IR 05000344/1979014
| ML19253B250 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/17/1979 |
| From: | Malmros M, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19253B248 | List: |
| References | |
| 50-344-79-14, NUDOCS 7910030731 | |
| Download: ML19253B250 (9) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Report No.
50-344/79-14 Docket No.
50-344 License No.
NPF-1 Safeguards Group Portland General Electric Company Licensee:
121 S. W. Salmon Street Portland, Oregon 97204 Facility Name:
Trojan Inspection at:
Rainier. Orecon Inspection conducted:
July 2-31,1979 Inspectors:
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'I L /1 19 M. H.94algrJA, ' R
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Date Signed
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Date Signed
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Approved By:
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D. M. Sternberg, Chief,> Reactor Project Section 1, Da'te Signed Reactor Operations and Nuclear Support Branch
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Sumary: Inspection on July 2-31, 1079 (Report No. 50-344/79-14)
Areas Inspected:
Routine inspections of plant operations, maintenance, physical security, surveillance testing, modifications, radiological waste operations, and followup on licensee event reports, IE Bulletins, and a Part 21 Report.
The inspection involved 90 inspector-hours by the NRC Resident Inspector.
Results:
No items of noncompliance or deviations were identified.
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RV Form 719 (7)
7910030 7 3 [
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DETAILS 1.
Persons Contacted
- B. D. Withers, Plant Superintendent
- F. H. Lamoureaux, Assistant Plant Superintendent R. P. Barkhurst, Operations Superviser D. L. Bennett, Instrument & Control Supervisor C. J. Fleming, Administe !.ive Supervisor D. F. Kielblock, Trainint Supervisor W. S. Orser, Engineering Supervisor J. C. Pe. ry, Administrative Engineer 11. k. Bell, Chemistry Supervisor J. D. Reid, Quality Assurance Supervisor (Acting)
C. A. Chead, Maintenance Supervisor 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 operations performed during July 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 applica-ble 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 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
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-2-the following observations:
(1)
Instrumentation for monitoring the status of the plant was operating.
(2)
Radiation controls were properly established.
(3)
Piping systems did not show any signs of excessive vibration or leakage.
(4)
Detailed system alignment and operability of the diesel fuel oil system and the boric acid transfer portion of the chemical and volume control system were verified by the 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 perforced in accordance wi:a the administrative orders and good watchstanding practice:
(6)
Routine sampling of the reactor coolant system for boron and strontium were observed by the inspector.
The liquid samples were analyzed consistent with facility procedures.
No items of noncompliance or deviations were identified.
3.
Surveillance Testing The inspector observed the surveillance testing of the centrifugal charging pumps, digital rod position indication system, and the design basis accident sequencers.
Reactor testing observed by the inspector included the monitoring of the core power distribution and target axial flux difference and the verification of the incore and excore detector calibration. For each of the surveillance tests, the following items were verified.
a.
The test prerequisites were met.
b.
Applicable limiting conditions for operation were met, c.
The requirement; of the test procedure were adhered to by the personnel performing the test.
d.
The test was performed by qualified personnel.
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-3-e.
The test results were reviewed by the licensee and found to be within the acceptance criteria specified in the technical specifications.
flo items of nonconpliance or deviations were identified.
4.
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 M ers 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 pl an.
Escorts were provided for personnel and vehicles when required c.
inside the protected area.
d.
The security organization for each shift was found to be properly organized and manned.
e.
Shif t turnover, shift routines, and coninunications were accomplished in accordance with the requirements of the physical security plan and applicable administrative orders.
fio items of noncompliance or deviations were identified.
5.
Radiological Waste Systems Operation The inspector examined the records associated with liquid effluent releases and gaseous effluent releases. The records for liquid and gaseous releases during June and July,1979, were examined and found to indicate that required sampling had been perform;d and that timely release approvals had been obtained. Liquid releases from the treated wast. monitor tanks during July 1979 were observed by the inspector and found to have been perfomed in accordance with approved facility procedures.
Instrumentation.for monitoring the liquid releases was 1C71 355
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u I-4-verified to be operational and in a current state of calibration at the time of the release.
No items of noncompliance or deviations were identified.
6.
Licensee Event Report (LER) Followup The circumstances and corrective action described in LER Nos. 79-07, 79-08, 79-09, 79-10, and 79-11 were examined by the inspector.
The inspector found that each LER had been properly reviewed by the licensee and reported to the NRC within the proper reporting interval. Corrective action for each event was as follows:
a.
LER 79-07: The hydraulic actuator for the feedwater isolation valve was disassembled and inspected. The actuator had failed
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to properly function due to a faulty pressure reducing valve.
The pressure reducing valve was repaired and adjusted.
The hydraulic actuator system was tested and the feedwater isolation valve was returned to an operable status.
b.
LER 79-08: The licensee reported that under certain postulated conditions the containment ventilation valves closure during a LOCA could not be assured. The specific details under which this condition exists were reported by the licensee to NRR by separate letter dated May 31, 1979. Until necessary design changes have been approved and modifications have been installed, the licensee has established appropriate administrative controls to keep the containment purge and exhaust valves shut during all plant operation in Modes 1-4.
c.
LER 79-09: The licensee reported that three transmitters, each in a different instrumentation system, were found out of calibration due to instrument drift.
The transmitters were recalibrated and each instrumentation system was verified to meet the set points prescribed in the technical specifications.
d.
