ML20055F913

From kanterella
Jump to navigation Jump to search
Amend 26 to License R-81,changing Tech Specs to Delete Surveillance Requirements When Reactor Defueled & Does Not Require Ph & Conductivity Measurements to Be Made Weekly If No Fuel in Pool
ML20055F913
Person / Time
Site: 05000054
Issue date: 07/17/1990
From: Weiss S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20055F912 List:
References
R-081-A-026, R-81-A-26, NUDOCS 9007190356
Download: ML20055F913 (6)
v • d • e


Text

.. - . . - ~ . ~ .- - - .

,L UNITED STATES f *l  :

'[

s NUCLEAR HEGULATORY COMMISSION  ;

f E- WASHINGTON, D. C. 20666 To

% /

i

?

g i o,

CINTICHEM. INC.

DOCKET NO. 50-54 t AMENDMENT TO FACILITY OPERATING LICENSE' i Amendment No. 26 License No. R-81 i

1. The Nuclear Regulatory Comission (the Comission) has' found that:

A. The application.for amendment to facility Operating. License L.

No. R-81 filed by Cintichem, Inc. (the licensee), dated June 19, i

1990, complies with the standards and requirements of the Atomic ,

Energy' Act of 1954, as amended (the Act).. and the Comission's '
regulations as set forth in 10.CFR Chapter I; LI L

B. . The facility will operate in conformity with the application, the i provisions of the Act, and the regulations of the Commission; j 1

C. There is reasonable assurance: (1)thatthe=activitiesauthorized s1 by-this amendment can be conducted without endangering the health-h; and safety of the public, and (ii) that such activities will be L' conducted in compliance with the Comission's regulations set forth -

[ in 10 CFR Chapter I-1 :1 D. ' The. issuance of this amendment will'not be inimical .to the comon l

~ defense and security or to the health and safety of theipublic; q 1

s The issuance of this amendment-is in accordance with.10 CFR'Part 51

~

-E.

of the Comission's regulations and all applicable requirements have 1 q.

been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105(a)(4) J and publication of notice for this amendment is not required by -1 10CFR2.106(a)(2).

r f

'9007190356ADOCK 05000, 900717 DR O

i n ._

. l

.. . 2 } .

'2. Accordingly, the license is amended by changes to the Technical l Specifications as-indicated in the enclosure to this license amendment, y and paragraph 2.C(2) of License No. R.81 is hereby amended to ' read as E follows:

l4 H .(2) Technical Specifications  !

The Technical Specifications contained in Appendix A, as revised l through Amendment No. 26, are hereby incorporated in the license.- l The licensee shall operate the facility in accordance with the l Technical Specifications.

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

, h d Seymo r H. Weiss, Director ..

Non-Power Reactor, Decommissioning and Environmental Project Directorate Division of Reactor' Projects - Ill, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

Appendix A Technical i

. Specifications Changes Date of Issuance: July 17,1990 s

_ ____________..-_____________m _ - ,- *,

p E'

ENCLOSURE T0 LICENSE AMENDMENT NO.:26

-TO FACILITY OPERATING LICENSE NO. R-81 I'

DOCKET NO. 50-54 ,

- Replace the following pages of the Appendix A Technical Specifications with ,

the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.  ;

e Remove Insert i

23 23 24 24 25 25 9

1 1

i i

s

?-

1 '-

( '

b

, ;, 4.0 SURVEILLANCE REQUIREMENTS Applicability: The requirements listed below generally prescribe tests or inspections of systems and components, Those items marked with an

  • are not applicable if the reactor is completely defueled, but they must be; performed if the reactor is refueled.

Obiective: The objective is to periodically verify that the serformance of required systems is in accordance with specifications given a>ove in Sections 2.0 and 3.0.

