ML20012C269

Forwards MITNRL-031, SER for BWR Coolant Chemistry Loop.

ML20012C269
Person / Time
Site:	MIT Nuclear Research Reactor
Issue date:	03/09/1990
From:	Bernard J, Harling O MASSACHUSETTS INSTITUTE OF TECHNOLOGY, CAMBRIDGE
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20012C270	List: ML20012C269 ML20012C277
References
NUDOCS 9003200424
Download: ML20012C269 (2)

Text

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, . sw NUCLEAR REACTOR LABORATORY RPh k AN INTERDEPARTMENTAL CENTER OF MASSACHUSETTS INSTITUTE OF TECHNOLOGY e$7f[

l O.K. HARUNG 138 Albany Street, Cambodge, Mass. 02139 J A. BERNARD, JR.

O,roctor Teletax No. (6171253 T330 Director of Reactor Operations Telex No. 92-1473 MIT CAM Tel. No. (617)233-4211/4202 hiarch 9,1990 U.S. Nuclear Regulatory Commission

. Washington, D.C. 20555 A*ITN: Document Control Desk

Subject:

Evaluation of Unreviewed Safety Question,10 CFR 50.59(b)(2)

Facility License No. R 37, Docket No. 50-20 Gentlem::n:

The hiassachusetts Institute of Technology Nuclear Reactor Laboratory is forwarding herewith a safety evaluation by the hilt Research Reactor Staff providing the bases for the determination that there are no unreviewed safety questions concerning the installation and operation of an experiment on the hi!TR l!.

The experiment is a boiling coolant chemistry loop which will be installed in the tractor core and which is described in the enclosed " Safety Evaluation Report for the BWR Coolant Chemistry Loop (BCCL)," Report No. hilTNRL-031, dated hiarch 9,1989. The purpose of the experiment is to study water radiolysis under simulated BWR coolant conditions (normat and hydmgen water chemistry) with an overall objective of qualifying computer codes and contnbuting to the reductic 1 of envimnmental degradation of materials in BWR plants.

Because experiments of this type are not described in the " Safety Analysis Repon for the hilt Research Reactor (hilTR ll)," Report No. hilTNE 115, October 22,1970, as amended, a safety review of the experiment has been conducted by the Project Personnel, the Reactor Staff, and the hilt Reactor Safeguards Committee, including a safety evaluation as to the existence of any unreviewed safety questions (Safety Review

1. 0-89-20, dated December 20,1989 enclosed). No unreviewed safety questions have been identified.

In accordance with 10 CFR 50.59(b)(2), evaluations of unreviewed safety questions have routinely been reported to NRC in the annual report required by paragraph 7.13.5 of the hilTR-Il Technical Specifica tions, Facility License No. R 37. Because of the unusual nature of this experiment, we are reporting the safety evaluation required by 10 CFR 50.59(b)(1) at this time rather than wait until the next hilTR Il annual report, which will be issued in August 1990.

Our schedule calls for the initial installation of the BCCL on the reactor to occur in April 1990.

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m USNRC Page 2 If you should have any questions regarding the evaluation or any of the information furnished, we request that you contact us as soon as possible. It will be noted that the enclosed safety evaluation references two MIT documents. These are Safety Evaluation Report for the PWR Coolant Chemistry Loop (MITNRL-020) and a Safety Review, PWR Coolant Chemistry Loop,"(SR#0-86-9). Both have been previously submitted to NRC.

Sincerely, b)'% Q John A. Bernard, Ph.D Director of Reactor Operations

< MIT Research Reactor

Enclosures:

Safety Evaluation Report, March 9,1989 Safety Review #0-89 20, December 20,1989 JAB:CRll cc: MITRSC (with enclosures)

USNRC - Region 1 - Chief, Reactor Pmjects, Section 3B USNRC - Region 1 - Project Engineer, Reactor Projects Section 3B USNRC - Senior Resident inspector, Pilgrim Nuclear Station -

USNRC - Pmject Manager, Standardization and Non Power Reactor Project Directorate l

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