ML20133K480
| ML20133K480 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/16/1985 |
| From: | Williams J TOLEDO EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20133K483 | List: |
| References | |
| 1197, NUDOCS 8510220036 | |
| Download: ML20133K480 (10) | |
Text
--
TOLEDO
% EDISON Docket No. 50-346 JOE WILUAMS.,Ja s
- w. a== - *o.,
License No. NPF-3 lj@lllOs Serial No. 1197 October 16, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United Stated Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
The enclosed materials comprise Revision 2 to the Davis-Besse Course of Action submitted to you on September 10, 1985 (Serial No. 1182). A list of effective pages and document control receipt containing instructions for revising this document are included in the revision package. The document control receipt must be returned to Toledo Edison Company to ensure compliance with our document control procedures.
Very truly yours,
.-_A_ _ i
- VJM:lah Enclosures cc: DB-1 NRC Resident Inspector r
DOC
/
P THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43052
-, C
-AOi 1 EFFEL11VE F r.BLE L - i. L O Uii S E OF 0,2T;uu 1 4.: 1. - ;.
THIS LIST OF EFFECTIVE PAGES IS ISSUED FOR INFORMATION ONLY VOLUME 1 EFFECTIVE PAGES REVISION
===
==
==
TABLE OF CONTENTS PAGE i
REV. 2 PAGE ii INITIAL ISSUE PAGE iii REV. 2 PAGE iv INITIAL ISSUE SECTION I - INTRODUCTION PAGES 01 - 08 INITIAL ISSUE SECTION II.A PAGES 09 - 11 INITIAL ISSUE SECTION II.B.1 PAGES 12 - 35 INITIAL ISSUE SECTION II.B.2 PAGES 36 - 37 INITIAL ISSUE SECTION II.B.3 PAGES 38 - 42 INITIAL ISSUC PAGE 43 REV. 2 PAGE 44 INITIAL ISSUE PAGE 45 REV. 2 PAGE 46 INITIAL ISSUE SECTION II.C.1 PAGES 47 - 56 INITIAL ISSUE SECTION II.C.2 PAGES 57 - 63 INITIAL ISSUE SECTION II.C.3 PAGES 64 - 72 INITIAL ISSUE SECTION II.C.4 PAGES 73 - 74 INITIAL ISSUE SECTION II.C.5 PAGES 75 - 77 INITIAL ISSUE SECTION II.C.6 PAGES 78 - 80 INITIAL ISSUE SECTION II.C.7 PAGES 81 - 91 INITIAL ISSUE SECTION III - CONCLUSIOllS PAGES 92 - 93 INITIAL ISSUE REFERENCES 01 PAGE INITIAL ISSUE ACRONYM GLOSSARY PAGES 01 - 02 ItJI T I AL ISSUE VOLUME 2
==
TABLE OF CONTENTS PAGE i
REV. 2 PAGE ii INITIAL ISSUE PAGE iii REV. 2 PAGE iv INITIAL ISSUE IV APPENDICES 01 PAGE INITIAL ISSUE APPENDIX b.1.1 PAGE 01 INITIAL ISSUE D-B MGT. STRUC. ORG. CHART 01 PAGE INITIAL ISSUE NUC. ENG. DIV. ORG. CHART 01 PAGE INITIAL ISSUE PLANT MAINT. ORG. CHART 01 PAGE INITIAL ISSUE APPErIDIX B.2.1 PAGES 01 - 11 INITIAL ISSUE AFFENDIX C.1.1 PAGE 01 INITIAL ISSUE PAGE O2 REV. 2 FINDINGS, CORRECTIVE ACTIONS, AND GENERIC IMPLICATIONS REPORTS CURRENT REVISION PLAN NO. 1A L 18/1C REV. 2 PLAN NO. 1D REV. 2 PLAN NO.
5, 6L7 REV. 2 PLAN NO. 8 REV. 2 PLAN NO. 9A/98 REV. 2 PLAN NO. 15A REV. 2 PLAN NO. ISB REV. 2 PLAN NO. 16 REV. 3 PLAN NO. 18 REV. 2 PLAtt NO. 26 REV. 4 PLAN NO. 27 REV. O
f
.e...-e i%GE.