Specifications: The specifications are as follows:

4.1 Heasu' ring.and. Safety Channel Calibration .

  • A channel calibration of each measuring and safety channel shall be performed l

. annually (see Section 3.3.4 and 3.3.5).  ;

L 4.2 Reactivity Surveillance .

l I * (1) The reactivity worth of each control rod (including the regulating rod) l

[ '

and the shutdown margin shall be determined whenever operation requires a ",

l reevaluation of core physics parameters, or annually, whichever occurs first. The rod worth will be determined using the reactivity-period or rod-drop-methods. l

  • (2) The reactivity worth of an experiment shall be estimated, or l i measured at low power, before conducting the experiment. I l
  • -(3) Boron carbide rods shall be gauged quarterly and any dimensional l changes reported promptly to the Commission. Silver / indium / cadmium control rods shall be gauged annually, or, in the case of newly q installed rods, at the end of the first 6 months. If any Ag/In/Cd i

l L'

or boron aluminum alloy rod does not meet the acceptance criteria,

! -it.shall be removed from service. In addition, all other rods L manufactured from the same batch shall-be inspected.

J L 4.3 control and Safety System Surveillance  !

s '

  • (1) The scram time shall be measured annually. If a control rod is l removed'from the core temporarily, or_if a new rod is installed, L its scram time shall be measured before reactor operation. If the bridge is moved, the scram time will be measured before subsequent reactor operation.

1 L

  • (2) A channel test of each measuring channel in the reactor safety l l' system shall be performed monthly or prior to each reactor operating I period, whichever occurs first, unless the preceding shutdown i period is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or less. A channel test before startup is, l l

however, required-on any channel receiving maintenance during the shutdown period.

1 Amendment No. 26

)

    • ~(3) A channel check of each measuring channel (except for the pool l I level)'in the reactor safety system shall be performed daily when the reactor is in operation, ,

4 Radiation Monitoring System  ;.

(1) The excursion, stack, and area monitors shall be calibrated annually, (2) The excursion, stack, and area monitors shall receive a channel test monthly.

(3) The excursion, stack and area monitors shall receive a channel check and asetpointverificatIondailyduringreactoroperatingperiods.

4.5 Engineered Safety Features 4.5.1 Excursion Monitor: See Section 4.4, above.

4.5.2 Emergency Generator (1) The ability of the emergency generator to start, to run normally, and to  :

generate 440 V AC shall be checked weekly.

(2) The generat6r shall be tested for its ability to accept, via the automatic transfer switch, the reactor electrical load once every l 6 months. A commercial power outage and subsequent pickup of load by the emergency generator will count as a successful load test.

4.5.3 Confinement ,

i l (1) The efficiency of the charcoal-filters and of the-absolute filters in l 1: the emergency exhaust system shall be measured annually and the flow rate verified.

1 (2) The operability of the evacuation alarm and containment isolation system  ;

l- shall be tested, and negative pressure verified, semiannually. A

, utility power outage may be used to initiate such tests..

4.6s Reactor Fuel (1)~ Upon receipt from the fuel vendor, all fuel elements shall be visually L inspected and the accompanying quality control documents checked for compliance with specifications.

-(2) Each new fuel element will be inspected for damage and flow obstructions prior to insertion into the core.

4.7 Sealed Sources-l

-The antimony-beryllium sealed source shall be leak tested in accordance with the procedures described in the application for License Amendment No. 5, except that the frequency of leak testing will be in accordance with 10 CFR 34.25(b).

Amendment No. 26

c. , .

4.3 Pool Water (1) The pHLand specific resistence of the pool water shall be determinet each week, whenever the pool contains reactor fuel. ,

(2) An analysis of the pool water for radioactive isotope identification ,

shall be done at semiannual intervals. This analysis is to include  !

Sb-124 as an indicator of Sb-Be neutron source integrity.

..(3) Activity of the pool water will be measured weekly. 1 4.9 Core. Spray.

The core spray in the reactor operating position shall be tested for

, operability semiannually.

4.10 Ilux Distribution

'l

  • In order to verify that power gradients among fuel element do not cause l peaking factors to exceed those used in the basis of Section 2.1, the radial neutron flux distribution will be determined whenever a .'

significant core configuration change is made, l

'l s-l E

?

L l

l-~

i l

l r Amendment No. 26 l-l

{ *

Retrieved from "https://kanterella.com/w/index.php?title=ML20055F913&oldid=3635989"