ML20134C553

Application for Amend to License R-67,revising Tech Specs to Authorize Performance of Routine Calibr or Maint on Radiation Monitors During Extended Operations.Fee Paid

ML20134C553
Person / Time
Site:	General Atomics
Issue date:	08/12/1985
From:	Mowry W GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
To:	Thomas C Office of Nuclear Reactor Regulation
References
67-7092, NUDOCS 8508160351
Download: ML20134C553 (3)

Text

.- - _ - .-

e In Reply Refer To: 67-7092 GA Technologies Inc.

SkN D EGOUFORNIA 92138 (619) 455 3000 Dr. Cecil 0. Thomas, Chief Standardization & Special Projects Branch Division of Licensing -

U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Docket 50-163: R-67; Application for License Amendment and Technical Specification Change. (19 copies)

Dear Dr. Thomas:

GA Technologies Inc. (GA) has need to make a change in its subject reac-tor technical specification for reasons stated below. Accordingly, we re-quest that our subject license reactor technical specifications, Section 6.2.3 (a), (b), and (c) and 10.2.6 (f)(2), both of which deal with radia-tion monitors, be amended to read:

6.2 3: The following monitoring systems shall be operable during reactor operation or when work is done on or around the reactor core.

(For periods of time for maintenance to the radiation monitoring systems, the intent of this specification will-be satisfied if the installed system is replaced as needed with alternative or portable gamma-sensitive instruments having their own alarms or which shall be kept under visual observation).

(a) An area radiation monitoring system capable of activating the evacuation alarm.

(b) A continuous monitoring system for airborne radioactivity

, having a readout and audible alarm which can be heard in both the reactor and control rooms.

(c) The monitoring systems in (a) and (b) shall be cali-brated annually and their set points verified weekly.

.10.2.6 (f)(2)

When devices are present in the core regardless of reactor power level:

t (i) Reactor scram if the reactor room continuous air monitor registers 50,000 counts per minute or more (scram bypass is permissible during scram test or maintenance operations).  ;

Attached are the fees required to accompany this license amendment re-quest. %p 8508160351 850812

, MC g/F PDR ADOCK.05000163 I

l P PDR l ca C gg

4 Dr. Cecil 0. Thomas 67-7092 l'% ,

The purpose of this request is to seek authorization to perform routine calibration or maintenance on any of the radiation monitors including the continuous air monitor (CAM), during extended operations. According to Sectio 5*$gt.4, the reactor safety systems shall be verified to be oper-able at leWPc once .each day the reactor is operated, unless the operation .

extends continuoc!2y beyond one day, in which case the operability of the reactor safety. system need only be verified prior to the extended run.

Prudence suggests that. provision should be made to verify operability of these systems at least weekly during a long continuous run. Tb check the CAM scram during operation it is neced Q g +p use a scram bypass. In addition, a defective CAM may need to be r)hasced by an alternative CAM with scram. To permit these desirable surveillance anda aintcnance oper-ations, we seek the additional wording in the applicable Techn'ical- Speci-fications suggested above.

Justification for providing scram bypass or temporary alternative instru-mentation for the radiation monitors is the following:

1. The Mark III TRIGA reactor license (R-100) authorized the re-quested substitution of temporary, portable instrumentation under visual observation (Sections 3 2 neactor Instrumentation) .

For periods of time for maintenance to the radiation monitoring systems, the intent of this specification will be satisfied if the installed systems are replaced with portable gamma-sensitive instruments having their own alarms or which shall be kept under visual observation.

2. To instrument for the present continuous reactor operation, we have in operation a large number of radiation sensitive moni-tors: namely, ,

, 2 Area monitor detectors; 1 Crntinuous Air Monitor with a standby CAM in the immediate vicinity;

~ 1 Radiation Monitor in ,the ' Absolute Air Filter (in stack exhaust line);

1 Cell top radiation monitor near the thermionic cells; 1 Stack monitor.

With such an array of radiation monitors, there is no credible possibil-ity that dangerous release of radioactivity would be detected by only one of the above monitors. Release of such a quantity would be immediately detected by at least four of these detectors: the CAM, the absolute fil-ter radiation monitor, the stack monitor, and the cell top monitor.

..- o .

Dr. Cecil' O. Thomas 67-7092 r

~The desire both to test routinely the CAM scram and to provide mainte-

~

nance during a long term test stems from our interest to assure continued long term operation of the safety circuits. The temporary replacement of any of the above radiation monitors does not decrease the system safety (because of the obvious redundancy) and does in fact actually increase the assurance of continued proper operation of these components of the safety system.

GA conclude:S that rx) safety: considerations are altered by this request for ability to test and maintain the radiation monitors during a long

' reactor operation.

. We ,would appreciate your assiistance in expediting this request and look

<_ rorward to receiving the registsted license amendment at your earliest 127 - - s_ conveni'ence, :Should you have 'any questions in the matter, please

, ' ' promptly contact by telephnn.e. either Dr. W. L. Whittemore at (619) 455-32TI or me at (619) 455-2823 .._

q. Very truly yours', -

William R. Mowry Licensing Administration WRM:WLW:he

Attachment:

Check for $150.

t w

d L

f e

1

- 1

- - . .. . , . - . . . _ . -