U-601519, First Refueling Outage Startup Rept

First Refueling Outage Startup Rept

ML20246E875
Person / Time
Site:	Clinton
Issue date:	08/21/1989
From:	Holtzscher D ILLINOIS POWER CO.
To:	Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
U-601519, NUDOCS 8908300048
Download: ML20246E875 (3)

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'llLIN0/S POWER COMPANY

, CLINTON POWER STATION, P.O. BOX 678', CLINTON. ILLINOIS 61727 I ,

. August 21, 1989 L

'10CFR50.36 9

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Docket No. 50-461 Mr. A. B. Davis Regional Administrator

-Region III U.S Nuclear Regulatory Commission 799 Roosevelt Road

.Clen Ellyn,' Illinois' 60137

Subject:

Clinton Power Station First Refueline Outace Startun Reoort

Dear Mr. Davis:

In'accordance with Clinton Power Station (CPS)' Technical Specifications 6.9.1.1, 6.9.1.2 and6.9.1.3, Illinois Power (IP) is-submitting the attached summary report of plant startup and power escalation testing following the First Refueling Outage (RF-1).at CPS.

The testing addressed in the attached report fulfills IP's commitment specified in Attachment 8 to letter U-601239 (dated September 6, 1988).

Sincerely yours, 3 7/

'D. L. Holtzscher Acting Manager -

Licensing and Safety GSL/krm Attachments cc: NRC Clinton Licensing Project Manager NRC Resident Office

. Illinois Department of Nuclear Safety

, NRC Document Control Desk B908300048 890821 r+

- f PDR ADOCK 05000461 y ll P PNU g g

0 Attechm:nt-1 to U-601519 j Page 1 of 2 L First Refueline Outane Startun Report f

1 Core Verification Test The purpose of the Core Verification Test is to verify that all fuel assemblies are loaded in the correct location and are properly oriented.

This verification test validates the assumptions made in the reactor analyses for safe operation.

In accordance with CPS Procedure No. 2209.01, CORE VERIFICATION, the core verification video tapes were filmed on February 22, 1989, and verified on February 23 and 24, 1989. No discrepancies from the specified loading pattern were identified.

Control Rod Testine The purpose of the control rod testing is to verify that each control blade is coupled to its control rod drive and that all control rods are functioning properly. The applicable control rods have been friction tested, timed, and SCRAM tested to assure proper operation and compliance with Technical Specification requirements.

During RF-1, ten control rod drives were rebuilt. Control rod coupling for these control rods was verified in accordance with Technical Specification 4.1.3.4.c. These control rods were also friction tested with satisfactory results.

After the completion of core alterations, all control rods were SCRAM time tested. However, one control rod drive mechanism developed a leak during the reactor vessel pressure test. The seal for this control rod drive mechanism was replaced and the SCRAM time test for this control rod was repeated after plant startup. All control rod SCRAM times were within the criteria established by Technical Specification 3.1.3.2.

Shutdown Marcin Test The purposes of the Shutdown Margin Test are to determine the amount of shutdown margin in the core and to demonstrate compliance with Technical Specification requirements. The Shutdown Margin Test is designed to demonstrate that the shutdown margin will be met throughout the operating cycle.

The Shutdown Margin Test was performed following initial criticality of the reloaded core. The Shutdown Margin was determined to be 2.940%

delta k/k. This is greater than the Technical Specification 3.1.1 requirement to maintain a shutdown margin of at least 0.38% delta k/k.

Reactivity Anomalv Test The purpose of the Reactivity Anomaly Test is to check for possible differences between the predicted reactivity and the actual reactivity effected (theoretically and actually) by a selected control rod configuration or density. The reactivity equivalence of the difference

'.'~ Attachmsnt i l- to U-601519 l Page 2 of 2 between the actual density and the predicted rod density must be within the limit specified in the Technical Specifications.

As stated previously, the Shutdown Margin was determined to be 2.940%

delta k/k. The predicted Shutdown Margin was 2.931% delta k/k. The reactivity anomaly was thus determined to be 0.009% delta k/k which is within the 1.0% delta k/k required by Technical Specification 3.1.2.

Core Performance Evaluation Test The purposes of the Core Performance Evaluation Test are to evaluate power distribution limits and to verify that the limits are within their Technical Specification limits. Technical Specifications require limits on the Minimum Critical Power Ratio (MCPR), Linear Heat Generation Rate (LHGR), and Average Planar Linear Heat Generation Rate (APLEGR).

The power distribution limits were monitored during the power ascension fo.11owing the completion of RF-1. MCPR, LHGR and APLHGR were verified to be in compliance with their applicable Technical Specification limits for all applicable power levels (i.e., 25% to 100% rated thermal power).

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