ML19330B306

Forwards Request for Addl Info Re RCS Vents for Review of OL Application

ML19330B306
Person / Time
Site:	McGuire, Mcguire
Issue date:	07/23/1980
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Parker W DUKE POWER CO.
References
NUDOCS 8007310338
Download: ML19330B306 (5)

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8 UNITED STATES

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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JUL 2 31980 Docket Nos.:

50-369 and 50-370 Mr. William 0. Parker, Jr.

Vice President - Steam Production Duke Power Company Post Office Box 33183 422 South Church Street Charlotte, North Carolina 28242

Subject:

Task Action Plan Item II.B.1 - RCS Vents (McGuire Nuclear Station, Units 1 & 2)

As a result of our review of your application for operating licenses for the McGuire Nuclear Station, we find that we need additional information regarding reactor coolant system vents. The specific information required is listed in the Enclosure.

It is requested that this infonnation be provided on or before August 1, 1980.

Sincerely, Wu bEh Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

Enclosure:

As Stated ces w/ encl:

See next page 4

800732o 76

o Mr. Willian 0. Parker, Jr.

Vice President, Steam Production Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, Nor th Carolina 28242 cc:

Mr. W. L. Porter David Flesichaker, Esq.

Duke Power Company 1735 Eye Street, fl. W.

P. O. Box 2178 Suite 709 422 South Church Street Washinaton, D. C.

20006 Charlotte, North Carolina 28242 Mr. R. S. Howard Richard P. Wilson, Esq.

Power Systems Division Assistant Attorney. General State of South Carolina Westinghouse Electr ic Corporetion 2600 Bull Street P. O. Box 355 Columbia, South Carolina 29201 Pittsbur gh, Pennsylvania 15230 Mr. E. J. Keith i

EDS Nuclear Incorporated 220 Montgomery Street San Francisco, California 94104 Mr. J. E. Houghtaling NUS Corpor ation 2536 Countryside Boulevard Clear water, Flor ida 33515 Mr. Jesse L. Riley, President The Car olina Envir onmental Study Group 854 Henley Place Charlotte, North Carolina 28207 J. Michael McGarry, !!!, Esq.

Debevoise a Liberman 1200 Seventeenth Street, N. W.

Washington, D. C.

20036-Rober t M. Lazo, Esq., Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. Emmet h A. L uebk e Atomic Safety and Licensing Board U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Dr. Cadet H. Hand, Jr., Director Bodega Marine Lab of California P. O. Box 24 7 Bodega Bay, California,94923 i

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Mr. William O. Parker, Jr. cc: David Flesichaker, Esq.

1735 Eye Street, N. W.,

Suite 709 Washington, D. C.

20006 Richard P. Wilson, Esq.

Assistant Attorney General State of South Carolina 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 County Manager of Mecklenburg County 720 East Fourth Street Charlotte, North Carolina 28202 U. S. Environmental Protection Agency ATTN: EIS Coordinator Region IV Office 345 Courtland Street, N. W.

Atlanta, Georgia 30308 O

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ENCLOSURf JUL 2 a 1980 TASK ACTION PLAN'II.B.1 McGuire 1.

Provide your design of the pressurizer vent system per our November 9,1979 letter. Assure that all requirements and recommendations of that letter are satisfied.

2.

Demonstrate that the vent system is qualified to RPS safety grade standards.

Include seismic design, IEEE-279 requirements, minimize inadvertent actuations, vent valve position indice. tion in the control room, qualification to pass non-condensibles, steam, water and combinations thereof, etc.

3.

Demonstrate that the exhaust from the vent system will not impinge on other equipment, that the vent system will vent RCS hot legs, and that the vent exhaust is to a portion of the containment wich maximum ventilation and cooling.

4.

Provide an analysis of the vent system discharge capacity. Assure that the 1/2 kCS volume per hour guideline of our November 9,1979 letter is satisfied.

5.

Provide justification that the thermal-hydraulic characteristics for a break in the vent line at the reactor vessel head is adequately modeled. This justification should consider the differences between the break location of the vent and the classical LOCA analyses.

It should consider the differences associated with flow distribution and depressurization rate.

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.. 6.

Provide procedural guidelines and analytical. bases (preferably, generically developed by owners group) for vent operation and termination as related to plant performance. The procedures should be based on the following criteria:

(1) the plant must meet'the requirements of 10 CFR 50.46 and 10 CFR 50.44 for DBA's; and (2) the plants ability to maintain core cooling and containment integrity for events beyond DBAs must be increased. Procedures should also address methods to (1) assure natural circulation through the U-tube portions of the steam generator with the potential accumulation of gases in this region, and (2) assure that combustible limits are not exceeded.

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