ML20197H976

Forwards Three Copies of Updated TS Section 1.0, Definitions, for Approval.Explanation of Changes Provided & Additions Are Underlined

ML20197H976
Person / Time
Site:	University of Iowa
Issue date:	12/22/1997
From:	Wendt S IOWA STATE UNIV., AMES, IA
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9801020045
Download: ML20197H976 (7)

Text

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OF SCIE NCE AN D T EC11NO1.OG Y 2025 11. M. lilack Engineering Building Ames. Iow.a Soot 1216o 515 394-1423 rAX $15 294 326:

Docket No. 50-116 December 22,1997 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Suoject: Technical Speci6 cations for the Iowa State University Reactor Facility, Update of Technical Specifications

Dear Sir:

Three dennitions have been added to the facility's Technical Specifications and are submitted for approval. : Enclosed are three copies of the complete text of the definitions section with the changes incorporated and an explanation for those changes. The additions have been underlined.

Questians may be directed to me during normal working hours at (515) 294-0539.

Sincerely,

,, rXS flA Scott E. Wendt Reactor Manager Enclosure

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(without enclosures)

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A.F. Rohach, Chm., Reactor Use Committee

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D.B. Bullen, Facility Director E.E. Sobottka, Dir., Environmental Health & Safety R.A. Jacobson, Chm., Radiation Safety Committee

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T. Burdick, US NRC, Region l!!

,f W.R. DeVries, Chm., Mechanical Engineering Department 9801020045 971222 PDR ADOCK 05000116 P

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CilANGE TO DEFINITIONS SECTION OF TECIINICAL SPECIFICATIONS I

freneral Background For years, the UTR-10 facility was operated under tie incorrect assumption that a 10% ' grace' period of existed on surveillance and main!cnance due daies. During the latest h%C inspecilon, this error was brought to our attention. Since that time, all surveillarce and maintenance requirements have been completed with no grace period. With this submittal, we would like to define the terms monthly, quarterly and annually to better specify the frequencies with which surveillance and maintenance requirements must be completed. A ' grace' period, which is similar to those at oiler facilities, has been irm porated into these definitions.

Page 11 Addition of the term ANNUALLY to the definitions section. Under this definition, a 30 day grace petiod would be allowed on annual requirements.

Rcason for the Changs.;

To specify the frequency of an annual requirement and include a 30 day grace period for completion of the requirement.

Safety ImMiggiQns; No reduction in safety results from the proposed addition of the definition of annually.

Page 12 Addition of the term MONTilLY to the definitions section. Under this definition, a 15 day grace period would be allowed on a monthly requirement. The definition restricts the usage of the grace period to 15 days on two consecutive periods and further requires that 12 monthly requirements be performed in cach calendar year. These restrictions nre included to prohibit repeated use of grace periods.

Egason for the Chance:

To specify the frequency of an event that is required to be done monthly and include a 15 day grace period.

Safety lmolicaliQDs:

No reduction in safety results from the proposed addition of the definition of monthly.

Page 1-2 Addition of the term QUARTERLY to the definitions section. Under this definition, a 30 day grace period would be allowed on a quarterly requirement. It restricts the usage of the grace period by requiring that 4 quarterly requirements be performed in cach calendar year. These restrictions are included to prohibit repeated use of gn cc periods.

Reason for the Chan2q; To specify the frequency of an event that is required to be donc quarterly and include a 30 day grace period.

Safety Imnlications:

No reduction in safety results from the proposed addition of the definition of quarterly.

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.,x c 1.0 DEFINITIONS -

LTheterms Safety Limit, Limiting Safety System Setting, and Limiting Condition

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for Operstion are as dermed in paragraph 50.36_ of 10 CFR Part 50.-

ANNUALLY.- If a surveinn-or other activity is 16 be nerfornwi at an=t anan=Hv. it shall be -

l performed at laa** ance everv 12 months. not to excaad 12 months + 30 days.

