|
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18066A6641999-09-30030 September 1999
Proposed Tech Specs Re Surveillance Implementation
ML18066A6501999-09-17017 September 1999
Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8
ML18066A5911999-07-30030 July 1999
Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432
ML18066A5691999-07-19019 July 1999
Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS
ML18066A5011999-06-11011 June 1999
Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9
ML18068A5851999-05-0303 May 1999
Proposed Tech Specs Section 3.5,converting to ITS
ML18066A4551999-04-0707 April 1999
Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1
ML18066A4431999-03-30030 March 1999
Proposed Tech Specs Section 3.7,converting to ITS
ML18066A4251999-03-22022 March 1999
Revised TS Pages for ITS Section 3.4
ML20207B2501999-03-0101 March 1999
Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS
ML18066A3281998-11-0909 November 1998
Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17
ML20195E4451998-11-0909 November 1998
Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI
ML20154N2901998-10-12012 October 1998
Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs
ML18066A3021998-09-14014 September 1998
Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages
ML20151Z8111998-09-14014 September 1998
Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1
ML18066A2011998-06-17017 June 1998
Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses
ML18066A1841998-06-10010 June 1998
Simulator Four-Year Test Rept & Schedule for Performance Testing for Next Four-Year Period.
ML18068A3451998-04-29029 April 1998
Rev 9 to EI-9, Offsite Radiological Monitoring.
ML18068A3441998-04-28028 April 1998
Rev 3 to EI-6.6, Gamma E Determination.
ML18065B2271998-04-21021 April 1998
Reactor Vessel Neutron Fluence Methodology.
ML20217C3101998-03-24024 March 1998
Palisades,Review of Actual Fluence Determination
ML18065B1801998-03-13013 March 1998
Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown
ML18065B2021998-03-10010 March 1998
Rev 7 to Relocated TS Per GL 89-09.
ML18067A8161998-01-26026 January 1998
Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20
ML18066A4901998-01-20020 January 1998
Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment.
ML20197G3851997-12-17017 December 1997
Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan
ML18065B2321997-10-24024 October 1997
Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18067A7071997-10-0101 October 1997
Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12
ML18067A6731997-09-0303 September 1997
Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys
ML18067A6771997-09-0303 September 1997
Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16
ML18067A6001997-06-27027 June 1997
Proposed Tech Specs Revising Electrical Power Systems
ML18067A4701997-03-28028 March 1997
Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174
ML20137H5901997-03-27027 March 1997
Proposed Tech Specs Change Request Re Change in Co Name
ML18067A4531997-03-26026 March 1997
Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown
ML18067A5151997-02-11011 February 1997
Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18065B2011996-12-24024 December 1996
Rev 11 to Offsite Dose Calculation Manual.
ML18065B0861996-11-27027 November 1996
Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20.
ML20134P4071996-11-19019 November 1996
Suitability,Training & Qualification Plan, Rev 16
ML20137G3871996-10-29029 October 1996
Rev 6 to Relocated TS Per NRC GL 89-09
ML18065B0331996-10-25025 October 1996
Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS
ML18065B0171996-10-18018 October 1996
Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR
ML18065A9551996-10-0202 October 1996
Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves
ML18065A9111996-09-0404 September 1996
Proposed Tech Specs 3.7, Electrical Power Systems.
ML20117K9581996-09-0303 September 1996
Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments
ML18065A8631996-08-14014 August 1996
Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items
ML18065A7661996-06-10010 June 1996
Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys.
ML18065A7651996-06-10010 June 1996
Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys.
ML18065A5861996-03-29029 March 1996
Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1
ML18065A8021996-02-21021 February 1996
Rev 2 to EM-09-13, ISI Pressure Testing Program.
ML20137G3631996-02-16016 February 1996
Rev 10 to Offsite Dose Calculation Manual
1999-09-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18068A3451998-04-29029 April 1998
Rev 9 to EI-9, Offsite Radiological Monitoring.
ML18068A3441998-04-28028 April 1998
Rev 3 to EI-6.6, Gamma E Determination.
