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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206T4771999-05-31031 May 1999
Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology
ML20203J8581998-01-31031 January 1998
Rev 2 to Catawba Nuclear Station PRA Summary Rept, for Jan 1998.W/one Diskette
ML20094N0751995-10-31031 October 1995
Validation of Crest, Interim Rept
ML20117M8021995-07-31031 July 1995
CNS Standby Nuclear SW Pond Analysis
ML20094N0641995-07-31031 July 1995
Computer Program for Coupled Response Spectrum Analysis of Secondary Sys
ML20086F4711995-06-30030 June 1995
Interim Plugging Criteria 90 Day Rept
ML20098A4511995-04-30030 April 1995
Stations Replacement SG Topical Rept
ML20083N7541995-04-24024 April 1995
Rn Sys Corrosion in Stainless Steel Welds Metallurgical Analysis Rept
ML20117M7911995-02-28028 February 1995
Standby Nuclear SW Pond Physical Testing Conducted During Feb 1995
ML20077R7101994-12-20020 December 1994
CNS Units 1 & 2 10CFR50.59 Evaluation of FSAR Change Related Edsfi Deviation 50413,414/92-01-02 (IEEE 308-1974)
ML20077C5771994-11-0303 November 1994
1 Cycle 7 Interim Plugging Criteria Assessment & Projected EOC-8 Slb Leakage
ML20072T4441994-08-31031 August 1994
Selected Licensee Commitments
ML20063E2801994-01-31031 January 1994
Duke Power Co Catawba Nuclear Station Special Rept RHR Pump Vibration
ML18010B0841993-05-0505 May 1993
NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216.
ML18010A9521992-11-30030 November 1992
NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216.
ML20062G7271990-11-19019 November 1990
Eddy Current Exam Rept Catawba Unit 2 June 1990 Refueling Outage 3
ML20043E7701990-02-28028 February 1990
Rev 0 to Catawba Unit 2 Cycle 3 Core Operating Limits Rept.
ML20043E8101990-02-28028 February 1990
Rev 0 to Catawba Unit 1 Cycle 5 Core Operating Limits Rept.
ML20154K2091988-09-0909 September 1988
Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld
ML20196L6281988-05-20020 May 1988
Rev 2 to ATWS Mitigation Sys Actuation Circuitry (Amsac)
ML20212K1201987-01-23023 January 1987
Final Design Description,Atws Mitigation Sys Actuation Circuitry
ML20207H9651986-05-13013 May 1986
SPDS Software Verification & Validation Summary Package, Catawba Nuclear Station
ML20155F7451986-04-30030 April 1986
Draft Main Bearing Shell Analysis 2B Emergency Diesel Generator-Catawba Unit 2
ML20155F7381986-04-30030 April 1986
Diesel Generator 2B 7 Main Bearing Failure Rept,Low Power License Condition 13,Attachment 1,Item 9
ML20198J4071986-04-30030 April 1986
Rev 1 to Catawba Nuclear Station Diesel Engine 2A Component Revalidation Insp
ML20203N4171986-04-30030 April 1986
Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications
ML20207H9701986-04-28028 April 1986
SPDS Maint Summary Package,Catawba Nuclear Station
ML20207H9601986-04-23023 April 1986
SPDS Human Factors Program Summary Package,Catawba Nuclear Station
ML20207H8901986-03-27027 March 1986
SPDS Design Basis Summary Package,Catawba Nuclear Station
ML20210E5111986-03-25025 March 1986
Rev 13 to Pages from Analysis of Hydrogen Control Measures at McGuire Nuclear Station, Responding to Questions Transmitted by Youngblood
ML20207H9211986-03-14014 March 1986
SPDS Critical Safety Function Selection Summary Package, Catawba Nuclear Station
ML20207H9541986-03-14014 March 1986
SPDS Logic Verification Summary Package,Catawba Nuclear Station
ML20207H9501986-03-14014 March 1986
SPDS Logic Generation Summary Package,Catawba Nuclear Station
ML20207H9331986-03-14014 March 1986
SPDS Status Trees Development Summary Package,Catawba Nuclear Station
ML20138P4801985-12-17017 December 1985
Diesel Engine 2B Component Revalidation Insp
ML20137V9141985-09-25025 September 1985
Diesel Engine 2A Component Revalidation Insp
ML20215C4221985-08-31031 August 1985
Rod Swap Methodology Rept for Startup Physics Testing
ML20128E9831985-06-21021 June 1985
Diesels - Tdi Owners Group Design Review/Quality Revalidation Final Rept,Summary of Recommendations
ML20115E0231985-04-30030 April 1985
Main Steamline Break Inside Containment, Bimonthly Status Rept for Apr 1985
ML20198B5701985-02-28028 February 1985
Rev 1 to Tdi Diesel Generator Design Review & Quality Revalidation Rept, Vols 1-4
ML20090J0071984-07-31031 July 1984
Description of Deviations from Generic Emergency Response Guidelines (Westinghouse Owners Group ERG-Basic Edition)
ML20092N7021984-06-29029 June 1984
Diesel Engine 1A Component Revalidation Insp Final Rept
ML20092J2441984-06-20020 June 1984
Duke Power Co 12 H Shift Experience
ML20092J2671984-06-0808 June 1984
Util Advisor Evaluation Team Rept on Catawba Nuclear Station Shift Advisor Program,840606-08
ML20091J0561984-06-0101 June 1984