- FFEC T i s L i,.C E. E L-i. _ UL: 2_
C-
..i., i I bi,
1,-u;_-i.,
APPENDIX C.1.2 PAGE 01 INITIAL ISSUE FINDINGS, CORRECTIVE ACTIONS AND GENERIC IMPLICATIONS REPORT PLAN NO. 12 REV. 2 APPENDIX C.1.3 PAGE 01 INITIAL ISSUE FINDINGS, CORRECTIVE ACTIONS AND GENERIC IMPLICATIONS REPORT PLAN NO. 10 REV. 2 APPENDIX C.1.4 PAGES 01 - 02 INITIAL ISSUE APPENDIX C.2.1 PAGES 01 - 12 INITIAL ISSLE APPENDIX C.2.2 PAGES 01 - 04 INITIAL ISSUE APPENDIX C.2.3 PAGE 01 INITIAL ISSUE APFENDIX C.3.1 PAGES 01 - 12 FIGURE C.5.1.1 THRU INITIAL ISSUE FIGURE C.O.1.17 APPENDIX C.3.2 PAGE 01 INITIAL ISSUE COVER LETTER DATED 7-16-95 INITIAL ISSUE PAGES 01-34 L 66 INITIAL ISSUE PAGES OS - 85 NOT ISSUED
- APPENDIX C.3.3 PAGE 01 REV. 2 APPENDIX C.4.1 PAGES 01 - 25 INITIAL ISSUE APPEllD I V C.4.2 PAGES 01 - 03 INITIAL ISSUE PAGE 04 REV. 2 PAGE 05 REV. 2 AFFENDIX C.5.1 PAGE 01 INITIAL ISSUE APPEtJDIX C.7.1 PAGE 01 INITIAL ISSUE APPENDIX III.1 PAGE 01 INITIAL ISSUE I.A PAGES 01 - 02 INITIAL ISSUE I.B PAGE 03 INITIAL ISSUE II.A PAGE 04 INITIAL ISSUE II.B PAGE 05 INITIAL ISSUE III.A PAGE 06 INITIAL ISSUE IV.A PAGE 07 INITIAL ISSUE APF EtJDI X III.2 PAGE 01 INITIAL ISSUE SUMMARi SCHEDULE FLOWCHART 01 PAGE INITIAL ISSUE WOR}:ItiG SCHUDULE SHEETS 01 - 03 I'NITIAL ISSUE
+ CONTAINS PROFRIETARY INFORMATION NOTE: I!1I T I AL ISSUE DOES NOT CONTAIN FOOTNOTES i
TABLE OF CONTENTS VOLUME 1 PAGE I.
Introduction.
.1 II.
Toledo Edison's Course of Action A.
Overview.
.9 B.
Detailed Course of Action.
.12 1.
Restructuring and Strengthening of the Nuclear Mission.
.12 Summary of Major Changes Within the Nuclear Mission.
.13 New Organizational Structure of the Nuclear Mission.
.16 Key Management Appointments
.18 Consolidation and Redirection of Nuclear Engineering.
.22 Centralization of all Planning Activities.
.25 Reatructuring of Maintenance Organization.
.26 Training Program Enhancement.
.27 Additional Staffing.
.29 Additional Responsibilities for the Assistant V.P., Nuclear.
.31 Improvement of Management Practices.
.31 Reassessment of Existing Corrective Action Programs.
.34 2.
Incorporation of Existing Performance Improvement Programs.
. 36 Performance Enhancement Programs.
. 37 SALP Improvement Programs
. 37 3.
Maintenance Improvement Progran.
.38 Reorganization of the Maintenance Department
.39 Administrative and Technical Procedures.
.40 Training
.42 Preventive Maintenance.
.43l Spare Parts and Materials Control..........
431 2
Engineering Interface and Support.
. 44 Plant Cleanliness and Material Readiness.
. 44 2
Maintenance Facilities Improvement
.45l i
Rev. 2
TABLE OF CONTENTS PACE VOLUME 2 IV.
Appendices Appendix B.I.1 - Charts of Organization.
..,.1 Appendix B.2.1 - Reassignment of Performance Enhancement Program (PEP) and SALP Improvement Program Activities..
.1
- Items which will be given high priority emphasis.
2
- Items which will be completed as scheduled..
.4
- Items which will be integrated into the normal Course of business.
6 Appendix C.1.1 - NURE( 1154. Table 5.1 Equipment Deficiencies
- Index of Findings, Corrective Actions and Generic Implications Reports.