ML18065B2271998-04-21021 April 1998
Reactor Vessel Neutron Fluence Methodology.
ML18065B2021998-03-10010 March 1998
Rev 7 to Relocated TS Per GL 89-09.
ML20197G3851997-12-17017 December 1997
Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan
ML18065B2321997-10-24024 October 1997
Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18067A5151997-02-11011 February 1997
Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18065B2011996-12-24024 December 1996
Rev 11 to Offsite Dose Calculation Manual.
ML18065B0861996-11-27027 November 1996
Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20.
ML20134P4071996-11-19019 November 1996
Suitability,Training & Qualification Plan, Rev 16
ML20137G3871996-10-29029 October 1996
Rev 6 to Relocated TS Per NRC GL 89-09
ML18065A7661996-06-10010 June 1996
Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys.
ML18065A7651996-06-10010 June 1996
Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys.
ML18065A8021996-02-21021 February 1996
Rev 2 to EM-09-13, ISI Pressure Testing Program.
ML20137G3631996-02-16016 February 1996
Rev 10 to Offsite Dose Calculation Manual
ML20137G3581996-02-15015 February 1996
Rev 6 to CPC Pnp Process Control Program
ML18064A8141995-06-29029 June 1995
Procedure EOF App B, INPO Emergency Response Assistance Agreement, Dtd 950426
ML20100H2621995-06-18018 June 1995
Rev 2 to Reactor Vessel Exam Program Plan Interval 2,Period 3 & Interval 3,Period 1
ML18064A8881995-03-16016 March 1995
Rev 0 to Palisades Nuclear Power Plant Third Interval ISI Program for Class 1,2 & 3 Components & Supports, Vols I & II
ML18064A6301995-03-0303 March 1995
Rev 7 to App H, Emergency Planning EOF Training Matrix.
ML18064A6341995-02-27027 February 1995
Project Plan,Alloy 600,Palisades Nuclear Plant, Rev 1,dtd 950227
ML20072K7741994-07-15015 July 1994
Rev 0 to Palisades Performance Enhancement Plan
ML20072K7641994-07-0606 July 1994
Rev 1 to Palisades Plant Restart Plan from 1994 Forced Outage
ML18059B0481994-06-0303 June 1994
Attachment 4 to Procedure EM-09-13,Rev 1, ISI Pressure Testing Program Procedure.
ML20069D3081994-05-24024 May 1994
Suitability,Training & Qualification Plan
ML20069G2511994-05-20020 May 1994
Rev 30 to Procedure MO-7A-2, Emergency Diesel Generator 1-2 (K-6B)
ML20069G2391994-05-20020 May 1994
Rev 30 to Procedure MO-7A-1, Emergency Diesel Generator 1-1 (K-6A)
ML20064E4831994-03-0606 March 1994
ASME Section XI Repair Program, 0054-00101-001-100,rev 0
ML20064E5011994-03-0404 March 1994
Procedure for Application & Exam of Weld Overlay Repairs to Austenitic Stainless Steel Piping Systems, 0054-00101-001-101,rev 0
ML18059A6981994-02-23023 February 1994
Reactor Vessel Integrity Project Plan.
ML18059A6881994-02-15015 February 1994
Editorial Changes to Rev 6 to Emergency Implementing Procedure EI-6.13, Protective Action Recommendations for Offsite Populations.
ML18059B0201993-12-31031 December 1993
Methods of Alleviating Adverse Consequences of Fluctuating Water Levels in Great Lakes - St Lawrence River Basin, Rept to Govts of Canada & Us,Dtd 931231
ML18059A5541993-11-19019 November 1993
Rev 4 to Attachment 3 to Procedure REC-1, Recovery Plan Format.
ML18059A4781993-10-27027 October 1993
Rev 5 to Administrative Procedure 9.11, Engineering Analysis.
ML18059A4231993-10-0707 October 1993
Rev 0 to Palisades Plant Pressurizer Safe End Crack Repair Action Plan.
