IR 05000344/1978025
| ML19263B885 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/13/1978 |
| From: | Malmros M, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19263B884 | List: |
| References | |
| 50-344-78-25, NUDOCS 7901250017 | |
| Download: ML19263B885 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
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REGION V
Report No. 50-344/78-25 Docket No. 50-344 License No.
tiPF-1 Safeguards Group Licensee: Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Facility Name:
Trojan Inspection at:
Rainier, Oregon Inspection c ducted:.,floVember 1-9, 22-30 and December 1, 1978 u
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Inspectors:
M. H. Malmros, Resident Rea tor Inspector
' Dat'e Signed Date Signed
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Date Signed N E %%
l 13 bef Approved By :
D.M.Sternberg, Chief,'hclearSupportBranch Rejctot Project Section 1
' Date Signed i
Reactor Operations and t Sutomary :
Inspection on tiovember 1-9, 22-30 and December 1,1978 Report flo. 50-344/78-25 Areas Inspected:
Routine inspections by the Resident Inspector of plant operations, maintenance, calibration, security, radiation protection operations, and other specific activities independently selected by the inspector. The inspection involved 50 inspector-hours by the f4RC Resident Inspector.
Results: tio items of noncompliance or deviations were identified.
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DETAILS
1.
Persons Contacted
- B. D. Withers, Plant Superintendent
- F. H. Lamoureaux, Assistant Plant Superintendent
- R. P. Barkhurst, Operations Supervisor D. L. Bennett, Instrument and Control Supervisor C. J. Fleming, Administrative Supervisor
- W. S. Orser, Engineering Supervisor
- J. C. Perry, Administrative Engineer L. W. Quinn, Chemistry Supervisor
- J. D. Reid, Quality Assurance Supervisor (Acting)
D. J. Thompson, flaintenance Supervisor (Acting)
- T. D. Walt, Radiation Protection Supervisor The inspector also interviewed and talked with other licensee employees during the course of the inspection.
These included shift supervisors, reactor and auxiliary operators, maintenance personnel, plant technicians and engineers, and quality assurance personnel.
- Denotes those attending the exit interviews.
2.
Plant Operations a.
Facility Logs and Operating Records The inspector examined the log entries contained in the control room log and the shift supervisor's log for facility opera-tions performed during November 1978.
The log entries were found to have been made consistent with the requirements of the facility administrative orders and to accurately reflect the mode 5-cold shutdown status of the facility.
Facility logs were reviewed by applicable staff members and operating orders issued by the operations supervisor did not conflict with the intent of the technical specification requirements.
Sufficient information was contained in the control room log and the shift supervisor's log to identify potential probleus and to verify compliance with technical specification reporting requirements and limiting conditions for operatio.
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b.
Facility Tour and Observation of Operations Tours of the facility were made by the inspector in the con-trol building, reactor auxiliary building, fuel building, intake structure, and the turbine building.
During the tours, assessments of equipment and plant conditions were made with the following observations:
(1)
Instrumentation for monitoring the cold shutdown status of the plant was operating.
(2) Radiation controls were properly established.
(3) No conditions here observed that represented a fire hazard or personnel safety hazard.
Fire protection equipment was found operable.
(4) Piping systen r for those systems in operation did not contain fluid leaks or show evidence of excessive pipe vibrations.
(5) Detailed system alignment and operation were verified for the radiation monitoring systems and the safety injection system.
Compliance with the limiting conditions for operation of the technical specifications for mode 5 operations was verified for these systems.
(6) 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 a.1nunciated alarms on plant operations.
Shift turnovers were found to be performed in accordance with the administrative orders and good watchstanding practices.
(7) Sampling of the reactor coolant system (RCS) and the spent fuel storage pool (SFSP) were observed.
The analysis of the RCS sample for pH, conductivity, boron, and gross radioactivity, and the analysis of the SFSP sample for boron were performed in accordance with the applicable facility procedures.
The results of the chemical analyses were within the acceptance criteria specified in facility procedures and the technical specifications.
No items of noncompliance or deviations were identifie..
3.
Physical Protection Based on discussions with licensee representatives, observations, and examinations of facility procedures, the inspector verified that the measures employed for the physical protection of the facility were consistent with the requirements of the physical security plan, applicable administrative orders, and regulatory requirements.
Specific aspects of physical protection examined by the inspector included the following:
a.
Protected area and vital area barriers were verified to be properly closed and locked.
b.
Personnel provided access to the protected and vital areas were properly authorized, identified and badged.
Personnel, vehicles, and packages were searched as required by the physical security plan, c.
Escorts were provided for personnel and vehicles when required inside the protected area.
d.
The security organization for each shift was found to be properly organized and manned.
e.
Shift turnover, shift routines, and communications were accom-plished in accordance with the requirements of the physical security plan and applicable administrative orders.
f.
Weapons qualification training and night familiarization training were conducted and proper records maintained.
fio items of noncompliance or deviations were identified.
4.
Maintenance Maintenance operations on the intake structure basin, process radiation monitoring system, and the radioactive waste processing system were witnessed by the inspector and verified to have been performed in accordance with established procedures and technical specification requirements.
During the examination of maintenance activities related to the above components or systems, the inspector made the following observations:
a.
Maintenance requests had been properly prepared to provide the required administrative approval prior to initiating the work.
b.
The maintenance was performed by qualified members of the maintenance organizatio.
c.
System tagging operations and plant status controls properly indicated the performance of the maintenance activities.
d.
Applicable limiting conditions for operation as specified in the technical specifications were met during the above main-tenance.
No items of noncompliance or deviations were identified.
5.
Calibration The calibration of plant instrumentation used in the local leak rate testing system was directly observed by the inspector.
The inspector verified that the calibrations were perforced in accord-ance with approved facility procedures by properly qualified personnel. Test equipment used during the calibration of the insttamentation was found to be in a proper calibration state and records showed that the calibration accuracy was traceable to the National Bureau of Standards.
No items of noncompliance or deviations were identified.
6.
Radiation Protection Operations The inspector examined various facets of the licensee's radiation protection program to verify compliance with technical specifi-cation requirements, regulatory requirements and facility procedural requirements. Activities examined and observations made by the inspector were as follows:
a.
Ins trumenta tion:
On November 27, 1978, the inspector toured the facility and examined radiation protection instruments in use to verify operability and currency of calibration.
Instruments examined included the following; process radiation monitors, area radiation monitors, continuous air monitors, friskers, portal monitors, and portable survey instruments.
Calibration status of each instrument was found current as indicated on affixed calibration labels.
Operability status was verified by direct observation of equipment operation and functional tests.
Battery operated instruments were verified to contain batteries that were in a proper state of charge.
b.
Exposure Control:
The exposure control requirements of three separate radiological work permits (RWPs) were verified for maintenance activities conducted inside the controlled areas.
Direct observation by the inspector verified that maintenance personnel complied with the dosimetry and clothing require-ments expressed in each RW.
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c.
Posting and Control _:
High radiation area access points were found to be properly posted and controlled as required by
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regulatory requirements.
The posting of Notices to Workers as required by 10 CFR 19 was verified by direct observation of the posted notices at applicable facility access points.
No items of noncompliance or deviations were identified.
7.
Items Identified by the Inspector During the course of the inspection, the following items were examined by the inspector to verify compliance to commitments made to the NRC or determine the status of safety-related modification activities.
a.
Spent Fuel Pool Storage Modification:
The inspector observed the performance of visual examinations and liquid penetrant testing of the new spent fuel storage racks as part of the licensee's program to prepare the racks for installation in the spent fuel storage pool.
Approved inspection procedures were used by properly qualified inspection personnel.
b.
Steam Generator Primary Nozzle Rings:
The inspector discussed with licensee representatives the installation of the steam generator primary nozzle rings; and the nondestructive exam-inations which were performed following the installation of the nozzle rings.
The licensee stated that liquid penetrant tests had been performed, but that records of the tests were not available onsite.
Copies of the test records will be obtained from the company that installed the nozzle rings during construction for examination by the inspector during subsequent inspections.
(50-344/78-25-01)
c.
Emergency Diesel Annunciator Modification:
The licensee commitment to the NRC to provide for an annunciator in the control room which indicates that the emergency diesels are
"not ready for auto start" was discussed with facility engi-neering personnel. The design change (RDC-78-08) was being processed by engineering and the licensee anticipates instal-iing the modification by the commitment date of December 31, 1978.
The inspector will verify the completeness of the modification during subsequent inspections.
(50-344/78-25-02)
No items of noncompliance or deviations were identified.
8.
Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) on November 9 and December 1, 197f..
During these meetings, the inspector summarized the scope and findings of the inspection.