LER 79-10: The licensee repaired the seats of the two valves which had caused the leakage rate for all valves and penetrations to exceed the technical specification limit.
Test results following repairs of the valves indicated that valve leakage was within limits.
e.
LER 79-11: The low-low level trip set points for the steam generators have been changed from 5% to 15% as recomended by the reactor supplier.
Facility procedures have been revised to reflect this change in set points.
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No items of noncompliance or deviations were identified.
7.
IE Bulletin Followuo IE Bulletin No. 79-10: The statistical data concernino the requalification proaram was forwarded to the NRC id the licensee as requested in the bulletin. The information provided by the licensee is accurately reflected in the records maintained by the Trainino Supervisor.
No further action is required by the licensee.
Copies of the bulletin and the response were available in the onsite files.
IE Bulletin No. 79-11-The information in the licensee's response to the bulletin was examined by the inspector and found to be accurately reflected in the as-built facility records and drawings.
The concerns expressed in the bulletin are not applicable to the facility since the overcurrent trip devices used in the electric circuit breakers for safety related systems do not use an air dashpot for settina the delay times of the overcurrent trip.
No further action is required by the licensee at this time.
Copies of the bulletin and the response were available in the onsite files.
No items of noncompliance or deviations were identified.
8.
Maintenance Mdintenance operations on the service water system, pressurizer instrumen-tation system, security alarm system, emeroency diesel aeneratino systen, and the chemical and volume control system were witnessed by the inspector and verified to have been performed in accordance with established proce-dures and technical soecification reauirements.
Durina the examination of maintenance activities related to the above systems, the inspector made the following observations:
a.
Maintenance request had been properly prepared to provide the required administrative approval prior to initiatina the work.
b.
The maintenance was performed by qualified members of the maintenance organization.
Safety-related equipment outage worksheets were prepared prior to the c.
removal of safety system components from service.
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d.
System taggina operations and plant status controls properly indicated the performance of the maintenance activities.
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-6-Applicable operability tests were performed upon return of the e.
safety-related component to an operable condition.
f.
Applicable limiting conditions for operation as specified in the technical specifications were met during the above maintenance activities.
No items of noncompliance or deviations were identified.
9.
Part 21 Report Followup The information and corrective action described in the licensee's letter of April 16, 1979, was examined by the inspec'.or.
The letter provided information pursuant to the criteria of 10 CFR21 regarding a potential defect in the containment spray pumps that night result in the loosening of the impeller locknuts. The corrective action onsite by the licensee to preclude the loosening of the impeller locknuts on the containment spray pumps and on the similar residual heat removal pumps was discussed with the Maintenance Supervisor and records of the completed maintenance actions were examined with the following observations made by the inspector, Request for Design Change (RDC) No.76-581 provided the design a.
details for the inclusion of a mechanical locking mechanism to preclude the loosening of the impeller locknut during pump operat. on.
b.
Facility records indicate that the modification was installed on the residual heat removal pumps during 1976 and on the containment spray pumps during the recently completed Spring of 1979 maintenance outage.
No other pumps are used at this facility which would be subject c.
to this potential design defect.
No items of noncompliance or deviation were identifid.
10. Modifications Based on discussions with licensee representatives and observations of work activities, the inspector verified that modifications as described in PGE Report No.1012, " Trojan Nuclear Plant Fire Protection Review",
were being implemented in accordance with the licensee's quality assurance program and facility procedures.
Observations by the inspector included the following:
1C71 358
-7-Request for Design Change (RDC) No.76-560 is the basic design a.
control document that details the proper review and approval of the fire protection system modifications.
b.
Detailed Construction Packages (DCP's) have been prepared to provide the information necessary to install the fire protection systems modifications.
c.
Work associated with modifications to cable tray fire stops and fire dampers was observed by th inspector and was found to have been performed in accordance with the applicable DCP.
d.
The compressor for filling breathing air canisters has been functionally tested and is available for use.
e.
When modification work resulted in the disruption of existing fire barriers or fire suppression systems, fire watches or roving fire patrols were esta'31ished.
f.
Administrative controls have been established to control combustible material and ignition sources in the facility.
g.
Tours of the control room, cable spreading room, East switchgear room, the remote shutdown panel room, by the inspector, verified that the administrative controls for control of combustible material and ignition sources were being complied with by the workmen per-forming modification activities.
h.
The complete fire protection modification program as described in RDC No.76-560 is scheduled for completion April 1980, prior to the commencement of cycle 3 operations following the 1980 refueling outage.
No items of noncompliance or deviations were identified.
11.
Followup on Previous Inspection Findings The following items were examined by the inspector with the results as indicated.
(78-12-02, Closed) The licensee has installed and tested a reactor vessel water level monitoring system using a television camera in the containment and a television monitor in the control room.
This system is to be used for reactor vessel water level indication when the reactor coolant system is depressurized and drained to the level required for reactor coolant pump or steam generator maintenance.
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-8-(79-07-03/04, Closed) The corrective action in the licensee's response to the items of noncompliance described in IE Inspection Report No. 50-344/79-07 was verified by the inspector.
(79-07-02, Closed) The Chemistry Manual has been revised to accurately reflect the latest revision of the technical specifications.
No items of noncompliance or deviations were identified.
12.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
on July 6,13, 20, 27, and 31,1979.
During these meetings the inspector summarized the scope and findings of the inspection.
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