ML19281B236

License for Transnuclear,Inc to Export 2,059.75 Mci Cf-252 as Cement Wire to France

ML19281B236
Person / Time
Issue date:	04/18/1979
From:	Oplinger G NRC OFFICE OF INTERNATIONAL PROGRAMS (OIP)
To:
References
79-108-01-(TNP2, 79-108-1-(TNP2, NUDOCS 7905020506
Download: ML19281B236 (2)

Text

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THIS LICENSE EXPIRES 01 I1hY 1980 7

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.EE l Pursuant to the Atomic Energy Act of 1954,os mended.ond the the licensee, o license is hereby issued to the licensee author ;, :.ME M

i Energy Reorganization Act of 1974 and the re ; lotions of the izing the export of the mote.iols ond/or production or utilization l Nuclear Regulatory Commission issued pursuant thereto, and in facilities listed below, subject to the terms and conditions herein. l M

reliance on statements and representations heretofore made by J.E i

uCtNsEE ULTIMATE CON 51GNEE IN FOREIGN COUNTRY b

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k~~E Transnuclear Inc.

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Attn: Vicki Matson F

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, NmE Transnucleaire S.A.

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11 bis rue Christophe Colomb c/oSavannahRiverLaboratoriesj-

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Aiken South Carolina 29801 in e

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.5sf5 uruCANrs REr. NO-79-108/01 (TNP275)

CouNTn Ce utT=TE oesTmTiON France ouANTirY l :EsClieriON OF MATERIALS CR FAOUTIES g

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2059.7l5 millicuries of Californium-252 As cemet wire.

i Conditions 3 and 6 on page two of this license apply to this export.

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Y Neither mis license nor any right under this license shall be assig i-Q THIS UCENSE t5 IN%d UNE55 qGNEo SELOW g-GeraldG."OpEnh7r['AssTEaEt. Director ed or otherwise transferred in violation of the provisions of the E

g' Atomic Energy Act of 1954, os amended and the Energy Reorgon-Export /Ir: port and International

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iration Act of 1974.

! TN.s 'icense is subject to the right of recapture or control by Section Office of International Programs I

1. 108 of trie Atomic Energy Act of 1954, os omended and to all of the g

g oiber prov s.ons of said Acts, now or hereafter in effect and to oil

[4 vond rules and regulations of the Nuclear Regulatory Commission.

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. (7 751 Pag. 2 of 2 Poses U.S. NUCLEAR REGULATORY COMMISSION EXPORT LICENSE XB0b1025 Conditions License Number Condition 1 - Licensee shall file with the Customs Officer or the Postmester two copies, in addi-tion to those otherwise required, of the Shipper's Export Declaration covering each export and mark one of such copies for transmittel to the U.S. Nuclear Regu-lotory Commission, Washington, D.C. 20555. The following declaration should ac-company or be placed on the Shipper's Export Declarctions for such exports:

=e "This shipment is being made pursuant to specific license number (specific license number) filed at(location of Customs office where license is filed),

• HE on (date license was filed). This license expires on (expiration date of license), and the unshipped balonce remaining on this license is sufficient to cover the shipment described on this declaration.

Condition 2 - Exports cuthorized in any country or destination, except Country Groups Q, S, W, X, Y, and Z in Port 370, Supplement No.1, of the Comprehensive Export Schedule cf the U.S. Department of Commerce.

Condition 3 - This license covers only the nuclear content of the material.

Condition 4 - The material to be exported under this license shall be shipped in accordonce with

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the physical protection requirements for special nuclear material in 10 CFR 73.

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Conditior. 5 - Special nuclear meterial authorized for export under this license shall not be trcnsported outside the United States in passenger-carrying aircraft in shipments

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exceeding (1) 20 grams or 20 curies, whichever is less, of plutonium or uranium 233, or (2) 350 grams of uranium 235.

Condition 6-This license authorizes export only and does not authorize the receipt, physical possession, or use of the nuclecr materici.

Condition 7 - The licensee shall complete and submit en NRC Form 741 for each shipment of source material exported under this license.

