ML20207M654

Interim Deficiency Rept RER-QSE 86-41 Re Withdrawal of Limitorque Operators from Warehouse W/O Required Design Changes.Initially Reported on 861205.Operators Located & Procedures Reviewed.Next Rept Delayed Until 870306

ML20207M654
Person / Time
Site:	Palo Verde
Issue date:	01/02/1987
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
ANPP-39577-JGH, RER-QSE-86-41, NUDOCS 8701130242
Download: ML20207M654 (4)

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$/ 00 Arizona Nuclear Power Project "4 8 P o. sox 52034

• PHOENIX. ARfZONA 85072-2034 January 2, 1987 O ANPP-39577-JGH/DJW/DRL-92.11 U. S. Nuclear Regulatory Commission Region V 1450 Maria' Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. F. Kirsch, Director Division of Reactor Safety and Projects Palo Verde Nuclear Generating Station (PVNGS) '

Units 1, 2, 3 Docket Nos. 50-528, 529, 530

Subject:

Interim Report - RER-QSE 86-41 A 50.55(e) Potentially Reportable Deficiency Relating to Control of DCP's in the Warehouse File: 86-006-216

Reference:

Telephone Conversation between Jo Bianchi for R. C. Sorenson and D. R. Larkin on December 5, 1986 (Initial Notification -

RER-QSE 86-41)

Dear Sir:

The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) days.

(January 5, 1987)

Due to the extensive investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by March 6, 1987 at which time a complete report will be submitted.

Very truly yours, l

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8701130242 870102 8 ADOCK 0500 PDR ~~ J. G. Haynes l 6

' Vice President Nuclear Production JGH/DRL/dlm Attachments cc: See Page 2 I i L

16-27

RER-QSE 86-41 Mr. D. F.' Kirsch

. Director Page Two January 2, 1987 ANPP-39577-JGH/DJW/DRL-92.11 cc: J. M. Taylor Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 A. C. Gehr (4141)

R. P. Zimmerman (6295) i Records Center Institute of Nuclear Power Operations

. 1100 Circle 75 Parkway . Suite 1500 Atlanta, Georgia 30339 4

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INTERIM REPORT - RER-QSE 86-41 POTENTIAL REPORTABLE DEFICIENCY ARIZONA NUCLEAR POWER PROJECT (ANPP)

PVNGS UNITS 1, 2, 3 I. Potential Problem During October 1986, Quality Assurance identified three cases where it appeared that Limitorque Operators had been withdrawn from the warehouse without required design changes. Additionally, six Limitorque Operators still in the warehouse did not appear to have required design changes.

II. Approach To and Status of Proposed Resolution A. Installed Operators

1. Request on Stores (ROS) 130521 withdrew Limitorque Operator Model SMB-1-60 for installation in the Safety Injection system of Unit 2 .~ Design Change Packages (DCP) SI-051 and SI-034 had been written due to changes required for Equipment Qualification (EQ) purposes. An inspection was conducted to determine whether the changes required by the DCP's had been incorporated. This inspection (Work Order 192342) documents 4

that the required changes were incorporated and that no deficiencies exist.

2. Request on. Stores (ROS) 191887 and 191870 withdrew Limitorque Operator Model SMB-00-10 for installation in the Main Steam system of Unit 3. This valve is not quality-related and does i not require the implementation of identified design changes.

[ Therefore, no work is -required to this operator and no deficiencies exist for this operator.

B. Operators in the Warehouse

( Six (6) Limitorque Operators located in the warehouse were identified as being affected by design change. All six of these operators have been put into Quality Control (QC) Quarantine with Non Conformance (NCR) tcgs. Work Request #202865 has been written to inspect these operators. Any changes required to these operators by the DCP's will be incorporated.

C. Interim Operation of Units 1 and 2 l

No deficiencies have been identified for Units 1 and 2, therefore, continued operation is justified.

D. Transportability Additional review is necessary to determine whether a programmatic deficiency exists in the implementation of DCP's and Plant Change Packages (PCP) for equipment which was located in the warehouse.

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E A review plan is being implemented to determine whether there is a programmatic deficiency, to assess transportability, to determine

, the root cause, if any; and to implement any necessary corrective 1 actions.

1. Procedure Review Review of the existing DCP/PCP procedures shows that responsibilities are clearly defined for the update of the Station Information Management System (SIMS), the Material Management Information . System (MMIS), and for the implementation of the DCP's into the warehoue "on the shelf" stock. An assessment is being conducted to determine whether responsibilities are appropriately assigned and to develop or revise instructions / procedures for these implementation responsibilities. ' Additional training requirements are also being assessed.

2. DCP Review Initial investigation in conjunction with the As-Bailt Records Management (ABRM) group has determined that there have been a significant number of DCP's written against the plant.

A random sample of 100 DCP's from all DCP's will be selected and reviewed. If one deficiency.or less is identified in the ,

sample of 100 DCP's, it will establish a 95% confidence level that 95% of the remaining DCP's have no deficiencies. This is considered to be an acceptable level of confidence.

i The sample DCP review will entail the following:

l A) Review of . the sample DCP's to determine if warehouse j stock was affected.

- B) If warehouse stock was affected,

1) Verify by inspection or document review that design

. changes have been incorporated.

l l 2) Inspect items issued from stock to the field after i

che date of the DCP to determine if the DCP was incorporated.

completion of this additional review is scheduled for 1 February 20, 1987, contingent upon access to equipment

'- requiring inspection. i III. Projected Completion of Corrective Action and Submittal of the Final Report The complete evaluation and final report are forecast to be completed by March 6, 1987.

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