ML20235E127

Requests Permission to Perform 25% Power Startup Tests at 18 to 20% Power Under Present 20% Power License.Performing Tests at 18 to 20% Power Shows That Initial Calibr & Fine Tuning of Various Sys Will Be Accomplished

ML20235E127
Person / Time
Site:	Quad Cities, 05000000
Issue date:	04/14/1972
From:	Butterfield L COMMONWEALTH EDISON CO.
To:	Morris P US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20235B311	List: IA-87-111, Submits Rept on Plant,As Discussed in ACRS 150th Meeting on 721012-14.Listed Items Can Be Resolved During Const & Facility Can Be Constructed W/Reasonable Assurance for Operation W/O Undue Risk to Public Safety IR 05000254/1972009 IR 05000358/1972003 IR 05000358/1973001 IR 05000358/1973002 IR 05000358/1973003 IR 05000358/1973005 IR 05000358/1973006 IR 05000358/1973007 IR 05000358/1974001 IR 05000358/1974002 IR 05000358/1974003 IR 05000358/1975004 ML20235B308 ML20235B364 ML20235B401 ML20235B405 ML20235B424 ML20235B456 ML20235B461 ML20235B465 ML20235B477 ML20235B488 ML20235B507 ML20235B552 ML20235B582 ML20235B585 ML20235B588 ML20235B605 ML20235B618 ML20235B623 ML20235B649 ML20235B656 ML20235B662 ML20235B670 ML20235B679 ML20235B683 ML20235B687 ML20235B702 ML20235B708 ML20235B713 ML20235B714 ML20235B718 ML20235B720 ML20235B730 ML20235B734 ML20235B748 ML20235B754 ML20235B762 ML20235B764 ... further results
References
FOIA-87-111 NUDOCS 8709250490
Download: ML20235E127 (3)

Text

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Commonwealth Edison Company ONE FIRST N A T I O N A L. PLAZA

• CHICAGO. ILLINOlt Aaleses Asply se, POST OF FIC E 80X 767

• C H I C A G O. ILLINOl8 60690 t- t April 14, 1972 cl n

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.g Dr. Peter A. Morris, Director Division of Reactor Licensing b9 47 . I/S g 7

.U.S. Atomic Energy Commission -

Washington, D.C. 20545

Subject:

Start-up Test Program for Quad- Citie s J hits 1 and 2 for a 20% Power License

Dear Dr. Morris:

Commonwealth Edison Ccmpany and Iowa-Illinois Gas and Electric Company hereby request permission to perform the 255 power start-up tests as-shown in the FSAR, Amendment 13, Sec-tion 13, page 13 19 4 at 18 to 20% power under the present 20%

powar license. Our evaluation of performing these tests at 18 to 20% power shows that the desired functions of initial calibration and fine tuning of the various systems will be accom-plished and does not present hazards greater than those previously .,

analyzed. Therefore, the next higher test point in the power test {

program for Quad-Citi3s Units 1 and 2 will be the 50% power test i program. .

The tests to be performed at 20% power on Quad-Cities )

Units 1 and 2 are outlined below along with a description of each: ]

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1 - Chemical and Radiochemic al tests - These tests consist of collecting water and gas samples from the various reactor systems. These samples are analyzed to determine both the chemical and radiochemical constituents and te verify s pi'oper operation. These measurements are also used as j base measurements for future operation.

l 2 - Radiation Measurements - With the reactor operating at 20%

of rated power, radiation measurements are made within the reactor and turbine buildings. The purpose of these measure-ments is to check the adequacy of the shielding and te provide base measurements of the radiation profile of the station.  ::

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j, .Dr.fPeter A. Morris . April'14, 1972-3 - IRM Calibration - This IPM calibration is: the initial.

calibration of the. system. . It is ' performed' by adjusting the instrumentation to ' agree . with a heat balance measure-ment:which'is made.at 20% power.

'4 - LPRM Calibration .- The'LPRM calibration is. performed by using the-traveling in-core probe to obtain axial and radial power distribution information. This, in.conjunc-tion'with reactor heat balance, is used;to adjust.each of the LPRM instrument channels'so that it gives the' correct surface heat flux information.

APRM Calibration

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.The APRM calibration consists of adjusting the' gains of the APRM channels so that the APRM instrumentation reads in accordance with the results of a heat balance which is taken at 20% power.

6 - Axial- Power Distribution Determination --The axial power distribution determination is mada by reviewing the traveling in-core probe traverses at various locations within the core. .This determination is made to check that the axial power distribution is as calculated for the specific rod withdrawal sequence being used.

7 - Core Performance Evaluation - This evaluation consists of

.a calculation of the Minimum Critical Heat Flux Ratio and the linear power generation for the 20% power condition.

8 - Neutron Flux Response to Control Rod Movement - In this test control rods are withdrawn and the neutron flux response to this control rod motion in various parts of the core is obtained. From-this data the transient response of the reactor to control rod movement is verified.

9 - Pressure Regulator Test - This test consists of making near step changes in reactor pressure by adjustment of the pres- -)

sure regulator.and recording the response of important variables such as pressure, steam flow, and neutron flux.

From the data collected, a transient response of the reactor to this type of perturbation is determined. i 10 - Feedwater System Teat - In this test a near step change in i feedwater flow is made and the response of steam flow, l pressure and neutron flux is recorded. From the date the j transient response of the reactor to a perturbation in j feedwtter flow is verified. l 1

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Commonwealth Edison Comp.ny

. k Dr. Peter A. Morris April 14, 1972 i l

11 - Bypass Valve Test - In this test a bypass valve is opened .

and closed to' introduce a small pressure transient into the reactor. system. This test is similar to the pressure regulator test and provides the same information.

12 - Main steamline Isolation Valve Test - In this test a functional check of each of the main steamline isolation valves is made to verify their operability.

13.- Relief Valve Test - In this' test the operation of each of the electromatic relief valves is checked. In addition, the capacity of each valve is determined by allowing the valves to blowdown to the suppression pool. Following the capacity check, each of the' valves is checked for leak tightness.

14 - Recirculation System Test - The purpose of this test is to calibrate the instrumentation associated with the recircu-lation system and jet pumps.

One signed original plus 39 copies of this request are submitted for your use.

Very truly yours,

%ud '

L. .D. Butterfield, Jr.

Nuclear Licensing Administrator

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April 20, 1972 Docket Nos. 50-254' and 50-265 i'

Dr. Chester F. Siess Chainnan, Advisory Cmmittee on Beactor Safeguards U. S. Atcraic Energy Camission

. Washington, D. C. 20545

Dear Dr. Siess:

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copies.of the following are transmitted for the Sixteen (16)

Connittee's information Letter from Commonwealth Edison Company dated April 12, 1972, requesting authorization to complete all testing of each unit (Quad Cities Units 1 and 2) up to its full power rating and also requesting authorization to oper-ate the station after testing is completed until September 15, 1972.

Letter from Co h nwealth Edison Company . dated April 14, )

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1972', requesting permission to perform 251 power searcup tests at Quad Cities Units 1 and 2, under the present- 20%

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power licenses. 4'/4, (

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D_is tribution M cket File She@8 Branch Reading MGroff. DRL  !

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D:>rald J. Jovholt Assistar.t Lirector for Reactor Operations Division of Reactor Licensing 3 Enclostr.ms:  ;

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