IR 05000344/1986047
| ML20210F140 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 01/21/1987 |
| From: | Mendonca M, Pereira D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20210F135 | List: |
| References | |
| 50-344-86-47, IEIN-86-026, IEIN-86-052, IEIN-86-057, IEIN-86-26, IEIN-86-52, IEIN-86-57, NUDOCS 8702110003 | |
| Download: ML20210F140 (9) | |
Text
-
p
<
-
.
U. S. NUCLEAR REGULATORY COMMISSION
'
REGION V
Report No. 50-344/86-47 Docket No. 50-344 License No. NPF-1 Licensee:
Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Facility Name:
Trojan Nuclear Plant Inspection at:
Rainier, Oregon Inspection Cond tecl:
D cemb 5-19, 1986 and January 5-9, 1987 Inspector:
ad (4/A4 M/ 8 D. B. Pereira, Reactor Inspector Date Signed Approved by:
-
2'/E7
'
M. M. Mendonca, Chief Date Signed Reactor Project Section 1 Summary:
Inspection During the Period of December 15-19, 1986 and January 5-9, 1987 (Report No. 50-344/86-47)
Areas Inspected:
Routine, unannounced inspection of Electrical Maintenance (Inspection Procedure (IP) 62705), Maintenance Program (IP 62702), Containment Leak Rate Test Results Evaluation (IP 70323), Followup items on Information Notices (IP 92701), Onsite Followup of Events (Familian Products Investigation) (IP 93702) and Exit Interview (IP 30703).
Results:
No items of noncompliance or deviations were identified.
0702110003 870122 PDR ADOCK 05000344 O
-
.
.
DETAILS 1.
Persons Contacted
+ *R. Schmitt, Manager, Operations and Maintenance W. S. Orser, General Manager
+ *C. A. Olmstead, Manager, Quality Assurance Department and General _ Manager
+ *J. D. Reid, Manager, Plant Services D. L. Bennett, Supervisor, Control and Electrical
+
D. W. Swan, Supervisor, Maintenance
-
+ *C. H. Brown, Operations Branch Manager, Quality Assurance
+ *S. Bauer, Engineer, Nuclear Safety.and Regulation Department
+ *G. Kellund, Trojan Resident, U. S. Nuclear Regulatory Commission
- J. K. Aldersebaes, Manager, Plant Modifications
+
B. Kershul, Engineer, Nuclear Safety and Regulation Department
- Denotes attendance at exit interview conducted at Trojan Nuclear Plant on December 19, 1986.
+ Denotes attendance at exit interview conducted at Trojan Nuclear Plant on January 9,1987.
2.
Electrical Maintenance (Components and Systems)
The purposes of this. inspection were to determine that corrective maintenance and preventive maintenance on electrical components and systems were conducted in accordance with licensee-approved procedures and instructions, and that the procedures and instructions meet the requirements of regulatory guides and codes.
This objective was to be met by direct observation of work, work activities scheduled and/or review of quality records.
Administrative Order (AO)-3-9 provides the procedure for initiation, preparation, performance, and documentation of work and post-maintenance testing on all electrical maintenance.
The inspector reviewed the following completed system procedures for the licensee's corrective and/or preventive maintenance program:
A.
Emergency Diesel Generators and Associated Equipment (1) Maintenance Procedure (MP)-12-7 - Emergency Diesel Generator (EDG) plant, Revision 15, issued December 5, 1986.
Data Review indicated no discrepancies.
(2) Periodic Operating Test (P0T)-12-2 - EDG Performance Loss of Offsite Power, Revision 14, issued May 30, 1986.
Data Review indicated no discrepancies.
B.
Safety-Related AC and DC Control Power Systems (1) MP-1-13 - D. C. Distribution Control Centers and Breakers, Revision 10, issued August 27, 1986.
Data Review indicated no discrepancie w _
._
r
-
-
,
~
-
.
,
,
%,
.. _
- .*
T r
,n(2);hP-1-14'-125 Volt Station' Batteries, Revist'on 14, issued
'
N
.. '.
' October 4, 1986.
Data Review of the Annual Maintenance and 4(-
Service Test indicated that the data sheets marked "65 hours7.523148e-4 days <br />0.0181 hours <br />1.074735e-4 weeks <br />2.47325e-5 months <br />.
y into equalize charge," "After Equalize Charge Returned to Float
-
N Prior to Reading," and "62_ hours into equalize charge" did not.
w have the approved by and date-filled out.
This discrepancy was
'
'.
discovered in the middle of the results of.the annual
'
maintenance of the 125 volt battery as= initiated per
-
-
- .
. Ma'!ntenance Request (MR)-86-0031~ : The; maintenance manager was
.'
'
'
-
-
' informed and was researching this mis ~sedJapproval/ review
signatures'and dates 'This.will be followed-up on a subsequent
'
'
3-inspection and is Unresolved, item'86-47-01; C..
Engineered Safety Feat 0res/(ESF)~ '
,
'
-
-
,
,
,
(1) Periodic ~ Instrument and Control Test (PICT)-22-1.-' Time w
~ Response Coordinating Document, Revision 7, issued November 6,'
1984.
Data Review indicated no. discrepancies.
(2) PICT-22-2 - ESF Actuation Response Time',' Revision 9, issued August 15, 1986.
Data Review' indicated no discrepancies.
D.
Reactor Protection ^and Control Systems
-
(1) MP-2-27
, Rod Control System,I evision 0,I ssued October 26, R
i 1984.
(2) MP-1-5 - Reactor Trip and Bypass Breaker, Revision 4, issued August 29, 1986.
,
(3) MP-1-10 - Control and Instrument Distribution Panels, Revision 6, issued May 18, 1984.
(4) MP-1-9 - Rod Drive M.6. Sets and Switch gear, Revision 9, issued November 21, 1986.
,
,
The above procedures' data review indicated no discrepancies.
.
In general, the record review of completed m31ntenance activities indicated the following items as being completed satisfactorily:
Required administrative approvals were obtained before initiating the work.
The acceptance criteria were met.
Maintenance activities were made in accordance with licensee's procedures, and maintenance records were complete.
- Functional testing, adjustments, and calibrations were completed before returning the equipment to operations.
Qualified personnel performed the activity.
.
% -. -. -
- - -
-.
- - -
. -
- -
.
. - -. - -
-
.
-
-
.
Corrective and preventive maintenance records are assembled, stored, and retrievable.
f-
Referenced procedures were approved and appeared adequate.
The inspector reviewed the above maintenance procedures and this review determined that they included the following items:
Administrative approvals for removing the system from service and returning it to service with attention to system lineup and verification.
- Designated Quality Assurance / Quality Control (QA/QC) steps for inspection / audit sign off.
Provisions for returning the item maintained and the affected systems to the original configuration following maintenance, and verifying that the configuration is correct.
Provisions for operational readiness testing of an item maintained and affected systems following maintenance.
,
Procedures to ensure that materials, parts, and components were correct and suitable.
Precautions for ensuring that limiting conditions for operation contained in the technical specifications were identified and satisfied during the repair period.
Provisions for the control of housekeeping and for cleaning safety-related systems / components during the maintenance effort.
s
'
Provisions for removal of appropriate jumpers and restoration t
of lifted leads.
Appropriate acceptance criteria and performer'and. verifier
signoff in data tables.
Provisions to record measurement and test equipment identification numbers and calibration dates, if used.
-
The electrical maintenance procedures reviewed indicated no discrepancies or deviations.
The licensee's electrical maintenance program activities appear to be conducted in accordance with the requirements of regulatory guides, industry codes, and the Technical Specifications.
No violations of NRC requirements or deviations were identified in the inspection of the above described items.
3.
Maintenance Program The purpose of this inspection was.to determine whether the licensee is implementing a maintenance program that is in conformance with Technical
i.'.'
'
~
?
- ,
'
'?
"
-
p, g y s
,
.
,
,
.f-
<
,,
~,
,
-
.
-
-
,
- __
,
, -,
,'
,
p
.
,
,
-
..
,
?f'
~
'
'
'
,
,
,
,
Specifications,lr'egulatory 'requirdents,(licensee commitminis and
~
"
.. _ y
~ industry guides or standards. The. foDowing licensee procedures were
'
,
'7,
. reviewed:
'
'
"
'
,
.
,, ~
...,
Title Revision ~
~
Procedure No.
'
<
.
n
.
,,A0-1-4 Operations and Maintenance c13 t
-
>
,. 7
.
Responsibilities:
-
-
.'
,
.
.
'
'
(
- AO-3-9 Maintenance Requect
,
,
~
'
,
,
.
.
.
,-3-141 Safety-Related Equipment ~0utag'es'
141 e -
0
'
~
Plant Safety and. Housekeeping
' 13.
t A0-10-1
,
,
'*
~
'
'MP-3-3'
' Welding an'd Brazing: Procedures
' >
<
- Cleanliness Control
.,
MP-3-7-Weld /Nraz'eand' Welder /BrazerRecords
'11
'
'
'
5-
'MP-3-8 Trojan Preventive Maintenance
+
-
Scheduling Program
,
<
,nr, a
,
TrojanHol'dout;and{aggingPr'ocedure PS-3-30
,
PS-7
. Welding, Cutting, Grinding and Brazing 7'
,
'
r..
