1CAN098609, Forwards Proprietary & Nonproprietary, Inadequate Core Cooling Monitoring Sys Final Design Description, Per NUREG-0737,Item II.F.2.Proprietary Rept Withheld (Ref 10CFR2.790)

Forwards Proprietary & Nonproprietary, Inadequate Core Cooling Monitoring Sys Final Design Description, Per NUREG-0737,Item II.F.2.Proprietary Rept Withheld (Ref 10CFR2.790)

ML20214P742
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/17/1986
From:	Enos J ARKANSAS POWER & LIGHT CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML19292F918	List: 1CAN098609, Forwards Proprietary & Nonproprietary, Inadequate Core Cooling Monitoring Sys Final Design Description, Per NUREG-0737,Item II.F.2.Proprietary Rept Withheld (Ref 10CFR2.790) ML20214P748
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 1CAN098609, 1CAN98609, NUDOCS 8609240043
Download: ML20214P742 (4)

Text

ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 (501) 371-4000 September 17, 1986 1CAN098609 Mr. John F. Stolz, Director PWR Project Directorate No. 6 Division of PWR Licensing - B U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 ANO-1 ICC Monitoring System Final Design Description, NUREG-0737, Item II.F.2

Dear Mr. Stolz:

Our March 18, 1986 letter (ICAN038604) committed to providing the Final Design Description for the ANO-1 ICC Monitoring System in order to complete the documentation requirements of NUREG-0737, Item II.F.2. Attached is the subject document.

The subject document was scheduled for submittal by July 4, 1986. When it was determined that this schedule would not be made, Mr. Guy Vissing was informed via a telephone conversation on July 3, 1986.

The ANO-1 ICC Monitoring System consists of:

• Subcooling Margin and Superheat Temperature Monitor;

• Core Exit Thermocouples (CETs);

• Reactor Vessel Level Monitoring System (RVLMS); and

• Hotleg Level Monitoring System (HLMS).

The Subcooling Margin and Superheat Temperature Monitor for ANO-1 is presently installed and operational. The details of the system were provided in our letter dated January 18, 1980 (BCAN018022).

ANO-1 has 32 non qualified CETs monitored by the plant computer and Safety Parameter Display System (SPDS). During the ANO-1 seventh refueling outage (IR7), sixteen qualified CETs will be installed in order that four qualified CETs will be located in each core quadrant. The signals from the CETs are inputs to the SPDS in the control room. The displayed temperature range is 100 - 2300*F. hp?

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' Mr. ' J::hn F. Stolz .SIptembrr 17, 1986 ~I The RVLMS consists.of two redundant Radcal Level Instruments (RLIs) (each containing ten Radcal Gamma Thermometer (RGT) sensors to detect reactor coolant inventory above the core), a Data Acquisition System with primary and secondary display devices.

The HLMS is based on AP transmitters (one wide range and four narrow range transmitters per hotleg). The system is designed to infer the water level in the hotlegs during no-flow conditions.

We are including proprietary and non proprietary versions of the ANO-1 Final Design Description. Pursuant to 10CFR2.790 we request that the proprietary version be withheld from public disclosure. The reasons for the proprietary classification of this report are delineated in the enclosed affidavit.

Very truly yours,

/M--

J. T nos, Manager Nuc1 r Engineering and Licensing JTE/MJS/sg

AFFIDAVIT-SUBMITTED TO NUCLEAR REGULATORY COMMISSION CONCERNING PROPRIETARY INFORMATION AND TRADE SECRETS CONTAINED IN ARKANSAS POWER AND LIGHT COMPANY _ REPORT ENTITLED " ARKANSAS NUCLEAR ONE - UNIT 1 INADEQUATE CORE COOLING (ICC) MONITORING SYSTEM FINAL DESIGN DESCRIPTION" STATE OF ARKANSAS )

) ss:

COUNTY OF PULASKI )

'l T. Gene Campbell states as follows on behalf of Arkansas Power and Light Company:

1. I am Vice President, Nuclear Operations for Arkansas Power and Light Company.

2. I am familiar with the contents of the enclosed document entitled

" Arkansas Nuclear One - Unit 1 Inadequate Core Cooling (ICC)

Monitoring System Final Design Description."

3. Arkansas Power and Light (AP&L) Company in June 1983 entered into a contract with Technology for Energy Corporation (TEC) to supply an Inadequate Core Cooling (ICC) Monitoring System for Arkansas Nuclear One. Since that time, AP&L and TEC have designed and conducted an extensive experimental test program to verify ICC capability and to provide licensing support and design data for the system hardware.

This design and testing program required substantial financial investment by the above parties. The disclosure of the details and/or results of these tests could cause substantial harm to the competitive position of the parties since it is feasible that similar systems may be purchased by other utilities seeking to modify their ICC program. Under an agreement between AP&L and TEC, such a purchase would be financially beneficial to both.

4. Therefore, the contents of the enclosed report includes information considered to be proprietary in accordance with the guidelines established in 10CFR2.790.

I JM4 v T. Gene Campbell pf Vice President, Nuclear Operations STATE OF ARKANSAS ) ss:

)

COUNTY OF PULASKI )

On this /[ day of' 14 1986, before me, a Notary Public in and for The State of Arka'nsds, duly commissioned and sworn, personally appeared T. Gene Campbell, to me known to be Vice President, Nuclear Operations for Arkansas Power and Light Company and on oath stated that he was authorized to make- this affidavit on behalf of the corporation.

IN WITNESS WHEREOF, I have set my-hand and affixed my official seal the day and the year first above written.

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MyCommission~Expirp: '). /943 f

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