ML19320D494

Forwards Physical Security Plan & Proposed Changes to Tech Specs.Plan Withheld (Ref 10CFR2.790)

ML19320D494
Person / Time
Site:	University of Virginia
Issue date:	07/15/1980
From:	Shriver B VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA
To:	John Miller Office of Nuclear Reactor Regulation
Shared Package
ML19320D495	List: ML19320D494 ML19320D499
References
NUDOCS 8007210429
Download: ML19320D494 (2)

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\, UNIVERSITY OF VIRGINIA SCHOOL OF ENGINEERING AND APPLIED SCIENCE

, ,v CH AR LOTT ESVILLE. 22901 V

D EP A RTM ENT CP NUCLEAA ENGI N EERIN G AND ENGIN EERIN G PHYSICS T ELEPHON E: 804-0 24-713 e KEACTCF PACILITY July 15,1980 Mr. James R. Miller, Chief Standardization and Special Projects Branch Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Physical Security Plan and Technical Specifications for License L66 (Docket 50-62) and License R-123 (Docket 50-396)

Dear Mr. Miller:

Six c) pies of the proposed physical security plan for the University of Virginia Reactor Facility are enclosed in accordance w3th 10 CFR 73.67 and 10 CFR 70.21. The proposed plan meets the requirements of 10 CFR 73 and in in the format specified in the proposed Regulatory Guide dated July 1979. It is requested that the physical security plan be withheld from public disclosure in accordance with 10 CFR 2.790. -

Also enclosed are 19 copies of proposed changes to the UVAR technical specifications which were submitted to the Commission for approval on January 19, 1979. The copies of the technical specifications submitted in  ;

January 1979 should be updated by replacing original pages with the updated pages which are enclosed.

l The proposed changes include the following three catagories:

1. Changes which were identified in a letter to the Chief of Operating Reactors Branch #4 dated September 18, 1979.

Specific changes to Sections 3.3, 4.1, 4.2, 6.2 and 6.3 were identified, and justified in the September 1979 letter. The present enclosure provides the revised pages l so the proposed technical specifications can be updated, l'

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2. Change to Section 4.8 " Reactor Fuel Dose Measurements."

The enclosed change supercedes the version of Section 4.s SCOY submitted to the Chief of Operating Reactors Branch #4 in 5 a letter dated September 17, 1979. The proposed revision allows more flexibility in the frequency of physical in-

//f ventories and dose rate measurements to determine the amount of nonexempt SNM than the September 1979 version. N The proposed revision is adequate to ensure that the 5 amount of nonexempt SNM is accurately known and will reduce the radiation exposure to personnel since the number of dose rate measurements will be reduced. The proposed revision has been approved by the Reactor Safety Committee.

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Letter to James R. Miller July IS, 1980 Page 2

3. Change to Section 3.10 " Emergency Removal of Decay Heat" to clarify the intent that the core spray system be operable during forced convection cooling, but is not required in the natural convection cooling mode. This change is only a clarification of the existing requirements which allow operation of the reactor in the natural convection mode at any location in the reactor pool. This clarification does not re-quire any change in the procedures or safety analysis report and is consistent with (NAR technical specification 3.8 ' Height of Water Above the Core in Natural Convection Mode of Operation" allows operation with only one foot of wat r above the core. The core spray system is not operable in that condition. This change has been approved by the Reactor Safety Committee.

Sincerely, a - M B. I. Shriver, Director Reactor Facility 9

BLS:ph Enclosures cc: Reactor Safety Coc:mittee Dr. T. G. Williamson Mr. J. P. Farrar Mr. H. Bernard-NRC Project Manager NRC Document Management Branch w