IR 05000202/2003001
| ML17277B705 | |
| Person / Time | |
|---|---|
| Site: | Columbia, 05000202  |
| Issue date: | 03/22/1985 |
| From: | Johnson P, Toth A, Waite R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17277B704 | List: |
| References | |
| 50-397-85-08, 50-397-85-8, NUDOCS 8504110062 | |
| Download: ML17277B705 (12) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report No:
50-397/85-08 Docket No:
50-397 Licensee:
Washington Public Power Supply System P.
O. Box 968 Richland, Wa.
99352 Facility Name: Washington Nuclear Project No.
(WNP-2)
Inspection at:
WNP-2 Site near Richland, Washington Inspection Conducted:
February 2 - March 1, 1985 Inspectors:
A.
D oth, Senior Resident, Inspector
~R.
S.
aite, Resident Inspector Date Signed l~<~~
Date Signed Approved by:
P.
H.
hnson, Chief React Projects Section
Date Signed Summary:
Ins ection on Februar 2 - March
1985 (50-397/85-08)
Areas Ins ected:
Routine, unannounced inspection by the resident inspectors of control room operations, engineered safety feature (ESF) status, surveillance program, maintenance program, power ascension test program, licensee event reports, special inspection topics, and licensee action on previous inspect>,on findings.
This inspection involved 131 inspection-hours on site by two resident inspectors, including ll hours during backshift work activities.
Results:
No violations or deviations were identified.
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DETAILS Persons Contacted Washin ton Public Power Su l S stem D. Hazur, Managing Director J.
Shannon, Assistant Managing Director for Operations J. Martin, Plant Manager-C. Powers, Assistant Plant Manager R. Corcoran, Operations Manager'.
Cowan, Technical Manager J.
Landon, Haintenance Manager R. Graybeal, Health Physics and'Chemistry Manager D. Feldman, Plant (}uality Assurance Manager J. Peters, Administrative Manager P. Powell, Licensing Manager M. Wuesterfeld, Reactor Engineering Supervisor
-" Personnel in attendance at exit meeting The inspectors also interviewed various control room operators, shift supervisors and shift manageis, and engineering, quality assurance, and management personnel relative to activities in progress and records.
General The Senior Resident Inspector and/or the Resident Inspector were on site February 4-8, 10-15, and 25-28, and Harch l.
Eackshift inspections were conducted February 10,12,13, and 14.
Several regional office inspectors visited the site this month for routine inspection activities.
These activities were documented in separate inspection reports.
A regional office Reactor Safety Inspector (P. gualls)
was on site February 4-8.
Regional office management personnel (D. Kirsch, A. Chaffee and A.
Johnson)
were on site February 11-12 for review of inspection findings and inspection of the plant facilities.
Plant Status The plant operated at 100
% power level for most of the month.
0 erations Verifications The resident inspectors reviewed the control room operator and shift manager log books on a daily basis for this report period.
Reviews were also made of the Jumper/Lifted Lead.Log and Nonconformance Report Log to
'C
verify that there were no conflicts with Technical Specifications and that the licensee was actively pursuing corrections to conditions listed in either log.
Events involving unusual conditions of equipment were discussed with the control room personnel available at the time of the review and evaluated for potential safety significance.
The licensee's adherence to Limiting Conditions for Operation (LCO's), particularly those dealing with ESF and ESF electrical alignment, were observed.
The inspectors routinely took note of activated annunciators on the control panels and ascertained that the control room licensed personnel on duty at the time were familiar with the reason for each annunciator and its significance.
The inspectors observed access control, control room manning, operability of nuclear instruments, and availability of on site and offsite electrical power.
The inspectors, also made regular tours of accessible areas of the facility to assess equipment conditions, radiological controls, security, safety and adherence to regulatory requirements.
During the followup of LER-85-011 (Paragraph 7 below) the inspector accompanied a field engineer and a health physicist, unannounced, into the containment drywell. The health physicist was unaware of the specific location of existing leaks in the primary coolant boundary, and could not assure that dripping condensation in the drywell was not also mixed with water from such leaks.
The technician did identify the condensation as a
condition which warranted a further health physics survey of the area than that which had been conducted to that point.
He prop'erly insisted that personnel exit the drywell until such a survey was performed.
No violations or deviations were identified.
Surveillance Pro ram Im lementation i
The inspectors ascertained that surveillance of safety-related systems or components was being conducted in accordance with license requirements.
In addition to observing and occasionally'itnessing and verifying daily control panel instrument checks, the inspectors observed portions of several detailed surveillance tests by operators and instrument and control technicians.
No violations or deviations were identified.
Honthl Haintenance Observation Portions of selected safety-related systems maintenance activities were observed.
By direct observation and review of records the inspector determined whether these activities were consistent with LCOs; that the proper administrative controls and tag-out procedures were followed; and that equipment was properly tested before return to service.
The inspector also reviewed the outstanding job orders to determine if the licensee was giving priority to safety related maintenance and verify that backlogs which might affect system performance were not developing.
No violations or deviations were identifie f
7.
S ecial Ins ection Activities The inspectors examined records, interviewed personnel, and inspected plant conditions relative to the following matters requested by the regional office, or which involved unusual events:
The inspectors interviewed personnel and examined records and equipment associated with the inadvertent generator load rejection and reactor scram which occurred January 31, 1985.
The inspectors arrived in the control room within 10 minutes of the event, and observed the activities to recover from the event and initiate corrective measures.
An inspector toured the plant during the period 30 minutes after the scram and observed conditions of plant equipment and switchgear, and activities of various licensee personnel in response to the event.
