ML19332B123

Submittal Updating Applicant 800903 Response in Opposition to Carolina Environ Study Group Motion to Reopen OL Record Re Hydrogen Generation Control Issue Arising from TMI Accident.Certificate of Svc Encl

ML19332B123
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/19/1980
From:	Mcgarry J, Porter W DEBEVOISE & LIBERMAN, DUKE POWER CO.
To:	Atomic Safety and Licensing Board Panel
References
ISSUANCES-OL, NUDOCS 8009260010
Download: ML19332B123 (6)

Text

_ , c Vef I?, /? 20

.

e a .---~~ \NI /A,

'

%

UNITED STATES OF AMERICA -

Spp oge ,

NUCLEAR REGULATORY COMMISSION

[

Sp % A -

BEFORE THE ATOMIC SAFETY AND LICENSING BOARD

't,  %

%7 In the Matter of )

• g Y

)

DUKE POWER COMPANY ) Docket Nos. 50-369

) 50-370 (William B. McGuire Nuclear )

Station, Units 1 and 2) )

APPLICANT'S SUBMITTAL UPDATING THE RECORD WITH MATERIAL BEARING UPON CESG'S REVISED MOTION TO REOPEN THE OPERATING LICENSE PROCEEDING AND TO RAISE NEW CONTENTIONS Subsequent to the filing of " Applicant's Response to CESG's l j

Revised Motion to Reopen the Operating License Proceeding and to Raise New Contentions" (September 3, 1980), several actions have transpired which are relevant to Applicant's response to CESG's motion. Applicant submits that such actions, noted below, support Applicant's position that the hydrogen genera-tion issue raised by CESG is being adequately treated by the Commission and is not of such gravity to warrant reopening the i record.

1. On September 4, 1980, the Commission approved the publication for 30-day comment of " Proposed Interim Requirements Related to Hydrogen Control and Certain Degraded Core Con-siderations."

SECY-80-399 (August 25, 1980)". %ede.' proposed

.

interim requirements are designed "to provide assurance that' the public health and safety will be adequately protected" during the pendency of the long-term rulemaking effort on  :

degraded core conditions. SECY-80-399, Encl'osure A at pp.

'

1-4.

3 4

9 6_ _

. ,h -

8000M w - ' ~ ~ ~ ~

..

Cr

_ _

-4 w

I

. 2.

'r

.' Applicant will comply with each immediate requirement con-tained in the proposed rule and is committed to comply with any additional requirements contained in the final interim rule.

2. On September 4, 1980, the Commission approved pub-lication for comment of an advanced notice of proposed rule-making regarding the long-term degraded core rulemaking effort

,

which includes the hydrogen generation issue. SECY-80-357 (July 29, 1980).

3. On September 5, 1980, the Advisory Committee on Reactor Safety, in response to a Commission request for its opinion on the hydrogen generation issue, provided a written statement which concluded that the Sequoyah ice condenser containment "could withstand the pressure produced in the TMI-2 hydrogen burn" and "Sequoyah can be operated at 100%

power . . .

without undue risk to the public health and safety."

(Statement attached).1

4. On September 16, 1980, the Commission approved the issuance of a full power operating license for Sequoyah.

The Commission imposed three hydrogen-related requirements on TVA pertaining to testing, analysis, installation of a mitigation system and reports on the research prog.'am.

1/ The Sequoyah containment structure is virtually identical to the McGuire containment structure.

'

i

h 2.w . =. . .. . . 1 : . _.a z ,_. _; - _

u_= . n . . _ _w -

.. .

'

. , _ -__ -- -

_ -

V

,

3.

.

Applicant is engaged in joint efforts with, and proceeding on a course similar to, TVA.

Respectfully subm ed, I

k) - .

William L. Portef we '

)

Duke Power Company P. O. Box 33189

• Charlotte, North Carolina 28242 Of Counsel:

J. Michael McGarry, III Debevoise & Liberman 1200 Seventeenth Street, N.W.

Washington, D. C. 20036 September 19, 1980 l

k

{ N.I$ '

'I

.i I UNITED STATES OF AMERICA 1

NUCLEAR REGULATORY COMMISSION

! BEFORE THE ATOMIC SAFETY AND LICENSING BOARD

-

In the Matter of )

)

DUKE POWER COMPANY ) Docket Nos. 50-369

) 50-370 (William B. McGuira Nuclear )

.

Station, Units 1 and 2) )

.

CERTIFICATE OF SERVICE I hereby certify thet copies of " Applicant's submittal Updating The Record With Material Bearing Upon CESG's Revised Motion To Reopen The Operating Licen1e Proceeding and to Raise New Contentions" dated September 19, 1980 in the captioned matter, have been served upon the following by deposit in the United States mail this 19th day of September, 1980.

Robert M. La=o, Esq. Edward G. Ketchen, Esq.

Chairman, Atomic Safety and Licensing Board Counsel for NRC Regulatory U.S. Nuclear Regulatory Staff Commission Office of the Executive Legal Director Washington, D.C. 20555 U.S. Nuclear Regulatory Dr. Emmeth A. Luebke Commission Atomic Safety and Licensing Washington, D.C. 20555 Board U.S. Nuclear Regulatory J. Michael McGarry, III, Esq.

Commission Debevoise & Liberman Washington, D.C. 20555 1200 Seventeenth Street, N.W.

Washington, D. C. 20036 Dr. Cadet H. Hand, Jr.

Director Bodega Marine Laboratory Chairman of California Atomic Safety and Licensing Post Office Box 247 Board Panel 3odega Bay, California 94923 U.S. Nuclear Regulatory Commission Jesse L. Riley Washington, D.C. 20555 President Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207

' %yrm -;<-..,.--.- -

--

-

2.

?

.. Chairman, Atomic Safety and Licensing r,

- Appeal Board U. S. Nuclear Regulatory Commission i*)

,/

Washington, D. C. 20555 Chase R. Stephens Docketing and Service Section Office of the Secretary U. S. Nuclear Regulatory Commission Washington, D. C. 20555 L h e ,

b)/ DM "

William L. Porte/4

,

- ~ ~

,

,,

71

.

s  ?

srATEMENT BY ACRS CHAIRMAN DURING ACRS MEETING WITH NRC CHAIRMAN AND

. COMMISSIONERS ON SEPTEMBER 5, 1980 With regard to containment structural capability, the various structural analyses have essentially converged to a value of at least 45 psig.

It is, therefore, concluded that the Sequoyah containment structure could

• I

,

1 withstand the pressure. produced in the TMI-2 hydrogen burn. There is l t

the possibility that there could be some leakage from the containment under severe burn conditions.

The Ccmmittee endorses the developnent of a hydrogen ignition system on a timely basis. The Sequoyah ignitor system appears to have promise, and the test program should be pursued. Some such mitigating system is indicated for eventual adoption in all ice condenser containments.

The Committee believes that Sequoyah can be operated at 100 percent power. -

as indicated in our letter of July 15, 1980, without undue risk to the public health and safety. Such full power operation is subject to an active continuing development of a hydrogen control system which would lead to the installation of accepted systems within a few additional reactor years of operation of ice condenser containment type plants.

.

'

m._

_

__