ML20067D380

Proposed Tech Spec Changes to Bring Surveillance Intervals Into Agreement W/Ans 15.1 & Revise Min Qualifications for Radiological Control Officer

ML20067D380
Person / Time
Site:	Purdue University
Issue date:	12/06/1982
From:	PURDUE UNIV., WEST LAFAYETTE, IN
To:
Shared Package
ML20067D377	List: ML20067D374 ML20067D380
References
NUDOCS 8212130240
Download: ML20067D380 (6)

Text

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PROPOSED CHANGES T0' Tite TECHNICAL SPECIFICATIONS' l

The following changes are proposed to bring continuity to the -

time interval between surveillance checks and the minimum qualifications for the Radiological Control Officer.

pg. 20 item 4.2.c.1 Change 14 months to 15 months pg. 20_ item 4.2.c.2 Change 14 months to 15 months pg. 21 item 4.2.d Change 7 months to 7h months pg. 21 item 4.2.e Change 14_ months to 15 months pg. 23 item 4.4.b Change 7 months to 74 months pg. 23 item 4.4.c. Change 7 months to 7h months pg. 23 item 4.4.d- ChangeL14 months to 15 months pg. 29 item 6.1.5 Change the last sentence to the following:

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Minimum qualifications for the Radiological Control Officer (RCO) is a bachelor's degree or the_ equivalent in a science or engineer-ing subject, including some ' formal training in radiation protection.

The PC0 should have at least five years of professional experience in applied radiation protection. A master's degree may.be con-sidered equivalent to one. year of professional experience, and a doctor's degree equivalent to two years of professional experience where course. work related to radiation protection is involved. At' least three' years of this professional experience should be in applied radiation protection work in a nuclear facility dealing with radiological problems.

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8212130240 821206 p' DR ADOCK 05000182 PDR

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4.2 Reactor Safety System Applicability This specification applies to the surveillance of the reactor safety system.

Objective The objective is to assure that the reactor safety system is operabic as required by Specification 3.2.

Specification

a. A channel test of each of the reactor safety system channels listed in Table III shall be performed prior to each reactor startup following a shutdown in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or if they have been repaired or de-energized.

TABLE III.

SAFETY SYSTEM CHANNELS CllECKED AFTER PROIDNGED SilUTDOWN Log Count Rate (startup channel)

Log N-Period Linear Level Safety Channel

, b. A channel check of each of the reactor safety system measuring channels-t l

in use or on scale shall be performed approximately every four hours when the reactor is in operation.

c. A channel calibration of the reactor safety channels shall be performed as follows:

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1. An electronic calibration will be performed at intervals not to i

exceed 15 months.

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2. A power calibration by foil activhtion will be performed at inter-i vals not to exceed 15 months.

d. The operation of the radiation monitoring equipment shall be verified l

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daily during periods when the reactor is in operation. Calibration of these monitors shall be performed at intervals not to exceed 715 months

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e. Shim-safety rod drop times will be measured annually, but at intervals not to exceed 15 month's. These' drop times shall also be measured prior to (

operation following maintance which could affect the drop time or cause-movement of the shim safety rod control assembly.

Bases A test or the safety system channels prior to each startup will assure their operability, and annual calibration will detect any long-term drift that is not detected by normal intercomparison of channels. The channel check of the neutron flux level channel will assure that changes in core-to-detector geometry or operating conditions will not cause undetected changes in the response of the measuring channels.

Area monitors will sound an alarm when they sense they are not operating correctly. In addition, the operator routinely records the readings of these monitors and will be aware of any reading which.

' indicates loss of function.

The area monitoring system employed at the PUR-1 has exhibited very ~-

good stability over its lifetime, and semi-annual calibration is considered adequate to correct long-term drift.

The measured drop times of the shim-safety rods have been consistent for 14 years since the PUR-1 was built. An annual check of this para-meter is considered adequate to detect operation with materially changed drop times. Binding or rubbing c.aused by rod misalignment could result from maintenance; therefore, drop times will be checked af ter such maintenance.

