IR 05000309/1978016

IE Inspec Rept 50-309/78-16 on 780821-23 During Which 1 Item of Noncompliance Was Noted:Failure to Log Details of a Fuel Handling Problem

ML20148J053
Person / Time
Site:	Maine Yankee
Issue date:	09/07/1978
From:	Keimig R, Lazarus W, Stavely J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20148J003	List: IR 05000309/1978016 ML20148H997 ML20148J012 ML20148J033 ML20148J044
References
50-309-78-16, NUDOCS 7811150105
Download: ML20148J053 (7)

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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report N O Docket N License N OPR-36 Priority --

Category C Licensee: Maine Yankee Atomic Power Company 20 Turnpike Road Westborough, Massachusetts Facility Name: Maine Yankee Atomic Power Station Inspection at: Wiscasset, Maine Inspection conduct d: August 21-23, 1978 Inspectors: fc- c2M44tV W dCLazaruyJ Keactor inspector () 7 date signed

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J. M. Stavely, Reactor Inspector Co-op date signed

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Approved by: / S p $.Q R.R. Kp(n/g, CMpf, Reactor Projects date signed Sectio Vo. 1 &NS Branch Inspection Summary:

Inspection on August 21-23,1978 (Report No. 50-309/78-16):

Areas Inspected: Routine uannnounced inspection by a regional based inspector of the licensees post refueline plant operations and of the facts surrounding a recent fuel handling problem. The inspection involved 18 inspector hours on site by one NRC regional based inspecto Of the two areas inspected one item of noncompliance was identified in one area (deficiency-failure to log details of a fuel handling problem-para 4).

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Region I Form 12 (Rev. April 77)

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DETAILS Persons Contacted

• P. Anderson, Staff Assistant to the Plant Manager J. Brinkler, Reactor and Computer Department Head M. David, Training Coordinator C. Frizzle, Assistant Plant Manager J. Hebert, Technical Assistant W. Paine, Operations Department Head N. Pillsbury, I and C Department Head R. Prouty, Maintenance Department Head

• S. Sadosky, QC and Audit Coordinator B. Tuthill, Assistant Engineering Aide

• E. Wood, Plant Manager The inspector also interviewed several licensed operators and members of the licensee's technical and administrative staff * denotes those present at the exit intervie . Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (309/77-22-02): Revise procedures 11-1 through 11-3 to include acceptance criteria on data cheet These procedures have been revise (Closed) Unresolved Item (309/77-22-03): Revise procedure 11-3 to require measurement of moderator temperature coefficient to reflect Core IV requirement (Closed) Unresolved Item (309/77-22-04): Prepare a procedure for calculation of shutdown margin. Procedure 12-200 had been issued to satisfy this requiremen (Closed) Unresolved Item (309/78-09-05): Procedures 11-2 and 11-3 need to be revised to reflect Core IV Startup Test Program require-ments. The procedures have been revised.

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. Post Refueling Plant Operations The inspector verified that systems disturbed during the outage were returned to service in accordance with approved procedures and that Technical Specification required surveillance tests had been conducted during the outage. The inspector observed the perform-ance of selected surveillance tests and plant operations and reviewed a sampling of compieted surveillance tests as follows: Observation of Selected Plant Evolutions

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3.6.2.2.8, Axial Offset Flux Trip, Completed August 23, 197 .17.6.3, Inservice Inspection - Pressure Leak Test, Completed August 22, 1978 (Hydrostatic Test of RCS).

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3.1.8, CEA Exercising, Completed August 22, 197 , Plant Heatup, Completed August 22, and August 23, 197 Review of Completed Surveillance Procedures

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3.1.14, Emergency Diesel Generator Cola Plant Testing, Revision Data: July 17, 197 .1.15.1, ECCS Operational Test: Containment Isolation System, Revision Data: July 20,197 ,

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3.1.15.2, ECCS Operational Test: Recirculation Actuation System, P.evision Data: July 20, 197 .1.15.3, ECCS Operational Test: Pump Flow Testing, Revision Data: July 19, 197 .1.15.4, ECCS Operational Test: Safety Injection Tank Check Valve Testing, Revision Data: July 17,1978.

