ML19309D632
| ML19309D632 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 03/17/1980 |
| From: | Ross D Office of Nuclear Reactor Regulation |
| To: | Keenan T GENERAL ELECTRIC OPERATING PLANT OWNERS GROUP |
| References | |
| NUDOCS 8004110040 | |
| Download: ML19309D632 (6) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
g WASMNGTON, D. C. 20555
% **"* /
MAR 17 toog Mr. Thomas D. Keenan, Chairman General Electric Boiling Water Reactor Owners' Group Vennont Yankee Nuclear Power Corporation Rutland, Vermont 05701
Dear Mr..Keenan:
SUBJECT:
DISCUSSION OF ANALYSIS OF ACCIDENTS AND TRANSIENTS AND PREPARATION OF EMERGENCY PROCEDURE GUIDELINES We have developed additional guidance concerning the analysis of accidents and transients and the preparation of emergency procedure guidelines required by Darrell G. Eisenhut's letter dated September 13, 1979 to all licensees of operating nuclear power plants. A copy of that guidance is enclosed.
We plan to discuss the enclosed guidance with each of the operating plant owners groups at separate meetings in Bethesda, and would like to. meet with your. group at a mutually convenient time. We have been advised by Mr. Dave Waters of your group that April 2, 1980.would be an acceptable date for such a meeting.
Consequently, we have arranged for a meeting in Bethesda, Maryland on that date, to be held in Room 114, Phillips Building, at 1:00 P.M.
Please let me know if these plans are suitable.
Sincerely,
%s *V D.
. Ross, Jr., Acting Director Division of Project Management
Enclosure:
Guidance.for the Evaluation and Development of Procedures for Transients and Accidents f
l 8004110delf-O 1
ENCLOSURE.
GUIDA' ICE FOR THE EVALUATION AND DEVELOPMENT OF PROCEDURES FOR TRANSIENTS AND ACCIDENTS NUREG-0578, Section 2.1.9 position requires that procedures and operator training be developed for transients and accidents. The initiating events to be considdred should include the events presented in the FSAR, loss of -
instrumentation buses, and natural phenomena such as earthquakes, floods, and tornadoes.
For each event analyzed, control function diagrams and a sequence of event
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diagram should be provided. The control function diagrams identify the input functions (including power sources for the sensors and limitations on operating conditions), output functions such as valves / pumps controlled, and auxiliary systems needed (pneumatic, hyraulic, cooling) for each of the rele-vant control systems that could have an impact on the events whether or not the control system is safety-grade. The control function diagrams provide an effective means for evaluating the completeness of the sequence of event diagram and potential common mode failures. The control function diagrams should be applicable to all scenarios.
The sequence of event diagrams should identify major functional requirements and how they are accomplished and/or perturbed. The major functional require-ments include reactivity control, pressure and level control in the primary and secondary systems, electric power source, containment isolation, and so forth. The sequence of event diagram should contain single and multiple failures (up to 3) in both nomal control systems and mitigating systems.
The types of failures to be censidered are operator errors of omission and comission, total system failure if you don't have diversity, consequential failures, loss of.offsite power, failure of instruments and instrument buses which could mislead the operator.
It is recognized that consideration.of all these failures is an enormous effort, therefore, assumptions used to limit the number of sequence branches considered must be clearly defined and the basis for omitting branches must be documented to avoid redundant effort. The methodology used to develop the sequence of event diagrams should be described.
Analyses should be performed to provide a basis for the symptoms and time available for operator actions, and observations.
In particular, analyses should be provided for those branches of the sequence diagram where the consequences cannot be.'udged intuitively or timing of the operator action may be important. The basis for the limited analyses associated with each event should be provided consistent with the above requirements.
A general description of the computer codes used for all of the analyses should be provided and code limitations and calculational uncertainties discussed. Reference to more detailed descriptions and verification data should be provided.
Selected analyses will be audited by the staff. We will require initial conditions and other input data sufficient to perform audit calculations for the following selected analyses:
(a) steam line break (b) turbine trip without bypass (c) loss of normal feedwater flow It is recognized that the analyses will be presented for a specific plant and that other plants may have different response characteristics because of variations in control systems. Therefore, the process of assessing the applicability of those results to specific plants should be discussed to assure that the operator training and procedures that use these results will not be misleading.
The purpose of this effort is to develop guidelines for operator action following a reactor scram because of an operational occurrence or an accident.
A prerequisite for this activity is an understanding of the operator's disposi-tion with regard to the guidelines and their use. To this end, the following information should be provided:
What is the operator supposed to know by rote? For a.
Knowledge example, does he know how to actuate ECCS or must control components be identified in the procedures? What pre-cautions does he carry around in his head?