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4.4 Containment Applicability

'This specification applies to the surveillance requirements for maintaining the integrity of the~ reactor room and fuel clad.

Objective The objective is to assure that the integrity of the fuel centainment

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is maintained.

Specification

a. The negative pressure of the reactor room will be recorded weekly. .

b. Operation of the inlet and outlet dampers shall be checked at inter-valc not to exceed 715 mont.hs.

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c. ' Operation of the air conditioner shall be checked at intervals not to exceed 713 months. l

d. Representative fuel plates shall be inspected at intervals not to-exceed 15 months. l Bases Specification a, b, and c check the integrity of the reactor room, and d the integrity _of the fuel clad. Based upon past experience these intervals have been shown to be adequate for insuring the operation of the systems affecting the integrity of the reactor room and fuel clad.

4.5 Experiments Applicability This specification applies to the surveillance of limitations on experimente.

Obj ect ive l The objective is to assure that the radioactive material content of experiments does not exceed the limits of parts f and g of specification 3.5.

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may.be' fulfilled by related academic or technical training on a

-one-for-one time basis.

c. Licensed Operator - At the time of appointment.to the active position, an. operator shall have a high school' diploma.or-equivalent.

d. Operator Trainee .An operator trainee shall have all'the-qualifications to'become a licensed operator except for.

possessing an operator's license.

6.1.5 A Radiological Control Of ficer who is organizationally independent--

of the PURil operations group shall advise the Reactor Supervisor-in matters concerning radiological safety. Minimum qualifications for the Radiological Control Officer (RCO) is a' bachelor's degree.

or the equivalent in a science or engineering subject, including some

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formall raining 5n radiaElon protection. The RCO should have at least ,

five years of professional experience in applied radiation pro-

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tedtion. A master's d'eirce may be considered equivalent to'one year of professional experience, and a doctor's degree equivalent

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to two years of prdfe'ssional experience where course work're-lated.to radiaEion protection is involved. .At least three years of this professional expirience should be in applied radiation protection work in a nuclear facility dealing with radiological problems.

.l.6 A licensed operator (LO) or licensed senior operator (LS0) pursuant to 10 CFR 55 shall be present at the controls unless the reactor is shut down as defined in these specifications. During training opera-tions an unlicensed operator may operate the controls but only un-der th'e direct supervision of an ID or an LSO.

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6.1.7 An LSO shall be present or reaaily available on call at any time that the reactor is operating.

6.1.8 The identity of, and method for rapidly contacting, the licensed senior operator on duty shall be known to the reactor operator at any time that the reactor is operating.

6.1.9 The presence of an LSO shall be required at the reactor facility during recovery from unplanned or unscheduled shutdowns except in instances which result from the following:

a. A verified electrical power failure or interruption exclusive of internal power supply failures or interruption of the reactor instrumentation, control, and safety systems;

b. Accidental manipulation of equipment in a manner which does not affect the safety of the reactor;

c. A verified practice or evacuation of the building initiated by persons exclusive of the reactor.

The LSO shall be notified of the shutdown and shall determine its cause. If due to one of the enumerated reasons above, he shall decide if his presence is necessary for a subsequent start up.

6.1.10 The presence of an LSO at the reactor facility is unnecessary for the initial daily start up, provided the core remains unchanged from the previous run.

6.1.11 The minimum crew for operating the reactor shall consist of 2 (two) persons, one of which must be a licensed member of the PUR-1 opera-tions group. The unlicensed crew member must be instructed as to how to shut down the reactor in the event of an emergency.

6.1.12 During fuel changes and movement of large bulk experiments, an LSO will be present in the reactor room.

6.1.13 The Reactor Supervisor or his designated alternate shall be respon-sible for the facility retraining and replacement training progran.

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