ML19323B952
| ML19323B952 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/18/1979 |
| From: | Dunning T Office of Nuclear Reactor Regulation |
| To: | Lynd S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19323B948 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8005140451 | |
| Download: ML19323B952 (4) | |
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UNITED STATES
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WASHING TON, D. C. 20555 Y
',/ p answ NOTE TO: Sue Lynd, FMEA Study Coordinator FROM:
T. Dunning, Section Leader, ICSB, DSS N
THRU:
R.M.Satterfield, Chief,ICSB,DSSg,(.l
SUBJECT:
FMEA INFORMATION REQUESTED BY THE PRESIDENTS TMI COMMISSION ICSB requirements for and use of FMEA's are as follows.
The responses are keyed to the unsigned June 15, 1979 note to the DSS Branches requesting this FMEA information:
1.
R.G. 1.70 requires an FMEA to be submitted in SAR's to demonstrate the single failure criterion has been met with the design of the reactor trip system and the portion of the protection system used to initiate and control operation of the engineered safety features systems and
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essential auxiliary supporting systems.
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2.
The FMEA is used to demonstrate how the requirements of the General Design Criteria and Part 50.55a(h) (i.e. IEEE-279) are met. The FMEA is submitted in the SAR.
3.
The staff reviewr the applicants FMEA to assure that the design satis-fies the design bases requirements. The conclusions drawn from the re-view contribute to bases for acceptability of the design.
4.
The philosophy of failure modes and effects analysis is applied throughout our case revier process, b'
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i T. Dunning, Sec 'on Leader Instrumentation and Control Systems Branch Division of Systems Safety cc:
V. Moore 1
1 V. Benaroya F. Rosa
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U.S. NUCLEAR REGULATORY COMMISSION November 1978 o
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(,egf,) REGULATORY GUIDE e.e*
OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 1.70 STANDARD FORMAT AND CONTENT OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS LWR EDITION k
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Rsvision 3 November 1978 Regulatory Guide 1.118, " Periodic Testing of Electric Power and Pro-tection Systems."
7.2 Reactor Trip System For standardized systems, it is preferred that the information listed be supplied in a topical report and that the topical report be referenced in the appropriate place in the SAR.
7.2.1 Description 7.2.1.1 System Description.
Provide a description of the reactor trip system to include initiating circuits, logic, bypasses, interlocks, i
redundancy, diversity, and actuated devices.
Any supporting systems l
should be identified and described. Those parts of any system not required for safety should be identified.
7.2.1.2 Design Basis Information. Provide the design basis infor-mation required by Section 3 of IEEE Std 279-1971. Provide preliminary logic diagrams, piping and instrumentation diagrams, and location layout drawings of all reactor trip systems and supporting systems in the PSAR.
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7.2.1.3 Final System Drawings.
In the FSAR, provide electrical i
schematic diagrams for all reactor trip systems and supporting systems, i
final logic diagrams, piping and instrumentation diagrams, and location layout drawings.
Describe the differences, if any, between the logic diagrams and schematics submitted in the PSAR and those in the FSAR and the effects on safety-related systems.
7.2.2 Analysis Provide analyses, including a failure mode and effects analysis, to demonstrate how the requirements of the General Design Criteria, IEEE Std 279-1971, applicable regulatory guides, and other appropriate cri-teria and standards are satisfied.
In addition to postulated accidents and failures, these analyses should include, but not be limited to, con-siderations of instrumentation installed to prevent or mitigate the con-sequences of:
1.
Spurious control rod withdrawals, 2.
Loss of plant instrument air systems, i
3.
Loss of cooling water to vital equipment, 4.
Plant load rejection, and 5.
-Turbine trip.
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,l Revision 3 November 1978 The analyses should also discuss the need for and method of changing to more restrictive trip setpoints during abnormal operating conditions such as operation with fewer than all reactor coolant loops operating.
Reference may be made to other sections of the SAR for supporting systems.
7.3 Engineered-Safety-Feature Systems For standardized systems, it is preferred that the i'nformation listed be supplied in a topical report and that the topical report be referenced in the appropriate place in the SAR.
7.3.1 Description 7.3.1.1 System Description.
Provide a description of the instru-mentation and controls associated with the engineered safety features (ESF), including initiating circuits, logic, bypasses, interlocks, sequencing, redundancy, diversity, and actuated devices. Any supporting systems should be identified and described.
Those parts of any system not required for safety should be identified.
7.3.1.2 Design Basis Inforrration. Provide the design basis infor-mation required by Section 3 cf. Tf5td 279-1971. For the PSAR review,
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l provide preliminary electrical schematic diagrams, logic diagrams, piping and instrumentation diagrams, and location layout drawings of all engineered-safety-feature instrumentation, control systems, and supporting systems.
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- 7. 3.1. 3 Final System Drawings.
In the FSAR, provide electrical
' schematic diagrams for all ESF circuits and supporting systems, and final logic diagrams, piping and instrumentation diagrams, and location layout drawings.
Describe the differences, if any, between the logic diagrams and schematics submitted in the PSAR and those in the FSAR and the effects on safety related systems, v 7.3.2 Analysis Provide analyses, including a failure mode and effects analysis, to demonstrate how the requirements of the General Design Criteria and IEEE Std 279-1971 are satisfied and the extent to which applicable regulatory guides and other appropriate criteria and standards are satisfied.
In addition to postulated accidents and failures, these analyses should include considerations of (1) loss of plant instrument air systems and (2) loss of cooling water to vital equipment. The method for periodic testing of engineered-safety-feature instrumentation and control equip-ment and the effects on system integrity during testing should be described.
7.4 Systems Required for Safe Shutdown For standardized systems, it is preferred that the information listed be supplied in a topical report and that the topical report be referenced
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in the appropriate place in the SAR.
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