IR 05000397/1987030
| ML17279A788 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/14/1988 |
| From: | Bosted C, Johnson P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17279A787 | List: |
| References | |
| 50-397-87-30, NUDOCS 8802010149 | |
| Download: ML17279A788 (13) | |
Text
U. S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report No:
Docket No:
Licensee:
50-397/87-30 50-397 Washington Public Power Supply System P.
0.
Box 968 Richland, WA 99352 Facility Name:
Washington Nuclear Project No., 2 (WNP-2)
Inspection at:
WNP-2 Site near Richland, Washington Inspection Conducted:
No em r
December 13, 1987 Inspector:
C.
Approved by:
p.
H. J Reacto ed, Senior Resident Inspector nson, Chief rojects Section
Date
'gned I/(ljgg Date Signed Summary:
Ins ection on November 6 - December
1987 50-397/87-30 Areas Ins ected:
Routine inspection by the resident inspector of control room operations, engineered safety feature (ESF) status, surveillance program, maintenance program, licensee event reports, special inspection topics, and licensee action on previous inspection findings.
During this inspection, Inspection Procedures 25026, 30702, 30703, 35701, 61726, 62703, 71707, 71709, 71710, 71881, 92700, 92701, and 92703 were covered.
Results:
No violations or deviations were identified.
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DETAILS Persons Contacted L. Oxsen, Assistant Managing Director for Operations R. Glasscock, 'Director, Licensing and Assurance C.
Powers, Plant Manager
"J. Baker, Assistant Plant Manager
"R. Corcoran, Operations Manager
"K. Cowan, Technical Manager
- D. Feldman, Plant guality "Assurance Manager R. Graybeal, Health Physics and Chemistry Manager J.
Landon, Maintenance Manager
- J. Peters, Administrative Manager P.
Powell, Licensing Manager
"J.
Harmon, Assistant Maintenance Manager S.
McKay, Assistant Operations Manager The inspector also interviewed various control room operators, shift supervisors and shift managers, engineering, quality assurance, and management personnel relative to activities in progress and records.
"Attended the Exit Meeting on December 17, 1987.
Plant Status At the start of the inspection period, the plant was operating at nearly 98K full power.
The plant operated at this level until November 9, when power was reduced to approximately 40X to perform several required surveillance activities and to exchange control rod sequences.
At this time, a freeze seal was attempted on the 'C'ondensate filter demineralizer lines.
The freeze seal would have allowed the changing of the resin trap and inspection of the filter demineralizer; however, after several attempts to freeze the 14-inch line, the effort was stopped and the 'C'ilter demineralizer was restored to normal operation.
The inability to produce a freeze seal was evaluated by the plant technical group.
During the power reduction, the 'B'ondensate booster pump was secured to change a leaking shaft seal.
After the seal was changed, it was discovered that the pump and motor were misaligned.
Efforts to realign the pump and motor limited the power increase to approximately 92K on November ll.
The pump was aligned and power was raised to 98K on November 12.
Power levels continued near this level until December 6, when the reactor was shut down for a scheduled three-day maintenance period, as further discussed in paragraph 15.
On November 26, a safety relief valve lifted during an instrumentation surveillance.
This item is discussed further in paragraph 12.
On December 10, the plant was restarted and taken critical at 3:49 pm.
Plant restart was delayed for a day due to a main condenser tube leak which was discovered when main circulation water flow was reestablished.
The plant was heated up and the generator was synchronized to the grid at 3:21 am December ll.
Power was raised in accordance with the fuel
preconditioning limits to 86K on December ll.
Plant power was reduced on December 13 to troubleshoot a potentially sticking main turbine governor valve.
Power was reduced to 20K and the main turbine was taken off line for the test.
Number 4 governor valve was found to sticking when the valve was above 50K open:
normal valve position for full power operation is approximately 12-15K open.
The power level was returned to the 80K level at the end of the reporting period while the sticking governor valve was evaluated.
3.
