Similar Documents at Salem |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 ML18106A6821998-06-24024 June 1998 Revised Charting Our Future. ML18106A6681998-06-17017 June 1998 Charting the Future. ML18106A2571998-01-19019 January 1998 Nuclear Business Unit Future Objectives. ML18106A2131997-12-15015 December 1997 Safety Evaluation Supporting Rev to TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing ML18102B3331997-02-28028 February 1997 Rev 0 to Cfcu Return Piping Inside CTMT,221F Temp Effect. ML20133D2201996-12-0606 December 1996 Root Cause Analysis of Struthers-Dunn Operate-Reset Relay Latch Failures for Salem Generating Station ML20133D2251996-10-30030 October 1996 Struthers-Dunn Model 255XCXP Relay Root Cause Evaluation for Salem Nuclear Generation Station ML18102A3231996-07-0101 July 1996 Reg Guide 1.121 Assessment of Indications at Salem Unit 2. ML18102A1591996-06-0404 June 1996 Fuel Handling Accident Analysis Radiological Evaluation. ML20101M6601996-03-24024 March 1996 Supplemental Submittal in Response to NRC GL 87-02/USI A-46, 'Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.' ML18102A1321996-03-15015 March 1996 Change 2EC-3332 to Rev 0 to Design Analysis, 125 Vdc Battery Charger Replacement. ML18102B0201996-02-28028 February 1996 Rev 0 to Evaluation of Structures for Increased Temps Due to Updated Main Steam Line Break. ML20129K1031995-07-10010 July 1995 Exam of Fasteners from Salem Nuclear Generating Station ML18101A7481995-05-19019 May 1995 Safe Shutdown Equipment List Rept for Salem Generating Station Units 1 & 2 ML18101A7491995-04-25025 April 1995 Relay Evaluation Rept, Volumes 1 & 2, for Salem Generating Station Units 1 & 2 ML18101A7501995-04-20020 April 1995 Seismic Evaluation Rept, for Salem Generating Station ML20134K1031995-03-24024 March 1995 Organizational Effectiveness Assessment Rept for Sngs, ML18102B6541995-03-24024 March 1995 Organizational Effectiveness Assessment Rept for Plant, Redacted Version ML18101A4391994-12-21021 December 1994 Fire Protection Review of Salem Reactor Coolant Pump Oil Collection Sys, Dtd 941221 ML20134C5791994-10-23023 October 1994 Salem/Maint SC.MD-GP.SW-0001(Q) Svc Water Silt Survey, Rev 5 ML18106B0541994-01-31031 January 1994 Criticality Analysis of Salem Units 1 & 2 Fresh Fuels Racks. ML18100A7971993-12-23023 December 1993 Simulator Four-Year Certification Rept. ML20069M2221993-10-15015 October 1993 Flux Thimble Thermocouple Ultrasonic Profilometry & Eddy Current Encircling Coil Insp of Stored Thimble Tubes Jul-Aug 1993 ML18100A6281993-09-16016 September 1993 Updated Page A4-4 of Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis, Changing Figure Numbers A5-1 & A5-2 to A4-1 & A4-2 at End of First Paragraph ML18100A6801993-08-20020 August 1993 Engineering Evaluation of Sgs 1 & 2 Control Room Evacuation for Fire Induced MOV Hot Shorts as Discussed in NRC Info Notice 92-018. ML20045B8801993-05-21021 May 1993 Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis for Salem Nuclear Generating Station, Units 1 & 2. ML18100A3401993-04-28028 April 1993 Licensing Rept for Spent Fuel Storage Capacity Expansion Pse&G,Salem Generation Station,Units 1 & 2. ML18096B3561993-02-11011 February 1993 Cycle 8 Peaking Factor Limit Rept. ML20135A8141992-12-29029 December 1992 Control Room Overhead Annunciator Lock-Up of 921213 ML18096B1661992-11-13013 November 1992 Rev 1 to Fracture Toughness Analysis for Salem Units 1 & 2 Reactor Pressure Vessels to Protect Against Pressurized Thermal Shock Events,10CFR50.61. ML18096B0081992-09-0202 September 1992 Analytical Data Rept, for Project 28173 ML18096A8061992-06-17017 June 1992 Rev 0 to Salem Unit 2 Response to Generic Ltr 92-01,Rev 1, 'Reactor Vessel Structural Integrity.' ML18096A8051992-06-17017 June 1992 Rev 0 to Salem Unit 1 Response to Generic Ltr 92-01,Rev 1, 'Reactor Vessel Structural Integrity.' ML18096A5831992-03-31031 March 1992 Rev 1 to Estimated Frequency of Loss of Off-Site Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations. ML18095A5151990-07-31031 July 1990 Vol 1 to Spring 1990 NDE of Selected Class 1 & Class 2 Components of Salem Generating Station,Unit 2. ML18095A3691990-07-26026 July 1990 Unit 1 Decommissioning Rept. ML18095A3681990-07-26026 July 1990 Unit 2 Decommissioning Rept. ML18095A3791990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co. ML18094B2241989-12-28028 December 1989 Simulator NRC Certification, Vols I-III ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20086U2571989-03-31031 March 1989 Estimated Frequency of Loss of Offsite Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations ML18093B2021988-09-30030 September 1988 Special Rept on Spare CRD Mechanism Weld Refurbishments. ML18093A7601988-02-18018 February 1988 Appendix R/Breaker Coordination as-Found Review (Pre-Audit 1987). ML18093A5471987-12-10010 December 1987 Breaker Coordination W/Respect to External & Internal Hazards. ML18093A4531987-10-14014 October 1987 Justification for Continued Operation of Salem Units 1 & 2 W/Outstanding Fire Protection Concerns. ML18093A4131987-10-0101 October 1987 Justification for Continued Operation of Salem Units 1 & 2 W/Outstanding Fire Protection Concerns. ML18093A3781987-09-16016 September 1987 Rev 7 to, Westinghouse Engineering Svcs Rept for Salem Nuclear Generating Station Units 1 & 2 Concerning RHR Sys Mid-Loop Operation Re NRC Generic Ltr 87-12. 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
