IR 05000344/1979007
| ML19242C062 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/23/1979 |
| From: | Malmros M, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19242C046 | List: |
| References | |
| 50-344-79-07, 50-344-79-7, NUDOCS 7908090695 | |
| Download: ML19242C062 (6) | |
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U. S. NUCLEAR REGULATORY Co:OiISSION OFFICE OF INSPECTION AND ENFORCEMEhT
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REGION V
50-344/79-07 Report No.
50-344 License No.
flPF-l safeguards croup Docket No.
Licensee:
Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Facility Narre:
Trojan Inspection at:
Rainier, Oregon Inspection conducted:
liarch 1-30, 1979 Inspectors:
At9 C,_
h13 /'79 w
11. H./Jialmros, Resident Reactor Inspector Date Signed Date Signed
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N Date Signed 4!!23!7}
Approved By:
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D. ii. Sternberg, Chqf,jP,eactor Project Section 1, Date' Signed
Reactor Operations antnuclear Support Branch S urrma ry :
Inspection on March 1-30, 1979 (Report tio. 50-344/79-07)
Areas Inspected:
Routine inspections by the Resident Inspector of plant operations, maintenance, physical protection, surveillance testing, radioactive waste systems operation, training, modifications, and follow-up on previously identified items.
The inspection involved 84 inspector-hours by the NRC Resident Inspector.
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Results:
No deviations were identified.
The apparent items of non-compliance (infraction - failure to provide proper escort within the protected area; and deficiency - failure to maintain a record of access to a designated vital area - Appendix A) were identified as related to physical protection.
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DETAILS
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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 D. F. Kielblock, Training Supervisor
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W. S. Orser, Engineering Supervisor J. C. Perry, Administrative Engineer L. W. Quinn, Chemistry Supervisor J. D. Reid, Quality Assurance Supervisor (Acting)
C. A. Olmstead, Maintenance Supervisor T. D. Walt, Radiation Protection Supervisor K. A. Smith, Security Supervisor J. K. Aldersebaes, Resident Engineer 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 facilit/ operations perforred during March, 1979.
The log entries were found to have been made consistent with the requirements of the facility administrative orders and to accurately reflect the operational status of the facility.
Facility logs were reviewed by appli-cable staff members and operating orders issued by the operations supervisor did not conflict with the intent of the technical specification requirements.
Sufficient information was con-tained in the control room log and the shift supervisor's log to identify potential problems and to verify compliance with technical specification reporting requirements and limiting conditions for operation.
b.
Facility Tour and Observation of Operations Tours of the facility were made by the inspector in the control 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:
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Instrumentation for monitoring the status of the plant was operating.
(2)
Radiation controls were properly established.
(3) Piping systems in operation did not show signs of ex-cessive vibration.
(4) A packing leak on CV5655 was identified by the licensee on March 19, 1979.
This leak resulted in the release of approximately 560 gallons of reactor coolant in the vicinity of the valve.
The radioactivity associated with reactor coolant leakage through the valve packing was calculated to be substantially below the limits for release to the facade area of the plant.
(5) Detailed system alignment and operation of the service water system and the component cooling water system were verified by the inspector.
(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 annunciated alarms on plant operations.
Shift turnovers were found to be performed in accordance with the administrative orders and good watchstanding.
(7) Routine sampling of the steam generators and the spent fuel pool for gross beta-gamma radioactivity levels was observed by the inspector.
The samples were analyzed consistent with facility procedures.
(8) Recent amendments to the facility license have required the revision of certain facility procedures.
The in-spector verified that procedure revisions were being processed as follows:
Licensee Amendment flo. 36 - Requires revision to POT 5-1 which prescribes surveillance testing require-ments for the auxiliary feedwater pumps, (79-07-01).
License Amendment flo. 39 - Requires revision of the chemistry manual for the prescribed diesel fuel oil chemical acceptance criteria to the criteria specified in ASTM D975-78, (79-07-02).
flo items of noncompliance or deviations were identified.
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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 regult tory requirements.
Specific aspects of physical protection examined by the inspector are described below.
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.
The security organization for each shif t was found to be properly organized and manned.
d.
Shift turnover, shif t routines, and communications were accomplished in accordance with the requirements of the physical security plan and applicable administrative orders.
During the inspection, the inspector observed two items of non-compliance related to the physical security program.
These were discussed during the exit interview.
flo deviations were identified.
4.
Radioactive Waste Systems Operations _
The inspector examined the records associated with liquid effluent releases and gaseous effluent releases. The records for liquid releases during February,1979, and gaseous releases during the first calendar quarter of 1979 were examined and found to indicate that required sampling had been performed and that timely release approvals had been obtained.
Preparations for a liquid release on tlarch 28, 1979 were witnessed by the inspector and found to have been accomplished in accordance with approved facility procedures.
Instrumentation for monitoring the liquid and gaseous effluent releases was verified to be operational and in a current state of calibration at the time of the release.
flo items of noncompliance or deviations were identified.
SSCD.
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Surveillance Testing The inspector observed the surveillance testing of containment tendons, containment spray pumps, and core power distribution including the determination of the target axial flux dif ference.
Observations made by the inspector included the following.
a.
The test prerequisites were met.
b.
Applicable limiting conditions for operation were met.
c.
The requirements of the test procedure were adhered to by the personne1 performing the test.
d.
The test was performed by qualified personnel.
e.
The test results were reviewed by the licensee and found to be within the acceptance criteria specified in the technical speci fica tions.
In addition to the above surveillance tests, the inspector dis-cussed with licensee representatives the preparations being made for the conta"nment integrated leak rate test which is to be pet formed during the Spring maiatenance outage.
No items of noncompliance or deviations were identified.
6.
Maintenance Maintenance operations on motor operated valves, service air system, diesel driven fire pump, rod position indication system, and the area radiation monitoring 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 organization.
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 specification were met during the above main-tenance.
No items of noncompliance or deviations were identified.
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7.
Training The inspector reviewed records of operator participation in plant drills and casualties. The records indicate that the required drills and control manipulations of the reactor have been performed as prescribed in the operator requalification program.
flo items of noncompliance or deviations were identified.
8.
Spend Fuel Pool flodification Based on discussions with licensee representatives, examination of facility records and direct observation of work activities, the inspector verified that the modification to expand the spend fuel storage capacity was completed in accordance with regulatory require-men ts.
Observations made by the inspector included the following:
a.
The modification was performed in accordance with Request for Design Change (RDC) fio.76-114 with specific work activities prescribed in associated Detailed Construction Packages (DCP's).
b.
Inspections were performed by qualified oersonnel on the new fuel storage racks to verify conformance to design requirements.
Similarly, inspections were performed during the installation process to verify proper assembly and alignment of the fuel storage racks in the spent fuel pool.
c.
Drag tests using a dummy fuel assembly were performed to verify the dimensions and storage rack alignment.
d.
The balting of the racks was verified by inspection to have been performed in accordance with fastening and torquing requirements of the RDC.
e.
License conditions and technical specification requirements associated with the spent fuel pool were met throughout the modification process.
!10 items of noncompliance or deviations were identified.
9.
Followup on Previously Identified Items The following items were examined by the inspector with the results as indicated:
(79-04-02, Closed) The corrective action in the licensee's letter dated flarch 13, 1979, in response to a flotice of Deviation related to LER 78-26, was verified by the inspector.
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