Previousl Identified NRC Ins ection Items The inspector reviewed records, interviewed personnel, and inspected plant conditions relative to licensee actions on previously identified inspection findings:
Closed Followu Item 397/87-01-01:
Procedural Com liance The licensee agreed to review several events for common cause and determined that additional emphasis was needed on procedural compliance.
The inspector reviewed an interdepartmental memorandum from the Plant Manager to the plant staff that emphasized additional effort in the area of procedural compliance.
In addition, the inspector also reviewed trending data gathered for 1986 and 1987 by the guality Assurance department that showed overall plant procedure compliance.
A decreasing trend in procedure adherence problems was noted during the past year.
The inspector concluded that the plant was making progress in reducing these violations.
This item is considered closed.
4.
0 erational Safet Verification a.
Plant Tours The following plant areas were toured by the inspector during the course of the inspection:
Reactor Building Control Room Diesel Generator Building Radwaste Building Service Water Buildings Technical Support Center Turbine Generator Building Yard Area and Perimeter b.
The following items were observed during the tours:
(1)
0 eratin Lo s and Records.
Records were reviewed against Technical Specification and administrative control procedure requirements.
(2)
Monitorin Instrumentation.
Process instruments were observed for correlation between channels and for conformance with Technical Specification requirement o)
for conformance with 10 CFR 50.54. (k), Technical Specifications, and administrative procedures.
(4)
E ui ment Lineu s.
Valve and electrical breakers were verified to be in the position or condition required by Technical Specifications and Administrative procedures for the applicable plant mode.
This verification included routine control board indication reviews and conduct of partial system lineups.
(5)
E ui ment Ta in
.
Selected equipment, for which tagging requests had been initiated, was observed to verify that tags were in place and the equipment was in the condition specified.
(6)
General Plant E ui ment Conditions.
Plant equipment was observed for indications of system leakage, improper lubrication, or other conditions that would prevent the system from fulfillingits functional requirements.
(7)
Fire Protection.
Firefighting equipment and controls were observed for conformance with Technical Specifications and administrative procedures.
(8)
Plant Chemistr
.
Chemical analyses and trend results were reviewed for conformance with Technical Specifications and administrative control procedures.
(9)
~Securit
.
Activities observed are discussed in paragraph 9.
(10) Plant Mousekee in
.
Plant conditions and material/equipment storage were observed to determine the general state of cleanliness and housekeeping.
Housekeeping in the radiologically controlled area was evaluated with respect to controlling the spread of surface and airborne contamination.
(ll) Radiation Protection Controls.
Areas observed are discussed in paragraph 8.
No violations of NRC requirements or deviations were identified.
5.
En ineered Safet Feature S stem Walkdown Selected engineered safety feature systems (and systems important to safety)
were walked down by the inspector to confirm that the systems were aligned in accordance with plant procedures.
During the walkdown of the systems, items such as hangers, supports, electrical power supplies, cabinets, and cables were inspected to determine that they were operable and in a condition to perform their required functions.
The inspector also verified that the system valves were in the required position and locked as appropriate.
The local and remote position indication and controls were also confirmed to be in the required position and operable.
Accessible portions of the following systems were walked down on the indicated date ~Setem Diesel Generator Systems, Divisions 1, 2, and 3.
Date November 7, ll Hydrogen Recombiners Low Pressure Coolant Injection, Trains "A"
"B" and "C" November
November
Low Pressure Core Spray November 10, December
Reactor Core Isolation Cooling Residual Heat Removal, Trains
"A" and "B" December
December
Scram Discharge Volume System Standby Liquid Control System December
December
No violations of NRC requirements or deviations were identified.
6.
Surveillance Testin a.
Surveillance tests required to be performed by the Technical Specifications (TS) were reviewed on a sampling basis to verify that:
1) the surveillance tests were correctly included on the facility schedule; 2) a technically adequate procedure existed for performance of the surveillance tests; 3) the surveillance tests had been performed at the frequency specified in the TS; and 4) test results satisfied acceptance criteria or were properly dispositioned.
