ML20004F902

Summarizes Implementation & Progress of Review of Fort St Vrain Items & Applicability to Htgrs.

ML20004F902
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/16/1981
From:	Anderson C, Bartholomew C LOS ALAMOS NATIONAL LABORATORY
To:	Kuzmycz G Office of Nuclear Reactor Regulation
References
CON-FIN-A-7258 Q-13:81:188, NUDOCS 8106260156
Download: ML20004F902 (2)

Text

y -

_osAamos _,_::: t"uM' '

=^'t stor 576 Los AlamosNationalLaboratory Los Alamos.NewMexico 87546 retyet (505) 667-5150 Energy Diwsion [

f George Kuzmycz

/,@'%' r9 t

{A *gd3

~

Standardization & Special Projects Branch . L!

Office of Nuclear Reactor Regulation /

U.S. Nuclear Resulatory Connission 4 y/

. Washington, DC 20555  % 3/

N e

Dear George:

The project entitled " Review of Fort St. Vrain Items and Their Applicability to HTGR's (Contract-7405-Eng-36, Laboratory Program Code R647) begin as scheduled in Laboratory FIN /189a No. A7258 on May 18,1981. Work began on the following tasks:

Task 1: Inservice inspection - no milestones reached or missed.

Task 2: Plateout probe eva " ation - no milestones reached or missed.

Task 4, Subtask B: PCRV liner cooling system hot spots - no milestones reached or missed.

Funds expended for both manpower and computer services were:

Manpower: Task 1 -

1.2 K Task 3 1.2 K Task 4, Subtask B 1.2 K Computer: No computer charges j Prot,lems or delays encountered or anticipated: No:.e 1

l A summary of progress to date includes:

Task 1 (1) Reviewed Fort St. Vrain (FSV) FSAR Test and Inspection Section l 3.10, Secs. 3.10.1, Fuel and Reflector Elements, and 3.10.3, l Core Nuclear Characteristics.

(2) Requested, by telephone from ASME headquarters in New York, information on obtaining a copy of proposed ASME Boiler and Pressure Vessel Code,Section XI, Division 2, Rules for l

Inspection and Testing for Gas-Cooled Plants. A copy of the l code will be forwarded to R. J. Bartholomew.

U06200l -

,t l Task 3- (1) Reviewed FSV FSAR Sec. 3.10.3, Fission Product Control.

(2) Reviewed NUREG/CR-0060, LA-7239-MS, "SUVIUS: A Circulating and -l Plateout Activity Program for Cas-Cooled Reactors with Arbitrary i Radioactive Chains," by Courtney E. Apperson, Jr. Program appears applicable and useful for evaluation of plateout probe l data.

~

Task 4 Subtask B

^

(1) Have begun familiarization with thermal hot spot problems areas and parameters affecting them.

Plans for the next reporting period include:

Task 1- -

(1) Pending receipt of original and revisec ISI Program submitted by Public Service Company of Colorado (PSCo) to NRR, begin review of original and revised documents.

(2) Pending receipt of proposed 'ASME Boiler and Pressure Vessel Code,Section I, Division 2, begin comparison of original and revised ISI Program with this code.

Task 3 (1) Pending receipt of design and technical specifications governing ,

platecut proce will review same.

(2) Perfonn an example calculation with SUVIUS to gain familiarity.

with the computer code.

Task 4 Subtask B (1) Will begin to formulate thermal-structural models of PCRV -liner.

Sincerely, k MM C. A. Anderson and R. Bartholonew Advanced Engineering Technology

~CYS: D. Eisenhut, Directer, Division of Licensing R. Tedesco, Assistant Director for Licensing J. Miller, Chief, Standardization and Special Projects Branch B. Grenier, Technical Assistance Program Manager R. Haarman, ADEP /

J. Jackson, Q-CJ Q-13 File

. .. . _ , - ~ . -

. - . . _ - , . ,~ _. .___.-.A.. _- _ , . - . - . _ - _ . . .-.