ML20056G549

From kanterella
Jump to navigation Jump to search
Submits Response to Observations Discussed in 930629 Telcon During F Collins Visit to Facility in May 1993 to Administer NRC Operator Exams
ML20056G549
Person / Time
Site: University of Missouri-Rolla
Issue date: 08/26/1993
From: Freeman D
MISSOURI, UNIV. OF, ROLLA, MO
To: Mendonca M
NRC
References
NUDOCS 9309030257
Download: ML20056G549 (2)


Text

I g .  !

. Nuclear Reactor Facility Nuclear Reactor

II Rolla. MO 65401-0249 Telephone (314) 341-4236 l UNIVERSITY OF MISSOUR!-ROLLA Missouris Technological University August 26, 1993 l

l l Marvin Mendonca l Project Manager l U.S. Nuclear Regulatory Commission PDNP M.S. 11-B-20 Washington, D.C. 20555

Dear Marvin:

We have reviewed the observations made by Frank Collins during his visit to our facility in May, 1993 to administer NRC operator examinations. This letter presents our response to the four observations discussed in our phone conversation of June 29, 1993.

Observation 1 noted that we have no SOP for how to measure excess reactivity. Although we regularly perform this task (primarily as a student laboratory), and each of our operators is very well

, trained in the measurement, we agree that a written procedure would

! be appropriate. We will develop and implement an SOP covering how l to measure excess reactivity in the near future.

I Observation 2 noted that Tech Specs require written procedures for the installation and removal of experiments; however we have no single explicit procedure addressing this. After review of our procedures we find that we do have several procedural statements addressing the installation and removal of experiments. We also find that developing a single explicit procedure governing experiment installation and removal would improve our SOPS.

Therefore, we agree to develop and implement a procedure addressing the installation and removal of experiments.

Observation 3 noted that although several procedural statements exist describing proper alarm responses, no single specific l l procedure dedicated to alarm response exists. After reviewing our l procedures, we agree that development and implementation of an

" Alarm Response" procedure is appropriate. We plan to implement such a procedure in the near future.

Observation 4 referenced a table summarizing core data that is located in the control room. The observation noted that no reference was made as to how the core data was generated. The core data was generated during initial start-up testing of our new LEU l fuel core. The core data located in our control room is simply copied from our report to you (NRC), " Initial Loading and Testing of LEU Fuel At The UMR Reactor Facility" (January,1993) . Detailed hand calculations and raw data for all core data parameters are s l I i

9309030257 930826 PDR ADOCK 05000123 E4 C on enu3, omananannsinui,on .

i V PDR !_2 l

]

l l

s-documented in a separate internal UMRR report.  !

l The core data located in the control room is initiated and dated by l the Reactor Manager signifying authorization. We have no  ;

procedural requirement that core data be maintained in the control room. Procedurally, required core data (i.e. excess reactivity, shutdown margin, and rod worths) are logged on the "UMRR Core and j Rack Storage Form" as required by SOP 207, " Fuel Handling". These i forms are maintained in 3-ring binders.

We feel the format of the data as it is presented in the control room is better suited to operator and student usage than the format of the SOP 207 form.

Finally, we rarely change our core configuration. We only run about 10MW-hr per year, so we have no need to change configuration for burn-up. When the core is changed, it is a major event, and all core data will be updated at that time.

We believe it is appropriate to continue our current practice wita regard to core data located in the control room.

In summary, we believe it is appropriate to implement procedural changes for the first three observations. We believe our current practice with regard to the fourth observation is appropriate.

Please contact us if further discussion or information is necessary.

Sincerely,

/ Hi% ?!difS{,

avid W. Freeman UMR Reactor Manager DWF/lp copy to: Dr. Albert E. Bolon, UMR Reactor Director Dr. Lee W. Saperstein, Dean, School of Mines and Met Signed before me this 7/ day of ,[mj /Il3 .

o ,

z u / u/b-Notary Public St E HUnIAM NOTARY PUBLIC STATE OF MISSCURI IHEU5 COUNTY MY CEEM!$5AN EXP. AUG. M194