Portions of the following surveillances were observed by the inspector on the dates shown:
Procedure 7.4.4.7 7.4. l. 3. 2 9. 3. 11 7. 4. 8. 2. 1. 20 7. 4. 3. 3. 1. 6 7.4. 12 7. 4. 3. 1. 1. 4 7. 4. 11. 2. l. 2. 2 Descri tion Main Steam Isolation Valve (MSIV) Closure Tests Control Rod Drive Scram Timing Control Rod Sequence Exchange Weekly Battery Test Low Pressure Core Spray (LPCS) Minimum Flow Reactivity Anomaly Average Power Range Monitor (APRM) 'F'alibration Monthly Gas Sample Dates Performed November
November
November
November
November
November
December
December
C..
On November 18, during the performance of a surveillance test for Technical'pecification (TS) 4.8.2. l.a.2, Safety Related Battery Voltage Test, the technician erroneously checked a step in the procedure as satisfactory when it was not.
The procedure required that the 250 VDC battery charger was to be equal to or greater than 258 volts; the technician read and recorded the voltage as 255 volts.
Following the test completion, the technician informed the shift manager that the test was satisfactory.
At 5:31 a.m., the Shift Manager signed the completed surveillance test and the document was sent to the maintenance shop for review.
The electrical supervisor reviewed the surveillance test at approximately 7:30 a.m.,
noted that the 250 volt battery charger was less than the TS requirement, and notified the Shift Manager.
The charger was reset to the required voltage at 8:21 a.m.
The TS 3.8.2 action statement requires that the battery and/or charger be operable or be restored within two hours or that the plant be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
During fol lowup of this event, the inspector became aware of a difference in opinion among members of the plant staff regarding the time when the TS action statement should be entered following an unsatisfactory surveillance test.
One opinion was that the time should start with the Shift Manager's signing the completed surveillance.
Other staff members were of the opinion that the time of discovery was when the craft supervisor made his review, although PPM l. 5. 1, "Technical Specification Surveillance Testing Program,"
did not provide specific guidance.
The inspector also questioned several shift managers regarding the restoration of equipment to service following surveillance testing.
They all stated that when the Maintenance Department was completed with a surveillance test and the Shift Manager signed off the work request, equipment removed from service for the test was considered to be operable.
The issue of when to declare equipment operable or inoperable will be examined further during the next report period.
(87-30-01)
Licensee actions to provide additional staff attention to the proper performance of surveillance activities (also refer to paragraph 12)
will be evaluated during future inspections (87-30-02).
No violations of NRC requirements or deviations were identified.
7.
Plant Maintenance During the inspection period, the inspector observed and reviewed documentation associated with maintenance and problem investigation activities to verify compliance with regulatory requirements, compliance with administrative and maintenance procedures, required gA/gC involvement, proper use of safety tags, proper equipment alignment and use of jumpers, personnel qualifications, and proper retesting.
The inspector verified reportability for these activities was correct.
The inspector witnessed portions of the following maintenance activities:
Descri tion Dates Performed
Control Rod Maintenance per MWR AV 1480 Control Rod Drive Timing per MWR AT 1502 Seal replacement, Condensate Booster Pump 2B per MWR AT 0572 Replacement of Condensate Valve V-2318 per MWR AT 1038 Replacement of Condensate Valve V-231D per MWR AT 1976 Inspection of condensate filter deminerializers A&C per MWR AT1446 Removal of Reactor Building Outside Air (ROA) Fans A and B per MWR AT 194 Replacement of Main Generator
, Bus Duct per MWR AT 1535 Changing of Battery Cells per MWR AT 1539 November
November 9, December
November 10,
December
December
December
December
December December
No violations of NRC requirements or deviations were identified.
8.
Radiolo ical Practices The inspector periodically observed radiological protection practices to determine whether the licensee's program was being implemented in conformance with facility policies and procedures and in compliance with regulatory requirements.
The inspector verified that health physics supervisors and professionals conducted frequent plant tours to observe activities in progress and were generally aware of significant plant activities, particularly those related to radiological conditions and/or challenges.
