ML20151R696

Forwards SER for PWR Coolant Chemistry Loop MITNRL-020 & Sser for PWR Coolant Chemistry Loop (Pccl) MITNLR-020

ML20151R696
Person / Time
Site:	MIT Nuclear Research Reactor
Issue date:	04/21/1988
From:	Lisa Clark NUCLEAR REACTOR LABORATORY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20151R699	List: ML20151R696 ML20151R727 ML20151R734
References
NUDOCS 8804280067
Download: ML20151R696 (2)

Text

aI,.

4 b,

NUCLEAR REACTOR LABORATORY U

@ AN INTERDEPARTMENTAL CENTER OF w-  %.y

'!v% $' g /

MASSACHUSETTS INSTITUTE OF TECHNOLOGY I O.K. HARLING 138 Albany Street Cambridge, Mass. 02139 L CLARK, JR.

Dirsctor (617)253-4 20 2 Director of Reactor Operations April 21, 1988 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk, M.S. OWFN 11-H-3 Washington, D.C. 20555

Subject:

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

MIT Reactor License No. R-37, Docket No. 50-20 Gentlemen:

The Massachusetts Institute of Technology Nuclear Reactor Labora-tory is forwarding herewith a safety evaluation by the MIT Research Reactor Staf f providing the bases for the determination that there are no unreviewed safety questions concerning the installation and opera-tion of an experiment on the MITR-II.

The experiment is a pressurized coolant chemistry loop which will be installed in the reactor core and which is described in the enclosed "Safety Evaluation Report for the PWR Coolant Chemistry Loop (PCCL)", Report no. MITNRL-020, dated February 13, 1987 and its Supplement dated April 19, 1988. The purpose of the experiment is to investigate the formation, transport and deposition of radioactive crud in a carefully controlled loop that will simulate pressurized water reactor conditions, all with the obj ective of learning how to reduce radiation exposures to personnel during maintenance work on these reactors.

Since experiments of this type are not described in the "Safety Analysis Report for the MIT Research Reactor (MITR-II)", Report No.

MITNE-115, October 22, 1970, as amended, a safety review of the exper-iment has been conducted by the project personnel, the reactor staff, and the MIT Reactor Safeguards Committee, including a safety evalua-tion as to the existence of any unreviewed safety questions (Safety Review #0-86-9, dated April 19, 1988 enclosed). No unreviewed safety questions have been indentified.

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 MITR-II Technical Specifi-cations, 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 MITR-II g annual report, which will be issued in July or August 1988.

• I l'

8804280067 880421 PDR ADOCK 05000020 P DCD

c 9 s I USNRC Page 2 Our schedule calls for the initial installation on the reactor to occur in May.

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.

Sincerely, l- '

Lincoln Clark, Jr.

Director of Reactor Operations Associate Director, Nuclear Reactor Laboratory

Enclosures:

Safety Evaluation Report, February 13, 1987 Supplement to the Safety Evaluation Report, April 19,1988 Safety Review #0-86-9, April 19, 1988 LC/crh cc: MITRSC USNRC - Region I Chief, Reactor Projects Section IB USNRC - Region I Project Inspector, Section IB USNRC - Resident Inspector, Pilgrim Nuclear Station

_ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ -