IR 05000266/1987017

Insp Repts 50-266/87-17 & 50-301/87-17 on 870901-30.No Violations or Deviations Noted.Major Areas Inspected:Generic Ltr Followup,Maint,Surveillance,Physical Security, Operational Safety,Enforcement Conference & LER Followup

ML20236A933
Person / Time
Site:	Point Beach
Issue date:	10/09/1987
From:	Defayette R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20236A925	List: IR 05000266/1987017 ML20236A923
References
50-266-87-17, 50-301-87-17, GL-85-05, GL-85-13, GL-85-14, GL-85-22, GL-85-5, NUDOCS 8710230242
Download: ML20236A933 (8)

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.U.' S.' NUCLEAR REGULATORY COMMISSION ~

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- REGION III

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t ' Reports No. 50-266/87017(DRP); 50-301/87017(DRP).:- ;i

.l lDocketNos.. 50-266;.'50-301 . Licens'es No.'DPR-24; No..DPR-27 Licensee: Wiscon' sin Electric Company '

231 West Michigan .

Milwaukee, WI-- 53203 Facility Name: Point Beach; Uni.t 1 and 2 _

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' Inspection At: :Two Creeks, Wisconrin l

Inspection.. Conducted: September 1 through September 30, 198 '

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! Inspectors: JR. L. Hague- 1 j

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R.'J..Leemon

' Approved By: . eFayhte,Ch' /0 9F7

- Reactor Projects. ection 2B Datd ' !

Inspection Summary i

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Inspection'from September l'through September 30, 1987, (Reports L

No.50-266/87017(DRP); 50-301/87017(DRP))

Areas: Inspected: . Routine, unannounced inspection by resident inspectors of

. generic letter followup; operational safety; maintenance; surveillance;.

physical security; enforcement conference; radiological protection and licensee event report follow u Results: No violations or deviations were identifie .I j

8710230242 871009 PDR ADOCK 05000266 G PDR

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DETAILS

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1. Persons Contacted i s

• J. J. Zach, Manager, PBNP T. J. Koehler, General Superintendent G. J. Maxfield, Superintendent - Operations

• J. C. Reisenbuechler, Superintendent - EQRS W. J. Herrman, Superintendent - Maintenance & Construction D. F. Johnson, Superintendent - Health Physics R. Krukowski, Security Supervisor F. A. Flentje, Administrative Specialist ,

• J. E. Knorr, Regulatory Engineer T. L. Fredrichs, Superintendent - Chemistry The inspectors also talked with and interviewed members of the Operation, Maintenance, Health Physics, Chemistry and Instrument and E Control Section ;

• Denotes personnel attending exit. interview {

2. Generic Letter Followup (92703)

The resident inspectors have ascertained that the information discussed j in the following generic letters has been properly addressed by the licensee:

85-05 " Inadvertent Boron Dilution" - This generic letter was provided to the licensee for information only, and did not involve any reporting requirement Therefore, this generic letter is clcse " Transmittal of Nureg-1154 Regarding the Davis-Besse loss of Main and Auxiliary Feedwater Event" - The generic actions addressed in this generic letter have been evaluated by the licensee. This generic letter was provided to the licensee for information only, and did not involve any reporting requirements. Therefore, this generic letter is close " Commercial Storage at Power Reactor Sites of Low-Level Radioactive Waste Not Generated by the Utility" - The licensee does not '

plan on making an application for a license to store low-level waste on site that was not generated by the utilit This generic letter is considered close " Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage" - This generic letter was routed to the group within the organization that is responsible for conducting 10 CFR 50.59 reviews. No written response or specific action was required by this lette Therefore, this generic letter is closed.

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. . Operational Safety Verification and Engineered Safety Features System Walkdown (71707 and 71710)

The inspectors observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the period of inspection. During these discussions and observations, the inspectors ascertained that the operators were alert, cognizant of plant conditions, '

attentive to changes in those conditions, and took prompt action when appropriate. The inspectors verified the operability of selected emergency systems, reviewed tagout records'and verified proper return to service of affected components. Tours of the Auxiliary and Turbine Buildings were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenanc The inspectors observed plant housekeeping / cleanliness condition During !

