IR 05000266/1987021

Insp Repts 50-266/87-21 & 50-301/87-22 on 871019-29.No Violations or Deviations Noted.Major Areas Inspected: Licensee Implementation of Generic Ltr 83-28 in Areas of Equipment Classification & Reactor Trip Sys Reliability

ML20236V103
Person / Time
Site:	Point Beach
Issue date:	11/09/1987
From:	Gardner R, Neisler J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20236V089	List: IR 05000266/1987021 ML20236V087
References
50-266-87-21, 50-301-87-22, GL-83-28, NUDOCS 8712040087
Download: ML20236V103 (6)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION III

Reports No. 50-266/87021(DRS); 50-301/87022(ORS)  ; Docket Nos. 50-266; 50-301 Licenses No. DPR-24; No. DPR-27 i Licensee: Wisconsin Electric Power Company ) 231 West Michigan Milwaukee, WI 53203 Facility Name: Point Beach Nuclear Power Plant, Units 1 and 2

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Inspection At: Point Beach Site, Two Creeks, Wisconsin Inspection Conducted: October 19-29, 1987 Inspector: J. H. Neisle .

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Approved By: R. N. Gardner, Chief // f 87 l , Plant Systems Section Date

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' Inspection Summary l Inspection on October 19-29, 1987 (Reports No. 50-266/87021(DRS); I ' No.50-301/87022(DRSM j Areas Inspected: Routine announced inspection of the licensee's l implementation of Generic Letter 83-28 in the areas of equipment classification, vendor interface, post maintenance testing and reactor j trip system reliabilit Closed TI 2515/64R1 and TI 2515/9 ' Results: No violations or deviations were identifie PDR G ADOCK 05000266 PDR __________________;

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DETAILS l 1. Persons Contacted Principle Licensee Employees l '

*J. J. Zach, Plant Manager
*J. C. Reisenbuechler, Superintendent, EQRS
*J. E. Knorr, Regulatory Engineer W. B. Fromm, Modification Engineer M. J. Reiff, Engineer, Nuclear T. R. Branam, Maintenance Electrical Engineer
*R. D. Seizert, Licensing Engineer, NPERS
*F. A. Flentje, Administrative Specialist P. A. Dent, Supervisor, Staff Services M. B. Honzik, Document Specialist N. L. Hoefert, Superintendent, I&C W. A. Henning, Engineer, Nuclear Modifications R. D. Mitchell, CHAMPS Coordinator H. J. Gleason, Training Coordinator R. J. Bruno, Superintendent, Training
* Denotes those persons attending exit intervie . TI 2515/64R1 (Closed) TI 2515/91 (Closed) Equipment Classification i

The inspector selected four components in the Reactor Trip l System (RTS) and eight components in the containment spray system ' for examination during this inspection. The components selected were: j i RTS Containment Spray System Reactor Trip Breaker Containment Spray Pump P-14A Manual Trip Switch Containment Spray Pump Motor Control Rod Drive Regulated Motor Operated Valve 1-860A s Power Supply Motor operated Valve 1-870A

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Control Rod Drive Latch Check Valve 1-862A Assembly Level Transmitter LT-931 Flow Transmitter FIT-930 Flow Transmitter FT-962 (1) The inspector reviewed the QA scope lists (the Point Beach equivalent to a Q-List) in the licensee's Quality Assurance Policy Manual. Point Beach is converting from the manual lists to a Computerized Huster and Maintenance Program System (CHAMPS) that will identify the safety classification of all plant components, systems and structures. The inspector reviewed selected print-outs from the CHAMPS to verify that correct equipment classifications were being included in the syste ] i Each of the items were correctly classified on the CHAMP );

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(2) To determine the level of plant management oversight the inspector reviewed plant procedures controlling maintenance, modifications,. procurement,-inspection and testing.o ..

safety-related items. .For activities-impacting safety-related structures, systems and. components the inspector' reviewed quality assurance' procedures, audits,. surveillance activities, and corporate level procedure (3) Equipment classification is controlled by quality assurance procedures and the. Quality Assurance Policy Manual. These procedures and directives establish responsibilities and _ methods-for assuring the proper classification of plant structures, systems and components. The addition 'and deletion of-' component is reviewed and approved by the quality assurance organizatio prior to the initiation.of any action that affects the: item's classificatio (4) The inspector reviewed approved procedures issued by corporate' and plant management for procurement, maintenance, modifications, inspection, testing and, surveillance activities'affecting; safety-related structures,-systems and component (5) The inspector reviewed procedures established.to' control'the training and indoctrination of personnel. performing activities affecting safety-related structures, systems and component Included in the review were procedures for' training maintenance and I&C personnel,' staff engineers and managers, and quality-assurance personnel. In addition, the . inspector reviewed '

