ML19350D073

Forwards Listing of Changes,Tests & Experiments Completed During Mar 1981

ML19350D073
Person / Time
Site:	Quad Cities
Issue date:	04/01/1981
From:	Kalivianakis N COMMONWEALTH EDISON CO.
To:	Case E Office of Nuclear Reactor Regulation
References
NJK-81-133, NUDOCS 8104130252
Download: ML19350D073 (4)

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Commonwealth Edison c2 Quad Citie3 Nuclear Pow;r St:ti:n 22710 206 Avenue North

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Cordova, Illinois 61242

{ *2,6 Telephone 309/654-2241 sy-ur NJ K-81-133 April 1, 1981 y

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Q Hr. Edson G. Case, Deputy Director

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,g Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Conunission Washington, D. C.

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Dear Mr. Case:

Enclosed please find a listing of those changes, tests, and experiments completed during the month of liarch 1981, for Quad-Cities Nuclear Power Station Units One and Two, DPR-29 and DPR-30.

A summary of the safety evaluation is being reported in compliance with 10 CFR 50.59 Thirty-nine copics are provided for your use.

Very truly yours, COMit0NWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION jfA tyd N. J. Kalivianakis Station Superinteddent bb Enclosure cc R. F. Janecek l

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SPECIAL TEST l-48 Unit One Cycle 6 Startup Test Program Test Description This test documents the formal startup test program performed for Unit One Cycic 6 Startup. Attached Table 1 provides those tests performed, and the associated test conditions.

Summary of Safety Evaluation 1.

The probability of an occurrence or the consequence of an accident, or malfunction of equipment important to safety as previously evaluated in the FSAR is not increased by any of the startup tests. The unit was operating at normal startup and steady state operating conditions.

No unusual or unanalyzed valve or equipment configurations are called for by any of the test procedures. The startup program is made up entirely of existing station procedures.

4 All data were taken externally, that is data acquisition did not interfere in any way with normal system operation.

No tests were performed which affected the capability for safe shutdown of the plant, or Jeopardized the safety of the public.

2.

The possibility for an accident or malfunction of a different type than any previously evaluated in the FSAR is not created.

The normal function and intent of all systems involved in the testing were not altered. No new type of equipment was installed which had not been analyzed previously.

No new valve line-ups or special operating procedures were used in conducting any of the startup tests.

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3 The testing program itself will not reduce the margin of safety as defined in the basis for any Technical Specification.

In fact, the purpose of the Startup Test Program is to satisfactorily demonstrate that fechnical Specifications can be met and that the plant may continue to operate safely.

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TA!il.E 1 STARTUP TEST PROGRAM Open Prior To

?recedure Titic/ Description Vessel Startup Startup Heatup 25%

50%

95%

X Je.:00-1 Core Verification g

X X

X X

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QC? 600-6 Chemical & Radiochemical Measurements X

X X

^7." 300-4 Radiation Measurements X

X X

'X

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QT? 1113-1

? recess Computer - Nucicar Check X

3)

TS 1104-1 Shutdo:in Margin Demonstration / Specific Cases Deter.ined by Nuclear Engineer X

6)

QTS 130-3 Control Red Friction and Settic Testing X

7)

QTS 120-1 Control Red Insert-Withdrav Tining X

X 3)

QTS 130-4 Control Red Scra: Timing QOS 300-6 CFD Mechanical Coupling Check T

X D

X

'M QT? 1106-2 Initici Critical ?rediction g

X X

X X

X

11) QOS 300-4 Nucicar Instre.~ent Response to Rod Movement D

X 12)

QTP 1109-1 SRM ?crformance Check M

i X

X 13)

QTP 1110-1 1RM Perf ormance Check g

X X

X X

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QIS 1512-1 A?RX Calibration g

X X

X

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QTS 1311-1 L?RM Calibration /*

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TABLE 1 STARTUP TEST ?ROGR.E Cpen Prior To

?rocedure Titic/ Description Vess el Startup Startup Hectup 25%

50%

95%

Core Flow Calibration / Check Flow Bias onl l X

X

? 1130-1 A?

0:'s X

X q?? '.;30-2 Jet Punp 3cce Data

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s X

'. P 8,'T S *. 51? -l Cciculation of Ther=ci Li its Using the 3cckup ?rocess Computer in Chicago E

10) QTS 1519-2 ECCS Limits on ?over Distribution X

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QTS 1300-1 Reactivity Anomaly Surveillance X

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OT? 1118-1 Core ?over Distribution Sy= metry Analysis X

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QTP 1600-3 Flow Control Line Deter =inction T

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