IR 05000275/1986020

Insp Repts 50-275/86-20 & 50-323/86-20 on 860706-0809.No Violations or Deviations Noted.Major Areas Inspected:Plant Operations,Maint & Surveillance Activities,Followup of Onsite Events,Lers & Independent Insp Activities

ML17083B786
Person / Time
Site:	Diablo Canyon
Issue date:	08/14/1986
From:	Mendonca M, Padovan M, Polich T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML17083B785	List: IR 05000275/1986020 ML17083B784
References
50-275-86-20, 50-323-86-20, NUDOCS 8608290169
Download: ML17083B786 (20)

Text

U. S.

NUCLEAR REGULATORY COMMISSION

REGION V

H 50-275/86-20 and 50-323/86-20

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Pacific Gas and Electric Company'7 Beale Street, Room 1451 San Prancisco, California 94106,,

I CJ if Facility Name:

Diablo Canyon Units 1 and 2,

I Diablo Canyon Site,': San Luis 'Obis'po County, N

Inspection Conducted:

July 6 through Augusti 9, 1986 Report Nos:

Docket Nos:

50-275 and 50-323 License Nos:

DPR-80 and DPR-82 Licensee:

N it California Inspectors:

Approved by:

M. L. Padovan, Resident Inspector T. J. Polich, Resident Inspector C

M. M. Mendonca, Chief, Reactor Projects, Section

agiwEIe Date Signed J/Zyy< i, Date Signed

~/iyis.p Date Signed Summary:

Ins ection from Jul 6 throu h Au ust 9, 1986 (Re ort Nos. 50-275/86-20 and 50-323 86-20)

Areas Ins ected:

The inspection included routine inspections of plant operations, maintenance and surveillance activities, follow-up of on-site events, and LERs, as well as selected independent inspection activities.

Inspection Procedures 30703, 50095, 61726, 62703, 71707, 71710, 90712, 92700, 92701, and 93702 were applied during this inspection.

Results of Ins ection:

No violations or deviations were identified.

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DETAILS 1.

Persons Contacted R. A. Clarke, Chairman of the Board J.

D. Shiffer, Vice President Nuclear Power Generation R.

C. Thornberry, Plant Manager

• J. A. Sexton, Assistant Plant Manager, Plant Superintendent J.

M. Gisclon, Assistant Plant Manager for Technical Services

• R. G. Todaro, Security Supervisor D. B. Miklush, Maintenance Manager D. A. Taggert, Director Quality Support W. G. Crockett, Instrumentation and Control Maintenance Manager J.

V. Boots, Chemistry and Radiation Protection Manager

• L. F. Womack, Engineering Manager T. L. Grebel, Regulatory Compliance Supervisor S.

R. Fridley, Senior Operations Supervisor

• R. S. Weinberg, News Service Representative D. D. Malone, Senior I&C Supervisor The inspectors interviewed several other licensee employees including shift foreman, reactor and auxiliary operators, maintenance personnel, plant technicians and engineers, quality assurance personnel and general construction/startup personnel.

>Denotes those attending the exit interview.

Note:

Acronyms are used throughout this report; refer to the Index of Acronyms at the back of the report.

2.

0 erational Safet Verification a ~

General During the inspection period, the inspectors observed and examined activities to verify the operational safety of'the licensee's facility.

The observations and examinations of;,,those activities were conducted on a daily, weekly or monthly basis.

On a daily basis, the insp'ectors ob'served control room activities to verify compliance with selected LCOs as prescribe'd in the'facility TS.

Logs, instrumentation, recorder tr'aces, and other operational records were examined to obtain information<,on plant conditions, and trends were reviewed for compliance with regulatory requirements.

Shift turnovers were observed on a,sample basis to verify that all pertinent information of plant status was'elayed.

During each week, the inspectors toured the accessible areas of the facility to observe the following:

(a)

General plant and equipment condition '

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(c)

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(d)

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(e)

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(f)

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(g)

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(h)

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The inspectors talked with opexators in the control room, and other plant personnel.

The discussions centered on pertinent topics of general plant conditions, procedures, security, training, and other aspects of the involved work activities.

No violations or deviations were identified.

Event Follow-u a.

Inadvertent Steam Generator (SG)

Blowdown Isolation On July 24, 1986 while obtaining'SG blowdown readings on Unit 1 for STP R-2B "Operator Heat Balance",

an operator unintentionally contacted a push button power switch with his clipboard, de-energizing radiation monitors RM 23 and RM 27.

The operator recognized this situation and re-energized the radiation monitors in about two seconds.

The momentary loss of power to the radiation monitors caused closure of the SG blowdown and sample valves.

However, SG blowdown valve FCV-157 did not close and blowdown tank drain valves FCV-498 and 499 did not transfer to the equipment drain receiver.

The licensee subsequently functionally tested the above mentioned valves in accordance with STP I-18F1 "Functional Test of SG Blowdown Tank Vent (RM-27) and Discharge Monitors (RM-23),"

and determined the valves to be performing correctly.

The licensee concluded de-energizing the radiation monitors for only. two seconds was insufficient time to cause FCVs 157, 498 and 499 to actuate.

b.

Unit 2 Reactor Tri Due to Feedwater Pum

. Loss On July 9, 1986 while at about 49 percent power, Unit 2 experienced a reactor trip due to a low SG level and steam flow-feedwater flow mismatch following a trip of the 2-1 main,'feedwater pump (MFWP).

At that, time Unit 2 was restricted to 49 percent"power as a result of an out-of-service circulating water pump.

MFWP 2-2 was previously removed from service for instal'lation of a Lovejoy control system.

MFWP 2-1 tripped due to either an overspeed or high discharge pressure signal.

The licensee'investigated the-cause of

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the MFWP trip but was unable to determine the cause of the speed increase in the pump.

While unable to recreate the MH6'-1 trip, the licensee believes the trip was caused by the work in process on the MFWP 2-2 controller.

The licensee also had instrumented MFWP 2-1 and monitored it for anomalies.

Balancing 'of the MFWP 2-2 control system continued through the end of this report period.

C ~

Unit 1 Containment Vent Isolations (CVIs)

On July 10 and July 16, 1986 CVIs were automatically initiated on Unit 1.

The sources of the initiating signals were indeterminate, as radiation monitors, which were expected to have caused the CVIs, did not "latch in."

A secondary radiation monitoring system was used to confirmed no increased radiation levels were present in the containment, verifying the initiating signals were spurious.

The licensee made proper notifications and th'en returned the radiation monitor isolation'valves to their normally open configuration.

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At 9:12 a.m.

on July 30, 1986 aCVI was initiated as a result of a voltage transient on instrument power bus PY-llA.

The voltage transient on PY-llA occurred when an=-ISC technician was replacing pressure switch PS-526 in "accordance with work order COOO'1795.

The technician laid'own a lead 'to,its terminal"and,created a spark when two solenoids were energized,

At 1:57 p.m.

and again at 2:52 p.m~,'on~July30, 1986, additional CVIs were initiated due to hi'gh,radiation-'alarms on, radia'tion" monitor RM-12.

Containment radiation<levels wer'e 'alsothen,checked and found to be normal."',,

i During the past year, 'over a',dozen CVIsf have 'occurred on Units 1 and 2 due to spurious signals'in radiation','mon'ltoring electrical circuitry.

The circuitry is especially se'nsiti've 'toswitching operations -'ln the 500 KV swftchyar'd since the, power lines to the switchyard are located. next to,the containment'n near proximity to the radiation monitors.

The licensee has established a radiation monitor noise reduction program and continued to investigate and troubleshoot the source of the spurious radiation monitor signals (see Section 4b. of this report).

The noise reduction program is staffed with team members that have specialized noise training.

Over the next few years, the present 'radiation monitoring system will be replaced with a new digital syst'm which will be significantly less susceptible to noise'nterference.

January 1,

1987 is the target date to award the contract to the vendor selected to supply the new system.

In the interim, radiation monitors are being evaluated and new, more sensitive test equipment is being brought on-site.

Additionally, Sargent

& Lundy Engineering personnel were contracted to evaluate radiation monitor shielding and grounding adequacy, and have submitted a preliminary report to the licensee for evaluation.

The inspector will follow the licensee's noise reduction program as part of the routine inspection program.

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4.

Maintenance The inspectors observed portions of, and reviewed records on, selected maintenance activities to assure compliance with approved procedures, technical specifications, and appropriate industry codes and standards.

Furthermore, the inspectors verified that maintenance activities were performed by qualified personnel in accordance with fire protection and housekeeping controls, and that xeplacement parts were appropriately certified.

a.

Fuel Handlin Buildin Su

Fan Portions of routine preventative maintenance of Unit 1 fuel handling building supply fan S-1 was observed by the inspector.

Electrical Maintenance Procedure E-53.1 "Maintenance of 115 and 480 Volt Motors" was used to steam clean the motor, bake the stator windings and inspect the motor.

Meggering identified a ground in the stator windings, and non-energized motor space heaters were discovered.

The grounding problem was attributed to moisture in the windings and was corrected by baking.

Required administrative approvals and clearances were obtained, and approved procedures were used.

QC hold points were established and observed by two QC inspectors.

b.

Radiation Monitor RM-12 C ~

The inspector observed licensee inservice troubleshooting of containment gas monitor RM 12, which provides a CVI signal upon detecting high gaseous activity in the containment.

Appropriate administrative approvals and clearances had been obtained prior to initiating the work.

Fuse block wiring supplying electrical power to the monitor was checked for 'wire.tightness and good fuse contact.

Also power fuses for monitor 1'atching relays were found to be secure.

Switch contacts were clean",

and routinely'llifted circuits to the solid state protection system were tight arid 'properly routed.

The technician also reviewed monit'or'alibration records.'o determine if the detector tube had 5'een<prdviously'replaced.

From discussions with the technician, the ins'pe'ctor found, the technician to be knowledgeable about troubleshooting "the inservice 'radiation monitor, and control room operators'ere,awaie of the possibility of the technician's investigations creating a'nother. AVI.'

It Auxiliar Feedwater Pum (AFWP) 2-2 tt I

Disassembly and inspection of the outboard bearing, of Unit 2 motor driven AFWP 2-2 was observed by the inspector. 'hile taking samples of the bearing oil, the licensee discovered the oil was discolored, and issued maintenance Work Order 1665 to disassemble the outboard bearing and inspect for wear and damaged parts".; Appropriate administrative approvals and equipment clearances.:were obtained prior to initiating the work.

Repositioned

"sealed valves" were verified to be controlled, and work was performed in accordance with approved instructions.

QC hold points were also established, and evidence of QC verification was noted by the inspecto !>>.,[

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d.

Unit 2 Boric Acid Heat Trace Installation of heat tracing on channels 230 (boric acid transfer pump 2-1)

and 224 (boric" acid filler outlet), performe'd by electrical maintenance personnel, was observed by the inspector.

Action Request A 0028376 was issued for this work as a result of low temperature alarms generated by, failed heat tracing.

Work was performed in accordance with Maintenance Procedure E-57.3A

"Installation and Repair of Econo-Trace Heating Cable",

and proper administrative approvals and equipment clearances had been obtained prior to initiating the work.

The inspector veiified.maintenance personnel observed radiological controls specified in the'valid special radiation work permit.

Through discussions with the maintenance personnel, the inspector 'determined the individuals were qualified to perform the work.

No violations or deviations were identified.

5.

Surveillance By direct observation and record review of Unit 1 selected surveillance testing, the inspectors assured compliance with TS requirements and plant procedures.

The inspectors verified that test equipment was calibrated, and acceptance criteria were met or appropriately dispositioned.

a.

Containment H dro en Monitor The inspector observed I&C 'surveillance testing of Unit

containment hydrogen monitor 1-CEL-82 in accordance with STPs I-46 A and B.

Required administrative approvals and clearances were obtained prior to initiating work.

However, further calibration was delayed while technicians corrected excessive hydrogen leakage encountered during pressure integrity verification of the system.

At that time, the inspector identified the calibration of a Data Precision Model 3500 digital voltmeter was overdue by one day.

This voltmeter was to be used later in the test to verify proper operation of electronic circuitry in the hydrogen monitor.

This discrepancy was discussed with the I&C foreman, instrument calibration personnel and the I&C Department Manager.

The instrument was immediately removed from the job.

The licensee's investigation determined the instrument was taken to the hydrogen monitor location while it was calibrated, but had been left at the location for several days while leakage in the monitor was being repaired.

Administrative Procedure D-450 "Control of I&C Department Measurement and Test Equipment" specified the digital voltmeter was to be stored in the instrument shop when not in use.

Accordingly, the voltmeter should have been returned to the instrument shop when it was not used on the first day.

Since the voltmeter was not used, there is no safety significance to the incident.

Further, since the data sheet for STP I-46B required documenting the voltmeter calibration date, it is unlikely the technicians and data sheet reviewers would have overlooked the instrument's overdue calibration date.

At a tailboard session with I&C personnel, the licensee plans

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to discuss the importance of returning test equipment to its proper storage location.

b.

Containment Isolation Valve Leak Rate Test Leak rate testing of Unit 2 containment penetration exhaust purge valves RCV ll and 12 was observed by the inspector.

This testing was required by Technical Specification (TS) Surveillance Requirement 4.6.3.4 since the valves had been opened for containment purging.

Additionally, this test satisfied the inservice testing leak rate requirements specified by TS 4.0.5 for these valves.

Required test equipment was properly calibrated, appropriate administrative approvals and equipment clearances had been obtained',

and the test was conducted in accordance with approved procedures.

Re-positioning of sealed valves for the test was controlled in accordance with NPAP C-9 "Sealed Valves."

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The inspector observed selected portions of STP M-9A, "Diesel Engine Generator Routine Surveillance Test" on DG l-l.

The DG achieved proper speed, voltage and frequency within the required times.

The DG was paralleled and loaded by an assistant control operator under the supervision of a licensed operator.

The shift foreman declared DG l-l operable at the completion of the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> run.

Fire Water Pum (FWP) 0-2 Portions of STP P-13A "Fire Pumps Performance Test" performed on FWP 0-2 was observed by the inspector.

This test,was performed to comply with technical specification requirements and to establish new pump baseline data since the pump impeller, packing, and wear rings had been replaced.

The pump was placed on reci'rculation, and test data on pump suction'nd<discharge pressures were obtained at different flow rates for comparison with the pump head capacity curve.

The inspector verified proper clearances'ad been obtained to perform the test, and control room pe'rsonnel were cognizant of the ongoing activity.

Test instrumentation w'as verified toibe calibrated, and test personnel were knowledgable of the testing activity.

Pump flow data recorded (2198 gpm) did" not'appear at first to meet the 2500 gpm acceptance criteria; however,

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No violations or deviations were identified.

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Inde endent Ins ection Effectiveness of Licensed 0 erators The inspectors have given particular attention'to control room demeanor during this inspection period.'he licensed operators continue to conduct plant operations in a, professional manne \\

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During critical evolutions or plant trips the shift foreman or senior control operator takes charge and clears unnecessary personnel from the control room.

Licensee management is cognizant of the need for a professional atmosphere in the control room and assists the operators in clearing the control roo'm of extraneous personnel when necessary.

Licensee management makes frequent tours of the control room and observes the conduct of operations.

No violations or deviations were identified.

7.

Licensee Event Re ort Follow-u Based on an in-office review, the following LERs were closed out by the resident inspectors:

Unit 1:

84-36, 84-39, 85-37, 85-39, 86-02, 86-06 Unit 2:

84-36, 85-23, 86-06, 86-09, 86-17, 86-18 The LERs were reviewed for event description, root cause, corrective actions taken, generic applicability and timeliness of reporting.

The LERs identified below was also closed out after in-office review and on-site follow-up inspection was performed by the inspectors to verify licensee corrective actions:

Unit 2:

86-16 was closed out based upon the inspector witnessing disassembly and corrective maintenance of circulating water pump 2-2 motor coils.

No violations or deviations were identified.

8.

Meetin with Cor orate Mana ement The inspectors met with the licensee's new Chairman of the Board and Chief Executive Officer, R. A. Clarke, and the Vice President of Nuclear Power Generation, J.

D. Shiffer, to discuss corporate management's position on previous inspection findings and future operational suppo'rt for Diablo Canyon.

Topics discussed included the licensee's problem resolution program, ongoing improvements in the surveillance control program, and a strong corporate commitment to preventive maintenance for future operations.

The inspectors emphasized that NRC inspections are performed on a sampling basis and do not replace the need for effective comprehensive management controls.

Mr. Clarke assured the inspectors that corporate management would continue to be actively involved in plant operations.

The inspectors noted that plant operations had been relatively trouble-free, and that continued management support may provide added benefits in plant safety and operations.

Mr. Clarke reaffirmed that adequate support would be provided'to Diablo Canyon as evidenced by currently planned plant improvements and work activities.

No violations or deviations were, identified.,

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Exit On August 8, 1986 an exit meeting was conducted with the licensee's representatives identified in paragraph 1.

The inspectors summarized the scope and findings of the inspection as described in this repor E

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,Radiation Monitor Steam Generator Surveillance Test Procedure Technical Specification

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