Diesel Engine 1A Component Revalidation Insp Rept
ML20091L8721984-05-31031 May 1984
Sqrt Audit Resolution for Ser,Catawba Unit 1
ML20090G6731984-04-30030 April 1984
Nuclear Physics Methodology for Reload Design
ML20083P9381984-04-17017 April 1984
Sqrt Audit Resolutions for Sqrt Audit Conducted 840313-16. W/Seven Oversize Drawings.Aperture Cards Are Available in PDR
ML20087M6281984-03-28028 March 1984
Nonproprietary, Methodology for Addressing Superheated Steam Releases to Ice Condenser Containments
ML20080U4541984-02-29029 February 1984
Rev 10 to Analysis of Hydrogen Control Measures at McGuire Nuclear Station
1999-05-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217H0201999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2
ML20216E5401999-09-0707 September 1999
Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826
ML20212B4711999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2
ML20217H0321999-08-31031 August 1999
Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2
ML20211B1281999-08-31031 August 1999
Dynamic Rod Worth Measurement Using Casmo/Simulate
ML20211A9791999-08-20020 August 1999
Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2
ML20211F3441999-08-17017 August 1999
Updated non-proprietary Page 2-4 of TR DPC-NE-2009
ML20211C1291999-08-17017 August 1999
ISI Rept Unit 1 Catawba 1999 RFO 11
ML20210R1051999-08-0606 August 1999
Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced
ML20210S2891999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2
ML20212B4871999-07-31031 July 1999
Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2
ML20209E4361999-07-0909 July 1999
SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation
ML20196K6631999-07-0707 July 1999
Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers
ML20210S2951999-06-30030 June 1999
Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2
ML20209H4501999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2
ML20209H4561999-05-31031 May 1999
Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2
ML20206T4771999-05-31031 May 1999
Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology
ML20196L1881999-05-31031 May 1999
Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology
ML20196A0001999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2
ML20206P5201999-05-14014 May 1999
Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
ML20206N8391999-05-0404 May 1999
Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr
ML20206R1811999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2
ML20196A0041999-04-30030 April 1999
Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2
ML20206N8261999-04-22022 April 1999
Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included
ML20205S5551999-04-21021 April 1999
Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML20205N3651999-04-12012 April 1999
Safety Evaluation Accepting IPE of External Events Submittal
ML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML20206R1931999-03-31031 March 1999
Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2
ML20205P9521999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2
ML20205P9561999-02-28028 February 1999
Revised Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2
ML20204C9111999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2
ML20203A2581999-02-0505 February 1999
Safety Evaluation of TR DPC-NE-3002-A,Rev 2, UFSAR Chapter 15 Sys Transient Analysis Methodology. Rept Acceptable. Staff Requests Duke Energy Corp to Publish Accepted Version of TR within 3 Months of Receipt of SE
ML20204C9161999-01-31031 January 1999
Revised Monthly Operating Repts for Jan 1999 for Catawba Nuclear Station,Units 1 & 2
ML20199K8711999-01-13013 January 1999
Inservice Insp Rept for Unit 2 Catawba 1998 Refueling Outage 9
ML20199E3071998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Catawba Nuclear Station,Units 1 & 2
ML20216F9931998-12-31031 December 1998
Piedmont Municipal Power Agency 1998 Annual Rept
ML20205E9441998-12-31031 December 1998
1998 10CFR50.59 Rept for Catawba Nuclear Station,Units 1 & 2, Containing Brief Description of Changes,Tests & Experiments,Including Summary of Ses.With
ML20206P2081998-12-31031 December 1998
Special Rept:On 981218,inoperability of Meteorological Monitoring Instrumentation Channels,Was Observed.Caused by Data Logger Overloading Circuit.Replaced & Repaired Temp Signal Processor
ML20203A4101998-12-22022 December 1998
Rev 16 to CNEI-0400-25, Catawba Unit 2 Cycle 10 Colr
ML20203A4041998-12-22022 December 1998
Rev 14 to CNEI-0400-24, Catawba Unit 1 Cycle 11 Colr
ML20198B1341998-12-14014 December 1998