ALARA consideration was given to each job that was observed.
The Drywell was toured by the inspector during the final Senior Reactor Operator (SRO) inspection on December 10.
No major concerns were identified; several small housekeeping items were discussed with plant management.
Material conditions in the Drywell were noted to be acceptable for plant operation.
No violations of NRC requirements or deviations were identified.
9.
Ph sical Securit The inspector periodically observed security practices to ascertain that the licensee's implementation of the security plans was in accordance with site procedures.
The inspector observed that the number of guards was adequate for the requirements of the security plan; that the search equipment at the access control points was operational; that the protected area barriers were well maintained without breaks; and that personnel allowed access to the protected area were badged and monitored and the monitoring equipment was functional.
Night illumination inside the protected area was observed and obstructions were lighted adequately.
Surveillance equipment was also observed during this inspectio No violations of NRC requirements or deviations were identified.
10.
Licensee Event Re ort LER Followu The following LER associated with an operating event was reviewed by the inspector.
Based on the information provided in the report it was concluded that reporting requirements had been met, root causes had been identified, and corrective actions were appropriate.
The below LER is considered closed.
LER NUMBER DESCRIPTION 84-91-01 RHR Isolation and Reactor Low Water Level Trip The following Licensee Event Reports were followed up at the time of occurrence by the inspector.
The short term corrective actions have been accomplished and the long term corrective actions will be followed by the routine inspection program.
These LERs are considered closed.
LER NUMBER 87-18-00 87-19-00 87-20-00 87-22-00 87-23-00 DESCRIPTION Reactor Scrams Due to Turbine Control Valve Fast Closure Reactor Scram Due to Component Failures Reactor Scram Caused by Equipment Failure Low Reactor Level Scram Caused by.Power Breaker Trip Which Caused a Loss of Feedwater RPS Component Surveillances Not in Compliance with Technical Specifications No violations of NRC requirements or deviations were identified.
ll.
Review of Periodic and S ecial Re orts Periodic and special reports submitted by the licensee pursuant to Technical Specifications 6.9. 1 and 6.9.2 were reviewed by the inspector.
This review included consideration of report content as required to be reported by NRC requirements; test results and/or supporting information consistent with design predictions and performance specifications; and the validity of the reported information.
Within the scope of the above, the following reports were reviewed by the inspector.
o Monthly Operating Report for October 1987.
o Monthly Operating Report for November.1987.
No violations of NRC requirements or deviations were identified.
12.
Safet Relief Valve 0 enin Durin Test On November 26, during the performance of a Technical Specification Surveillance (TSS),
a personnel error caused one safety relief valve (SRV) to be opened twice.
TSS 7.4.3. 1. 1.50
"RPS Isolation and RCIC-Reactor Water Level Div II" required that an ohmmeter be placed on
terminals EE-1 and EE-2 in instrument rack H22-P026.
Due to an error, the technician placed the instrument leads on terminals FF-1 and FF-2, which opened safety relief valve (SRV) MS-RV-2D.
The technician manipulated the instrument and caused the SRV to be opened a second time.
The valve was opened the first time for approximately 10 seconds, and the second time for approximately six'inutes.
SRV HS-RV-2D had an acoustic flow monitor device installed, but the instrument card had been deactivated because spurious alarms were being generated by a defective sensor.
A Technical Specification amendment had been granted on October 16 that allowed this monitor to be deactivated.
When the SRV opened, the operating crew became aware of the plant changes by other alarms in the control room.
A correct diagnosis of the problem was made after the second opening and the control room operator manually shut the valve.
The shift manager performed a root cause analysis of the immediate concerns and a formal root cause was in progress by the maintenance department at the end of the reporting period.
As a result of the SRV being opened, the Suppression Pool temperature increased by approximately
F and level increased approximately
inches.
The temperature and level were restored by the operator placing the 'B'HR system in the suppression pool cooling mode of operation.
