ML20113C731

Forwards Responses to NRC Questions Generated by Review of QA Program Submitted by 841109 ltr.Q-list for Structures,Sys & Components Encl

ML20113C731
Person / Time
Site:	University of Texas at Austin
Issue date:	04/04/1985
From:	Bauer T, Klein D TEXAS, UNIV. OF, AUSTIN, TX
To:	Thomas C Office of Nuclear Reactor Regulation
References
NUDOCS 8504120012
Download: ML20113C731 (5)

Text

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I I-THE UNIVERSITY OF TEX AS COLLEGE OF ENGINEERING AUSTIN, TEXAS 78712 Department of AfechanicalEngineering Nuclear Engineering Program 312 - 471-3136 April 4, 1985 Standardization and Special Projects Branch Division of Licensing Nuclear Regulatory Commission Washington, D.C. 20555-Atten: Cecil Thomas Re: Docket #50-602

Dear. Sir:

Enclosed are the written responses to questions

. generated by review of the quality assurance program submitted as part of the license submittal by The University of Texas at Austin (letter dated November 9, 1984).

Sincerely,

).

Thomas L. Bauer Assistant Director / Supervisor Nuclear Engineering Teaching Laboratory TLB:bb Enclosure cc: Dr. G.J. Fonken Dr. D.E. Klein Dr. H.A. Walls OY I I Dr. fale E. Klein 5 41200 [ 2

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G RESPONSE TO QUESTIONS THE UNIVERSITY OF TEXAS AT AUSTIN l QUALITY ASSURANCE 1

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1. The subject paragraph of section 9.1 will be replaced with the following paragraph:

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Safety-related identifications for quality assurance I are determined from safety analyses. Although sev- l eral systems such as the reactor safety and pro-tection system, engineered safety features and ra-diation monitoring systems are important to safety, '

only one reactor component, the fuel element clad-ding is identified as safety-related. The quality assurance program is not applied to routine reactor operations and surveillance activities but shall be implemented for nonroutine activities determined to be safety related in nature or affecting safety related components. Activities shall include de-sign, construction, testing, modification and main-

tenance of safety related items. Other components related to safety limits, limiting conditions for operation and design features, as identified in

f. technical specifications, will apply only those elements of quality assurance necessary to es-tablish reliable performance of the intended structure, system or component function. The following table lists the components subject to the quality assurance program or selected sec-tions of the program.

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l p2 Q-List for IMW UT TRIGA OC/0A Structures. systems or connonents Safetv* Snees Fuel Element Cladding structure 1 manuf.

Shipping package 1 Reactor Core Structural components 2 manuf.

Tank structure 2 design Shield structure 2 constr.

Experiment Equipment (core reflector)

Beam tube components 2 design .

Rotary rack system 2 design Experiment Equipment (core grid) i Pneumatic tube components 2 design Installed cc a system 2 design Protective System.

Instrumentation system 2 manuf.

Control system 2 manuf.

Safety system 2 manuf.

Auxiliary Systems Pool coolant system 2 design Water purification system 2 design Room confinement components 2 const.

Ares ventilation components 2 const.

Area radiation monitor system 2 manuf.

Air radiation monitor system 2 manuf.

1 - All sections of quality assurance program shall be con-sidered applicable.

2 - Specific sections of_ quality assurance program should be applied as required to assure reliable performance.

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2. The word "shall" is to replace the word "should" in

a. Section 9.2.1 first paragraph, line 7

b. Section-9.2.1 third paragraph, line 4

c. Section 9.3.1 third paragarph, line 1 The word "or" in the last sentence of section 9.2.4 and 9.2.5 is replaced by the word "and".

3. The word "shall" in line 13 of section 9.1.3 is changed to "may". The following sentence insert is added as the next to last sentence of section 9.1.2:

"The facility supervisor shall have the ultimate responsibility for both the specifications of quality:related requirements and the functions of quality related activit'ies."

The following sentence is added to section 9.1.4:

"The checklist or approval shall be incorpor-

' .ated in the table format for the acceptance of each specified quality assurance element by the facility supervisor."

4. Rephrase the first paragraph last sentence of section 9.2.1 to read "...., that is knowledgeable of the design criteria and is informed of the quality requ'irements."

Rephrase the first paragraph last sentence of section 9.2.2 to read "..., that is knowledgeable of the procure-ment specifications and is informed of the quality require-ments."

5. In section 9.3.1 delete the word " Maintenance" as the first word of the last sentence of the first paragraph.

Replace the last paragraph of section 9.3.1 with

" Procedures shall provide for identification of inspected and tested' items. Provisions shall be made=to clearly identify nonconforming items from conforming items. In situations that inspections are not' advantageous a descrip-tion shall be provided for monitoring actions."

Add the following paragraph to the end of section 9.3.1:

" Procedures shall be~ written for in service inspections of safety-related structures, systems or components."

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6. Replace the last sentence of section 9.3.4 with "The disposition of nonconforming materials will be docu-mented."

7. Add the.following section:

9.3.6 Experimental Equipment. Design, construction, modification, inspection, testing and maintenance of experimental equipment shall be subject to this quality

- assurance program to the extent that these activities are safety related.

< 8. Add the following section:

9.3.7 Replacements, modifications or changes. Insofar as possible, the replacement, modification, or change to structures, systems or components with a safety-related function shall be documented as meeting the requirements i

of the original structure, system or component. Evalua-tion should establish a performance and reliability equi-valent or exceeding the original.

I 9. The last sentence of section 9.1 and reference 1 of section 9 should reference regulatory guide 2.5 not 5.2.

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