ML20059A5181993-09-30030 September 1993
Public Version of Rev 36 to General Ofc Emergency Planning Procedure,App G, Emergency Telephone Numbers. W/931019 Release Memo
ML18058B7871992-12-15015 December 1992
Rev 3 to HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18058B0341992-05-11011 May 1992
Rev 6 to Odcm.
ML18058A4331992-05-0707 May 1992
Rev 5 to General Ofc Emergency Planning Procedure EOF-4, Communication Support Team, Page 3,reflecting Editorial Changes
ML20090A3401992-02-27027 February 1992
Rev 5 to ODCM
ML18058A1461992-01-27027 January 1992
Rev 45 to General Office Emergency Planning Gort/Eof Procedures Index
ML18058A1471991-12-0909 December 1991
Rev 5 to General Ofc Emergency Planning Procedure EOF-3, Emergency Operations Facility Administrator. Approval Summary Encl
ML18058A1441991-12-0909 December 1991
Rev 5 to General Ofc Emergency Planning Procedure EOF-4, Communication Support Team. Approval Summary Encl
ML18058A1451991-12-0909 December 1991
Rev 6 to General Ofc Emergency Planning Procedure EOF-2, Emergency Operations Facility Director. Approval Summary Encl
ML20091S2361991-12-0909 December 1991
Rev 8 to General Ofc Emergency Planning Procedure GEN-3, On-Shift Sys Power Controller. Approval Summary Encl
ML18058A1421991-12-0909 December 1991
Rev 7 General Office Emergency Planning Procedure GORT-1, General Office Response Team (Gort). Approval Summary Encl
ML18058A1431991-12-0909 December 1991
Rev 10 to General Ofc Emergency Planning Procedure GEN-1, Overview. Approval Summary Encl
ML18057B3281991-10-17017 October 1991
Rev 2 to Procedure EI-15.2, Quarterly Communications Test Telephone Number,Verifications.
ML20086T2811991-09-16016 September 1991
Rev 0 to Functional Description FC-888,covering Replacement of All Four Channels of Reactor Protection Sys Power Supply Assemblies,Trip Unit Assemblies,Interconnection Modules, Bistable Trip Units & Auxiliary Trip Units
ML18057B0221991-05-10010 May 1991
Rev 15 to EM-09-04, Inservice Testing of Selected Safety- Related Pumps, Reflecting Complete Rewrite of Procedure to Omit Vertical Lines
1998-04-29
[Table view] |
Text
...
ATTACHMENT Consumers Power Company Palisades Plant - Docket 50-255 SUPPLEMENT 1 TO NUREG-0737, MILESTONE ACTIVITY - SUBMITTAL OF AN UPDATED DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM PLAN June 7, 1983 r--8306130335 -830607___ _ 11 Pages PDR ADOCK 05000255 F PDR OC0683-0002D-NL02
- e I. INTRODUCTION The program to review the human factors of the Palisades Nuclear Plant Control Room was initiated in late 1980. A substantial amount of the work has already been completed. The control room configuration has been documented, a full scale mockup has been constructed, procedures have been walked-through utilizing that mockup, and much of the control room has been evaluated against human factors guidelines. Some further work in these areas remains to be completed. Assessment of the findings and the formulation, evaluation, and implementation of corrective action has begun. The basic objectives are identical to those in NUREG-0700, but because the review was initiated far in advance of that document's issue, there are some differences in methodology. However, we believe they are differences in form and not in substance and that the end results of the Palisades human factors review will be consistent with the guidance provided by NUREG-0700.
The human factors review will make use of information from NRC mandated updating programs - such as the updating of emergency procedures. Consumers Power Company, however, does not plan to delay the control room review effort at Palisades until these other programs are complete. Because the "window" Revised May 1983 OC0683-0002C-NL02
2 to do significant work in the control room is constrained in practice to planned refueling shutdowns, delaying the control room review would jeopardize the ability to do any significant improvements in the next shutdown (1983). As information from these programs becomes available, it will be factored into the review. For example, new walk-throughs will be conducted if necessary and corrective action implemented as appropriate during plant shutdowns.
