ML20209H586

Rev 3 to Course of Action

ML20209H586
Person / Time
Site:	Davis Besse
Issue date:	10/28/1985
From:	TOLEDO EDISON CO.
To:
Shared Package
ML20209H568	List: ML20209H561 ML20209H586 ML20209H648 ML20209H680
References
NUDOCS 8511110174
Download: ML20209H586 (60)

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PAGE 1 EFFECTIVE PAGES D-B COURSE OF ACTION 28-Oct-85 THIS LIS T OF EFFECTIVE PAGES IS ISSUED FOR INFORMATION ONLY VOLUME 1 EFFECTIVE PAGES REVISION

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TAELE OF CONTENTS PAGE i

REV. 2 PAGE ii REV. 3 Pt.JE iii REV. 3 PAGE iv REV. 3 SECTION I - INTRODUCTION PAGES 01 - 08 INITIAL I SSLIE SECTION II.A PAGES 09 - 11 INITIAL I SELIE SECTION II.B.1 PAGES 12 - 33 INITIAL ISSUE SECTION II.B.2 PAGES 36 - 37 INITIAL ISSUE SECTION II.B.O PAGES 38 - 42 INITIAL ISSUE PAGE 43 REV. 2 PAGE 44 IMITIAL ISSUE PAGE 45 PEV. 2 PAGE 46 INITIAL ISSUE SECTION II.C.1 PAGES 47 - 56 IN!TIAL ISSUE SECTION II.C.2 FAGES 57 - 60 INITIAL ISSUE SECTION II.C.0 PAGES 64 - 72 INITIAL ISSUE SECTION II.C.4 PAGES 70 - 74 INITIAL ISSUE SECTICN II.C.5 PAGES 75 - 77 INITIAL ISSUE SECTION II.C.6 PAGES 78 - 80 INITIAL ISSUE SECTION II.C.7 PAGES 81.- 82 INITIAL ISSUE PAGES 83 - 86 REV. 3 PAGES 87 - 39 INITIAL ISSUE PAGES 90 - 91 REV. 3 SECTION III - CONCLUSIONS PAGES 92 - 93 INITIAL ISSUE REFERENCES 01 PAGE INITIAL ISSUE ACRONYM OLOSSARY PAGES 01 - 02 INITIAL ISSUE VCLUME 2

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TABLE OF CONTENTS FAGE i

REV. 2 PAGE ii REV. 3 FAGE iii REV. 3 PAGE iv REV. 3 IV APPENDICES 01 PA3E 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 AFPENDIX B.2.1 PAGES 01 - 11 INITIAL I SSLIE AFFENDIX C.1.1 PAGE 01 INITIAL ISSUE PAGE O2 REV. 3 FINDINGS, CORRECTIVE ACTIONS. AND GENERIC IMPLICATIONS RCPCRTS CURRENT REVISION PLAN NO. 1A & 1B/1C REV. 2 PLAN NO. 1D REV. 3 FLAN NO.

5, 6&7 REV. 2 PLAN NO. 8 REV. 2 PLAN NO. 9A/99 REV. 2 PLAN NO. 15A REV. 2 PLAN NO. ISS REV. 2 PLAN NO. 16 REV. 3 8511110174 BS1031 PDR ADOCK 05000346

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4 t e PAGE 2 EFFECTIVE PAGES D-B COURSE OF ACTION 28-Oct-85 PLAN NO. 18 REV. 2 PLAN NO. 26 REV. 4 PLAN NO. 27 REV. 3 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 ACTICNS AND GENERIC IMPLICATIONS REPORT PLAN NO. 10 REV. 3 APPENDIX C.1.4 PAGES 01 - 02 INITIAL ISSUE APPENDIX C.2.1 PAGES 01 - 12 INITIAL ISSUE APPENDIX C.2.2 PAGES 01 - 04 INITIAL ISSUE APPENDIX C.2.3 PAGE O1 IH!TIAL ISSUE APPENDIX C.3.1 PAGES (.

- 12 FIGURE C.3.1.1 THRU INITIAL ISSUE FIGURE C.3.1.17 APPENDIX C.3.2 PAGE 01 REV. 3 COVER LETTER DATED 7-16-S5 INITIAL ISSUE PAGES 01-34 & 66 INITIAL ISSUE PAGES 35 - S5 NOT ISSUED

• COVER LETTER DATED 9-20-85 REV. 3 PAGES 01 - 22 REV. 3 APPENDIX C.3.3 PAGE 01 REV. 2 APPENDIX C.4.1 PAGES 01 - 25 INITIAL ISSUE APPENDIX C.4.2 PAGES 01 - 03 INITIAL ISSUE PAGE 04 REV. 2 PAGE 05 REV. 2 APPENDIX C.5.1 PAGE 01 INITIAL ISSUE APPENDIX C.7.1 PAGES 01 - 10 REV. 3 APPENDIX III.1 PAGE 01 INITIAL ISSUE TABLE OF ACTIONS TO BE COMPLETED PAGES 01 - 06 REV. 3 APPENDIX III.2 PAGE 01 INITIAL ISSUE

SUMMARY

SCHEDULE FLOWCHART 01 PAGE INITIAL ISSUE WORKING SCHEDULE SHEETS 01 - 03 INITIAL ISSUE

• CONTAINS FROPRIETARY INFORMATION NOTE: INITIAL ISSUE DOES NOT CONTAIN FOOTNOTES

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.s TABLE OF CONTENTS PAGE C.

