ML20028H379
| ML20028H379 | |
| Person / Time | |
|---|---|
| Site: | 05000131 |
| Issue date: | 12/20/1990 |
| From: | Mendonca M Office of Nuclear Reactor Regulation |
| To: | Turcotte R DEPT. OF VETERANS AFFAIRS MEDICAL CENTER, OMAHA |
| References | |
| NUDOCS 9101020190 | |
| Download: ML20028H379 (5) | |
Text
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December 20, 1990 Docket No. 50-131 Mr. R. L. Turcotte, Director Veterans Administration Medical Center 4301 Woolworth Avcoue Onaha, Nebraska 68105
Dear Mr. Turcotte:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION We are continuing our review of your application for amendment of Facility Operating License No. R-57 submitted on October 15, 1990. During our review of your applicetion for amendment, questions have trisen for which we require additional information and clarification.
Please provide response to the enclosed Request for Additional Information within 60 days of the date of this letter, so that we may continue our evaluation of your application.
If you have any question on this review please contact me at (301) 492-11?8.
The reporting and/or record keeping requirements containea in this letter affect fewer than ten respondents; therefore, Office of Management ano Eudget clearance is not required under Public Law 96-511.
Sincerely, Original signed by:
Marvin M. Mendonca, Senior Project Manager Non-Power Recctors, Decomissioning and Environmental Projects Directorate Division of Advanced Reactors and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
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December 20, 1990 Docket No. 50-131 Mr.-R. L. Turcotte.. Director Veterans Administration Medical Center 4101 Woolworth Avenue Omaha, Nebraska 68105
Dear Mr. Turcotte:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION We are continuing our review of your application for amendment of facility Operating-License No.-R-57 submitted on October 15, 1990. During our review of your application for amendment, questions have arisen for which we require additional information and clarification.
Please provide response to the enclosed Request for Additional Information within 60 days of the date of this letter, so that we may continue our evaluattor, of your application.
If you have any question on this review please ntactmeat(301)492-1128.
The reporting and/or record-keeping requir(
",s contained in this letter af feet fewer than ten respondents; therefo';, Of fice of Management and Budget clearance is not required under Public-Law 96-511.
Sincerely, M
T Marvin M. Mendonca, Senior Project Maneger Non-Power Reactors,-Decommissioning and Environmental. Projects Directorate Division of Advanced Reactors and Special Projects-Office ef-Nuclear Reactor Regulation
Enclosure:
As stated i
cc w/ enclosure:
See next page
Yeterans Administration Docket No. 50-131 Medical Center cc: Director, Department of Environmental Control Executive Building, 2nd Floor Lincoln, Nebraska 68509 Mayor City of Omaha Omaha, Nebraska 681rp Dr. Alan blotcky Reactor Director Veterans Adraini',tration Hospital 4101 Woolworth Avenue Omaha, Nebraska 68105
REQUEST FOR ADDITIONAL INFORMATION DEPARTMENT OF VETERANS AFFAIRS TRIGA REACTOR l
General Comment:
Your submittal of October 15, 1990 attempted to revise the staff's previous Safety Evaluation Report on your facility. Although this was helpful in the NRC staff's understanding of your proposed amendments, your submittal and response to the questions below should be presented in the form of your separute, independent safety analyses.
If you wish tu revise an existing document to describe amendments to your facility, appropriate revisions could be made to your Final Safety Analysis Report.
1.f you choose this option, complete replacement pages should be provided for ti.c changes and all safety I
aspects, including the below questions, should be,ncluded.
1.
Provide a description of your verification and validation plan for installation of the new console, a.
Include considerations to assure that the testing program verifies correct function and reliability of the new equipment while rc.aintaining the proven performance of the existing systen functions until the new system takes over those functions.
b.
Include a list of the mejor problems and resolutions found during your test sequence.
c.
Incluce description of how response time (e.g., scram), and sensitivity (e.g., detector locations) are established and verified.
2.
Describe any changes raade to the loss of high voltage to neutron detector scram function.
3.
Provide description of the locations and installation configuration for the new instrumentation and control system.
o.
Include evaluation or specification of the tenperature and humidity conditions and the systems capability to function under expected and abnormal conditions, b.
Include evaluation of enclosures, ccbinets, and connections to building structures for ger.eral ruggedness under potential dynamic conditions, e.g., seismic.
c.
Include evaluation of potential contact chatter during dynamic conditions.
Is the system designed to scram on potential contact chatter conditions? Describe this design feature, d.
Include evaluation of cable and component shielding, configuration and/or isolation to mitigate the consequences of electro-magnetic interference (EMI). Evaluate the consequences of EMI, e.g., scram, malfunction, etc.
e.
Include evaluation of power supply buffers to mitigate power transient effects. Describe surveillance programs to assure proper system function after pwer losses.
l
s REQUEST FOR ADDITIONAL INFORMATION DEPARTMENT OF VETERANS AFFAIRS TRIGA REACTOR (CONTINUED) f.
. Include evaluation of instrument isolation devices. Describe manufacturer's or related testing that-assures adequate isolation capability between safety and non-safety functions.
4.
Provide a description of the maintenance and surveillance program to assure acceptable safety function of the new system.
5.
Provide a description of operator training on the-new system..
6.
Page 2 to your " Revision to Safety Evaluation Report of Omaha V. A.
Medical Center Research Reactor, Docket No. 50-131," second paragraph in section 7.4.1.b states that "...the NMIOOO trip output is also hardwired into th; sr. ram loop..."
Provide a description of how this is hardwired and include reference to Figure 7.2 of this submittal to show the connections.
.7.
In regard to your Figure 7.2:
a.
Verify that there is a connection between the Campbelling unit and counter'1.
It appears there is not a line connection between the "Y/F cony." to " Counter 1".
Describe this connection, b.
-Describe how the remote display functions (flags 1 and 2) is installed and used, c.
Describe the calibration generator, logic and switch function.
Provide an evaluation of calibration accuracy and assurance that
-the ~ calibration function can not inadvertently interfere with system
- function, 8.
Provide prososed Technical Specification changes to include the watchdog scram in. Table 7.1 Minimum reactor: safety channels.
Include in the bases for this; specification a de.ecription of the' maximum time for the watchdog.
timer scram function and its safety significance.
9.
Provide a change bar for proposed change-to Technical Specification page 8, second paragraph in " Bases" section,-second line for change to "10 counts per second."
10.
Provide the reason for changing the minimum count rate rod withdrawal-interlock.
t
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