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 ML18102B4651997-06-30030 June 1997 Evaluation of Macrohabitat Utilization by Loggerhead Sea Turtles in Delaware Estuary Using Sonic & Satellite Tracking Techniques 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. ML18101B1951996-01-31031 January 1996 IPE for External Events 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 ML20138H0381994-12-15015 December 1994 Engineering Assessment of Salem Bill of Matl (BOM) Validation of Pc 4 Class Codes Used on Q Boms, Final Rept 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 ML20106E1231992-10-31031 October 1992 IPE Level II Analysis Preliminary Summary ML20138G9901992-10-0606 October 1992 Controls Equipment - Troubleshooting 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. 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARLR-N99-0448, Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With LR-N99-0449, Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With ML18107A5571999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr ML18107A5581999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20212B7221999-09-14014 September 1999 Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively LR-N99-0416, Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With ML18107A5311999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 LR-N99-0415, Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 9909131999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 05000272/LER-1999-006-02, :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.With1999-08-26026 August 1999
- 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
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 LR-N99-0379, Monthly Operating Rept for July 1999 for Salem,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With LR-N99-0380, Monthly Operating Rept for July 1999 for Salem,Unit 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With ML18107A4821999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr 05000311/LER-1999-008, :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.With1999-07-28028 July 1999
- 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
ML20210B7371999-07-21021 July 1999 Safety Evaluation Supporting Amends 223 & 204 to Licenses DPR-70 & DPR-75,respectively ML18107A4411999-07-0909 July 1999 SER Denying Licensee 980730 & 990222 Requests to Revise TS 3/4.7.6, Control Room Emergency Air Conditioning Sys, & Associated Bases to Change Acceptable Criteria for Control Room Emergency Air Conditioning System 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 05000311/LER-1999-007, :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.With1999-07-0606 July 1999
- 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
05000272/LER-1999-005-02, :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.With1999-07-0202 July 1999
- 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
ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 10) Second Interval,Second Period,Second Outage (99RF) 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 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 05000311/LER-1999-002, :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.With1999-07-0101 July 1999
- 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
05000311/LER-1999-006, :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.With1999-07-0101 July 1999
- 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
ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept LR-N99-0325, Monthly Operating Rept for June 1999 for Salem,Unit 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With LR-N99-0324, Monthly Operating Rept for June 1999 for Salem,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With 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 ML18107A4161999-06-23023 June 1999 Safety Evaluation Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions 05000272/LER-1999-004-02, :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.With1999-06-17017 June 1999
- 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
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 05000272/LER-1999-003-02, :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).With1999-06-0909 June 1999
- 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
05000311/LER-1999-005-01, :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.With1999-06-0202 June 1999
- 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
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 LR-N99-0275, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With LR-N99-0278, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 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 05000272/LER-1999-002-02, :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.With1999-05-12012 May 1999
- 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
05000311/LER-1999-004-01, :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.With1999-05-10010 May 1999
- 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
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 05000311/LER-1999-003-01, :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.With1999-05-0404 May 1999
- 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
ML20206H2631999-05-0404 May 1999 Safety Evaluation Supporting Amend 222 to License DPR-70 05000311/LER-1999-002-01, :on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With1999-05-0303 May 1999
- 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
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 1999-09-30
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NUCLEAR OVERSIGHT COMMITTEE FIFTH OUARTERLY REPORT JANUARY 18, 1985 Membership:
Dr.
M.
R. Gottlieb, Chairman Dr. S. Levy Dr. K. C. Rogers Admiral E. P. Wilkinson Dr.
W.
F. Witzig l
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PAGE 1 NUCLEAR OVERSIGHT COMMITTEE FIFTH OUARTERLY REPORT The fif th regular meeting of the Nuclear Oversight Committee (NOC) of Public Service Electric & Gas Company (PSR&G) took place on the evening of December 5, 1984 and on December 6 and 7, 1984.
Management Response to NOC Ouarterly Report of October 22, 1984 NOC finds that the Management response to the quarterly report of October 22, 1984 recognized the NOC concerns and addressed each one.
The Availability and Capacity Factor Improvement Task Force has been commissioned and is assigned the tasks of identifying ways of improving failure and root-cause analyses.
The Reliability and Assessment Group will examine the record of past equipment failures and reactor trips to determine whether generic patterns exist.
NOC looks forward to reviewing the findings of both groups at the March meeting.
The problem of DCR and DCP backlogs is being addressed in several ways.
A Change Control Board has been established to exercise better screening and priority assignments to both new and backlogged design change requests.
A new " Integrated Living Schedule" will make possible adjustments in scheduling to meet changing priorities and available resources.
Additional contract personnel have been added to reduce the backlog of DCRs awaiting final documentation.
NOC notes the serious attention being paid to the improvement of engineering support for Salem Station operations.