Condition 8 - The licensee shall advise the NRC in the event there is any change in the designa-tion of the company who will package the nuclear material to be exported under this license, or any change in the location of the packaging operation, at least three weeks prior to the scheduled dcte of export.

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-s lir. Harold R. Denton, Director _ April 27.1979 He expressed our concern with _this directive in our letter to Itr. Keppler dated April 19, 1979. We advised fir. Keppler that we waru conducting a safety review and preparing an appropriate modification request which would recovo the pressurizer low-level signal actuation circuitry and provide for a two-out-of-three pressurizer low pressure actuation. However, in response to urgent and, in our. opinion, inappropriato coercion from your staff, we made the changes -requested to both units at Point Beach Nuclear Plant on the morning of' April 27.

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We have completed our safety review and have prepared.a modification request to change the safety injection actuation instrumentation to a two-out-

/ of-three pressurizer low pressure actuation. The instrumentation logic will U take pressurizer-pressure signals from three of the four pressurizer pressure instruments and initiate safety injection whenever two of the three signals reach the low pressure setpoint of 1715 psig.'

The four pressurizer pressuru' instruments also provide control and interlock inputs to the power operated relief valves. Two separate' pressurizer pressure instruments supply each peuer operated relief valve controller.

In order to meet.the. IEEE-279 Section-4.7 criteria for interaction of protection and control actions, the interlock setpoint for the pressurizer power operated relief valves are also being changed such that each power. operated relief valve will. require' two-out-of-two high pressurizer pressure signals to open.

Approval of the' attached changes to the Technical Specifications is requested..These changes correct the safety injection actuation discussion in the bases of Specification 15.3.5 and revise Item 3 of Table'15.3.5-1 and Iten 12 0f Table 15.3.5-3 to specify automatic safety injection actuation on two-out-of-three low pressurizer pressure signals. The attached pages include the necessary changes.. Changes on each page are identified by appropriate -

nargin bars.

We have reviewed the requirements of 10 CFR Part 171.22 regarding the schedule of fees for facility license acendments.. It is our determination that this. license amendment for DPR-24 should be classified'as a Class III amendment.- The license amendment for DPR-27 is a duplicate of:the Unit I amendment and is, therefore. a Class I amendment.. Accordingly, we have enclosed herewith check number 432351 for;the amendment fees of $4,400.

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fTr. fiarold R. Denton, Director 3-1 April 27,1979 We have enclosed herewith three signed originals and forty copies of this change request.

In, order to allow you to review and approve thi," license amendment request as promptly:as possible, we have also telecopied this letter and the attached pages to 1tr. Trarrcell of your staff on this date.

Very truly yours,

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Sol Burstein Executive Vice President Enclosures Subscribed and sworn to before ne this 27th day of April,1979.

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Safety Injection System Actuation Protection against a Loss of Coolant or steam line break accident is brought about by automatic actuation of the Safety Injection System [ SIS] which provides emergency cooling and reduction of reactivity.

The Loss of Coolant accident is characterized by depressurization of the Rea tor Coolant System [RCS} and loss of reactor coolant to the containment. The Engineered Safety Features have been designed to sense the effects of the Loss of Coolant Accident by detecting low pressurizer pressure and generating signals actuating the SIS active phase based upon this signal. The SIS active phase is also actuated by a high containment pressure signal (Hi) brought about by addition of high enthalpy coolant to the containment. This actuation signal acts as a backup to the low pressurizer pressure signal actuation of the SIS and also adds diversity to protection against loss of coolant.

Signals are also provided to actuate the SIS upon sensing the effects of a steam line break accident.

Therefore, SIS actuation following a steam line break is, designed to occur upon sensing low steam line pressure.

The increase in the extraction of RCS heat following a steam line break results in reactor coolant tempera' 2re and pressure reduction. For this reason protection against a ste&m line break accident is also provided by a low pressurizer pressure signal actuating safety injection.

Protection is also provided for.a steam line break in the containment by actuation of SIS upon sensing high containment pressure.

SIS actuation injects highly borated fluid into the Reactor Coolant System in order to ' counter the reactivity insertion brought about by cooldown of the reactor coolant which occurs during a steam line break accident.