the period of inspection, the inspectors walked down the accessible portions of the Auxiliary Feedwater, Vital Electrical, Diesel Generating, Component Cooling, Safety Injection, and Containment Spray systems to verify operabilit These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under Technical Specifications, 10 CFR and administrative procedure At 3:23 a.m. on September 8, 1987, during a safety injection pump test (IT-01), the "B" pump's breaker would not close. Unit 1 was at 100% power at the time. A review of the station log showed that on August 19, 1987, the "B" SI pump had been tested satisfactorily at 12:45 a.m. so that maintenance could be done on the "A" SI pum Following this maintenance the "A" SI pump was returned to service at 10:00 p.m. on August 19, 1987. No work had been done on the "B" pump breaker and it had not been racked in or racked out between the time it was tested satisfactorily on August 19 and when it failed to close on September 8. The licensee notified the NRC of the failure at 6:45 on September 8, 1987 (event number 9909). The licensee found that the

"B" SI pump breaker did not close because a micro switch was loose. The switch was adjusted and the pump was tested satisfactorily. The "A" SI pump had bc.en tested satisfactorily before it was found that the

"B" pump would not ru Repair of the "B" SI pump breaker was accomplished in about three hour The micro switch which was found loose is called the " latch check switch".

This switch is routinely checked for tightness during each annual overhaul ';

of the breaker. The breaket type is a Westinghouse DH-350 and breaker testing is done in accordance with Westinghouse Bulletin 32-251-4. There is no way to ascertain when the switch opene !

l On September 10, 1987, the auxiliary building operator was instructed to l line up to recirculate the "B" boric acid storage tank (BAST) using the j IP4B boric acid transfer pum This is a routine evolution performed I twice per week to accommodate sampling by chemistry. The line-up is 3  ;

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r accomplished by referencing the piping flow diagra There is no local indication that would indicats an incorrect or inadequate line-up. The only remote indication of an incorrect line-up would be changing levels in the BAST's which is displayed in the control room. The auxiliary building operator failed to open one of tae suction valves to the transfer pum The pump subsequently overheated and tripped off the line, The non-conformance report (NCR) on this event is still being reviewed with consideration being given to providing a procedure or check off list for the evolution and/or providing instrumentation which would alert the operator to a faulty line-up. The inspectors will follow the licensee's resolution of this NCR. This is an open item (266/87017-01 (DRP)).

No violations or deviations were identifie . Monthly Surveillance Observation (61726]

The inspector observed technical specifications required surveillance testing on the Reactor Protection and Safeguards Analog Channels and Nuclear Instrumentation and verified that testing was performed in accordance with adequate procedures, the test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical specifications and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personne The inspector also witnessed or reviewed portions of the following test activities:

TS-1 Emergency Diesel Generator 30 TS-3 Main Turbine Stop and Governor Valves, Unit 1 i TS-10A Containment Airlock Door Seal Testing, Unit 2 TS-11 Boric Acid Heat Tracing l l

IT-01 Inservice Testing of High Head Safety Injection Pumps & Valves )

Unit 1 IT-03 Inservice Testing of Low Head Safety Injection Pumps & Valves  !

Unit 1 l IT-07 Inservice Testing of Service Water Pumps & Valves, Units 1 & 2 IT-505 Leakage Reduction & Preventative Maintenance Program Test of Post-Accident Reactor Coolant Sampling System IT-525A Leakage Reduction & Preventative Maintenance Program Test of the Safety Injection System

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IT-545A Leakage Reduction & Preventative Maintenance Program Test of Containment Spray System ICP-2.11 Analog Rod ~ Position, Unit 1 ICP-2.12 Independent Overspeed Protection System, Unit 1 & 2 WMTP 9.2 ~ Nuclear Power Range Detector Calibration Quarterly Axial Offset Test PT 5-2 Periodic Test Diesel 3D Redundant System Check No violations or deviations were identifie . Monthly Maintenance Observation (62703)

Sta',lon maintenance activities on safety related systems and components !

listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with technical specification The following items were considered during this review: the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; L

parts and materials used were properly certified; radiological controls ,

were (mplemented; and fire prevention controls were implemente '

Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may af fect systeri performanc The following maintenance activities were observed / reviewed:

• Diesel Generator 4D Annual Overhaul

• Repair of Main Feed Regulating Valves on Unit 1

• Repair of Boric Acid Recirculating Pump (IP4B)

e Adjustment of Micro Switch on Safety Injection Pump Breaker (P158)