.. personnel training and indoctrination records to verify. that the required training was being accomplishe (6) The inspector reviewed eight audit reports of safety-related activities that had been performed by.the plant quality assurance organization and seven audit reports that documented audits performed by the off-site corporate quality assurance organization. The quality assurance organizations maintain schedules of planned audits and inspections for. safety-relate activities of the facilit (7) The corrective action program for safety-related equipment is controlled by the quality assurance procedures. The inspector's-review of corrective action for audit and . inspection findings revealed that the corrective actions for those findings were adequate, timely and complet (8) Review and evaluation of information concerning malfunctioning-of equipment is controlled by the licensee's Nonconformance Report (NCR) procedure. Equipment malfunctions identified'by NCR are reviewed by quality assurance, management ~and engineering to determine whether.an identical replacement could be cxpecte to perform reliabl r-- -
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l-(9) The inspector reviewed 11_' safety-related modifications'. involving-the reactor trip system ~and the containment spray system. . Th . modification packages, drawings,. work requests and inspection 1 documentation were clearly' identified as. safety-relate .) No violations or deviations were identifie Vendor' Interface The inspector reviewed licensee procedures established to assure _- that vendor.information~for safety-related components is current'and-complete. Vendor manuals for four. components in. the reactor-trip l system and eight components in the containment spray system were reviewed for completeness and to determine whether the manuals accurately reflected the installed equipment. Guidance provided in 1 the manuals has been included in the maintenance, test and j inspection procedures used in the facilit No' components.wer _ identified as being manufactured by vendors who have since goneout

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of busines The inspector reviewed' vendor recommended mod'ifications on'the'RTS breakers. The modifications included the modification to automatically activate the shunt trip and the modifications.to enable the licensee to perform on-line. functional testing of the reactor trip syste Post modification test results' indicated that : , the modifications functioned according to design requirement = 1 The licensee's procedures controlling-maintenance and mo'ifications, d 3 and the document control procedures pertaining to vendor technical ' information were reviewed. The procedures were determined to be 1 adequate to control ~ replacement of equipment:in situations'where a I vendor goes out of business or will not supply adequate information to the plan .l The licensee is participating in the INP0 Nuclear Plant Reliability Data System (NPRDS) and Nuclear Utility Task Action Committee ,

 (NUTAC). The inspector determined that procedures were in place to require periodic surveillance of vendors of safety-relate components and services. Procedures have been established for the reporting and evaluation of NPRDS and- SEE-IN informatio No violations or deviations were identifie Post Maintenance Testing The inspector selected five valves, two RTS breakers, one level  ..

transmitter and a containment-spray pump for review to verify that  ! the licensee was implementing a post maintenance.tett progra : For the selected components, the inspector determined the foilowing:

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(1) Post maintenance 1 testing and surveillance.are controlled by written procedures. The inspector reviewed 12' completed maintenance work requests involving preventive and corrective maintenance. Each. work request indicated that the required
. post maintenance testing had been performe (2) Criteria and responsibilities.for maintenance and fo designating maintenance activities'as safety-related and'

non-safety-related have been established in the work' request initiation procedures and in the plant modification: procedure Post maintenance test inspection is controlled by the quality assurance inspection progra (3) Methods for performing functional testing following maintenance of safety-related components have been developed and'.are delineated in published plant procedures, operator surveillance procedures and in maintenance and I&C pro'cedure (4) The inspector reviewed completed work requests and supporting documentation retrieved from document control records storag The documentation contained approvals of work requests, the identity of persons who performed the activity and the individuals who performed post maintenance reviews and test (5) The inspector verified that the' licensee wa's performing surveillance of the shunt trip attachment by reviewing completed surveillance procedures and surveillance' reports'.

(6) The inspector reviewed completed surveillance procedures and checklists to verify that the licensee is independently testing the ability to manually trip the RTS breakers through;the use of either the undervoltage trip attachment (UVTA) or the: shunt =

trip attachment (STA).

No violations or deviations were identifie d. Reactor Trip System Reliability l The inspector verified that the licensee has established a

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l preventive maintenance and surveillance program for the reactor trip breaker The program includes procedures for. maintenance, lubrication, UVTA and STA trip force measurements, breaker cleaning i and breaker adjustment.

g The licensee is performing monthly testing of the diverse trip ) I features of'each reactor trip' breaker. The testing includes on-line ; testing of the UVTA and STA in addition to the test utilizing trip- 1 signals from the reactor protection syste The inspector ascertained that life cycle testing had been performed ; for the reactor trip breakers, shunt trip attachments and undervoltage j l ' trip attachments and that procedure's for the replacement of components j were consistent with the results of the life cycle tests.

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1 3. Exit Interview l The inspector met with licensee representatives (denoted under Paragraph 1).

at the conclusion of the inspection and summarized the scope and findings of the inspection. The licensee acknowledged the inspector's comment 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 or processes as proprietar I

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