IR 05000344/1979008
| ML19241C199 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 05/16/1979 |
| From: | Malmros M, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19241C193 | List: |
| References | |
| 50-344-79-08, 50-344-79-8, NUDOCS 7907300135 | |
| Download: ML19241C199 (7) | |
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U. 5. NCcLEAR IZCULAN ET CCHMI3 SIC 3 CTTICE OF INSFECION AfD ENFCRCDODC
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REGION Y
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Xsport No. 50-344/79-08
,_7 Dockat No.
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I,tcenses :
Portland General Electric Cos:pany
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121 S. W. Salmon Street Portland Oregon 97204 !
Facility Name:
Trojan
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Inspection at:
Rainier. Gregon Inspeccion e ucted:.
April 2-30, 1979 N
' LubV IG{71 Ins pectors :
M. H. Malmros, Resident Reactcr Inspector Date signed
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Data signed
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Date Signed
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Approved 3y:
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0. M. Starnberg. Chief,1teactor Project Section 1
' D*** Sisn'd Reactor Operations and Nuclear Suppcrt Branch Surve ry :
Inspection _o_n, Acril 2-30,1979 (Report No. 50_344/79-C8)
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Areas Inspectec:
Routine inspections oy tne Resident inspector of plant
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operations',' pnysical protection, surveillance testing, calibration.
procurement, rey!ew and audit, new fuel receipt inspections. and followup
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on licensee event reports and previously identified items. The inspection _.
involved 71 inspector-hours by the NRC Resident Inspector.
Results: No deviations were identified. One apparent item of non-
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compliance (infraction - failure to perfom technical specification surveillance. Paragraph 2) was identified as related to facility operation.
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DETAILS
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Persons Contacted
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- B. D. Withers Plant Superintendent
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- F. H. Lamoureaux. Assistant Plant Superintendent
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R. P. Barkhurst Operations Supervisor
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0. L. Bennett, Instrument and Control Supervisor
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C. J. Flening, Administrative Supervisor D. F. Kielblock. Training Supervisor W. S. Orser. Engineering Supervisor
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J. C. Perry. Administrative Engineer
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L. W. Quinn, Chemistry Supervisor
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J. D. Reid. Quality Assurance Supervisor (Acting)
C. A. Olmstead. Maintenance Supervisor T. D. Walt, Radiation Protection Supervisor The inspector also interviewed.and talked with other licensee
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en:ployees during the course of the inspection. These included snift supervisors, rr'tetor and auxiliary operators, maintenance personnel, plant technicians and engineers, and quality assurance personnel.
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- Denotes those attending the exit interviews.
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2.
Plant Ooerations
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a.
Facility Logs and Coerating Records
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The inspector examined the log entries contained in the control room log and the shift supervisor's log for facility operations performed during April,1979. The log entries were found to
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have been made consistent.with the requirements of the facility
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administrative orders and to accurately reflect the operational status of the facility.
Facility logs were reviewed by appli-
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cable staff members and operating orders issued by the operations supervisor did not conflict with the intent of the technical specification requirements. Sufficient inforr.ation was contained in the control room log and the shift superviscr's log to identify potential problems and to verify compliance with technical specification reporting requirements and limiting conditions for operation.
During the review of the control rocm los on April ll,1979, the inspector found that no entry existed to indicate that a surveillance test required by Technical Specification 3.8.1.1 had been performen to verify the operability of the East Emergency Diesel Generator within one hour following the 5513CS ga c, 7 2 n,
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removal of the West Emergency Diesel Generator for maintenance purposes.. Discussion with. the-operator revealed that the
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operator had failed to perform the. test as required. Facility v.
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procedures clearly require the performance of the surveillance test and a review by.the inspector of facility records found that proper tasting of the Emergency Diesel Generators under similar conditions had been performed as required by Technical
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Specification 3.8.1.1 and properly recorded in the control m
room log. A new facility procedure. AD-3-14. " Safety-Related Equipment Outages" was issued on April 24, 1979, which ensures the proper scheduling and performance of surveillance tests on redundant equipment before removing safety-related equipment from service.
It is the conclusion of the inspector that this itera of noncompliance to Technical Spec'fication 3.8.1.1 was
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attributable to personnel error and cna
'he issuance of A0-3-14 should preclude the recurrence af a sic 11ar situation.
The licensee intends to sutrait a licensee event eport describing this event and the corrective 5: tion taken.
b.
Facility Tour and Observation of Operations Tours of the facility were rade by the inspector in the control building, reactor auxiliary ailding, fuel building, intake f
structure, and the turbine b ilding.
During the tours, assess-
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ments of equipment and plant conditions were raade with the
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following observations:
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(1)
Instrumentation for conitoring the status of the plant was operating.
(2) Radiation controls were properl'y established.
(3) Piping systems in operation did not show any signs of excessive vibration or leakage.
(4) Detailed system alignment and operability of the auxiliary feedwater system, enntainment spray system and the liquid radioactive waste system were verified by tne inspector.
(5) Control room observations verified that the facility manning was proper and discussions with shift supervisors and control operators revealed that they were cognizant of the effect of annunciated alarms on plant operations.
Shift turnovers were found to be pe-forraed in accordance w1th the administrative orders and good watchstanding.
(6) Routine monitoring of facility liquids for gross radio-activity was observed by the inspector. The samples were analy:ed consistent with facility prtcedures.
