IR 05000461/1987005

Insp Rept 50-461/87-05 on 870113-29.No Violations or Deviations Noted.Major Areas Inspected:Action on Previous Insp Findings & Startup Test Phase Procedure Review

ML20210F842
Person / Time
Site:	Clinton
Issue date:	02/05/1987
From:	Dupont S, Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20210F840	List: IR 05000461/1987005 ML20210F837
References
50-461-87-05, 50-461-87-5, NUDOCS 8702110175
Download: ML20210F842 (3)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-461/87005(DRS)

Docket No. 50-461 License No. NPF-55 Licensee: Illinois Power Cortpany 500 South 27th Street Decatur, IL 62525 Facility Name: Clinton Nuclear Power Station, Unit 1 Inspection At: Clinton Site, Clinton, Illinois Inspection Conducted: January 13-29, 1987 l

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Inspector: . u M/b

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y Approved Dy: G ief .

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Test Programs Section Date'

i Inspection Summary Inspection on January _13-29,1987 (Report No. 461/87005(DRS)]

Areas Inspected: Action on previous inspection findings and startup test phase procedure review, Results: No violations or deviations were identified.

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DETAILS i Person Contacted

• J. A. Miller, Assistant Manager, Startup

*D. L. Holesinger, Director, Startup Test

• K. A. Baker, Supervisor, Inspection and Enforcement Interface

• Denotes those attending the exit meeting on January 29, 1987. Actions on Previous Inspection Findings (Closed) Violations (461/86052-02(DRS) and 461/86052-03(DRS)): The licensee failed to perform maintenance activities in accordance with procedure CPS 1029.01 and to correct identified adverse condition The licensee reviewed and verified that all departmental procedures were in agreement with procedure CPS 1029.01, " Preparation and Routing of Maintenance Work Requests (MWR)." Quality Assurance procedure QAP 510.04 wa; revised to ensure that all dccumentation associated with a MWR will be attached to the MWR as required by procedure CPS 1029.01. Training was also conducted to ensure that the requirements of CPS 1029.01 are me The licensee also revised procedure CPS 1016.01, " Condition Reports" to ensure that all departments associated with an adverse condition are involved with investigating and resolving the conditions. The inspector reviewed these corrective actions and found them adequat (Closed) Open Item (461/85005-05(DRS)): Safety Evaluation Report, fiUREG-0853 (SER), Paragraph 5.2.2 required verification that manual and automatic actuation of Safety Relief Valves (SRV) were preoperationally tested in compliance with Regulatory Guide 1.68. The inspector reviewed the applicable portions of the following completed preoperational tests and found the results to be in compliance with Regulatory Guide 1.68; Test PTP-NB-02 verified the ADS logic, SRV valve control switch operation (manual) and the autcoatic operation of the Main Steam Pressure Relief function to the SRVs. Test FTP-NB-05 verified the design setpoints for SRV automatic operation and the operation of the temperature monitoring instruments on the SRV discharge lines. PTP-RS-01 tested the remote operation of the SRVs from the Remote Shutdown Pane PTP-MS-01 verified that the SRV accumulator capacities were sufficient to perform the design functions. The inspector has no further concern . Test Phase Procedure Review Thehnspectorreviewedthefollowingstartuptestphaseproceduresto

, ascctained that the requirements of the Licensee's Startup Manual,

.er 14 of the FSAR, American Nuclear Society Standard ANSI N18.7,

' Charlatory Regu Guide 1.68, and the Quality Assurance Manual were me In ,

i addition, the procedures were reviewed to verify that the acceptance criteria niet the requirements of the Technical Specifications and Chapter 14 of the FSAR:

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STP-10-0, Revision 3, "IRM Performance - SRM/IRM Overlap" STP-10-H, Revision 1, "IRM Performance - IRM Range 6/7 Overlap and Initial IRM/APRM Overlap" STP-06-0, Revisicn 3, "SRM Performance and Control Rod Sequence" STP-05-H, Revision 1, " Control Rod Drive System" STP-05-0, Revision 2, " Control Rod Drive System" STP-05-2, Revision 1, " Control Rod Drive System" STP-05-6, Revision 1 " Control Rod Drive System" STP-25A-H, Revision 1, "MSIV Function Test" STP-25A-1, Revision 1, "MSIV Function Test" STP-25B-6, Revision 1 "MSIV-Full Reactor Isolation" STP-27-2, Revision 1, " Turbine Trip Within Bypass Capacity" STP-27-6, Revision 1, " Generator Load Rejection" STP-28-2, Revision 1, " Shutdown from Outside the Control Room" STP-31-1, Revision 1, " Loss of Turbine Generator and Offsite Power All of the above procedures were found to be adequat No violations or deviations were identifie . Exit Interview The inspector met with licensee representatives (denoted under Paragraph 1) at the conclusion of the inspection on January 29, 198 The inspector sunnarized the purpose and findings of the inspectio The licensee did not identify any documents / processes as proprietar ,

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