ML20246F847

Forwards Questions Re High Enriched U/Low Enriched U Conversion at Univ.Tech Spec Sections,Needed to Accomodate Conversion,Should Be Resubmitted & Preparation of Emergency Shutdown Rod for Use in Event of Error Explained

ML20246F847
Person / Time
Site:	05000199
Issue date:	07/10/1989
From:	Michaels T Office of Nuclear Reactor Regulation
To:	Berlin R MANHATTAN COLLEGE, RIVERDALE, NY
References
NUDOCS 8907140067
Download: ML20246F847 (5)

Text

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1. D:cket No. 50-199 July 10, 1989 Dr. Robert E. Berlin Reactor Administrator Zero Power Reactor c/o Mechanical Engineering Dept.

Manhattan College Riverdale, New York 10471

SUBJECT:

QUESTIONS REGARDING HEU/ LEU CONVERSION AT MANHATTAN COLLEGE We have reviewed the Safety Analysis Report for the Manhattan College Zero Power Reactor, submitted by your letter dated May 8,1989, regarding the HEU to LEU conversion. Enclosed are the questions resulting from this review. If you have any questions, please call me at (301)492-1102.

Sincerely,

/s/

Theodore S. Michaels, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

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'Decket No. 50-199 Dr. Robert E. Berlin Reactor Administrator

. 2ero Powtir Reactor c/o Mechanical Engineering Dept.

Manhattan College Riverdale, New York 10471'

SUBJECT:

QUESTIONS REGARDING HEU/ LEU CONVERSION AT MJNHATTAN COLLEGE We have reviewed the Safety. Analysis Report for the Manhattan College Zero Power Reactor, submitted by your letter dated May 8,1989, regarding the HEU to LEU conversion. Enclosed are the questions resulting from this review, If you have any questions, please call me at (301)492-1102.

Sincerely,

," 5.hkIal-Theodore S. Michaels, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: See next page 3

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. Manhattan College 6-Docket No. 50-199 cc: Municipal Reference & Research Center 31 Chambers Street New York, New York 10007 Director-Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza Albany, New York I?223

t MANHATTAN CONVERSION QUESTIONS (1) What is the calculated "just critical" U-235 mass?

(2) What is the fuel element worth versus grid position for the LEO fuel?

(3) Are there provisions for any out of core fuel storage? Please explain what provisions han been made to safely store the HEU fuel elements in the event that shipment is not possible on the day they are removed from the core.

(4) Please provide any HEU versus LEU comparisons of power distribution in the fuel elements, and any power distribution versus fuel loading information in the partially loaced element.

(5) Neglecting bias, calculational uncertainty, etc., what are the Manhattan (best estimate) published values for regulatory and shim rod worth? Please give a technical justification for the values you choose. In reference to Table 3.2, page 19, please explain the meaning and operational implications of the two parenthetical statements about " biases".

(6) Please resubmit page 19 to show the deltas in Table 3.2 that are missing

(% k/k) end correcting an apparent typo in Section 3.3.1, seventh line, viz.

+

reversing vs. revising.

(7) In the HEU core, because of a slightly positive initial temperature coefficient, the maximum core reactivity occurs at 43.7 C and the Technical Specification limit for core excess of 0.44%A k/k is specified at this temperature. Because there is a possibility the LEU core will also exhibit a slightly positive temperature coefficient over the initial stages of a core heat-up, it is necessary that Manhattan conduct a test program to determine this comparable maximum reactivity temperature and the total reactivity defect between ambient and this temperature. Care must be exercised to ensure the maximum excess of 0.44%A k/k (under any core conditions or temperature) is not exceeded during these tests. Please provide NRC with the details of your Zero Power Physics Test program in this area. Additionally, since you will be loading a new untried fuel into your reactor, you should prepare a fuel loading plan. This should include, among other items, provisions for neutron multiplication measurements as a function of fuel loadings, pro-cedures for extrapolating and predicting criticality at regular intervals, discussion of location of neutron source, verification of detector oper-ability, etc. The plan should also explain clearly how you will continue loading beyond criticality, how you will calibrate the worths of your control reds, and how you will determine reactor power level in order to comply with your licenta. Please provide such a plan.

(8) In the current LEU SAR, it is assumed that handling accident where the fuel element is dropped results in no clad breach. Is this scenario the same as the handling accident discussed in your 1983 HEU SAR supporting the re-license? I i

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i (9) Please explain how you will prepare the emergency shutdown rod for rapid use in the event of an error or other occurrence during fuel changes. (See Section4.2,SAR.)

(10) Please resubmit only the revised sections of the Technical Specifications needed to accommodate the HEU to LEU conversion and any other change that you plan to make. Provide a brief rationale for the change.

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