(7) The facility tripped from approximately 85t of fu~il power on April 14, 1979, when the feedwater flow controller for the
'A" steam generator causet' a 10-10 steam generator
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reactor shutdown. Following repairs the facility was
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returned to normal power operation within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
During the preparations for startup the rain steam isolation valves (MSIV's) failed to activate from the
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open to.the shut position during the perfomance of the
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surveillance test to determine valve actuation time from
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tho open to the shut position. Adjustment to the valve packing freed the valves and acceptable valve operation was attained. The failure of the MSIV's to shut was promptly reported to che NRC and a report of the incident will be submitted by the licensee.
c.
Licensed Goerator Meeting On April 19. 1979. representativet from the NRC directly briefed licensed fact ity operators on the significant aspects of the Three Mile Island reactor incident and explained the concerns expressed in I.E. Bulletin No.79-06A issued to Westinghouse nuclear power plants.
On April 25.1979. the inspector held a sir.:1lar meeting for the licensed operators not able to attand the meeting on April 19. 1979.
One item of noncompliance was identified as described above (Iten a).
No deviations were identified.
3.
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Based on discussions with licensee representatives, observations.
and examinations of facility procedures, the inspector verified that the measures mployed for the physidal protection of the facility were consistent with the requirernents of the physical security plan, applicable administrative orders, and regulacry requirements.
Specific aspects of physical protection examined by the inspector included the following:
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a.
Protected area and vital area barriers were verified to be properly closed and locked.
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b.
Personnel provided access to the protected and vital areas were properly authorized. identified and badged.
Personnel.
vehicles, and pectages were searched as required by the physical security plan.
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Escorts were provided for personnel and vehicles when requirtd inside the protected area.
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The security organization for each shift was found to be properly organi:ed and manned.
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Shift turnover, shift routines, and cocinunications were accoc>-
plished in accordance with the requirements of the physical
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security plan and applicable administrative orders.
No items of noncocpliance or deviations were identified.
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4.
- Surveillance Testino The inspector observed the surveillance testing of contairment vertical tendons, facility batteries, and core power distribution.
Observations rade by the inspector included the following:
a.
The test prerequisites were mat.
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Applicable limiting conditions for operation were met.
The requirements of the test procedure were adhered to by the c.
personnel perfonning the test.
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The test was performed by qualified personnel.
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The test results were reviewed by the licensee and found to be within the acceptance criteria specified in the technical specifications.
No items of noncompliance or deviations were identified.
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Followup on Previous Insoection Findings The following item was examined by the inspector with the results indicated.
(79-07-01, closed) The licensee revised facility procedure, POT 5-1, to include the revised surveillance testing requirer:ents for the auxiliary feedwater pumps as prescribed to license amendment No. 35.
No items of noncompliance or deviations wert identified.
6.
Licensee Event Reoort (LER) Followup T:
-ircumstances and corrective action described in LER No. 79-02 regading the surveillance testing of the automatic isolation feature of the control rocm ventilation system were examined by the inspector.
The inspector verified that manual schedules were prepared to assure that surveillance tests on all facets of the control room ventilation system will be accomplished at the required testing frequency.
The LER had been reviewed by the licensee and was sutmitted to the NRC within the required reporting interval.
No items of noncompliance or deviations were identified.
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Procurenent l_ _ _._
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The inspectorYu~rdi the licensee's warehouse facility to verify tnat safety-related material and spare parts were being handled, stored, and identified in accordance with the requirements of the licensee's quality assurance procedures.
The inspector verified the following: ~.
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Safety-related nEterial and spare parts received onsite had a.
been inspected by qualified personnel.
b.
Records of receipt inspections were examined and found to be complete.
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Storage and packaging requirements were defined in the purchase requisit!cn and were being met during the storage of the applicable items.
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Preventive maintenance of stored items as applicable, was being performed by warehouse personnel.
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Material was identified to pemit traceability to on-file quality certification documents.
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Limited shelf life items were identified and controlled.
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No itens of noncompliance or deviations were identified.
8.
Receiot of New Fuel
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Based on an examination o facility procadures and direct obser-vation of new fuel handling activities, the inspector verified that
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the - eceipt of new fuel was perfont,ed consistent with regula*ary requirenents and facility procedures.
Observations by the in-spector included the following:
a.
The receipt of new fuel was perfomed in accordance with the procedural requirements described in Volume 8 of the Plant Operating Manual, " Fuel Handling Procedures."
b.
Shipping containers were received with the seals intact and were found free of any damage due to handling during transit.
c.
Fuel assemblies were removed from the containers, inspected and stored in the new fuel storage racks.
d.
Each fuel assembly was identified by an assembly serial nw.ber and a fuel cycle identification nu:nber.
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No deficiencies have been identified in the new fuel received at the site.
No items of noncompliance or deviations were identifie.
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Calibration
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The licensee's program for the' calibration of test and measuring equipent was examined by the inspectdb.
The rec:rds of several instrtsnents used.as standards for the calibration of plant in-
. strtsnen*2 tion were r* viewed and:found to accurately document the calibration status of the test: equipment.
For each test instrt..nent the inspector verified that the calibration f*equency had been met.
the accuracy of the calibration was traceable to the National Bureau of Standards and that the equipment was properly stored and controlled in accordance with facility procedures.
No items of noncompliance or deviations were identified.
10. Review and Audit The inspector attended a Plant Review Board meeting on April 23, 1979. as a nonparticipant to observe the conduct of this meeting.
The inspector found the meeting to have been conducted in accordance with the applicable technical specification requirements pertaining to mem.bershi,2 qualifications, quorum and the review process.
No iteens of noncompliance or deviations were identified.
11. Exit Interview The upector rnet with licensee representatives (denoted in Para-graph 1) on April 6.13. 20. and 30.1979.
During these meetings the inspector sur.arized the scope and findings of the inspection.
The apparent item of noncompliance discussed in Paragraph 2 was discussed.
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