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3-6.2.2.1, Power Range Safety Channels, Revision Data: August 23, 197 .2.2.5, Steam Generator Level, Revision Data: August 23, 197 .2.2.7, Contair, ment Pressure, Revision Data: August 23, 197 .2.2.8, Axial Offset Flux Trip, Revision Data: August 23, 197 .2.2.9, RPS Logic Matrix Test, Revision Data: August 23, 1978.

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3-6.2.2.9, Reactor Trip Breaker Monthly Test, Revision Data: August 23, 197 .17.6.3, Inservice Inspection - Pressure Leak Test, Revision 5.

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Data: August 22, 197 .1.8, CEA Exercising, Revision 6, 197 Data: August 22, 197 , CEA Extension Shaft Coupling and Precritical CEA'

Withdrawal, Revision Data: 1978 refueling outage, data not specifically date , Plant Heat Up, Revision Data: August 22, 23, 197 Except as noted below, no discrepancies were identifie (1) In the review of procedure 3.1.14, " Emergency Diesel Generator Cold Plant Testing", the inspector identified a change to two valve numbers (CH-M-1 and CH-M-87) which had been made by an operator without completion of a procedure change report. All other procedures with temporary changes of this nature were properly documented.

i The inspector verified that the change was required to

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5 properly conduct the procedure. The licensee agreed to promptly issue a proper procedure change request (PCR) to document the change. This item is unresolved pending review of this PCR by NRC RI (309/78-16-01).

(2) While witnessing the performance of the Reactor Coolant System Leak Test, the inspector observed that some Con-trol Room personnel were referring to procedure 3.1.18 but that inspection teams were using data sheets from procedure 3.17.6.3. Both procedures had the same title,

" Inservice Inspection-Pressure Leak Test." Further investigation revealed that procedure 3.17.6.3 had recently l superseded procedure 3.1.18 and that copies of 3.1.18 had not been removed from the Control Room. The licensee promptly removed the superseded procedures from the s

Control Room files, No items of noncompliance were identifie . Fuel Handlipp Problem The inspector reviewed the circumstances surrounding a fuel handling problem which occurred on July 31, 1978 when the refueling machine operator inadvertently skipped a step in a procedure while handling a fuel element. The error resulted in rotation of the refueling machine mast without retracting the spreader device which surrounds the assembly being handled. Findings as a result of this review are noted below: In an attempt to reconstruct the event, the inspector reviewed the Control Room Operators Log for the date of the occurrenc Although the event involved a suspension of fuel handling operations and a precautionary evacuation of the Containment, no mention of the event was made in this log. Failure to document the details of this occurrence in the Control Room Operators Log is contrary to the requirements of procedure 0-10-3 " Maintenance of Operations Department Logs" which requires details of all unusual events to be logged so that the event may be reconstructed, and Technical Specification 5.8 "Proce-dures, which requires, in part, that procedures be adhered t This represents a deficiency level item of noncomplianc (309/78-16-02)

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6 The inspector reviewed PORC meeting minutes for meeting 78-23 of July 31, 1978, which had a copy of a special procedure,

" Procedure to be used for Handling Assembly EF00 7H." This procedure had been reviewed by PORC and approved by the Plant Manage Discussion with the Shift Supervisor who supervised recovery disclosed that this procedure was changed to allow a different method of freeing the refueling machine from the fuel assemblies. The licensee stated that the changes were reviewed by the PORC and Plant Manager but they had failed to document the review. This item is unresolved pending review by NRC:RI of supplemental PORC minutes which are to be written (309/78-16-03). The inspector identified several items which have not yet been addressed by the licensee as a result of this occurrenc These concerns include:

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A thorough inspection of the refueling machine mast, grapple, and spreader devic Determination of the final disposition of the possibly damaged fuel assembl Investigation of refueling machine interlocks with the possiblity of including a spreader device-mast rotation interloc Involvement of Quality Assurance personnel, as necessary, in the above area This item will remain unresolved pending review by NRC:RI of the licensee's further evaluation of this event and any correc-tive action taken. (309/78-16-04). Unresolved Items Unresolved items are items for which more information is required to determine if the item is acceptable, an item of noncompliance, or a deviation. Details 3.c., 4.b., and 4.c. contain unresolved items.

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7 Exit Interview At the conclusion of the inspection the inspector met with licensee representatives (see detail 1 for attendees) to discuss the scope and findings of the inspection as detailed in this report.