IR 05000373/1985037

Insp Rept 50-373/85-37 on 851104-06.No Violation or Deviation Noted.Major Areas Inspected:Licensee Actions on Refueling Preparations & Activities & Spent Fuel Pool Activities

ML20137H307
Person / Time
Site:	LaSalle
Issue date:	11/26/1985
From:	Guildemond W, Milbrot W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20137H286	List: IR 05000373/1985037 ML20137H281
References
50-373-85-37, NUDOCS 8512020360
Download: ML20137H307 (4)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-373/85037(DRS)

Docket No. 50-373 License No. NPF-11 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: LaSalle County Station, Unit 1 Inspection At: LaSalle Site, Marseilles, IL Inspection Conducted: November 4-6, 1985 Inspector: W. Milbrot h, 4 N - 2. 5 - 6 Date

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Approved By: . mo',ThN#"" //-44 -A c'

Operational Programs Section Date Inspection Summary Inspection on November 4-6,1985 (Report No. 50-373/85037(DRS))

Areas Inspected: Routine announced inspection of licensee actions on refueling preparations and activities; and spent fuel pool activitie The inspection involved a total of 27 inspector-hours onsite by one NRC inspector including four inspector-hours onsite during off-shift Results: No violations or deviations were identifie h20hD G

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DETAILS i

1. Persons Contacted Licensee Employees

• J. Diederich, Manager, LaSalle Station

• D. Bishop, Services Superintendent

• R. Huntington, Assistant Superintendent, Operations

• Stewart, Fuel Handling Foreman

• H. Richter, Leader, Nuclear Group

• R. J. Cozzi, Quality Assurance USNRC M. J. Jordan, Senior Resident Inspector J. Bjorgen, Resident Inspector R. Kopriva, Resident Inspector The inspector also contacted and interviewed other licensee personnel during the inspectio * Denotes personnel attending the exit ir.terview held on November 6, 198 . Refueling Preparations The inspector reviewed procedures, tests, and surveillances covering the maintenance, testing and operational check out of refueling tools and equipment, systems, and instrumentation required to support fuel handling efforts to assure that Technical Specifications have been satisfied. Equipment and tools to be used for core alterations and support activities were checked for proper operation and verified ready for use. The inspector verified that the following refueling activities were completed as required: LFS 100-1, Revision 1, Refueling Platform Main Hoist Interlocks check for core alteration LOS-CS-MI, Revision 6, Secondary Containment Integrity, LOS-CS-QI, Revision 8, Secondary Containment Damper Oper:bility Tes LOS-VG-MI, Revision 7, Unit 1 Standby Gas Treatment System Operability Test LIS-NR-301, Revision 1, Unit 1 SRM Rod Block Functional Tes LIP-AR-02, Revision 2, Refuel Floor High Range Area Radiation Monitor Calibratio LTP-1600-22, Revision 4, SRM Performance Chec _ . _ . ._ _ _ _ . - _ - _ _ - . _ _ --- -

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A review was made of training activities ccmpleted by personnel assigned to perform core alterations. Training included both classrocm instruction covering certain administrative and fuel handling procedures and hands-on training operating the Refuel Bridge to identify fuel locations and orientations. The only documentation of this training material was a

' memorandum submitted to the Production Superintendent. The inspector suggested that a lesson plan be developed to identify the training requirements to ensure continuity between training sessions. This plan could cover the basic training requirements and be up-graded to include special training needs unique to a particular refueling outage. The lesson plan could also include actions to take in the event of abnormal and emergency situations. The licensee indicated that the preparation of a lesson plan would be considere The licensee has completed a 10 CFR 50.59 core reload safety evaluation and submitted the information to NRR for revie No violations or deviations were identifie . Refueling Activities Prior to performing core alterations the fuel handlers assured that the fuel accountability status boards in the Control Room and on the refuel floor represented correct fuel and core component locations, and established cleanliness and tool accountability controls. Any items used over the reactor cavity were secured with a lanyard. The area around the reactor cavity and Spent Fuel Pool (SFP) was roped off and marked with radiological sign ,

The inspector witnessed portions of two shifts of fuel handling. During this time period the licensee experienced a problem with the Refueling Platform Main Hoist Interlock limit switch cable causing core alterations to be' suspended temporarily. The wiring connected to the limit switch failed a continuity test. Spare wiring in the cable was used to replace the defective wires. The Refueling Platform Main Hoist Interlocks were retested-satisfactory and fuel handling was allowed to continu Movement of fuel was conducted safely in accordance with approved written procedures. Continuous voice corrcunication was maintained between the Control Room and the Refueling Platform. Status boards were maintained current and good cleanliness and radiological practices were exercise Periodic surveillances were completed using procedure LFS-100-4, Revision 2, Core Alterations Shiftly Surveillances. Checks important to refueling included SRM's operable, in correct location and with required count rate, Reactor Vessel water level, and Mode' Switch in the correct positio Radiation monitoring of the area was provided by refueling floor high radiation monitor and new fuel storage area high radiation monitor. The instruments were tested and within calibratio No violations or deviations were identifie _ _ _ _ - - - _ - _ _ _ - _ . - . _ _ _ _ - _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ - - _ _ _ _ _ _ _ - _ _ _ - _ _

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4. Spent Fuel Pool Activities The inspector made a review of SFP operations. Refueling manning, Refueling Platform Main Hoist checkout, cleanliness and radiological controls, core component accountability, ventilation and ARM requirements were verified during refueling activities and are covered in Paragraphs 2 and 3, abov Spent Fuel Pool water level was verified satisfactory each shift and recorded on the Shift Surveillance Log. Spent Fuel Pool cooling system capability including pump operation and flow paths was demonstrated operable during the Preoperational Test Program. Once a core load of used fuel is loaded into the SFP the licensee will conduct a heat balance capacity evaluation of the system to verify its cooling capability. This evaluation will be reviewed on a subsequent inspectio No violations or deviations were identifie . Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)

on November 6, 1985, to discuss the sco>e and findings of the inspection. The licensee acknowledged the statements made by the inspector with respect to items discussed in the report. The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify any such documents / processes as proprietar _