' CHANNEL TEST The introduction of a signal into the channel for verification that it is operable.

CHANNEL CALIBRATION - The adjustment of the channel such that its output corresponds

? with acceptable accuracy to known values of the parameter which the channel measures.

Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include a Channel Test.

{ CHANNEL CHECK - A' qualitative verification of acceptable performance by observation of channel behavior. This verification, where possible, shall include the comparison of the channel with other independent channels or systems measuring the same variable.

CONFINEMENT BOUNDARY - The surface surrounding the reactor facility defined by the interior panition walls of offices and labo-nries on the north, east and south sides of the building and by the west interior wall which isolatt

%sement, first floor, and the west corridor of the second floor from the central bay.

CONFINEMENT SECURED - The confinement shall be considered secured when:

a. Doors 1-2, CC 102,101,114,113-1, CX112,112,111-1, CX111, CS107, CEl17-2, CC201B,112A-4 are clcsed or we attended by a person with the ability to close the door in the event of an emergency, and i

b. Windows on the north, south, east and west sides of the penthouse, on the west wall of room 112A, on the south wall of room 101, on the east wall above door CX112, on the

- south wall of corridor CC201, on the west wall of corridor CC212, on the north wall of corridor CC211 are unbroken and closed or are attended by a person with the ability to close the window in the event of an emergency, and

. c. The interior partitioned walls _of the first floor offices and laboratories on the north, south, and east sides of the building; and the west interior wall which isolates the

! basement and first floor offices on the west side of the building from the central bay

area; and the second floor north, south, east and west interior walls which isolate the

. second floor from the central bay area are intact and capable of performing as a non-pressure tight boundary, and -

d. The roof covering the central bay area is intact and capable of performing as a non-pressare tight boundary.

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L CONTROL ROD.-~A' plate fabricated with Boral as the neutron absorbing material which is used

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to establish neutron flux changes and to compensate for routine reactivity losses. This includes :

Leafety-type and regulating rods.-

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CORE The portion of the reactor volume which includes the graphite reflector, core tanks,'and ~

- control rods. The thermal column and shield tank duct are not included.'

j DELAY TIME - The clapsed time between reaching a limiting safety system setpoint and the initial movement of a safety-type rtxt.

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- DELAYED NEUTRON FRACTION - When converting between absolute-and dollar-value reactivity units, a bete of 0.00763 is used.-

DROP TIME - The elapsed time between reaching a limiting safety system setpoint and the full

insertion of a safety-type' rod.

EXCESS REACTIVITY - That amount of reactivity that would exist if all control rods (control,

- regulating, etc.) were moved to the maximum reactive condition from the point _where the reactor is exactly critical.

EXPERIMENT - Any operatic <n, hardware, or target (excluding devices such as detectors, foils,

' etc.) which is designed to invettigate non-routine reactor characteristics or which is intended for irradiation within the core region, on or in a beam port or irradiation facility and which is not :

. rigidly secured to a core or shield structure so as to be a part of their design.-

MEASURED VALUE - The value of a parameter as it appears on the output of a channel.

MEASURING CHANNEL - The combination of sensor, line, amplifier and output desices which are connected for the purpose of measuring the value of a parameter.

MONTHLY - If a surveillance or other activity is to be nerformed et least monthly. it shall be nerformed at least once every 30 days. not to exceed 45 days and not to exceed 75 days in two consecutive periods. Also. twelve iganthly surveillance activities shall be performed in each cal-lar vear.

MOVABLE EXPERIMENT - An experiment where it is intended that the entire experiment may be moved in or near the core or into and out of the reactor while the reactor is operating.

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' OUARTERLY - If a surveillance or other activity is to be nerformed at least auarteriv. it shall be -

f nerformed at least 'once everv 90 days. not to exceed 120 days. "Also. four cuarterly surveillancs activities shall be nerformcd in each calendar year.

- OPERABLE / A component or system is capable of performing its intended function.