The inspectors witnessed activities to disassemble and test all switchgear of the SM-1 electrical bus to identify an apparent electrical fault. The licensee also br'ought in transformer specialists from the Bonneville Power Administration to assist in evaluation of the condition of transformers which had apparently experienced overheating during the unusual electrical transient.
(This event was initiated by an apparent inadvertent actuation of a relay, which also resulted in failure of the startup transformers to assume the plant electrical loads as designed.
For 14 minutes the plant remained on the 115 KV backup power supply transformer for power supply to the safeguards buses.)
This event was the subject of Special Inspection Report 84-09, which identifies violations of regulatory requirements and further NRC actions.
8.
Licensee Event Re orts The inspector performed an in-office review of the following Licensee Event reports Reports (LERs) relative to timeliness, adequacy of description, generic implications, planned corrective actions, and adequacy of coding.
Except for LER-85-011, these LERs are closed.
LER-84-057, Autostart of Control Room Emergency Filtration System (Chlorine Honitor Tape Depletio'n)
LER-84-093, (Same)
LER-84-128, (Same)
Initial corrective action on these items appeared insufficient.
Repeated occasions of collector tape runout prompted the licensee to modify procedures and surveillance intervals to assure that tape depletion is detected prior to complete runout.
The problem appears to not have recurred since December 3,
1984.
LER-85-002, Reactor Scram Due to Electrical Faults at ASHE Substation LER-85-003, Reactor Scram (Perturbation to off-site microwave link)
The inspector reviewed selected reports and supporting information on-site to verify that the licensee had reviewed the events,
corrective action had been taken, no unreviewed safety questions were involved, and violations of regulations or Technical Specification conditions had been identified. Violations were evaluated for significance relative to
CFR 2, Appendix C.
LER-84-027, (revisions 1 8 2) Grounds In Main Steam Relief Valve Solenoids Inspection of circumstances of the original report was documented in NRC inspection report 84-31.
The inspector verified the additional actions described in subsequent revisions and has routinely observed the proper functioning of the ground indicator test lamps in the control room. Shift turnover 'checklists include operator verification that the ground indicator test lamps are active.
LER-84-090, RPS Actuation On low RPV I,evel (Operator Inattentiveness during main steam drain blowdown)
The inspector verified incorporation of appropriate caution statements added to the startup procedure to alert the operators to the potential for excessive reactor water level reduction.
The general subject of operator attention to detail was addressed in NRC inspection report 85-09 and associated enforcement, for licensee corrective action.
LER-84-112, Reactor Scram (Incorrect reset of reactor pressure controller)
This event conditions correction subject of inspection corrective was due to operator error, with control panel lighting a contributing factor.
The inspector verified temporary of the lighting condition at the controller.
The general operator attention to detail was addressed in NRC report 85-09 and associated enforcement, for licensee action.
LER-84-115, RPS Actuation - IRM Hi Flux (Failure of feedwater control valve operator supply air tubing.)
The inspector witnessed the failed tubing and some of the activities in progress to investigate and correct the installation.
LER-84-117, Leak Detection Initiated RHR System Isolation The inspector verified the implementation of licensee corrective actions including posting of warning labels at the leak detection system panels in the control room.
LER-84-124, Reactor Scram (Low reactor water level)
LER-85-007, Reactor Scram (Inadvertent actuation of slave relay)
Inspection of circumstances of this item are discussed in Paragraph 7.a of this report, and special inspection report 85-0 ~i P
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LER-85-008, Diesel Generator Output Voltage I,ow Inspection of circumstance of this item are discussed in Paragraph
of this report, and special inspection report 85-09
'ER-85-011, Pressure Boundary Leakage (Socket welds)
(OPEN) The resident inspector was notified of this event at home and arrived on-site within about an hour to perform an immediate unannounced inspection of the conditions of the two socket welds in the containment drywell. The low leakage rate conditions observed were as subsequently described by the licensee in the LER.
The inspector did examine original fabrication records for the welds (RHR-899-48-FW-1 and RFW-419-4-FW-10)
and confirmed that quality control inspections had been performed of the completed welds,
'ncluding accepted liquid penetrant examinations.
Both socket welds were removed intact by the licensee, for metallographic examination.
This item is open pending review of the licensee's examination results and generic considerations.
9.
, Licensee Actions On Previous NRC Ins ection Findin s (
The inspectors reviewed records; interviewed personnel, and inspected plant conditions relative to licensee'actions on previously identified inspection findings:
a
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(Open) Violation (84-18-03) - Independent verification of systems returned to service after maintenance or surveilla'nc'e.tests.
On February 14 the inspectors met with the Electrical Supervisor and Instrument Supervisor to discuss the status of procedure revision activities in progress to clarify independent verification requirements.
They informed the inspectors that a review was to be completed by February 28 to deter'mine which procedures.under their cognizance would require revisions to reflect current pr'actices in independent verification.
As an interim measure, pending full revision of each such procedure, temporary procedure deviations would be approved and issued for any procedures requiring the addition of steps to reflect independent verification. The electrical supervisor also informed the inspectors that a shop meeting was held to inform all electricians that any jumpers used in the contiol room are to be obtained from the Shift Manager only.
Procedure 1.3.9 will be reviewed to avoid misinterpretation of apparently conflicting instructions.
This item remains open pending review of completed licensee actions.
10.
Mana ement Meetin The inspector met with the Plant Manager approximately weekly during this period, to discuss inspection finding status.
Principal inspection summary meetings were held as discussed in NRC inspection report 85-0 ~
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