The acoustic monitor was repaired and restored to service during the December 7 maintenance outage.
Licensee actions to ensure improved attention to surveillance test activities will be reviewed as part of followup item 87-30-01 (paragraph 6.c).
No violations or deviations were identified.
NRC Bul 1 etin 87-02 Fasteners On November 23 and 24, in response to NRC Compliance Bulletin 87-02, the inspector, along with members of the plant's engineering and technical staff, selected a sample of fasteners that were used in the plant's systems.
The technical staff determined the types of fasteners used in the plant and then the sample was based on these types.
The sample items, taken from stock used during construction and in present day operations, were located in the various site warehouses.
The Bulletin required that a sample be made of ten safety and ten non-safety fasteners and once selected, the fasteners be sent to an independent laboratory for chemical and physical examinations.
In addition to the samples selected, the inspector was made aware of some specially marked fasteners that were of interest to NRR.
During the inspection of fasteners in the warehouses, the inspector identified two bolts with the special head markings of "M" and "KS" which were included in the sample.
At the close of the inspection period, the samples were being tested at the laboratory.
The inspector also reviewed the licensee's warehouse receipt inspection program and material documentation review process associated with the above fasteners, which appeared to be in accordance with plant procedure No violations or deviations were identified.
Sto Work Order Issued b
ualit Assurance On November 18, the equality Assurance (gA) department issued a "Stop Work Order" to the plant staff based on discrepancies found in the "Materials Management System (MMS)".
The gA organization identified several discrepancies in the program used to determine the suitability of replacement spare parts in safety-related equipment.
The gA Stop Work Order was issued as a precaution following an audit of the spare parts issuance controls and directed that the computer data base not be used as a mechanism to determine the suitability of replacement parts for safety-related equipment.
Errors were identified in the computer data base used by the MMS system to identify safety related spare parts.
No actual spare parts were known to have been issued in error, but the possibility existed for this occurrence.
The=licensee's respective departments accepted this order and were working towards bringing their procedures and computer data base into conformance with gA approved standards.
The inspector is following the ongoing resolution to this order.
(87-30-03)
No violations or deviations were identified.
Scheduled Maintenance Outa e
A three-day maintenance outage was scheduled for December 7 through December 10.
A variety of items were included on the schedule with the most significant items being the correction of condensate filter deminerializer (F/D) problems.
The 'B'/0 could not be backwashed and precoated and the 'C'/0 resin trap was becoming plugged within several days of resin renewal.
In addition to the F/D problems, several steam leaks in the turbine building had the potential to become serious.
Flow isolation valves were replaced on the 'B', '0',
and 'E'/Ds and five of the six F/Ds were inspected for loose resin septa.
Three septa were found to be loose in the 'C'/D, and another 12 were found not to be fully seated and locked.
Three resin traps were also changed out in an effort to reduce the differential pressure drop across the F/Ds and resin traps.
A failure of Reactor Building Air Supply Fan lA motor and high vibration on the lB fan caused these fans to be overhauled during this outage.
The
- bearings on both fans and motors were replaced.
The turbine building steam leaks were repaired and at the conclusion of the outage a condenser tube leak was discovered.
An extra day was added to the outage while the cause of the leak was determined and corrected.
The leak was identified as a previously plugged tube that had become unplugged.
Four plastic plugs had become loose and were replaced.
The licensee told the inspector that this design would be reviewed in light of this experience.
The inspector followed the work schedule and noted that the maintenance items were worked in accordance with the priority 'established and that the amount of accomplished work was higher than expected.
The inspector
also noted that senior plant and executive levels of management were in the plant following plant maintenance activities and that frequent internal management meetings were held within the plant management staff to keep all departments aware of difficulties encountered during the outage.
No violations or deviations were identified.
The inspector met with licensee management representatives periodically during the report period to discuss inspection status, and an exit meeting was conducted with the indicated personnel on December 17, 1987.
The scope of the inspection and the inspector s findings, as noted in this report, were discussed and acknowledged by the licensee representatives.