This area was discussed at the December meeting and is commented upon later in this report.
Action Plan Status With minor exceptions, the Action Plan is on schedule.
Of the 26 Action Plans involving NRC commitments, 12 are now complete, with another 8 over 90% complete.
Of the total estimated manpower required for all Action Plans, about 50% has VdC,15 now been expended with about 2/3 of the remainder required for Plan 2.7.3, Information Systems, which is to be the last, plan to be completed (NRC commitment date of 6/87).
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~ Concern was expressed by the Action Plan Program Director as to whether the following four Action Plans can be completed on times-Action Plan 2.2.2 Commitment Identification, Tracking and Close-out 2.4.1 Maintaining Plant Cleanliness and General Appearance at a High Standard 2.4.4 Site Protection and Emergency Preparedness pdGS 2.6.2 Enhancing Maintenance Planning, Monitoring and Control While the delays seem minor and do not represent a threat to operations or safety, NOC feels that as a matter of internal pride and of credibility to the NRC, every effort should be made to meet commitments.
ManaQement attention is urged.
The implementation and evaluation processes, associated with some of the Action Plans do not in some cases form part of the NRC commitments.
NOC strongly urges that in all cases implementation and evaluation plans he developed, includino schedules, milestones, and assignment of responsibilities.
NOC expects to review on a continuing basis the implementation and evaluation activities.
Engineering Organization Considerable progress has been made under Action Plan 2.4.5 l
"To Strengthen the Nuclear Engineering Organization and Improve Coordiantion Between Nuclear Engineering and Operations."
In particular, a review of the Nuclear Engineering organizational structure is being carried out to enhance engineering capability to efficiently and effectively support plant operations.
- Also, i
a minor DCR System is being developed to permit accelerated I
implementation of minor changes requested by Salem Operations.
f(klb The NOC recommends that the implementation of these two' programs be accelerated and that adequate engineering resources be l
committed to " mother" the specific power plant systems they are assioned.
NOC further supports the assignment of an appropriate number of encineers to Plant Operations.
)
Maintenance Work Order Racklog
}
At the last NOC meeting the committee noted the effectiveness of the Maintenance Department in reducing the work IUNo4 order backlog from a peak value of some 3,000 work orders to less than 1,300.
This performance has not continued as the present backlog now numbers the same as a year age, approximately 1,800.
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The primary contributors to this increased backlog are Unit 2 outage and the general non-outage _ backlog.
Unit 1 outage work orders declined during this same time period.
Management is encouraged to give this matter th-e same JMt attention it previously gave to this issue which greatly reduced the backlog.
NOC notes that an outage manager position has been created with project management responsibilities for monies, personnel and schedule.
This is a positive step.
Audits NOC notes that. audits from many sources are becoming more numerous and more extensive.
It is apparent that these audits place an ever-increasing load on management.
NOC raises the question as to the extent of overlap between these audits and (J(J whether the resulting burden may even affect plant safety and operations.: NOC has requested more detailed information which will provide a basis for discussions at the March NOC meeting, j/
SALP Report
'N The recent SALP report designated several areas where deviciencies were observed.
What is' important is that prompt corrective action be taken with specific responsibility for bl N correction being assigned to specific individuals.
It was not clear to NOC whether specific responsibilities had been allocated J to individuals in this respect.
/
Persistent Problems h
NOC notes that there are persistent feed water problems which are being alleviated but not resolved.
While'these problems do not represent a direct threat to safety they do pgg affect operations.
Several methods are under test which may provide additional alleviation.
NOC raises the question as to M2.
whether PSE&G Research Corp. could provide assistance.
NOC further has requested information from both Operations and Engineering as to what other persistent problems exist in the Salem Plant.
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EHC System NOC notes that the Salem Unit 1 plant trips in November, 1984'were rapidly traced to the EHC system.
Further the subst!tution of " manual" operation of the turbine while. seeking the " root cause" of the difficulty is a prudent action.
Likewise the prompt investigation of the problem by the manufacturer who used a simulator and an outside expert 'is commendable.
These apparently intermittent failures are difficult.
Where the NOC believes this problem requires improved dgt attention is in the following:
gjpg A prompt autopsy of the " cards" used in the controller was in order.
The cards were located on a portable : test table several weeks after.the trip.
There is a question whether the monitoring equipment being used on the controller would indicate an intermittent failure involving fast transients.
It is unfortunate that, due to conflicting demands, there appears to be minimum or no Nuclear Engineering involvement.
j Engineerina Manpower
~
NOC notes 'that engineering staf fing 'is now close to targets.
There do seem to be shortages in at least one type of skill--digital circuit engineering.
While such personnel are -
RAf3 hard to find, the need will surely increase as the sophistication of instrumentation and control systems increases.
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