Revised Special Rept:On 980505,discovered That Certain Fire Barriers Appeared to Be Degraded.Caused by Removal of Firestop Damming Boards.Hourly Fire Watches Established in Affected Areas
ML20196J8351998-12-0808 December 1998
Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys
ML20199E3221998-11-30030 November 1998
Revised MOR for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 Re Personnel Exposure
ML20198E3151998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Catawba Nuclear Station,Units 1 & 2
ML20196C0251998-11-27027 November 1998
SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station
ML20196A6881998-11-25025 November 1998
Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds
ML20196D4041998-11-19019 November 1998
Rev 1 to Special Rept:On 980618,determined That Method Used to Calibrate Wind Speed Instrumentation Loops of Meteorological Monitoring Instrumentation Sys Does Not Meet TS Definition for Channel Calibration.Procedure Revised
ML20195E5521998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2
ML20198E3261998-10-31031 October 1998
Revised Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2
ML20154M7661998-10-12012 October 1998
LER 98-S01-00:on 980913,terminated Vendor Employee Entered Protected Area.Caused by Computer Interface Malfunction. Security Retained Vendor Employee Badge to Prevent Further Access & Computer Malfunction Was Repaired.With
1999-09-07
[Table view] |
Text
Attachment 8 SPDS MAINTENANCE
SUMMARY
PACKAGE CATAWBA NUCLEAR STATION Section I: Description of SPDS Maintenance Program Section II: Summary of SPDS Related Software Modifications Section III: Listing of Applicable Correspondence Robert G. Morgan Nuclear Operations Nuclear Production Department April 28, 1986 Page 1 of 6 -
8507250150 860715 4 DR ADOCK 0500
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i Attachment 8 I. Description of SPDS Maintenance Program
~
The Safety Parameter Display System (SPDS) Maintenance Program was developed to ensure that software modifications made to the SPDS received the same degree of verification and validation (V&V) as the initial development program.
The SPDS Maintenance Program addresses both software and hardware repairs and/or modifications. Existing Duke Power Company programs were utilized to govern most administrative aspects of SPDS Maintenance V&V. These programs include: 1) the individual station Work Request procedures for hardware repairs; 2) the Nuclear Station Modification (NSM) procedures for hardware modifications; and 3) the Process Computer Unit i Software Development Procedures for controlling SPDS software revisions. Figure I illustrates the various aspects of the Maintenance Program discussed in the following paragraphs.
The initiating event in the Maintenance program is the identi-fication of an SPDS " problem". The problem may only be the revision of a parameter setpoint due to a revision in the hard copy Emergency Procedures; or it may be the enhancement of the system based upon an evaluation of data following a unit transient. The monitoring of SPDS performance is accom-
, plished by various station and General Office groups. The day-to-day monitoring function is performed by the Operations group. When unexplained alarms are received, they are brought to the attention of appropriate station personnel to resolve. Following any reactor trip the Performance group evaluates SPDS alarms which were received to ensure their validity.
When one of the responsible Station groups, or other Duke Power departments (Design Engineering, Production Support, etc.), determine a revision is necessary to the SPDS, or that a problem exists with a process parameter input to the Operator Aid Computer (OAC), the appropriate documentation is submitted.
In the case of an input failure to the OAC, a station work request would be written to have the Instrument and Electri-cal group investigate and repair the problem. This repair evolution follows Duke Power's established maintenance practices, and involves the appropriate level of procedural and Quality Assurance control for the failed device.
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Page 2 of 6
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l Attachment 8 l
Hardware modifications are governed by the Nuclear Station Modification (NSM) program. The NSM procedures ensure an appropriate level of checkout and testing is accomplished .
l prior to closing out an NSM. As in the station work request program, the NSM documentation and methodology are controlled by procedures with specific responsibilities of the various groups clearly defined. An indepth description of the Work Request and Nuclear Station Modification programs may be found in Departmental and Station Directives.
