ML19331E002

Affidavit Re Hydrogen Generation & Control Following Postulated TMI-type Accident.Util Action Effectively Precludes Excess Hydrogen Generation.Certificate of Svc Encl

ML19331E002
Person / Time
Site:	McGuire, Mcguire
Issue date:	07/09/1979
From:	Canady K DUKE POWER CO.
To:
Shared Package
ML19331E001	List: ML19331E000 ML19331E002
References
ISSUANCES-OL, NUDOCS 8009050087
Download: ML19331E002 (7)

Text

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O UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )

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DUKE POWER COMPANY ) Docket Nos. 50-369

) 50-370 (William B. McGuire Nuclear )

Station, Units 1 and 2) )

AFFIDAVIT OF K. S. CANADY I, K. S. Canady, being first duly sworn, do depose and state:

I am employed by Duke Power Company in the position of Manager of the Project Coordination and Licensing Section of the Steam Pro-duction Department. As such I am responsible for coordinating the McGuire Nuclear Station (McGuire) licensing effort required to satisfy both the established NRC regulations and those that have evolved following the accident at Three Mile Island Unit 2 (TMI-2).

This Affidavit addresses the issue of hydrogen generation and control following a postulated TMI-type accident at McGuire.

Specifically, this Affidavit demonstrates that the action implemented by Duke Power Company with respect to McGuire ef-1 fectively precludes the generation of excess hydrogen resulting frcm a TMI-type accident.

McGuire will have an Emergency Core Cocling System (ECCS).

l The ECCS for McGuire has been designed to meet the low concen- l tration limits required by 10 CFR 50.44. The NRC Staff confirmed this point in its Safety Evaluation Report, Supplement No. 2, March 1979, p. 6-4. Accordingly, operation of the ECCS j l

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. . as designed, will not result in the generation of substantial quantities of hydrogen (in excess of the design basis of 10 CFR 50.44).

4 With respect to the actual operation of the ECCS in a TMI-type accident, such is assured by meeting the requirements for the Near Term Operating License plants set forth in NUREG-0694.

These requirements which are addressed below, have resulted in (1) changes in McGuire administrative procedures, (2) hardware modifications of the plant, (3) increased and more comprehensive training programs, and (4) additional and better informed control room personnel.

ADMINISTRATIVE PROCEDURES The most direct of these requirements was originally issued in the NRC/OIE Bulletins which explicitly instructed the operators not to prematurely turn off the ECCS. To implement this require-ment Duke has taken the following actions to assure that the shift personnel will properly operate the ECCS:

o procedures require that the operators not terminate 1

ECCS unless an adequate subcooling margin is veri-fied.

o checklists for. valves, power supplies, and pumps are incorporated into the procedures to assure readi-ness of the ECCS.

o shift turnover checklists are utilized to assure that oncoming operators are knowledgeable of ECCS equipment operating conditions.

. . o emergency procedures involving operation of the ECCS have been written or revised in accordance with the latest technological information from Westinghouse concerning TMI-type accidents.

EbOIPMENTANDINSTRUMENTATION In addition to the above procedural changes, instrumentation will be installed at McGuire to provide additional information to the operator regarding the cooling condition of the reactor core. This instrumentation includes safeti-grade auxiliary feedwater system flow indication and the iestallation of a reactor coolant subcooling monitor. Both provide the operator with advance warning of conditions which would lead to an in-adequate core cooling situation.'In such a circumstance, the procedures noted above will be implemented to assure that quantities of hydrogen in excess of design will not be generated.

Further, a reactor ccolant system vent will be provided to vent from the primary coolant any non-condensible gases which could i

interfere with cooling the reactor core.

TRAINING To augment procedural and equipment changes, the McGuire ,

i cperators have received intensive academic and simulator training in the TMI accident sequences. In addition, these operators will 1

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receive regular retraining in responses to accident conditions including ECCS operations. These training programs are reviewed and approved by the NRC staff.

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CONTROL ROOM PERSONNEL Additional post-TMI licensing requirements which serve to I improve nuclear plant safety and ECCS performance include (1) a technical advisor to the shift supervisor to aid in the diagnosis and control of transients, including ECCS operation, (2) a shift staffing change which provides for the continuous presence of a senior reactor operator in the control room, and (3) improvements to the McGuire control roo:a which facilitate presentation of information, including ECCS equipment status, to the operators.

In addition, the McGuire design has been modified to further reduce the possibility of a TMI-type accident. Position indi-cation of the pressurizer power-operated relief valves (PORV) and pressurizer safety relief valves will be provided in the McGuire control room. This indication was not available to the operators of TMI Unit 2. Furthermore, Duke has performed full scale steam flow testing of ?ORV and PORV block valves identical to those used at McGuire. These tests and the subsequent modifications to the valves provide additional assurance that the McGuire PORV l and PORV block valves will operate as designed.

These actions which I have briefly described above, in con-junction wich the existing McGuire design and Duke Power Company experience, assure that in the unlikely event of a TMI-type accident hydrogen would not be generated in excess of concen-tration limits set forrh in 10 CFR 50.44.

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~5-I hereby certify that the above statements are true and correct to the best of my knowledge and belief.

K. S./Canady Subscribed and sworn to before me on this 9th day of July, 1979.

6Ln 3 bG

. Notary Public l

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

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, DUKE POWER COMPANY ) Docket.Nos. 50-369

) 50-370 (William B. McGuire Nuclear )

Station, Units 1 and 2) )

i CERTIFICATE OF SERVICE I hereby certify that copies of " Applicant's Response to

, CESG's Revised Motion to Reopen the Operating License Proceeding and to Raise New Contentions" dated September 3,1980 in the cap-tioned matter, have been served upon the following by deposit in the United States mail this 3rd day of September, 1980.

i l Robert M. Lazo, Esq. Edward G. Ketchen, Esq. .

j Chairman, Atomic Safety and Counsel for NRC Regylatory i Licensing Board Staff U.S. Nuclear Regulatory Office of the Executive Commission Legal Director i Washington, D.C. 20555 U.S. Nuclear Regulatory 1

Commission Dr. Emmeth A. Luebke Washington, D.C. 20555

! Atomic Safety and Licensing Board William L. Porter, Esq.

U.S. Nuclear Regulatory Associate General Counsel Commission Duke Power Company Washington, D.C. 20555 Post Office Box 2178

Charlotte, North Carolina 28242 Dr. Cadet H. Hand, Jr.

Director Chairman Bodega Marine Laboratory Atomic Safety and Licensing of California Board Panel Post Office Box 247 U.S. Nuclear Regulatory i ' Bodega Bay, California 94923 Commission Washington, D.C. 20555 j Jesse L. Riley President Carolina Environmental Study Group

', 854 Henley Place Charlotte, North Carolina 28207 1

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Chairman, Atomic Safety Chase R. Stephens and Licensing Appeal Board Docketing and Service U.S. Nuclear Regulatory Section Commission Office of the Secretary Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 :

Michael McGhfry, Iti f 4

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