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OPERATING - A component or system is performing its intended function.

~ REdCTIVITY LIMITS - Those limits imposed on reactor core excess reactivity. Quantities are eferences to a Reference Core Condition '

REACTIVITY WORTH OF AN EXPERIMENT - The maximum absolute value of the reactivity change that would occur as a result ofintended or anticipated ' changes or credible malfunctions -

that alter experimen'. position or configuration.

REACTOR OPERATING _- The reactor is operatirig wher>ever it is not secured or shutdown.

5 REACTOR OPERATOR (RO) - An individual who'is licensed to manipulate the controls of a' reactor.-

' REACTOR SECURED - A reactor is secured when:

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= (1) It contains insufficient fissile msterial e moderator present in the reactor to attain criticality under optimum available conditions of moderation and reflection, or (2) A combination of the following:

a. The minimum number of neutron absorbing control rods are fully inserted or other safety devices are in shutdown position, as -

required by technical specifications, and

b. The magnet power keyswitch is in the off position and the key is removed from the lock, and

c. No work is in progress involving core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods, and c

d. No experiments in or near the reactor are being moved or serviced that have, on movement, a reactivity worth exceeding the

- maximum value allowed for a single experiment or 0.763% Ak/k whichever is smaller.

REACTOR SHUTDOWN - The reacter is shutdown ifit is subcritical by at least 0.763% Ak/k in

the Reference Core Condition and the reactivity worth of all experiments is accounted for.

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u REACTOR SAFETY. SYSTEMS - Those systems, including their associated input channels, which are designed to initiate automatic rasctor protection or to provide information for initiation -

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of manual protective action.

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READILY AVAILABLE ON CALL - Applies to an individual who

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(1) Has been specifically des.ignated and the designation known to the '

operator on' duty, and -

l(2) Keeps the operator on duty informed of where he~ or she maybe rapidly contacted (e.g., by phone, etc.), and

- (3) Is capable of getting to the reactor facility within a reasonable time under normal conditions (e.g., 30 minutes).

REFERENCE CORE CONDITION - The condition of the core when it is at ambient temperature a

. (cold) and the reactivity worth of renon is negligible, less than 0.23%' Ak/k.

REGULATING ROD - A low-worth control rod used primarily to maintain an intended power level that does not have scram capability. -It's position may be varied manually or by the servo-controller.

7 SAFETY CHANNEL - A measuring or protective chaanel in the reactor safety system.

SAFET Y-TYPE ROD - A tod that can be rapidly inserted by cutting off the holding current in its electromagnetic clutch. This applies to safety #1, Safety #2, and shim-safety.

SECURED EXPERIMENT - Any experiment, experiment facility, or component of an -

experiment that is held in a stationary position relative to the reactor by mechanical means. The teatraining forces must be substantially greater than those to whbh the experiment mi;;ht be subjected by hydraulic, pneumatic, buoyant, or other forces which are normal to the operatin5 environment of the experiment, or by forces which can arise as a result of credible malfunctions.

i SENIOR REACTOR OPERATOR (SRO) - An individual who is licensed to direct the activities of a Reactor Operator (RO) and to manipulate the controls or a reactor.

SHALL, SHOULD,- AND MAY - The word "shall" is used to denote a requirement, the word "should" to denote a recommendation, and the word "may" to denote permission, neither a requirement nor a recommendation.

SHUTDOWN MARGIN I The minimum shutdown reactivity necessary to provide confidence -

that the reactor can be made subcritical by means of the control and safety systems starting from any permissible operating condition although the most reactive rod is in its most reactive position, and that the reactor will remain subcritical without further operator action.

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K TRUE VALUE - The actual value of a parameter or variable.

' UNSCHEDULED SHUTDOWN - Any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operating error, equipment malfunction, or a manual shutdown in =

response to' conditions which could adversely affect safe operation, not iiscluding shutdowns which occur during testing or check-out operations.

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