.2 2*
Appendix C.I.2 - Reliability of Safety Related Valves.
1 Appendix C.I.3 - Reliability of the PORV.
1 Appendix C.I.4 - Confirmatory Testing.
1 Appendix C.2.1 - Actions to Improve Decay Heat Reliability
- Actions Relating to Auxiliary Feedwater Which Will Be Accomplished Prior To Startup.
.2
- Actions Relating to Auxiliary Feedwater System Which Are Longer Term.
.8
- Action Related to the Auxiliary Steam System.
..8
- Actions Related to the Motor-Driven Auxiliary Feedwater Pump.
.8 Appendix C.2.2 - Actions Related to SFRCS.
.1 Appendix C.2.3 - Probabilistic Evaluation of AFWS Reliability.
...1 Appendix C.3.1 - Transient Analysis Program Results.
.1 Appendix C.3.2 - Analyses of Event Effects on Equipment.
...1 Appendix C.3.3 - Single Failure Evaluations of Engineered Safeguards Systems.
...1 2
Appendix C.4.1 - Actions Related to Operating Procedures and Training.
...1
- Overall Findings.
..2
- Specific Findings..
...9
- Classification and Reporting of Events..
24 iii
- This appendix was previously revised at Revision i but not noted as such.
Rev. 2
Preventive Maintenance The program for Preventive Maintenance is being subjected to improvements from several perspectives. The newly formed Nuclear Plant Systems Department has been assigned responsibility for review of selected plant 2
systems. Results of the review will be used to improve the quality and effectiveress of the preventive maintenance program. Ongoing reviews of the results of testing, corrective maintenance, and preventive mainte-nance will provide additional information to upgrade the preventive maintenance program. To facilitate the incorporation of improvements to the Preventive Maintenance Program, the services of professional consul-tant personnel are being obtained from B&W, Bechtel, and several other experienced organizations. As disct'ssed previously, a central planning organization independent of the maintenance organization has been established to develop and implement an integrated plant maintenance and modifications schedule.
In order to assure Preventive Maintenance is completed in a timely manner, the schedule will assign higher priorities to the performance of Preventive Maintenance. The schedule will also ensure that a coordinated approach is used to complete preventive and corrective maintenance activities.
Spare Parts and Materials Control A program for upgrading spare parts and materials control has been devel-oped and is in the process of implementation. Specific aspects of the program which deal with spare parts adequacy and the inventory control system are being expedited. Aggressive implementation of this program coupled with the hiring of the Materials Manager (see Section II.B.1) will Rev. 2 43 r
under a supervisor reporting directly to the Assistant Plant Manager, Maintenance. The crew is devoted to a systematic, room-by-room, level-by-level walkdown of the plant. The crew is responsible for repairing minor problems, identifying larger maintenance action items, initiating work requests, and establishing schedules and priorities for a dedicated cleaning staff assigned to the crew.
A second feature of the progran has been the assignment of daily plant inspection responsibilities to each member of the Maintenance Department management and staff. Each individual has a specific area of the plant which he must inspect daily. Guidance has been provided to the individu-als as to what specifically to inspect for.
Essentially, each individual is looking for deficiencies related to his particular craft. Deficiencies are documented on Work Requests. Cleaning items are placed on punchlists which are routed to planning and scheduling, or to the composite clean-up crew.
Inspection schedules are being rotated on a monthly basis to assure that the entire plant is inspected in this manner every six months.
The requirements of the above programs are being incorporated into a new procedure entitled " Conduct of Maintenance," being developed by the Assistant Plant Manager, Maintenance. The procedure will formally estab-lish management policies concerning the duties and responsibilities of all Maintenance Department personnel and give specific guidance as to the overall goals and objective of the Maintenance Department. The current schedule for approval and issuance of this procedure is October 30, 1985.
2 Rev. 2 45
TABLE OF CONTENTS VOLUME 1 PAGE I.
Introduction.
.1 II.
Toledo Edison's Course of Action A.
Ove rview.
.9 B.
Detailed Course of Action.
.12 1.
Restructuring and Strengthening of the Nuclear Mission.
.12 Summary of Major Changes Within the Nuclear Mission.
.13 New Organizational Structure of the Nuclear Mission.
.16 Key Management Appointments
.18 Consolidation and Redirection of Nuclear Engineering.
