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Category:OPERATOR TRAINING/REQUALIFICATION PROGRAM
MONTHYEARML18092A7371985-08-20020 August 1985 Submits Second Annual Licensed Operator Requalification Program,Per NRC 840504 Ltr.No Mods Made Affecting Scope,Time or Frequency of Program.Preplanned Lecture Series Schedule Met for All Shifts.Simulator Available 100% of Time ML18089A2951983-08-0505 August 1983 Rev 5 to Training Procedure TP-305, NRC Licensed Operator Requalifcation Program for Salem Generating Station. ML18086B0421981-01-20020 January 1981 Revises Operator Requalification Training Program Incorporating Experience Review of 800611 St Lucie Event. Lesson Plan,Instructor Lesson Plan & Facility Study Assignment Sheets Encl 1985-08-20
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MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5301999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 ML18107A5031999-08-26026 August 1999 LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF). ML18107A4811999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr ML18107A4691999-07-28028 July 1999 LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr ML18107A4441999-07-0606 July 1999 LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr ML18107A4211999-07-0202 July 1999 LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr ML18107A4331999-07-0101 July 1999 LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr ML18107A4321999-07-0101 July 1999 LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF). ML18107A4351999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr ML18107A4341999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3951999-06-17017 June 1999 LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr ML18107A3661999-06-0909 June 1999 LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr ML18107A3551999-06-0202 June 1999 LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 ML18107A3541999-06-0101 June 1999 LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr ML18107A3681999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr ML18107A3721999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr ML18107A2931999-05-12012 May 1999 LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr ML18107A2781999-05-10010 May 1999 LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr ML18107A2791999-05-0404 May 1999 LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr ML18107A2741999-05-0303 May 1999 LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18107A2991999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr ML18107A2971999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr ML18107A2351999-04-23023 April 1999 LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. ML18107A1821999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr ML18107A1831999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr ML18106B1471999-03-29029 March 1999 LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr ML18106B1021999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr ML18106B1011999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML18106B0701999-02-16016 February 1999 LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0561999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr ML18106B0571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr ML20205P1671999-01-31031 January 1999 a POST-PLUME Phase, Federal Participation Exercise ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML18106B0491999-01-28028 January 1999 LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr ML18106B0401999-01-18018 January 1999 LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr ML18106B0251998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr 1999-09-30
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Public Service Electric and Gas Company Corbin A. McNeill, Jr. Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 Vice President -
Nuclear August 20, 1985 Mr. Steven A. Varga, Chief Operating Reactor Branch 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Varga:
LICENSED OPERATOR REQUALIFICATION PROGRAM
.Through a .series of letters beginning on August 9, 1983, Public Service Electric & Gas. Company (PSE&G) received approval for modifi-cations to our then existing Licensed Operator Requalif ication Program. The approved changes basically consisted of integrating the Salem Unit 2 Simulator into the program and administering one quarter of the annual written examination at the end of each of the 4 two-week training shifts.
Included in your approval letter (dated May 4, 1984) was a request to submit an annual report, each year for two years, on the effec-tiveness of the revised program. An attachment to that letter outlined the desired contents of the report. The second annual report follows and responds to each-of the four major topic areas individually.
TOPIC 1 Any modifications, including the reason for the modifications, made to the program within the conditions specified under Section 50.54(i-l) of 10CFR Part 50.
RESPONSE 1 No changes which affected the scope, time allotted for the program, or frequency in conducting different parts of the program were made.
The following changes were implemented during the 1984-85 Requali-fication Cycle:
( 8508280220 850820 I PDR : ADOCK 05000311 V . . PDR
Mr. S. A. Varga 8-20-85
- 1. The simulator was integrated into the entire cycle so that each trainee experienced a minimum of eight hours on the simu-lator each two-week segment. Because of Emergency Operating Procedure Training, each operator spent approximately 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> on the simulator during the annual cycle.
- 2. A time slot during each two-week segment was allotted for Operating Information and Industry Experiences. This allows timely discussion of current topics, such as design changes, LER's, SOER's, INPO Findings, etc.
- 3. The annual operational examination was conducted in the same basic manner as the NRC operator licensing simulator and plant walk-thru examinations. Written examinations continue to be administered at the end of each two-week segment.
- 4. The plant specific job analysis was utilized to develop lesson objectives. -
- 5. "Guest Expert" lecturers from the station and Company were utilized, as appropriate.
It is our intent to continue with future licensed operator requali-fication training in the same manner; without any major changes.
TOPIC 2 The licensee's evaluation of the revised program including=meeting commitments of the preplanned lecture series, annual requalification examination results, and any notable changes in on-the-job perform-ance.
RESPONSE 2 The preplanned lecture series schedule was met for all shifts.
For all intents and purposes, the simulator was available 100%
of the time.
Annual examination results were approximately the same. Our goal is fcir tcital performance-based training. Test questions are based on published instructional objectives. Instructional objectives were developed from the nuclear control operator (NCO) and shift supervisor (SS) task lists. The operators respond well to this type of examinatio~ and we are encouraged by both their performance and attitude. In addition to this performance-based testing and the agreed upon 33% change in questions each administration, we also:
- 1. Conducted a peer evaluation of each examination. An SRO li-censed or certified instructor performed this function.
Mr. S. A. Varga 8-20-85
- 2. Had an instructional technologist review each examination prior to administration. This was done to improve question clarity, grammar, and incorporate testing expertise into the program and staff.
No absolute correlation between on-the~job performance and the revised program can be drawn; howeve~ the shorter requal cycle allows for better feedback. In addition, the Unit 2 Simulator enhances operator capabilitiesi especially during emergency con-ditions.
TOPIC 3 Voluntary comments on the revised program by training staff instruc-tors and licensed personnel.
RESPONSE 3 There is a very positive attitude among licensed personnel concern-ing the program. Scheduling the training throughout the year allows for better coverage of topics and does not take the operator away from the plant for eight continuous weeks as was the case before.
Students submit course evaluations at the end of each training shift; these comments have been generally supportive of the new format. Comments on substance are incorporated into the program whenever possible. The cycle curriculum and schedule is developed by a Training Review Group that consists of Operations and Training personnel.
Staff instructors are enthusiastic about the program as well.
The shorter turnover of students provides better feedback and keeps the instructors better attuned to the needs of the students.
TOPIC 4 A summary of written, oral, and simulator examination results including any additional retraining required by the program.
RESPONSE 4 As previously stated, the annual examination results were excellent.
Two SRO's failed the simulator examination based on our observation that they were using poor management techniques during accident and transient plant conditions. One SRO averaged less than 80%
on his written examinations. They are all presently undergoing appropriate remedial training in accordance with our approved Requalification Procedure.
Mr. S. A. Varga 8-20-85 Overall, we feel that the program continues to improve and is effective. Our goal is to provide sound, performance-based training for all personnel. In March, 1985, all Salem Licensed Operator Programs were accredited by INPO.
Sincerely, C Mr. Donald C. Fischer Licensing Project Manager Mr. Thomas Kenney Senior Resident Inspector