During a paperwork audit on the installation of longer pigtails on various )

solenoid valves at the plant, it was discovered that the wire used to l

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extend the pigtails did not have proper environmental qualification ]

i paperwork. The wire, General Electric (GE) Vulkene Switchboard wire, part j l number SI-57275, was ordered under the quality assurance program but did not specify environmental qualification requirements. Only 11 of these valves are included on the licensee's environmental qualification list, i

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although it intends to maintain all valves at the same level of qualificatio The licensee has prepared a justification for continued I operation (JCO) which has been submitted to the NRC for review. Options presently open to resolve this issue are: obtain qualification verification of the installed wiring; replace the installed wiring with qualified wire; or sleeve the installed wire with approved Raychem sleevin The inspectors will follow the licensee's actions to resolutio This is an open item (266/87017-02 (DRP)).

No violations or deviations were identifie l 6. Physical Security (71881)

The inspectors, by observation and direct interview, verified that physical security was being implemented in accordance with the station security pla ,

During the inspection period, the inspectors verified that the security j force compliment was as required by the security plan, that search equipment was operational, and that access control for personnel and packages was implemented in accordance with licensee procedures. The inspectors verified that the protected and vital area barriers were being well maintained and, when required, appropriate compensatory measures were take No violations or deviations were identifie . Radiological Protection (71709)

During the inspection period, the inspectors verified that health physics supervisory personnel conducted plant tours and were aware of activities which may cause unusual radiological conditions. The inspectors verified that radiation work permits (RWP) contained required information and for l selected RWPs the inspectors verified controls were being implemented as required at the work site. The inspectors observed personnel within radiation controlled areas and determined that personnel monitoring equipment was properly worn and that the licensee's procedures for entry and exit were followed. The inspectors observed the posting of radiation areas, hot spots, contaminated areas, and labeling of containers holding radioactive material and verified postings using a calibrated beta gamma portable survey mete No violations or deviations were identifie . Enforcement Conference On September 23, 1987, an enforcement conference was held at the Region III offices between the licensee and members of the Region III staff to discuss a potential violation in which the control power to the MSIVs was tagged open inadvertentl (This issue is the subject of special inspection report 301/87003). During the conference, the

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,4 licensee presented the results of its investigation and proposed corrective actions to prevent recurrence of the even The licensee committed to completing the following actions by the indicated dates:

a Recommendations for better procedural control 12/31/87

• Independent verification guidance 12/31/87

• Review upgrading station log entries 12/31/87

• Develop safety related list 3/31/88

• In process red tag /31/88

• Modify DC power circuit alarm Next Outage Each Unit The licensee's presentation was thorough, in-depth, and indicated that it had actively pursued establishing the root caus Its proposed corrective actions include both plant modifications and programmatic changes which should not only prevent recurrence of this event, but should help preclude the types of miscommunications which led to this even The inspectors will follow the licensee's actions to complete the above commitment This is an open item (301/87017-01 (DRP)).

No violations or deviations were identifie . Event Followup (92700) l Through direct observations, discussions with licensee personnel, and review of records, the following licensee event reports (LERs) were l reviewed to determine that deportability requirements were fulfilled, j immediate corrective action was accomplished, and corrective action to

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prevent recurrence had been accomplished in accordance with technical specifications, j CLOSED LER (301/87-002-00) " Loss of Load Reactor Trip Due to Lightning Strike" - The "B" and "C" phases of the 19KV/345KV transformers were i inspected and tested satisfactoril The fast bus transfer circuitry response was tested and verified operable prior to Unit 2 startup. The reactor was taken critical on August 17, 1987, at 9:38 No violations or deviations were identifie , Open Items Open items are matters which have been discussed with the licensee, which will be reviewed further by the inspector, and which involve some action on the part of the NRC or licensee or bot Open items disclosed during the inspection are discussed in Paragraphs 3, 5 and _ _ _ _ _ .

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.O 11. Exit Interview (30703)

The inspectors met with licensee' representatives (denoted in Paragraph 1)

throughout the' inspection period and at the conclusion of the inspection period to summarize the scope and findings of the inspection activitie The licensee acknowledged the inspectors' comments. The inspectors also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspectors during the inspection. The licensee'did not identify any such documents / processes as proprietar .

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