15.3.5-2

Setting Limits 1.

The high containment pressure limit is set at about 10% of design containment pressure.

Initiation of Safety Injection protects against loss of coolant (2) or steam line break (3) accidents as c_scussed in the safety analysis.

2.

The hi-hi containment pressure is set at about 50% of design containment pressure for initiation of containment spray and at about 30% for initiation of steam line isolation.

Initiation of Containment Spray and Steam Line I

Isolation protects against large loss of cbolant or steam line break accidents (3 ) as discussed in the safety analysis.

3.

The pressurizer low pressure limit is set substantially below system operating pressure limits. However, it is.sufficiently high to protect against a loss of coolant accident as shown in the safety analysis. (2) 4.

The steam line low pressure signal is lead / lag compensated and its setpoint is set well above the pressure expected in the event of a large steam line break accident as shown in the safety analysis.(3) 5.

The high steam line flow limit is set at approximately 20% of nominal full load flow at the no-load pressure and the high-high steam line flow limit is set at approximately 120% of nominal full load flow at the full load pressure

'n order to protect against large steam break accidents.

The coincident low Tavg i

setting limit for steam line isolation initiation is set below its hot shutdown value.. The safety analysis shows that these settings provide protection in the event of a large steam break. (3)

Instrument Operating Conditions I

During plant operations, the complete instrumentation syste's will normally be in service. Reactor safety is provided by the Reactor Protection System, 15.3.5-4

TABLE 15.3.5-1 ENGir!EERED SAFETY FEATURES INITIATION INSTRUMENT SETTING LIMITS NO.

FUNCTIONAL UNIT CHANNEL SETTING LIMIT 1

High Containment Pressure (Hi)

Safety Injection *

< 6 psig 2

liigh Containment Pressure Oli-ili) a.

Containment Spray

< 30 psig b.

Steam Line Isolation of Both Lines j[20 psig 3

Pressurizer Low Pressure Safety Injection

• 3,1715 psig 4

Low Steam Line Pressure Safety Injection

• 3,500 psig Lead Time Constant 3,12 seconds Lag Time Constant j[ 2 seconds 5

Ifigh Steam Flow in a Steam Line Steam Line Isolation of d/p corres nding to Coincident with Safety Injection and Affected Line

<0.66 x 10 lb/hr at Low T 1005 psig avg 3,540 F 6

High-high Steam Flow in a Steam Line Isolation j[d/p corresponding to Steam Line Coincident with of Affected Line 4 x 106 lb/hr at Safety Injection 806 psig

• Initiates also containment isplation, feedwater line isolation and starting of all containment fans.

d/p means differential pressure T

TABLE 15.3.5-3 EMERGENCY COOLING e

1 2

3 4

5 OPERATOR ACTION NO. OF MIN.

MIN.

PERMISSIBLE IF CONDITIONS OF NO. OF CIIANNELS OPERAF,LE DEGREE OF BYPASS COLUMN 3 OR 5 NO.

FUNCTIONAL UNIT CIIANNELS TO TRIP CIIANNELS REDUNDANCY CONDITIONS CANNOT BE MET 1.

SAFETY INJECTION a..

Manual 2

1 1

1 Ilot Shutdown ***

b.

Iligh Containment Pressure 3

2 2

1 Hot' Shutdown ***

c.

Steam Generator Low Steam Pressure / Loop 3

2 2

1 Primary Pressure is Less than 1800 psig Ilot Shutdown ***

d..

Pressurizer Low Pressure 3

2 2

1 Primary Pressure is Less than 1800 psig flot Shutdown ***

2.

CONTAINMENT SPRAY a.

Manual 2

2 2

Hot Shutdown ***

b.

111 -111 Containment Pressure 2 sets 2 of 3 2 per 1/ set flot Shutdown * * *

(Containment Spray) of 3 in each set set

• • - Must' actuate 2 switches simultaneously.

• • • - If minimum conditions are not met within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, steps shall be taken on the affected unit to place the unit in cold shutdown conditions.

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