- ~
b.
Priorities What is the hierarchy for the operator performing cartain functions following a reactor scram, such as reactivity control, level control, etc.? Does the operator accomplish each function before proceeding to the next?
c.
Diagnosis What are the plant parameters that the operator monitors to diagnose the plant stability? Provide a time frame' for monitoring those parameters; for example, primary pressure and level may be monitored continuously while radiation monitors would not be scanned until 15 minutes after a reactor scram.
d.
Team Plan Describe how the guidelines are being tailored to utilize 2 or 3 operators in the control room.
The general philosophy of the guidelines should be discussed so that their application is understood. The discussion should include the basis for the procedures - such as event oriented, symptom oriented, or function oriented, and a clear description of the diagnostic process that will lead the operator into the correct procedure (or a conservative procedure). The purpose of caution statements and the time during which they are applicable should be discussed. The use of multiple procedures and the basis for departing from a procedure should also be discussed.
A flow chart should be presented with each guideline to show the various branches and a successful completion of each branch.
A discussion of the use of various material generated in this study for operator training should be provided, identifying plant-specific issues which must be resolved. A program for incorporating the results on a simulator for hands-on experience should also be provided.
A schedule for accomplishing the various phases of this study should be submitted to the staff.
- c. uavia nixel Hr. W. G. Counsil, Vice-President delear t.icensing Administrator t:uclear Engineering & C;eraticas ensumers Power Company Northea:t f;uclear Er.ergy Company 12 W::st Michigan Avenue P. O. B:x 270 sekson, Michigan 49201 Hartford,.i 06101
. Hugh G. Parris Mr. L. G. Mayer, :2.:...jer inager of Power t;orthern States Power Cocpany annessee Valley Authority 414 Ghollet Mall - Sth Floor 0A Chestnut Street, Tower II Minneapolis, Minnenta 55401 nattanooga, Tennessee 37401 Mr. Doncld ?. Dise R. J. A. Jones
<ccutive Vice-President Vice Presisant - Engineering trolins Power & Light Company Niagara Mohawk Power Corp.
35 Fayetteville Street 300 Erie Soulevard ilest aleigh, N. C.
27602 Syracuse, :ew York 13202
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Pilant, Director Mr. I. R. Finfrock, Jr.
icensing & Quality Assurance Vice President-Generation 1:raska Public Power District Jersey Central Power & Light Company
. O. Box.499 Madison Avenue at Punch Bowl Road 31umbus, Nebraska 68601 MorristCwn, N. J.
07960
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19101 e.'OanIArnold, President Mr. G. Carl Andognini Owa Electric Light & Power Company Boston Edison Company
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. Charles F. *a'hitmer The Cincinnati Gas i. Electric Co.
P. G. Box 950
':e President-Engineering targia Power Company Cincinna-i, Ohio 45201
. O. Box 4545 tlan.ta, GA 30302 Mr. Syron Lee, Jr., Vice-President Commonwealth Edison Ccmpany
. John C. Morrissey P. O. Box 767 ce-President & General Counsel Chicago, Illinois 60590 tcific Gas & Electric Company
' Beale Street in Francisco, CA 94106 I
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Chattanooga, Tennessee 37401 1945 West P:r::ali 7.cac-Jackson, *:tchigan 492C1 Kris K. Chitkara i
W yne Sna:Ia Cincinnati Gas & Electric P. O. Box 960 orthern 5:stes F wer Cc pany
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10019 P.ocky Hill Road Plymouth, Mass. 02360 g, ;;, y:nge;o fliagara Fohawk 6:er Corp.
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2301 Market Street Philadelphia, Penns 1vania 191Q1 c.
- 5. Waters Carolir.a Power & Lignt Co.
W. 'A. Widner P. 0.5cx 1551 Georgia Power Company Raleich, N. C.
27602 Power Generation Department f
Box 4545 270 Peachtree Street j
Jay M. Pflant Atlanta, Georgia 30302 tie:raska Public Power District P. O. Box 499 Colue:us, ::coraska 55601 Thomas J. Dente N
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. Keenan Martford, Connecticut 06101
'ter.on-Yankee ::uclear Pov.er C;r:.
77 3 rove 5:ree:
Ru:;anc, '!er:cr.t C57Ci Ed Connor Jersey Central Power & Light Co.
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Madison Avenue at Punchbotel P.oad Morristavn, New Jersey 07960 3ccerai Elec ric C: ;an./
175 :artner.acc.ue. :ai: Coce :r St.n J:se, Criti:.cnia 951:5 Tag; art ;ogers Pacific Gas 1 EleC riC 010 E:s* 5: Pee:. $Ji*.e 2200 San irar.cis;.s. California
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