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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NUCLEAR OVERSIGHT COMMITTEE FOURTH QUARTERLY REPORT OCTOBER 22, 1984 Membership:
Dr. M. B. Gottlieb, Chairman Dr. s. Levy Dr. K *. c. Rogers Admiral E. P. Wilkinson Dr. W. F. Witzig
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1 PDR ADOCK 05000272 /1 R PDR
PAGE 1 NUCLEAR OVERSIGHT COMMITTEE FOURTH QUARTERLY REPORT The fourth meeting of the Nuclear Oversight Committee (NOC) of Public Service Electric & Gas Company (PSE&G) was held during the evening of September 5, 1984 and on September 6 and 7, 1984.
Vice Presid-ent Nuclear Response to the NOC's Third Quarterly
The Not is 'appreciative of management's response to the NOC's Third Quarterly Report and in giving the needed attention to personnel staffing ~nd the management of the safety review
- process.
Relative to the safety review process, the NOC believes that the revised Nuclear Department Organization should enhance safety through clearer communication channels and a better definition of responsibility and accountability.* Regarding the new Nublear Safety Advisory Board structure, the NOC ackn6wledge~ that the Vice President ~ Nuclear feels the need of a ~afefy review group reporting ~irectly to his off ice to provide assurance of Nuclear Department safety performance.
- However, the NOC continues to believe th~t the primar~ need is for a safety review group reporting at a higher level and consisting mainly of outside members. The rationale for this belief is that PSE&G sho~ld have an independent body which reviews. the Vice President - Nu~lear act~vities and reports to higher levels. However, a satisfactory alternative is to . :"
implement the proposed arrangement:
- Nuclea~ Safety Advisory Board re~orting to-the Vice President - Nuclear, Nuclear Safety Assurance* group reporting to the Senior Vice President, and .the NOC composed of outside members reporting to senior management and/or the PSE&G Board of Directors.
The NOC does not feel it was effective in communicating,. in its last quarterly report~ two of its concerns to management in the areas of nuclear operations support and nuclear engineering. Specifically, these two conc~rns are:
- 1. The backlog of design change requests (DCR)1 and,
- 2. The addressing of longer term, generic problems with an emphasis on root.cause determination and long term remedies.
PAGE 2 Both of these areas are addressed again. in t_his report.
During this quarter, the NOC reviewed Nuclear Operations
. Support and Nuclear Engineering: *Personnel Reen.ii ting and Assimilation: "Zero Defects": Upper.Management Involvement: and lastly, Action Plans-NRC Milestones and Follow Up. This review was discussed with Messrs. Eckert and Uderitz on September 7, 1984.
Nuclear Operations Support and Nuclear Engineering
.The NOC continues to be concerned about the Engineering support of Station operations, the DCR/DCP backlog and the identificati6n of generic or fundamental aspects of plant trips. These primary areas. are developed in the* following:
- 1. Engineering support for operations has improved over the past year, but further improvement shOuld be attained. The NOC perceives a lack of problem recognition which.inhibits the development of methods to address the problem. With resources monopolized by high priority items and exacerbated by outages, long term plant reliability-improvements fall further behind.
- 2._ The NOC believes that the backlog of DCR's and DCP's is excessive. It appears .that high priority jobs are being done, but the continued sequence of unplanned outages places a drain bn engineering resources that has resuited in an increased backlog* of lower priority DCR's. The NOC believes that these lower priority tasks should be studied to identify those that could be safely eliminated thus making resources. available for the higher priority tasks. Tnis elimination review should be carried out by the about-to-be-created, Change Control Board.
There are a number of tasks which have been subject to very long delays. This backlog problem was recognized by MAC_in its report and the NOC believes that a plan should be implemented by preparing a schedule to add~e~s the close-out of DCR's and iricorporation of Design Change Packages (DCP). The NOC suggests that the. process used by the Salem Maintenance Department to -
reduce its backlog of work orders be considered by Nuclear Engineering to address its DCR/DCP backlog.
The NOC urges that a plan and schedule, complete with milestones, be prepared to reduce the backlog.
