ML19345E445

From kanterella
Jump to navigation Jump to search
Informs That ACRS Supports Proposed Change to Tech Specs to Permit Authorization for Installation of Six High Performance Fuel Assemblies in Reactor
ML19345E445
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 12/20/1967
From: Palladino N
Advisory Committee on Reactor Safeguards
To: Seaborg G
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19345E439 List:
References
NUDOCS 8101190316
Download: ML19345E445 (4)


Text

.

(

s COPY i

ADVISORY COMMITIII ON REACTOR SAFEGUARDS

)

I UNITED STATES NIOMIC ENERGY COMMISSION WASHING'IDN, D. C.

20545 December 20, 1967 Honorable Glenn T. Seaborg Chaiman U. S. Atomic Energy Ccmrission Washington, D. C.

Subject:

REPORT ON BIG ROCK POINT NUCLEAR PIME

Dear Dr. Seaborg:

At its eighty-ninth meeting, Septerber 7-9, 1967 and ninety-second meeting, December 7-9, 1967, the Advisory Cettmittee on Reactor Safeguards considered the application by Consumers Power Company for authorization to install six high perfonrance developnental fuel asse:rbliets in the Big Rock Point Reactor.

During its revicw, the Comrittee had the benefit of discussions with repre-sentatives of Consumers Power Company, General Electric Company, and the AEC Regulatory Staff and of the documents referenced. Subcomnittee meetings were held in Washington, D. C. on September 6, 1967 and December 5, 1967.

The six developmental assemblies are designed to obtain infomation concern-ing fuel rods operating with central me'. ting. Two of the six assemblies will contain fuel rods with a 0.57 inch outside diameter designed for incipient center melting during full power operation of the reactor. The fuel rods in the other four asserblies have an outside diameter of 0.70 inches and are to operate with considerable center melting. Consumers Power Company plans to install the test fuel assemblies during the next refueling period, currently scheduled for January 1968. After a peak exposure of 3000 MWD /T has been reached in the test fuel, the reactor will be shut down and the test fuel removed for examination. These fuel rods will be subjected to nondestructive examination. After a three-month decay period, four fuel rods will be shipped to Vallecitos Nuclear Center for destructive tests. During continuation of the irradiation program, the reactor will be shut down for periodic fuel examination.

1

//oN9dM t

a COPY Honorable Glenn T. Seaborg December 20, 1967 Because experience with high perfomance fuels, particularly those in which some of the fuel is in the molten state, is limited, the Comittee recomends The Com-that the applicant use caution in prosecution of the test program.

mittee recomends that extra caution be given to operations if signs of failum of the experimental fuel appear. To this end, the Comittee urges that work be done to develop improved methods for prapt detection of gross failure of an experimental fuel element.

As a further precaution, the Comittee recomends a more conservative approach to returning of the 0.70-inch center melt rods to the reactor after the first irradiation period. Specifically, it recomends that, after the first inspection period (at approximately 3000 W6/T burnup),

the 0.70-inch diameter rods not be returned to the reactor until the re-sults on the four rods selected for destructive examination have been obtained and show to the satisfaction of the AEC Regulatory Staff that the red thermal conditions and perfomance during irradiation are essential-ly as predicted and that additional irradiation may be undertaken safely.

The applicant reported that, as additional protection against core meltdown in the unlikely event of mpture of the core spray line, mearis will be pro-vided for prapt delivery of water from the fire protection system to the mactor pressure vessel. The Comittee rec.umerds ccripletion of this system before the experimental assemblies are operated.

In recognition of the safety aspects of the operation, Consumers Power Company has several programs in progress to improve the safety chameter-istics of the Big Rock Point Reactor. These ir;clude installation of another external power line (nearly ccrnpleted); examination of the safety instru-mentation system for possible negation of safety action through single faults; installation of a nozzle support system to protect against rod ejection in the unlikely event of control rod nozzle failure; and modification of the emergency core cooling system to improve its protective capacity (within a year or two). The Comittee approves of these steps, ard urges expedition of their completion.

The applicant is also planning a detailed inspection program for the primary system piping and ccmponents. It was stated that the inspection is ha,r.pewd by the radioactivity in the primary system, so that special arrangements and fixtures will be required. The Cmmittee recomends that the in-service inspection program be expedited, and that consideration be given to a hydro-static test of the primary system, before the developrnental assemblies are installed, at a pressum only slightly lower than the pressure-mlief valve settings.

t J

COPY Honorable Glenn T. Seaborg December 20, 1967 I

The Comnittee believes that, in view of the favorable characteristics of the Big Ec.k Point site, and subject to the rec.uauendations stated above, the reactcc can be operated with the high performance test assemblies with-out undue risk to the health and safety of the public.

Sincerely yours, ORIGINAL SIGNED BY N. J. PALIADDiO N. J. Palladino Chairnan References Attached.

i l

l

=

l s

COPY Honorable Glenn T. Seaborg December 20, 1967 References - Big Rock Point Reactor 1.

Consumers Power Cmpany letter, dated May 26, 1967, with Proposed Change No. 13 to the Technical Specifications for the Big Rock Point Reactor.

2.

Consumers Power Company letter, dated May 29, 1967, with Errata Sheet and Figure 25 for Proposed Change No.13.

3.

Consumers Power Company letter, dated August 15, 1967, with Answers to Mditional Infomation Requested Regarding Proposed Change No.13.

4.

General Electric 'IWX, dated August 24, 1967, to Division of Reactor Licensing zu Fesults of 2-Pump Trip from Rated Power.

S.

Consumers Power Company letter, dated Noverrber 10, 1967, with Mditional Information Required in Support of Proposed Change No.13.

j 6.

References Associated with Answer to Question 2 of Answers to Additional Information Requested Reganiing Proposed Change No.13.

{

1 1

.