ML19254B067
| ML19254B067 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 08/17/1979 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| REF-GTECI-A-09, REF-GTECI-SY, TASK-A-09, TASK-A-9, TASK-OR NUDOCS 7909240027 | |
| Download: ML19254B067 (4) | |
Text
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UNITED STATES g
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WASHINGTON, D. C. 2t 555 a
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AUG 171979 Docket Nos.:
Mr. William O. Parker, Jr.
Vice President, Steam Production Duke Pour Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Parker:
SUBJECT:
INTERIM ACTIONS NEEDED FOR PLANT OPERATION PENDING FINAL RESOLUTION OF ANTICIPATED TRANSIENTS WITH FAILURE TO SCRAM (ATWS) - MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 In December 1978 the Nuclear Regulatory Comission (NRC) staff issued Volme 3 of NUREG-0460 which describes the proposed type of plant modifications the staff believes are necessary to reduce the risk from anticipatec transients with failure to scram ( ATWS) to an acceptable level. The NRC's Regulatory Requirements Review Comittee completed its review in January 1979, and concurred with the staff's approach described in Volume 3 of NUREG-0460 insofar as it applies to McGuire Nuclear Station, Units 1 and 2. The staff has issued requests for the industry to supply generic analyses to confirm the ATdS mitigation capability described in Volme 3 of NUREG-0460. Subsequently, the staff plans to present its rec-omendations for rulemaking on ATWS to the Comission. The Ccmission would, by rulemaking, determine the required modifications to resolve ATWS concerns and the required schedule for the implementation of such modifications. The McGuire Staticr.
would, of course, be subject to the Comission's decision in this matter.
Based on considerations described in pages 42 through 45, Volume 3 of NUREG-0460, the staff generally concluded that plants with operating licenses can continue to operate without undue risk to the health and safety of the public during the estimated 2 to 5 year period needed to implement the necessary modifications.
However, the staff believes the following steps should be taken as a prudent course prior to the issuance of an operating license in order to further reduce the risk from ATWS events during the interim period before the required plant modifications as detemined by the Ccmission are cmpleted.
)e n 790924 w ;
Mr. William 0. ' Parker, Jr. M ' 7 979 1
1.
Emergency procedures shculd be developed to train operators to recognize an ATWS event, including consideration of scram indicators, rod position indi-cators, flux monitors, pressurizer level and pressure indicators, pressurizer relief valve and safety valve position indicators, coolant average tempera-ture, containment temperature and pressure indicators, steam generator level, pressure and flow indicators, and any other alarms annunciated in the control room including alanns not processed through the electrical portion of the reactor scram system. The emergency procedures should be sufficiently sim-piified and unambiguous to pennit prompt ATWS recognition.
2.
The operator should be trained to take actions in the event of an ATWS including consideration of manually scraming the reactor by using the manual scram buttons, prompt actuation of the auxiliary feedwater system to assure delivery of the full capacity of this system, and initiation of turbine trip. These actions must be taken immediately following the occurrence of the event. The operator should also be trained to promptly initiate baration by actuation of the high pressure safety injection system to bring the plant to a safe shutdown condition.
We require that you submit your procedures for our review. Please submit them by September 24, 1979. Our review will include a visit to your plant to deter-mine the feasibility of implementing your proposed procedures through operator simulation of tha steps. Our evaluation must conclude that acceptable procedures and operator training are in place prior to the issuance of an operating license.
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/ teven A. Yarga, Acti As sistant Director for Light L ter Reactors Division of Project Management ccs: See next page
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Mr. William O. Parker, Jr.
Vice President, Steam Production Duke Power Company P. O. Box 2178 422 South Church Strget Charlotte, North Carolina 28242 cc: Mr. W. L. Porter Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 Mr. R. S. Howard Power Systems Division Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230 Mr. E. J. Keith EDS Nuclear Incorporated 220 Montgomery Street San Francisco, California 94104 Mr. J. E. Houghtaling NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Mr. Jesse L. Riley, President The Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 J. Michael McGarry, III, Esq.
Debevoise & Liberman 1200 Seventeenth Street, N. W.
Washington, D. C.
20036 Shelley Blum, Esq.
418 Law Building 730 East Trade Street Charlotte, North Carolina 28202 Robert M. Lazo, Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Connission Washington, D. C.
20555 Dr. Emmeth A. Luebke Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comnission Wa,s.hington, D. C.
20555
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Mr. William O. Parker, Jr.
cc: Dr. Cadet H. Hand, Jr., Director Bodega Marine Lab of California P. O. Scx 247 Bodega Bay, California 94923 Ms. Brenda Best Carolina Action 1740 E. Independence Boulevard Charlotte, North Carolina 28205 Anthony Z. Roisman, Esq.
Natural Resources Defense Council 917 - 15th Street, N. W.
Washington, D. C.
20555 Richard P. Wilson, Esq.
Assistant Attorney General State of South Carolina 2600 Bull Street Columbia, South Carolina 29201 Mr. Geoffrey Owen Little P. O. Box 2501 Davidson College Davidson, North Carolina 28036 l
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