Additional internal or contract personnel may be required.
PAGE 3
- 3. The NOC continues to emphasize to management the need to aggressively pursue root causes, generic or fundamental aspects of plant trips and unplanned outages. It is recognized that high priority items may conflict with root cause efforts. In the long term it is essential that the reasons for the succession of failures be identified in order to break out of the "bad luck" pattern. The NOC recommends that a small experienced group, perha~s in Licensin~ and Reliability, be assigned this responsibility. This group could address questions such as: Is there some pattern that can be discerned in this broader perspective? Are there changes to equipment (i.e., the removal of unused test gear) or_changes in supervision, operational procedures, methods, or training which would change this pattern of performance?
Consideration of assigning an engineering "mother" to each system is also suggested.
Personnel Recruiting and Assimilation The NOC recognizes the size of the effort required to bring
_aboard the large number of qualified personnel as stated in the
- staffing plan, 1,760 by the end of 1984. Good progress is being made in this area. For example, the priority positions ~s identified in Action Plan 2.4.5 are mostly filled (18 out of 19) and the remaining one is expected to be filled in early October, 1984. Th~ key training positions identified in Action Plan 2.7.4 are 85% filled (29 out of 34), somewhat behind the schedule date of April, 1984. Ih the area of exempt recruiting, the year to date results are 153 acceptances with another 140 exempt personnel to be hired by year end.* In addition, approximately 100 non exempt personnel are to be recruited by year end. These tasks are formidable.
At the projected rate of hiring to year end, it will be-difficult to achieve th~se objectives. Since quality personnel' are essential to safe operations, special management attention
- will be required to achieve the recruiting objectives. The NOC also notes that as~imilation of this large riumber of new personnel is a requirement just as important and time consuming.
"Zero Defects" For the lack of a better title, the NOC has borrowed from
- NASA the term "Zero Defects" to describe a limited term, intensive effort for improved plant reliability, availability
PAGE 4 and safe operations. We know that the on-line availability of the Salem units is below management's expectation and below iridustry average performance. While a significant part of this unavailability is due to unusual equipment failures (e.g.,
turbine generators), personnel errors, .component deficiencies, component wearout, and plant trips have also contributed to the situation. The NOC recommends that a special, temporary program be implemented to strive for Zero Defects to keep the Salem plants safely on-line. The progr~m could incl~de such actions as:
o Using th~ most-experienced pe~sbnnel and/or extra personnel to carry out tests on partly disabled critical systems such as vital power busses7 o requiring apprentice personnel to demonstrate their procedures and planned actions prior to performing actions; o implementing plant-tours to identify deficiencies such as vibrations in the piping or air ingestion at pumps, and to take appropriate action before a plant shutdown might result; o .. eliminating superfluous equipment whicih could lead to plant trips (e.g., 2PR47);
- o coordinating engineering or QA participation in valve line-ups to assure correctness (this should also be implemented on balance of plant systems);
o implementing multi~discipline task force and management participation to resdlve post trip reviews; o and takirig other specific actioris PSE&G management feels would be effective in such a "Zero Defect" effort.
Upper Management Involvement in Post Plant Trip Review~
The NOC comment in this area is not a criticism of the dedication nor the amount of on-site presence of the Vice President - Nuclear, which is extensive. Rather, the comment is intended to deal with actions that senior management can take to improve the morale and spirit of the nuclear operation, particularly in post-trip reviews. With respect to post-trip reviews, it is suggested that upper management involvement and drive be more visible in encouraging the identification of root causes and the implementation of corrective action without,
- however, interfering with th~ r~sponsibility and authority of the Vice President - Nuclear. Plant trips frequently have
PAGE 5 safety implications. The primary objective should be to ensure, in a time urgent manner, the thorough investigation and implementation of corrective action a~ dictated by safety.
Upper level mariagement involvement on-site should facilitate decision making, encourage professional rigor and assure ear1ier availability 6f resources.
This management presence and ,involvement would se.nd a clear signal to assist in achieving an attitude of excellence in plant operations and engineerin~ ~ersonnel; one of pride in a safe, competent operation on the part, not only of management and engineering personnel, but even more importantly, of the non-exempt level employees.
Action Plan -*NRC Milestones and Follow Up
. An impressive number of manhours has been expended with good results on the Action Plans. Most of the milestones are being accomplished on schedule. An administrative* review of.
each Actio.n Plan is required to assure that the NRC commitment is met. Some of these commitments are required in the very near future in Action Plans 2.1.1, 2.1.2, 2.1.4, 2.2.1, 2.3.1, and 2.4.5. The administration of the plan should assure itself ~hat there are no misunderstandings with the NRC concerning wh~t constitutes Action Plan close out and NRC notification of same.
PSE&G has expended (and continues to expend) major resources to carry out the numerous Action Plans. Completion of the Actio~ Plans will_be followed by an implementation phase and then a phase of evaluating implementation effectiveness. The NOC will watch with gre~t inte~est these processe~. It is recommended that the follow up program be designed to provide feedback to make any changes necessary to the plan s6 it
- accomplishes its purpose.