Corrected |
- on 970403,incomplete Surveillance Testing of Radiation Monitors Occurred.Caused by Cognitive Personnel Error.Procedures Corrected
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1997-008, :on 970304,TS Surveillance of Pressurizer Cooldown Rate Was Missed Because Operator Did Not Recognize That real-time Evaluation Plant Data Was Required.Cooldown Transient Terminated |
- on 970304,TS Surveillance of Pressurizer Cooldown Rate Was Missed Because Operator Did Not Recognize That real-time Evaluation Plant Data Was Required.Cooldown Transient Terminated
| 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) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1997-009, :on 970509,class IE 125 Vdc Battery Surveillance Testing Was Completed on 3 Replaced Batteries, Indicating Apparent Drop in Capacity of Two.Caused by No Requirement to Test.Revised TS Bases |
- on 970509,class IE 125 Vdc Battery Surveillance Testing Was Completed on 3 Replaced Batteries, Indicating Apparent Drop in Capacity of Two.Caused by No Requirement to Test.Revised TS Bases
| 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) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | | 05000361/LER-1997-010-01, Forwards LER 97-010-01 for Check Valve in Charging Subsystem Which Failed to Open Completely.Single Rept for Unit 2 Is Being Submitted as Condition Involved Same System,Cause & Corrective Actions Applicable to Units 2 & 3 | Forwards LER 97-010-01 for Check Valve in Charging Subsystem Which Failed to Open Completely.Single Rept for Unit 2 Is Being Submitted as Condition Involved Same System,Cause & Corrective Actions Applicable to Units 2 & 3 | | | 05000361/LER-1997-011-01, Forwards LER 97-011-01,reporting Occurrence Involving Use of Wrong Boron Sample for Determination of Reactor Shutdown Margin,Per NUREG-1022 | Forwards LER 97-011-01,reporting Occurrence Involving Use of Wrong Boron Sample for Determination of Reactor Shutdown Margin,Per NUREG-1022 | | | 05000361/LER-1997-012, :on 970814,discovered Design Inadequacy in Backup N Supply to CCW Surge Tanks.Caused by Cognitive Personnel Error.Plant Personnel Immediately Took Compensatory Action to Restore Sys Operability |
- on 970814,discovered Design Inadequacy in Backup N Supply to CCW Surge Tanks.Caused by Cognitive Personnel Error.Plant Personnel Immediately Took Compensatory Action to Restore Sys Operability
| 10 CFR 50.73(c)(2)(1) | | 05000361/LER-1997-013, :on 971010,charcoal Filter Surveillance Testing Was Not Current.Caused by Cognitive Personnel Error.No Irradiated Fuel Has Been Moved in Either Fuel Bldg Since 970522.Filters Will Be Replaced Before Fuel Is Next Moved |
- on 971010,charcoal Filter Surveillance Testing Was Not Current.Caused by Cognitive Personnel Error.No Irradiated Fuel Has Been Moved in Either Fuel Bldg Since 970522.Filters Will Be Replaced Before Fuel Is Next Moved
| 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1997-014, :on 971020,licensed Operators Did Not Have Corrective Lenses for Use W/Full Face Respirators.Cause Due to Util Not Establishing Administrative Controls for Special Lens Inserts.Improved Associated Procedures |
- on 971020,licensed Operators Did Not Have Corrective Lenses for Use W/Full Face Respirators.Cause Due to Util Not Establishing Administrative Controls for Special Lens Inserts.Improved Associated Procedures
| 10 CFR 50.73(a)(2)(1) 10 CFR 50.73(a)(2)(viii)(3) | | 05000361/LER-1997-015, :on 971117,inadequate Surveillance Testing of Charging Pump Relay Contacts Noted.Caused by Inadequate Surveillance Test Procedure.Subject K108 Subgroup Relay Contacts Tested Satisfactorily & Procedures Revised |
- on 971117,inadequate Surveillance Testing of Charging Pump Relay Contacts Noted.Caused by Inadequate Surveillance Test Procedure.Subject K108 Subgroup Relay Contacts Tested Satisfactorily & Procedures Revised
| 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1997-016, :on 971202,SONGS Personnel Recognized That Fire Damper SARW504165001FD Was Not in Licensee Controlled Specification Surveillance Procedure.Caused by Cognitive Personnel Error.Occurrence Reviewed W/Appropriate Personnel |
- on 971202,SONGS Personnel Recognized That Fire Damper SARW504165001FD Was Not in Licensee Controlled Specification Surveillance Procedure.Caused by Cognitive Personnel Error.Occurrence Reviewed W/Appropriate Personnel
| 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | | 05000361/LER-1997-017, :on 971216,STAs Were Questioned Re Respirator Qualifications & Requirements Re Corrective Lense Wearers. Cause Not Determined.Util Has Requalified & Certified All STAs for Respirator Use |
- on 971216,STAs Were Questioned Re Respirator Qualifications & Requirements Re Corrective Lense Wearers. Cause Not Determined.Util Has Requalified & Certified All STAs for Respirator Use
| 10 CFR 50.73(a)(2)(1) |
|