IR 05000344/1982014
| ML20052C318 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/22/1982 |
| From: | Malmros M, Zwetzig G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20052C313 | List: |
| References | |
| TASK-2.B.2, TASK-2.F.1, TASK-TM 50-344-82-14, NUDOCS 8205040630 | |
| Download: ML20052C318 (6) | |
Text
,
.,
..
U. S. UUCLEAR RECUL\\ TORY C0!! MISSION
REGION V
' Report No. 50-144/9?-14 Docket No. 50-344 treense no, NPF-1 Safeguards croup Licensee: Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Facility Name: Trojan Inspection at: Rainier, Oregon Inspection conducted:
March 1 - April 16, 1982 Inspectors: h b
b2? 178%
A r4 M.6H. 4himrosQ Sedior Resident Inspector
/ Date Signed Date Signed Date Signed
---e Approved by:
Arb w Qhj)2,19 f ?
-
G.i$7 fasetzig9 Cl!ief, Recctor Projects Section 1
/ Date Sifned Reactor Operations Projects Branch Summary:
Inspection on March 1 - April 16, 1982 (Report 50-344/82-14)
Areas Inspected: Routine inspections of plant operations, surveillance testing, maintenance, security activities, training and follow-up on Licensee Event Reports and TMI modifications. The inspection involved 163 inspector-hours by the NRC Senior Resident Inspector.
Results:
No items of noncompliance or deviations were identified.
RV Form 219 (2)
8205040630 820422 PDR ADOCK 05000344
!
'
O PDR
]
.
.
- DETAILS 1.
Persons Contacted
- C. P. Yundt, General Manager R. P. Barkhurst, Manager, Operations & Maintenance C. A. Olmstead, Manager, Technical Services J. D. Reid, Manager, Plant Services D. R. Keuter, Operations Supervisor D. W. Swan, Maintenance Supervisor R. P. Schmitt, Engineering Supervisor G. L. Rich, Chemistry Supervisor T. O. Meek, Radiation Protection Supervisor R. E. Susee,-Training Supervisor D. L. Bennett, Control & Electrical Supervisor P. A. Morton, Quality Assurance Supervisor R. W. Ritschard, Security Supervisor H. E. Rosenbach, Material Control Supervisor J. K. Aldersebaes, Manager, Nuclear Maintenance & Construction 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.
Operational Safety Verification During the inspection period, the inspector observed and examined activities to verify the operational safety of the licensee's facility.
The observations and examinations of those activities were conducted on a daily, weekly, or biweekly basis.
.
On a daily basis, the inspector observed control room activities-to verify the licensee's adherence to limiting conditions for operations as' prescribed in the~ facility' technical specifications. Logs, instrumentation,
' recorder traces, and other operation records were examined to obtain information on plant conditions, trends, and compliance with regulations.
On the occasio~ns 'when-a shif t tufn'over was in ' progress, the turnaver
~
of.i_nformation 'on plant status'was. observed to determine that all
, pertinent.information.was relayed to the' oncoming shift.
D' ring each week, the.inspecto'r toured the accessible areas of the u
facilit to. observe the followiryg items:
a.
. General plant and equipment condit-ions.
b.
Maintenance requests and repair,
p
.
,.
-2-c.
Fire hazards and fire fighting equipment.
d.
Ignition sources and flammable material control.
e.
Conduct of activities in accordance with the licensee's administrative controls and approved procedures.
f.
Interiors of electrical and control panels.
g.
Implementation of the licensee's physical security plan.
h.
Radiation protection controls.
1.
Plant housekeeping and cleanliness.
j.
Radioactive waste systems.
The licensee's equipment clearance control was examined weekly by the inspector to determine that the licensee complied with technical specification limiting conditions for operation, with respect to removal of equipment from service. Veri _fication was achieved by selecting one safety-related system or component weekly and verifying proper breaker, switch, and
,
valve positions, both for removing the system or component frcm service and returning-it to service.-
During each week, the inspector conversed with operators in the control room, and-other plant personnel. The discussions centered on pertinent topics relating to general plant conditions, procedures, security training, and other topics aligned with the work activities involved.
Two groups were the subject of observation during shift turnover -
the ' control room operators and security personnel at the main gate.
The inspector examined the licensee's nonconformance reports to confirm the deficiencies were identified and tracked by the system.
Identified nonconformances were being tracked and followed to the completion of corrective action.
Logs of jumpers, bypasses, caution, and test tags were examined by the inspector. No jumpers or bypasses appeared to have been improperly installed or removed or to have ccnflicted with the technical specifications.
Implementation of radiation protection controls was verified by observing portions of area surveys being performed, and by examining radiation work permits currently in effect to see that prescribed clothing and instrumentation were available and used. Radiation protection instruments were also examined to verify operability and calibration status.
Each week the inspector verified the operability of a selected engineered safety features (ESF) train. This was done by direct visual verification of the correct position of valves, availability of power, cooling water supply, system integrity, and general condition of'the equipment.
ESF trains verified to be operable during the inspection period included the offsite and onsite electrical distribution system, the residual heat removal system and the safety injection syste,
.
.-
-3-On March 26, 1982, the facility was shutdown to commence the 1982 refueling outage which is scheduled for completion on July 9, 1982. The facility was shutdown approximately five weeks prior to the anticipated start of the 1982 refueling outage due to the abundant supply of hydroelectric power in the Northwest.
No items of noncompliance or deviations were identified.
3.
Maintenance Maintenance activities involving preventive and corrective maintenance were observed by the inspector during the inspection period. Observations by the inspector verified that proper approvals, system clearances and test of redundant equipment were performed, as appropriate, prior to maintenance of safety-related systems or components. The inspector verified that qualified personnel performed the maintenance using appropriate maintenance procedures. Replacement parts were examined to confirm proper certification of materials, workmanship and tests.
During the actual performance of the maintenance activity, the inspector checked for proper radiological controls and housekeeping, as appropriate.
Upon completion _of the maintenance activity, the inspector verified that the component or system was properly tested prior to returning the system or component to service.
During the inspection period, maintenance activities observed were associated with the emergency dies'el generators, area radiation monitors, and electrical circuit breakers.
No items of noncompliance or deviations were identified.
4.
Surveillance The surveillance testing of safety-related systems was witnessed by the inspector. Observations by the inspector included verification that proper procedures wcre used, test instrumentation was calibrated and that the system or component being tested was properly removed from service if required by the test procedure. Following completion of the surveillance tests, the inspector verified that the test results met the acceptance criteria of the technical specifications and were reviewed by cognizant licensee personnel. The inspector also verified that corrective action was initiated, if required, to determine the cause for any unacceptable test results and to restore the system or component to an operable status consistent with the technical specification requirements.
Surveillance tests witnessed during the inspection period were associated with the following systems:
electrical distribution system, auxiliary feedwater system, safety injection system and the residual heat removal system.
No items of noncompliance or deviations were identifie ]
,
,
.
...
s
.
.
-4-
'
5.
Training, The' inspector attended lectures addressing the subject of emergency procedures given as part of the licensed operator requalification training program. The training was found to be in accordance with the approved operator requalification program schedule and objectives. Based on discussions with several licensee employees (one instrument and control technician, one electrician, one. operator and one engineer),-the inspector verified that appropriate on-the-job training and technical training connensurate with the individual's job classification have been provided by the licensee as required by the facility technical specifications.
No items of noncompliance or deviations were identified.
6.
Licensee Event Report (LER) Follow-up The circumstances and corrective actions described in LER Nos. 82-02, 82-03, and 82-04 were examined by the inspector. The inspUctor found that each LER had been reviewed by the licensee and reported to the.
NRC within the proper reporting interval.
The corrective actions for each event were as follows:
LER 82-02 (Closed):
Tne licensee replaced the source range high voltage power supplies with redesigned power supplies provided by the vendor. The new power supplies incorporate several circuit improvements which provide for more stable operation. During the recent plant shutdown, the source range high voltage power supplies both automatically energized as required.
LER 82-03 (Closed): The process radiation monitor was repaired by facility personnel and returned to service. The failed vane in the pumping unit was attributed to normal wear.
LER 82-04 (0 pen): The licensee has revised Operating Instruction 0I-1-9, " Operation of 12.47 KV and 4.16 KV Air Circuit Breakers,"
to require the bump starting of electrical motors following the racking of a circuit breaker from the test to the connected position.
The LER described an occurrence where an operator failed to return equipment to service following the completion of surveillance testing. The revision to 01-1-9, described above, clarifies the operability verification required when circuit breakers are racked from the test to the disconnect position, and should preclude the recurrence of this event. As a result of this occurrence, the licensee has scheduled a review of all surveillance procedures to verify that the procedures clearly indicate the requirements for returning equipment to normal operation following completion of surveillance testing. This review is scheduled for completion September 1, 1982.
No items of noncompliance or deviations were identified.
.
.
[
-
- '
,.
,
-5-7.
TMI Modifications Based on discussions with licensee representatives and examination of facility records, the inspector verified that the following TMI modifications had been completed as specified in NUREG 0737 and correspondence bctween the licensee and the NRC.
a.
'T B.2. Plant Shielding.(Closed): The facility changes needed to incorporate changes identified as a result of the shielding survey have been installed under the following RDCs:
76-104,80-008,'80-009, and 80-010. The need to relocate the hydrogen monitor sampling lines has been deleted. since the new hydrogen monitoring system will not require the sampling lines.in occupied areas.
b.
II.F.1.4. Containment Pressure (Closed):
The licensee has installed redundant channels of recorded containment pressure (-5 psig to 200 psig). The modification was made in accordance.with design:
change RDC 79-092, and was completed in June 1981.
c.
II.F.1.5. Containment Water Level (Closed): The licensee has
. installed redundant, narrow and wide range containment water level instrumentation.. The instrumentation was installed in accordance with design change RDC 80-101, and completed in June, 1981.
No items of noncompliance or deviations were identified.
,
8.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
on March 19, March 31, and April 16, 1982. During these meetings the
'
inspector summarized the scope and findings of the inspection.
.
'
l