Actions Related to the June 9, 1985 Event.

47 1.

Event Investigation..........

47 Investigation and Troubleshooting.

50 Root Cause Findings.

54 Corrective Actions and Generic Implications.

54 Summary of Actions Taken.

55 2.

Decay Heat Removal Reliability Improvement Program....

57 Task Force Objectives................

59 Task Force Approach.........

59 Summary of Recommendations / Activities.

62 3.

Analysis Program 64 Capability to Mitigate Loss of Feedwater Events.

. 65 Effect of the June 9 Event on Plant Components.

66 Single Failure Susceptibility of the AFW/SFRCS.

68 4.

Review of Operations Procedures and Training.

73 5.

Control Room Improvement Program.

75 6.

Shift Technical Advisor.

78 7.

System Review and Test Program.

81 Program Objectives

... 82 Scope of Review 83 3

Program Approach

... 86 System Performance Review 87 Corrective Action Generation.

89 Surveillance Test Review.

90 3

Test Program.

... 91 III. Conclusions.

.92 References and Acronym Glossary ii Rev. 3

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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

- Index of Findings, Corrective Actions and Generic Implications Reports.

.2 3

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 on Equipment.

.1 3

Appendix C.3.3 - Single Failure Evaluations.

.1 Appendix C.4.1 - Actions Related to Operating Procedures and Training.

.1

- Overall Findings.

.2

- Specific Findings.

.9

- Classification and Reporting of Events.

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TABLE OF CONTENTS PAGE Appendix C.4.2 - Effect of Physical Security Provisions on Operations.

1 Apperdix C.S.1 - Specific Actions Related to Control Room Deficiencies.

1 Appendix C.7.1 - Selection of Systems for the System Review and Test Program.

1 3

- Development and Implementation of the Restart Test Program.

9

- System Review and Test Program Results.

10 Appendix III.1 - Actions to be Implemented by Toledo Edison.

1 Appendix III.2 - Schedule of Actions to be Implemented Prior to Restart.

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Identify testing requirements necessary to verify the adequacy of new system modifications.

Prepare and conduct a test program to assure 'that systems important to safe plant operation are fully functional.

Scope of Review The systems selected for review in this program are those deemed to have the most impact on the safe operation of the Davis-Besse Station. Not all of the systems included in the scope of review are covered by Technical Specifications; and conversely, not all those systems mentioned in Technical Specifications are included in the scope of this review.

The systems included in the scope of this review and the basis for their selection are contained in Appendix C.7.1.

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(THIS PAGE INTENTIONALLY LEFT BLANK MATERIAL MOVED TO APPENDIX C.7,1) 3 84 Rev. 3

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(THIS PAGE INTENTIONALLY LEFT BLANK MATERIAL MOVED TO APPENDIX C.7.1) 3 85 Rev. 3

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Program Approach Five System Review Groups have been established to conduct this program.

Systems are assigned to each in accordance with the groupings

. indicated in Table I, Appendix C.7.1.

The groups consist of Toledo Edison 3

engineering personnel and experienced support personnel from the nuclear industry. For each system, the lead review responsibility will be as-signed to a specific Toledo Edison individual. The support personnel are a

highly qualified industry representatives experienced in system design, operation, and testing.

4 The groups will conduct a review of past system performance by selected review of available documentation and interviews of Station personnel experienced in the operation, maintenance, and testing of the systems.

The review will identify known recurring problems, and the review groups will propose corrective actions as necessary, to resolve those problems.

The groups will also review surveillance testing associated with each system to identify and resolve weaknesses in the program.

The results of these efforts will be documented by the System Review Group and then will be reviewed and approved by an Independent Process Review Committee. This group is composed of senior Toledo Edison 3

engineering personnel and other top level industry experts operating in accordance with a formal charter.

86 Rev. 3

J presented to the Independent Process Review Committee (IPRC). The IPRC 3

will review the problem evaluation and proposed corrective actions. The-IPRC will accept or reject the proposals or will recommend alternatives to the proposed corrective actions. Upon approval by the IPRC, the l3 chosen corrective action will be implemented.

Surveillance Test Review Prior to startup, the System Review Groups will evaluate the scope of surveillance testing that currently exists for their respective systems.

