ML20052G948

Affidavit of Rg Azzarello Answering ASLB Questions.Upon Initiation of Total Loss of Feedwater,Remaining Steam Generator Water Inventory Would Allow Approx 10-15 Minutes Before Dryout Condition Would Occur

ML20052G948
Person / Time
Site:	Waterford
Issue date:	05/13/1982
From:	Azzarello R LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20052G935	List: ML20052G934 ML20052G948
References
NUDOCS 8205190178
Download: ML20052G948 (5)

Text

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May 13, 1982 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

)

LOUISIANA POWER & LIGHT COMPANY ) Docket No. 50-382

)

(Waterford Steam Electric Station, )

Unit 3) )

ANSWERS OF ROBERT G. AZZARELLO TO BOARD QUESTIONS Q1. If there is a transient initiated by loss of feedwater and condensate systems followed by a failure of emergency feedwater system for an extended period, do the emergency plan implementing procedures define an emergency classification? (Tr. 3069-73)

A1. Upon initiation of a total loss of feedwater (LOF), the remaining Steam Generator water inventory would allow approximately 10 - 15 minutes before a dry-out condition would occur. This unlikely condition would then be defined as a " loss of core heat-sink". The emergency plan implementing procedures establishes an action level for the General Emergency category which addresses a " loss of core heatsink, such that a core melt sequence is in progress, or imminent". The Waterford 3 action level scheme employs a conservative philosophy to immediately declare the highest emergency classification for which an action level has 8205190178 820514 PDR ADOCK 05000382 O PDR

been exceeded, without having previously declared a lower classification. Operators would declare a General Emergency immediately upon recognition'that a " loss of core heatsink" condition has occurred.

Q2(a). Do the example initiating conditions for emergency classifications in Appendix 1 of NUREG-0654 include concentrations of particular fission products in the containment atmosphere?

(Tr. 3075)

A2(a). The guidelines do not address that condition exactly, and not for specific isotopes. However, there are some related example initiating conditions in Appendix 1: _

ALERT - Initiating Condition 12: " Fuel damage accident with release of radioactivity"to containment or fuel handling building.

SITE AREA EMERGENCY - Initiating Condition 2:

" Degraded core with possible loss of coolable geometry (indicators should include instrumenta-tion to detect inadequate core cooling, coolant activity and/or containment radioactivity levels)."

SITE AREA EMERGENCY - Initiating Condition 10:

" Major damage to spent fuel in containment or fuel handling building (e.g., large object damages fuel or water loss below fuel level)."

SITE AREA EMERGENCY - Initiating Condition 13 a & b:

a. " Effluent monitors detect levels corresponding to greater than 50 mr/hr for 1/2 hour or greater than 500 mr/hr W.B. for two minutes (or five times these levels to the thyroid) at the site boundary for adverse meteorology."

b. "These dose rates are projected based on other plant parameters (e.g., radiation level in con-tainment with leak rate appropriate for existing containment pressure) or are measured in the environs."

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GENERAL EMERGENCY - Initiating Condition 1 a & b:

a. " Effluent monitors detect levels corres-ponding to 1 rem /hr W.B. or 5 rem /hr thyroid at the site boundary under actual meteorological conditions."

b. "These dose rates are projected based on other plant parameters (e.g., radiation levels in con-tainment with leak rate appropriate for existing containment pressure with some confirmation from effluent monitors) or are measured in the environs."

Q2(b). Does Waterford 3 have the capability to sample the atmosphere in the containment to determine the concentration of various fission products such as Iodine 131 and Xenon 133 and so forth? (Tr. 3075-78)

A2(b). Waterford 3 will have the capability to obtain containment atmosphere samples for iodine, particulate, and radioactive gas analysis. Grab samples will be taken for laboratory analysis. Results of the laboratory analysis do not define an emergency classification. However, the emergency plan implementing procedures provide that when the gross radiation level monitors in containment exceed preset limits, emergeacy classifi-cations are declared.

Q3. Will core exit temperature trigger a declaration of an emergency at Waterford 37 (Tr. 3088) ,

A3. A high core exit temperature condition would be detected by two seperate safety grade instrumentation systems. The Core l Protection Calculators of the Reactor Protective System utilize a reactor hot leg temperature signal as one input to derive a "

Departure from Nucleate Boiling Ratio (DNBR). A high core exit 1 temperature condition would result in exceeding the DNBR safety limit. The RCS Subcooling Margin Monitors perform a pressure /

temperature correlation by comparing reactor hot leg temperature to saturation temperature for the existing RCS pressure. A high core exit temperature condition would result in a loss of RCS Subcooling Margin. The Waterford 3 emergency plan implementing procedures utilize safety grade instrumentation to the extent possible to trigger declaration of an emergency condition. Action levels have been established for the Unusual Event category based on either exceeding the DNBR safety limit or a loss of RCS Sub-cooling Margin.

[ l P.dbERT G. AZZARELLO i

SUBSCRIBE,D AND SWORN to before me, a Notary Public in apdgo the STATE OF LOUIS A ap the PARISH OF ORLEANS this i

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

)

LOUISIANA POWER & LIGHT COMPANY ) Docket No. 50-382

)

, (Waterford Steam Electric . )

l Station, Unit 3) )

SERVICE LIST Sheldon J. Wolfe, Esquire Lyman L. Jones, Jr., Esquire Administrative Judge Post Office Box 9216 Chairman, Atomic Safety and Metairie, Louisiana 70055 Licensing Board U.S. Nuclear Regulatory Luke B. Fontana, Esquire Commission 824 Esplanade Avenue Washington, D.C. 20555 New Orleans, Louisiana 70116 Dr. Harry Foreman Atomic Safety and Licensing Adminstrative Judge Board Panel Director, Center for U.S. Nuclear Regulatory Population Studies Commission Box 395, Mayo Washington, D.C. 20555 University of Minnesota Minneapolis, Minnesota 55455 Atomic Safety and Licensing Appeal Board Panel Dr. Walter H. Jordan U.S. Nuclear Regulatory Adminstrative Judge Commission 881 West Outer Drive Washington, D.C. 20555 Oak Ridge, Tennessee 37830 Docketing & Service Section (3)

Sherwin E. Turk, Esquire (4) Office of the Secretary Office of the Executive U.S. Nuclear Regulatory Legal Director Commission U.S. Nuclear Regulatory Washington, D.C. 20555 Commission Washington, D.C. 20555 I

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