IR 05000266/1988002

Insp Repts 50-266/88-02 & 50-301/88-02 on 871215-880131.No Violations or Deviations Noted.Major Areas Inspected:Maint, Previous Insp Findings,Operational Safety,Surveillance, Physical Security,Radiological Protection & LER Followup

ML20149H865
Person / Time
Site:	Point Beach
Issue date:	02/11/1988
From:	Defayette R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20149H859	List: IR 05000266/1988002 ML20149H856
References
50-266-88-02, 50-266-88-2, 50-301-88-02, 50-301-88-2, NUDOCS 8802220152
Download: ML20149H865 (8)

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, ..- : NUCLEAR REGULATiM l

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Reports No. 50-266/88002(DRP); 50-301/88002(DRP) '

Docket Pos. 50-266; 50-30' 1icenses No. DPR-24; DPR-27

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Licensee:

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Wisconsin Electric Company \, ,

231 West Michigan- --

Milwaukee, WI 63903

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Facility Name: Point Beach Unit l'1nd 2 '

Inspection At: Two Creeks, Wir: nsin ' ~

Inspection Conducted: December 15, 1987 througn inuary 31, 1988 Inspectors: L. Hague '

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Approved By: R.DeFayette,h;hief 8 //

Reactor Projects Sectica. 2B Datfe '

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Inspection Summary Inspection on December 15, 1987 through January 31, 1988, (Reports No. 50-266/88002 (DRP); 50-301/88002 (DRP))

Areas Inspected: Routine, unannounced inspection by resident inspectors of previous inspection findings; operational safety; maintenance; surveillance; '

physical security; radiological protection; and licensee event report follow u Results: No violations or deviations were ido1tifie ~

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8802220152 880211 PDR 0 ADOCN 03000266 pcp

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, t DETAILS '  !

t 1. Persons Contacted

• J. J. Zach, Manager, PBNP T. J. Koehler, General Superintendent  :

G. J. Maxfield, Superintendent - Operations  !

• J. C. Reisenbuechler, Superintendent - EQRS

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W. J. Herrman, Superintendent - Maintenance & Construction l D. F. Johnson, Superintendent - Health Physics  :

R. Krukowski, Security Supervisor i *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,  !

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Maintenance, Health Physics, Chemistry and Instrument and Control' Section l

* Denotes personnel attending exit interview !

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2. Licensee Action on Previous Inspection Findings (92701) (92702)

i (CLOSED) Deviation 266/87002-01 - Failure to Comply with Commitment Made

{ in Response to I.E. Bulletin 79-2 j

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Specifically, the licensee response states in part that monitoring of i

heat traced lines in the facades is accomplished using "a multichannel l recorder located in the Auxiliary Building which tracks the status of each of the heat tracing channels. Trends and gradual changes in the l

performance of the heat tracing circuitry can be determined by observing }

these point recordings." l

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Ouring the inspection it was determined that several points have been out

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of service, one for over a year and the multichannel recorder mode switch is maintained in the "record on alarm" position which prevents routine l trending of any point i i

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A new recorder has been installed and is operatin The maintenance work l l requests (MWRs) of concern have been worked, and there have not been any  !

] freezing problems during the severe sub-zero cold weather. This item is  !

j close !

! (CLOSED) Unresolved Item 266/87005-01; 301/87005-01 - Adequacy of Control j Room Ventilation Fans, t i The control room emergency ventilation fans are not powered from a vital

bus. However, they were taken credit for in the control room habitability i stud :

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The licensee has put instructions in the night orders of how to repower these fans if the need arise (CLOSED) Open Item 266/87013-04; 301/87033-04 - Evaluation to Determine !

Cause of Blown Fuse with Special Testing Involved.

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The licensee experienced problems with the Unit 1 "A" reactor trip breaker DC control power fuses. The problem was initially attributed to fuse degradation and the current surge associated with breaker closur i However, the licensee could not "create" a degraded fuse during testin '

j The breaker was disassembled and very closely inspected. This inspection i revealed no clearance between the stationary and moving parts of the .

I closing mechanism housing. Further inspection determined that the  :

mounting bolts were causing a 54 mil distortion of the stationary housin !