The groups will review the testing for completeness and adequacy of testing with respect to design basis conditions. Concerns identified by the group will be documented and proposed test outlines for newly required testing will be created. The results of each system testing review will be forwarded to the IPRC. The IPRC will review the identified concerns and concur with the need for additional testing, if appropriate. The 3

IPRC will evaluate the proposed test outline and conceptually approve the te. ting as appropriate.

After the newly generated test requirements are conceptually approved, the System Review Group will initiate the development of new or revised surveillance tests which will be processed in accordance with existing procedural programs.

90 Rev. 3

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Test Program In conjunction with the development of new surveillance test requirements, the System Review Groups will develop proposed test outlines for post modification testing on their assigned systems. If testing beyond the scope of the newly modified surveillance test program is required, an outline.for a proposed Test Procedure (TP) will be developed. These test outlines will be submitted to the IPRC in the same manner as the surveil-lance test outlines. Test Procedures will be developed following approval 3

of the outlines by the IPRC.

The new or revised surveillance tests, new test procedures, and other surveillance testing necessary to satisfy Technical Specification opera-bility requirements will be scheduled and conducted in accordance with existing plant testing programs. The results of tests performed on systems will be reviewed by the designated System Review Group.

The System Review Group will assume the responsibility for resolution of any identified problems.

' Additional details regarding the development and implementation of the Restart Test Program are provided in Appendix C.7.1.

3 91 Rev. 3

J TABLE OF CONTENTS PAGE C.

Actions Related to the June 9, 1985 Event.

. 47 1.

Event Investigation...................

47 Investigation and Troubleshooting....

50 Root Cause Findings.

....54 Corrective Actions and Generic Implications.

..................54 Summary of Actions Taken.

. ~5 5 2.

Decay Heat Removal Reliability Improvement Program....

5 7.

Task Force Objectives.

. 59 Task Force Approach.................

59 Summary of Recommendations / Activities.

62 3.

Analysis Program

..................64 Capability to Mitigate Loss of Feedwater Events..............

65 Effect of the June 9 Event on Plant Components..............

66 Single Failure Susceptibility of the AFW/SFRCS...

68 4.

Review of Operations Procedures and Training......

73 5.

Control Room Improvement Program.

. 75 6.

Shift Technical Advisor.................

78 7.

System Review and Test Program.

. 81 Program Objectives

.................82 Scope of Review 83 3

Program Approach..................

86 System Performance Review 87 Corrective Action Generation.

. 89 Surveillance Test Review.

. 90 3

Test Program.

...................91 III. Conclusions.............................92 References and Acronym Glossary 11 Rev. 3

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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 e

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

- Index of Findings, Corrective Actions and Generic Implications Reports..

.2 3

Appendix C.1.2 - Reliability of Safety Related Valves.

.1 Appendix C.1.3 - Reliability of the PORV..

.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 4

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 3

Appendix C.3.3 - Single Failure Evaluations...........

.1 Appendix C.4.1 - Actions Related to Operating Procedures and Training..............

.1

- Overall Finaings.

.2

- Specific Findings.........

.9

- Classification and Reporting of Events.....

. 24 iii Rev. 3

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l' TABLE OF CONTENTS PAGE Appendix C.4.2 - Effect of Physical Security Provisions on Operations.

1 Appendix C.S.1 - Specific Actions Related to Control Room Deficiencies..........

1 Appendix C.7.1 - Selection of Systems for the System Review and Test Program.

1 3

- Development and Implementation of the Restart Test Program.

9

- System Review and Test Program Results......

10 Appendix III.1 - Actions to be Implemented by Toledo Edison..

1 Appendix III.2 - Schedule of. Actions to be Implemented Prior to Restart.

1 e

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1 TABLE C.1.1.1 INDEX OF FINDINGS,' CORRECTIVE ACTIONS AND GENERIC IMPLICATIONS REPORTS Action

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Plan No.

Revision Title 1A, IB, IC 2

Auxiliary Feed Pumps Overspeed Trips ID 3

AFPT Overspeed Trip Throttle Valve Problem 3

5,6,7 2

SFRCS Trip /MSIV Closure - Preliminary 8

2 Davis-Besse Main Feed Pump Turbine and Control System Failures 9A, 9B 2

Davis-Besse Turbine Bypass Valve Actuator Failure 101 3

Pilot Operated Relief Valve (PORV) 3 Operation 122 2

Auxiliary Feedwater System Valves AF599 and AF608 15A 2

Source Range Nuclear Instrumentation NI-1, Channel 2 ISB 2

Source Range Nuclear Instrumentation NI-2, Channel 1 16 3

Main Steam Header Pressure 3

18 2

Startup Feedwater Valve SP-7A Problem Analysis 26 4

Service Water Transfer 27 3

Main Steam System Valve MS-106 - Preliminary 3

1 This report is'provided in Appendix C.I.3 2

This report is provided in Appendix C.I.2 Appendix C.1.1 2

Rev. 3

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