The repair and modification of instruments and their respec-tive OAC interface does not alter the logic or design of the SPDS. These particular SPDS Maintenance procedures, there-fore, do not require the additional levels of V&V that SPDS software modifications do. As in the work request and NSM j programs, the software modifications to SPDS are made using i existing administrative procedures. All software programs on the OAC are modified by the Process Computer Unit within the Production Support Department. The Process Computer Unit has written procedures governing the development and modification of computer programs. When a Station or General Office group determines a modification to the SPDS software would be beneficial, a Process Computer Program Request (Form 349773 is initiated. This form describes the recommended change and the appropriate justification for the modification. The General Office, Nuclear Operations group, coordinates the resolution to the SPDS modification requests. The problem resolutions involve the appropriate Station and General Office groups and ensures that the requested enhancement to the SPDS is being resolved properly. This verification process also ensures the resultant software design continues to meet the functional requirements of the Safety Parameter Display System. When the modification nas been finalized, j
the Process Computer Unit develops the necessary software revisions. The Process Computer Systems Engineering group in Design Engineering then conducts a " desk top" V&V of the Process Computer Unit's software change. This review is to verify the change correctly implements the resolution devel-oped by the originating groups. Once the change is endorsed by Design Engineering, the new program is implemented on the Station OAC's. Hard copy data is retrieved from the computer and is used in the final validation of the SPDS change. The Design Engineering V&V process is described in greater detail in Attachment 7, "SPDS Software Verification and Validation Summary Package."
Page 3 of 6
Attachment 8 II. Summary of SPDS Related Software Modifications o Program Request P840104-0. Implemented recommendations
- 2 and #3 made following the human factors survey of the-Catawba SPDS. It eliminated the " blinking" symbol for non-alarm indications and provided double-spacing to improve readability of alarm list displays.
o Program Request P840125-0. Modified the following Critical Safety Function (CSF) SPDS logic as indicated.
Subcriticality: Modified logic to highlight an ATWS condition on the status tree supporting display. The program request also updated the reactor trip signals in the logic.
Core Cooling: Revised RVLIS lower range setpoint from 45% to 43%.
Heat Sink: Revised steam generator level setpoints.
Also deleted main feedwater flow logic.
Coolant Inventory: Revised the Adverse Containment Condition setpoint for Pressurizer-level from 32% to 45%.
o Program Request P840129-0. Modified the SPDS Alarm Summary to retain all SPDS alarms and identify specific logic paths which cause SPDS alarm.
o Program Request P840038-0. Modified the Operator Aid Computer software to support the installation of an additional video terminal and keyboard for the Shift Technical Advisor.
o Program Request P850011-0. Developed software to identi-l fy and block invalid input alarms generated by RVLIS.
o Program Request P850080. Modified SPDS logic to prevent the spurious "Subcriticality" alarm which occurred due to the SPDS program and the OAC process parameter samp-ling frequency not being synchronized. The Modification also prevented two invalid input alarms from being
! generated during normal operating conditions.
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Attachment 8 o Program Request P85142. Modified SPDS RVLIS setpoints to reflect actual startup data.
o Program Request P85143. Modified the Catawba Unit 2 Steam Generator high level setpoint to account for the Model D5 Steam Generator.
III. Listing of Applicable Correspondence The SPDS Maintenance Program is an ongoing activity. The correspondence listed below is for the period September 4, 1984 through January 31, 1986.
Date From To Subject 10/15/84 RL Brown RG Morgan Program Request MI Moser P840104-0:
Implement Recommendations from Human Factors Survey 01/10/85 RG Morgan RL Brown SPDS Alarm Summary and LJ Cope SPDS Performance Monitoring 01/14/85 EM Geddie RL Brown SPDS Alarm Summary RG Morgan RC Collins Program Completion Date 01/21/85 RL Brown RG Morgan Program Request MI Moser P840125-0:
SPDS Logic & Setpoint Revisions 02/22/85 RG Morgan RL Brown Computer Validation of RC Collins RVLIS Inputs 02/27/85 RL Brown GB Swindlehurst Revision to Hardcopy SPDS RG Morgan Logic Diagrams 02/27/85 RL Brown RG Morgan Program Request CR Miller P840129-0:
SPDS Alarm Summary Modification Page 5 of 6
r Attachment 8 Date From To Subject 03/06/85 RG Morgan RL Brown Source Range Nuclear RC Collins Instrumentation Alarms 03/25/85 RL Brown RG Morgan Program Request JS McCraw P840038-0:
OAC Software Revisions for SIA Panel 05/08/85 RL Brown RG Morgan Program Request P850011-0:
CR Miller Computer Validation of RVLIS Inputs 09/10/85 RL Brown RG Morgan Program Request P850080:
MI Moser Spurious SPDS Alarm Following Reactor Trip &
Invalid Input Alarms 01/27/86 RL Brown RG Morgan Program Request P850142:
MI Moser Modify RVLIS Setpoints to Reflect Startup Data 01/27/86 RL Brown RG Morgan Program Request P850143:
MI Moser Modify CNS2 S/G Level Setpoints for Model D5 Steam Generator i
Page 6 of 6 l
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