The schedule for completion of the control room review at Palisades is summarized in Table I-1.
I.2 Revised May 1983 OC0683-0002C-NL02
- 3 TABLE I-1 ESTIMATED SCHEDULE FOR PALISADES CONTROL ROOM REVIEW TASK ESTIMATED COMPLETION DATE Submit Program Plan to NRG March 1982 Complete Review of Main Panels December 1982 Identity Short Term Improvements February 1983 Required Update Program Plan and Submit to NRG June 1983 Implement Short-Term Improvements 1983 Outage Complete Review of Control Room June 1984 Including Review of New Emergency Procedure Guidelines Submit Interim Control Room Design September 1984 Review Report to NRG Implement Long Term Improvements Subsequent Outages Issue Final Control Room Determined by Plan Design Review Report I.3 Revised May 1983 OC0683-0002C-NL02
II. MANAGEMENT AND STAFFING The performance of the human factors review is the responsiblity of a team made up of personnel from Consumers Power Company (both engineering and operations), MPR Associates, and an independent outside consultant, Dr TB Sheridan of the Massachusetts Institute of Technology. The responsibility and functions of the members of the team are described below; resumes are included in Appendix B of this plan.
MPR Associates, Inc.
MPR is responsible to provide the major portion of the detailed management and review effort. This includes providing the full scale mockup and control room drawings, conducting the procedure walk-throughs, comparing the control room to the detailed guidelines, and establishing potential modifications. For this purpose MPR has assembled a working group consisting of Messrs H Estrada, D H Harrison, J Hibbard and A Zarechnak, with supporting services such as drafting. It may be augmented by other MPR staff personnel where special skills or experiences are required.
Revised May 1983 OC0683-0002B-NL02
2 Consumers Power Company Plant operations was previously represented on the review by Mr W S Skibitsky and is presently represented by Mr C Kozup. Mr Skibitsky was the Operations Superintendent and holder of a senior reactor operator license at the Palisades Plant until late 1982. Beginning in early 1983, Mr Kozup replaced Mr Skibitsky as Operations Superintendent and member of the review team.
Messrs Skibitsky and Kozup participate in planning, review results, and assure that plant operators' input is provided. Individual licensed operators participate in several aspects of the review including the procedure walkthroughs, environmental survey, and review of operating experience. Engineering is represented on the review team by four individuals: Mr R L Muzzi from the plant engineering staff and Messrs R R Biggs and K A Toner and R E Schrader from the general office engineering staff. Messrs Muzzi, Biggs and Toner participate in the planning, review results, and assure that engineering input from various sources is incorporated. This includes other ongoing plant modifications and obtaining necessary information from the architect-engineer and other contractors to Consumers Power Company. Mr Schrader's responsibilities include the human factors review of ongoing and future control room modifications. Messrs Skibitsky, Muzzi, Biggs and Toner participated in a Consumers Power Human Factors Training Seminar in January, 1982.
11.2 Revised May 1983 OC0683-0002B-NL02
3 Outside Consultant Dr T B Sheridan, Professor* of Engineering and Applied Psychology at the Massachusetts Institute of Technology provides the review team with assistance and an overview of the human factors aspects of the review such as methodology, interpretation of guidelines, assessment of error potentials, and evaluations of potential improvements.
II.3 Revised May 1983 OC0683-0002B-NL02
APPENDIX B PALISADES CONTROL ROOM REVIEW TEAM RESUMES
CHARLES S KOZUP Business Address: Consumers Power Company Palisades Nuclear Plant Route i2, Box 154 Covert, MI 49043 BS Metallurgical Engineering - 1971 MS Metallurgical Engineering - 1980 BS from Cleveland State University MS from Uriiversity of Pittsburgh Experience: Consumers Power Company - 1981 to Present Operations Superintendent-Palisades - 1982 Direct* activities in Operations Department Shift Technical Advisory - Palisades - 1981 Operation technical support, on shift Senior Plant Engineer - Westinghouse Electric Corporation Idaho Falls - 1977-1981 Supervised operation,* maintenance and training activities Senior Engineer, Westinghouse Electric Corporation Bettis Atomic Power Lab - 1973-1977 Technical followup of naval reactor core production Product Research Supervisor - Premier Industrial Corporation, Cleveland, Ohio -
1971-1973 Technical support in all areas
~*
ROBERT ELLSWORTH SCHRADER Business Address: Consumers Power Company 1945 W Parna~l Road Jackson, MI 49201 Education: US Navy Electronics Technician School, Class "A" Great Lakes, IL - 9/50 - 7/51 Basic electronics through operation and maintenance of communication, radar, sonar and test equipment.