By installing brass shim material, in the gaps, the distortion was reduced I to approximately 10 mils. The "after complete assembly" clearance

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obtained between the stationary and moving housing parts was approximately ;

5 mils. This open item is close !

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l The resident inspector has reviewed the licensee's corrective actions on ,

the open items listed below and was satisfied with its respons Therefore, the open items are close [

(CLOSED) Open Item 266/85013-05; 301/85013-05 - No Formal EQ Training i Program Establishe ,

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(CLOSED) Open Item 266/85013-06; 301/85013-06 - Inadequate Proceduies on l Reviewing Modification to EQ Lis i

, (CLOSED) Open Item 266/85013-07; 301/85013-07 - EQ Procedures not Yet in Effect for Electrical Equipmen (CLOSED) Open Item 266/85013-08 - Inadequate Conduit Connection at Valve Operator 1-MS202B i 1 (CLOSED) Open Item 266/85013-09; 301/85013-09 - Incomplete Information in i Rockbestos Firewall 3 Cable EQ Fil l

. 1 (CLOSED) Open Item 266/85013-10; 301/85013-10 - Discrepancies Between EQ j Summary Sheets and Doc. Files AOF ASCO Solenoid Valves, Hydrogen Analyzer j and Limitorque Operators.

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(CLOSED) Open Item 266/85013-11; 301/85013-11 - Insufficient Progress in l Licensee's Review of IEB 83-72 on Limitorque Operator . Operational Safety Verification and Engineered Safety Features System

Walkdown (71707 and 71710)

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The inspectors observed control room operations, reviewed applicable logs a and conducted discussions with control room operators during the period of l

inspection. During these discussions and observations, the inspectors

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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 3 service of affected components. Tours of the Auxiliary and Turbine ,

Buildings were conducted to observe plant equipment conditions, including l potential fire hazards, fluid leaks, and excessive vibrations and to i verify that maintenance requests had been initiated for equipment in need ,

of maintenanc !

The inspectors observed plant housekeeping / cleanliness condition During the per,od of inspection, the inspectors walked down the accessible portions of the Auxiliary Feedwater, Vital Electrical, Diesel Generating, i Component Cooling, Safety Injection, and Containment Spray systems to verify operability.

These reviews and observations were conducted to verify that facility 4 operations were in conformance with the requirements established under l

Technical Specifications, 10 CFR and administrative procedures.

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No violations or deviations were identified, f

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4. Monthly Surveillance Observation (61726)

l The inspector observed technical specifications required surveillance .

testing on the Reactor Protection and Safeguards Analog Channels and l Nuclear Instrumentation and verified that testing was performed in .

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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 '

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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 !

On December 23, 1987, Diesel 3D failed to start three times during l l surveillance testing. On the first attempt to start, the operator in the i

! diesel room heard only a puff of air go to the air start motors. The l diesel did not start. Then 30 was satisfactorily started and test ran ,

under load. It was decided to run 30 again. It cranked over but did not '

, star A fourth attempt was made to start 3 The results were the same, t

At this time 3D was declared out of service and 40 was tested I satisfactoril The start problems with 30 were evaluated and it was i j satisfactorily tested and returned to service the snme da j l

The assumption for the first start failure is that dirt in the starting 1 l air blocked the air passage in the air start solenoid valve. The :hird i

and fourth start attempts failed because the operator did not wait long i

enough for the stop timer to time ou Step 4.8 Note 2 of procedure TS-1

"Emergency Generator 3D Biweekly" does not appear to contain enough

) information to guide the operator in the operation of the timers.

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i However, if the diesel would have received an auto start signel while the ,

timers were timing out, the diesel would have starte This is an open i item (266/88002-01(DRP)).