.22 Centralization of all Planning Activities.
.25 Restructuring of Maintenance Organization..
.26 Training Program Enhancement.
.27 Additional Staffing.
.29 Additional Responsibilities for the Assistant V.P., Nuclear.
.31 Icprovement of Management Practices..
.31 Reassessment of Existing Corrective Action Programs.
34 2.
Incorporation of Existing Performance Icprovement Programs.
36 Performance Enhancement Programs..
. 37 SALP Improvement Programs
. 37 3.
Maintenance Improvement Program.
.38 Reorganization of the Maintenance Department
.39 Administrative and Technical Procedures.
.40 Training
.42
.43l Preventive Maintenance.
2 Spare Parts and Materials Control..........
431 Engineering Interface and Support.
44 Plant Cleanliness and Material Readiness.
44 2
Maintenance Facilities Improvement
.45l 1
Rev. 2
TABLE OF CONTENTS PAGE VOLUME 2 IV.
Appendices Appendix B.1.1 - Charts of Organization.
.1 Appendix B.2.1 - Reassignment of Performance Enhancement Program (PEP) and SALP Improvement Program Activities..
1
- Items which will be given high priority emphasis....
.2
- Items which will be completed as scheduled...
.4
- Items which will be integrated into the normal course of business.
.6 Appendix C.1.1 - NUREG 1154, Table 5.1 Equipment Deficiencies s
- Index of Findings, Corrective Actions and Generic Implications Reports..
.2 2*
(
Appendix C.1.2 - Reliability of Safety Related Valves..
.1 Appendix C.1.3 - Reliability of the FORV.
.1 Appendix C.1.4 - Confirmatory Testing.
.1 Appendix C.2.1 - Actions to Improve Decay Heat Reliability
- Actions Relating to Auxiliary Feedwater Which Will Be Accomplished Prior To Startup...
.2
- Actions Relating to Auxiliary Feedwater System Which Are Longer Term.
.8
' Action Related to the Auxiliary Steam System.
.8
- Actions Related to the Motor-Driven Auxiliary Feedwater Pump.
.8 Appendix C.2.2 - Actions Related to SFRCS.
.1 Appendix C.2.3 - Probabilistic Evaluation of AFWS Reliability.
.1 Appendix C.3.1 - Transient Analysis Program Results.
.1 Appendix C.3.2 - Analyses-of Event Effects en' Equipment.
..n.
.1 Appendix C.3.3 - Single Failure Evaluations of Engineered Safeguards Systems.....
.1 2
Appendix C.4.1 - Actions Related to Operating Procedures and Training.
.1 -
- Overall Findings.
.2
- Specific Findings....
.9
- Classification and Reporting of Events.
.24' ili
- This appendix was previously revised at Revision 1 but not noted as=
such.
Rev. 2
I TABLE C.1.1.1 INDEX OF FINDINGS, CORRECTIVE ACTIONS AND GENERIC IMPLICATIONS REPORTS Action Plan No.
Revision Title 1A, Ib, IC 1
Auxiliary Feed Pumps Overspeed Trips -
i Preliminary
[
ID 2
AFPT Overspeed Trip Throttle Valve Problem f
-_ Preliminary
[
5,6,7 2
SFRCS Trip /MSIV Closure j
i 8
2 Davis-Besse Main Feed Pump Turbine and
[
Control System Failures - Preliminary 9A, 9B 2
Davis-B' esse Turbine Bypass Valve
(
Actuator Failure i
1 10 2
Pilot Operated Relief Valve (PORV).
f Operation i
2 12 2
Auxiliary Feedwater System Valves AF599 and AF608 ISA (Later)
Source Range Nuclear Instrumentation NI-1, Channel 2 l
l 15B (Later)
Source Range Nuclear Instrumentation i
NI-2, Channel 1
[
16 3
Main Steam Header Pressure 2
l 18 2
Startup Feedwater Valve SP-7A Problem
(
Analysis
{
l 26 3
Service Water Transfer - Preliminary 27 3
Main Steam System Valve MS-106 - Preliminary l
l 1
I i.
j i
i f
I i
t i
i 1
This report is provided in Appendix C.1.3 i
2 This report is provided in Appendix C.1.2 i
'I i
)
~f f
Appendix C.I.1 2
-Rev. 2
_ -. _ _ _ _._.. _ _. _.,. _. _ _ _-