ML20210B944

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Repts on ACRS 680711-13 Meetings Re Review by Douglas United Nuclear Concerning Effluent Control Project Mods to Reactor. Recommends Implementation of Mods Designed to Assure Reactor Core Cooling Under Emergency Conditions
ML20210B944
Person / Time
Issue date: 07/19/1968
From: Zabel C
Advisory Committee on Reactor Safeguards
To: Seaborg G
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20210B278 List:
References
FOIA-86-346 ACRS-GENERAL, NUDOCS 8609180204
Download: ML20210B944 (3)


Text

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.s, ADVISORY COMMITTEE ON REACTOR SAFEGUARDS- .

UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON O.C. 20545 JUL 191968 Ronorable Glenn T. Seaborg i Chairman U. S. Atomic Energy Commission Washington, D. C. 20545 i

Subject:

REPORT ON N-REACTOR RFFLUENT CONTROL PROJECT

Dear Dr. Seaborg:

At its ninety-ninth meeting, July 11-13, 1968, the Advisory Committee on Reactor Safeguards reviewed a proposal by Douglas United Nuclear (DUN) to make certain modifications, known as the Effluent Control Project (ECP), to N-Reactor. The..ECF is part of a long-term program of improvement aimed at meeting the intent of the safety critaria applied to commercial power reactors, as recommended by the ACES in its report of March 26, 1965. During its current review the Committee had the benefit of the reports listed sad of discussions with represent-atives of Douglas United Nuclear, the AEC and their consultants. The present review included a subcomatittee meeting at the site, on June 25 and 26, 1968.

The present ECP proposal provides for additional and improved emergency cooling water capability and new waste decontamination facilities. An improved independent emergency raw water (ERW) system'is proposed, which util deliver river water for once-through reactor emergency cooling, by means of five diesel-driven piasps. In addition, the reserve of stored, domineralized water available for initial emergency cooling has been increased, and this water is protected from coatsmination by raw water from the ERW system by a ayphon flow deflector. DUN proposes to install a 5 psi quench tank having a volume of at least 1,150,000 gallons to replace the existing open basin for receiving a diasp of the primary coolant. The new quench tank will be part of the confined volume, and will permit controlled release of radioactive gases to the atmosphere during an accident by venting to the confinement system and the stack.

A gravity drain system will connect this quench tank, and the confined areas of the reactor buildings, through a 5 pai water seal to a new, large-capacity, below-grade disposal basin, to accessmodate amergency coolant water that would accumulate after the first few hours following 8609180204 860915 LC 346 PDR ' ~

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O s-Honorable Glenn T. S.aborg JUL 191968 an accident. Significant improvements are also being made in the fog spray system, the graphite cooling system, and the rupture vaste A new high-radistion-level handling and decontamination systems.

etack monitor will be installed.

The proposed ECP modifications are intended to provide en emergency core cooling system of high reliability and integrity, designed to assure reactor core cooling under any conceivable emergency conditions.

including earthquakes. In addition, the effluent control and water decontamination modifications will permit routine operation of M-Reactor in accordance with 10 CFR Part 20 without relying on further environ-mental dilution of liquid wastes, and will provide for confinement and The Advisory j

controlled release of any emergency radioactive affluents.

l Committee on Rvector Safeguards believes that these modifications repre-sent a significant step toward the goal of operation under the some basic safety criteria as those applied to commercial power reactors and recom-mends that the proposed Effluent Control Project be implemented.

A number of additional itema are being discussed by The DUNCommittee and the DRL expects Staff. including the 70 C neral Design Criteria.

to revicu the results of these studies when they are completed.

Dr. F. H. Bush did not participate in this review.

Sincerely yours.

Originni signed by Carroll W. Zabel Carroll W. Zabel Chairman References attached.

i

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Nonorable Glenn T. Seaborg JUL . 9195g ,

References - N-Reactor

1. RL-NRD-614. "N-Reactor Fadioactive Rffluent Control Program." dated November 24. 1965.
2. .RL-GEN-1125. " Control of Environmental Consequences of the Eclease of Radioactive Materials. M-Reactor." dated August 1.1966.
3. RL-GEN-1450. "N-Reactor Effluent Control Program." dated February 20, 1967.
4. RL-GEN-1533. " Presentations to Meteorology Subcoenoittee of ACRS.

March 8,1967." dated March 22, 1967.

5. EL-GEN-1546 SUP. " Effluent Control Program. Presentation to DEL and '

ACRS April 5-7, 1967," dated April 1. 1967.

6. "R. port on Effluent Control Project at N-Reactor" - RL-GEN-1743, dated June 21, 1967.
7. DUN-4439. " Presentations to Hanford Subecamittee of ACRS. June 25 and 26, 1968 N-Reactor Licensability." dated June 25, 1968.

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