. Unit 1 A steam generator low level BF-66F relay (463E) was founo to be  !

sticking in the energized direction when performing ICP 2.3 "Reai: tor '

Protection Logic Surveillance Test". The relay is spring loaded in the de-energized direction to cause safeguard actuation, therefore, the steam generator low level trip was operabl A pin that holds the arAature to the moveable contacts appeared to have rubbed on the side of tne relay casing. The relay was replaced and the logic test was completed ,

satisfactoril The inspector also witnessed or reviewed portions of the following test i activities: l i

ICP Reactor Protection and Safeguards Analog - Unit 1 l f

ICP Reactor Protection System Logic

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ICP Reactor Protection Logic - Unit 2 l ICP Nuclear Instrumentation Power Range Channels N41-N44 ,

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TS-5 Rod Exercise - Unit 1 i l

TS-6 Rod Exercis-e - Unit 2 l

TS-11 Boric Acid Heat Tracing IT-9 Inservice Testing of Turbine-Driven Auxiliary Feed l Pump - Unit 2 i i

IT-10 Inservice Testing of Electrically-0 riven Auxiliary '

Feed Pumps - Units 1 & 2  !

IT-11 Inservice Test of the Spent Fuel Pit Cooling Pumps WMTP 9. Rod Control System: Rod Position Verification & Rod l Position Indicator Alignment i

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No violations or deviations were identified, j Monthly Maintenance Observation (62703)

Station maintenance activities on safety related systems and components i 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 l l

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; l l

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activities were accomplished using approved procedures and were inspected [

as applicable; functional testing and/or calibrations were performed prior !

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to returning components or systems to service; quality control records l were maintained; activities were accomplished by qualified personnel; I parts and materials used were properly certified; radiological controls i were implemented; and fire prevention controls were implemente f 4 t

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Work requests were reviewed to determine status of outstanding jobs and to l

assure that priority is assigned to safety related equipment maintenance !

which may affect system performanc !

t l The following maintenance activities were observed / reviewed:

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• Retubing Component Cooling Heat Exchangers.

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• Troubleshooting the start failures on 3D Diesel Generator t f

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• Oil Changes for the Auxiliary Feedwater Pumps  ;

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l * Flow Switch Modifications for the Residual Heat Removal Pump !

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No violations or dtviations were identifie [

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1 6. Pnysical Security (71881) i

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The inspectors, by observation and direct interview, verified that l

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physical security was being implemented in accordance with the station ;

l security plan, i f

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During the inspection period, the inspectors verified that the security !

, force compliment was as req' u ired by the security plan, that search (

i equipment was operational, and that access control for personnel and  ;

j packages was implemented in accordance with licensee procedure The !

] inspectors verified that the protected and vital area barriers were being l a

well maintained and, when required, appropriate compensatory measures were i i taken, f

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s On December 24, 1987, the security force conducted an innovative security I q dril The drill checked the security department to the operation f 4 department interfac The purpose of the drill was to see if the security l t force would inform the plant on-call personnel of an operations department j

problem. The security force did notify the necessary on-call plant 5 personne l j No violations or deviations were identi'ie {

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7. Radiological Protectio 2 (71709)  !

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During the inspection period, the inspectors verified that health physics i i supervisory personnel conducted plant tours and were aware of activities 1 which may cause unusual radiological conditions. The inspectors verified ,

j that radiation work permits (RWP) contained required information and for I l  !

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selected RWPs the inspectors verified controls were being implemented as required at the work sit The inspectors observed personnel within radiation controlled areas and determined that personnel monitoring equipment were 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 . Event Fol'owup (92700)

Through direct observations, discussions, with licensee personnel, and I review of records, the following licensee event reports (LERs) were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with technical specification The following events were of minor safety significance !

and did not represent program deficiencies. These reports are close '

(CLOSED) LER 266/87005-00 - Reactor Trip with SI Due to Spray Valve Failur !

The broken solder connection in the spray valve controller was repaired, j and the pilot valve stem and associated orifices were replaced in the valve positione The spray valve has operated satisfactorily since the ;

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(CLOSED) LER 301/87005-00 - Turbine Runback Caused by a Dropped Ro The cause of the dropped rod was because of fuse failure caused by fuse !

fatigue in the moveable gripper circuit. The licensee has entered ;

call ups on the computerized history and maintenance planning system I (CHAMPS) to have the stationary gripper's fusos replaced every two years and to have the moveable gripper's fuses replaced every five year 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 An open item disclosed during the inspection is discussed in Paragraph . Exit Interview (30703)

The inspectors met with licensee representatives (denoted in Paragraph 1) l throughout the inspection period and at the conclusion c.f the inspection l period to summarize the scope and findings of the inspection activitie The licensee acknowledgert the inspectors' comments. The inspectors also l I

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o 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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