Consumers Power Company, General Off ice Jackson, MI - 5/61 (2 weeks)
Mathematics Course consisted of slide rule, logarithms, exponentials; algebra and trigonometry review; introduction to calculus symbols.
Jackson Junior College Jackson, MI - 6/61 - 7/61 (8 weeks)
Basic reactor tedhnology, applied reactor physics and health physics; use and inter-pretation of radiation measurement equipment.
DeVry Technical Institute Chicago, IL - 7/61 - 1/62 Electronic Controls for Automation Electronic fundamentals, circuitry and controls of motor control circuits, pro-cess controls, servo controls and nuclear instrumentation.
International Correspondence Schools Division I - Electrical Engineering Completed in 1965 North Central Michigan College Petoskey, MI Refresher Mathematics Course (Ill)
Completed January, 1969
- 1:' L. i * ...., I Experience:
- Consumers Power Company September 1956 to Present B C Cobb Generating Plant (510 MWe)
Muskegon, MI - 9/56 - 5/61 Laboratory Technician; Senior Laboratory Technician; Efficiency Analyst Plant efficiency calculations and monitor-
_ing of thermal performance, instrument maintenance, combustion control equipment maintenance and boiler water chemistry *
(900# and 2100# Combustion Engineering boilers).
Big Rock Point Nuclear Plant Charlevoix, MI - 2/62 - 1/68 Instrument & Control Technician; Plant Technician Performed trouble~shooting, calibration, performance testing, modifications, etc.
on all nuclear and conventional instrument and control systems associated with the plant.
2/68 - 10/76 Instrument & Control Supervisor Responsible for calibration and maintenance of all plant instrumentation and control systems. Instructed reactor operator license candidates in various phases of plaot instrumentation including neutron monitoring systems, reactor protection system, manual reactor control system, feedwater control system, turbine bypass valve control system, and miscellaneous lectures on plant systems. Responsible for design and implementation of plant modifications involving instrument and control and plant electrical systems.
10/76 - 9/77 Senior Technologist Responsible for plant projects; served as Project Engineer and Project Leader.
Completed projects involving ASME BP&V,Section XI and ANSI-B31.1 piping codes in addition to electrical and instrumentation
- ystems *.
"-- .... , ... ~.* *-'\..->.'
10/77 - 6/82 Technical Superintendent Responsible for all plant project engi-neering: reactor engineering: Inservice
- Inspection per ASME-BP&V Code, Section X~;
Shift Technical Advisor programs (post-TMI) and serving as On Duty Superintendent, as required. For approximately two years, responsibilities included direction of the onsite Quality Control group.
General Off ice - Nuclear Operations Department Jackson, MI - 7/82 to Present General Supervisor, Nuclear Instrumentation
& Control, Nuclear Plant Support Department.
Responsibilities include providing engineering assistance to Company operating nuclear plants in the areas of instrumentation &
Control~ plant electrical systems; process computer system and plant modifications.
US Navy - 7/50 - 5/54 Electronic Maintenance; attained Petty Officer Second Class (ET2).
- Central Paper Company Muskegon, MI - 6/54 - 10/54 Paper manufacturing Thomas A Edison, Inc Grand Rapids, MI - 10/54 - 8/56 Installation and servicing of dictating and centralized dictation systems.
Licenses Held: Senior Reactor Operator License (SOP-1174)
Expired - Big Rock Point Plant - 1969