.
A.
It was determined by review of the~ procedures listed above that the
-
maintenance program relating to. corrective. maintenance, preventive
,
,
,
. maintenance, equipment control,'special-processes kcleanliness p'
controls,andhousekeeping.controlswere. adequately l described.
^
.
..
.:
s,
. -
s B.
A review of' records of completed maintena'nce activities as detailed
% in paragraph 2.of this" inspection. report? indicated no significant.
~
'discrepanciestor deviations.,,In' general; the' maintenance procedures
provided1a means for: initiating requests forfroutine and emergency
,
maintenance; criteria and-responsibility for review and approval of
,
maintenance. requests, and designating the activity as safety versus
~
s non-safety related.
Provisions and responsibility.have been
established for the identification' of' inspection: hold points and for -
i
,
,
--
performing functional > testing of structures,' systems or components
~
~
following maintenance work and/or prior to their being returned to
-
,m service.
,
,
,,
.
h-
~
The. licensee's maintenance program activities appear to be conducted j
.in accordance with the Technical Specifications, regulatory
.
E requirements,. licensee commitments, and industry guides or.
h standards.
~
No' violations of NRC requirements or deviations were identified in
~
the inspection of the above described items.
.'
- ,
y,,h
+a
+. ~
,
-,.:-,.,,,-w,-n
-
..-,,.,,r,,,,l.,.-.
c
..~>.r.,,
,,,,
m..,, -..
n,
.,
,,-.,-.n,.,,,~-,.,,-,,.e--en-.
'
.
-
.
-
4.
Containment Leak Rate Test Results Evaluation The purpose of this inspection was to verify that the licensee has i
adequately performed, reviewed,- and evaluated operational Type A containment tests (containment integrated leak rate test (CILRT)) and Type B.(local leak rate test (LLRT)) for operational' plants.
The inspector reviewed the CILRT performed May 27-29, 1986 and verified that the "as found" (AF)-initial containment cendition and as left" (Ai.)-final containment conaition resuits for the C1LMi performed were.
submitted.
The inspector reviewed the test results and the analyses and interpretation of the leakage rate. test data and verified the following criteria:
A.
Required leakage rate computations were properly performed and reviewed.
B.
'The total measured leakage rate (0.017%/ day) met the required leakage rate acceptance criteria (0.075%/ day).
C.
The total measured leakage rate was corrected for random instrument errors.
In addition, the inspector reviewed the results and analyses of the supplemental verification test used to demonstrate Type A test validity.
The induced leakage rate (.127%/ day) was between the interval.75 to 1.25 of the maximum allowable leakage rate at peak test pressure.
The inspector verified that the leak rate test report included a schematic of the leakage rate measurement system, a description of the instrumentation used, and a discussion of the applicable test program.
The inspecto. verified the results of the Type B LLRT performed prior to the CILRT mec the required acceptance criteria and that the licensee conducted an adequate summary analysis for the LLRTs performed.
The licensee appears to have conducted the CILRT correctly, reviewed the data satisfactorily, and evaluated and presented the results in a proper manner.
No violations of NRC requirements or deviations were identified in the inspection of the above described items.
l 5.
Follow-up on Previous Inspection Findings A.
(Closed) Information Notice (IN) No. 86-26 - Potential Problems in Generators Manufactured by Electrical Products Incorporated (EPI)
On July 21, 1983, a Washington Public Power Supply System (WPPSS)
Unit 2 emergency diesel generator (EDG) 1A had high vibration level readings accompanied by sparks from the rotor shaft bearing area.
,
l Upon disassembly it was determined that a shim, required to maintain I
clearance at the thrust bearing, was missing.
The missing shim was installed and the damaged areas refurbished.
The original design, l
which placed electrical insulation between the rotor shaft and the l
l l
!,
-
,..w.
6' #r S
'
'
,
,
s..'
1 5
,
<
-
.
.
,
.k
%
g
'
slip-ring end bearing'. inn'er race:was m'aintained.
On' July 9,1984,
,
~
during monthly surveillance testing,'a high vibration alarm was-
-
,
. observed on emergency DG 1B.
Investigation' revealed that.the
"~
slip-ring end bearing had turned:on the shaf.t insulation, destroying the insulation. =The reduction in insulation cross sectional thickness allowed the rot'or shaft'to drop slightly'fter this failure-and-rub on the bearing housing.
The, corrective a'ction employed a was a' design modification.. The insulation between the bearing and the; shaft was removed land the bearing was mounted directly on the shaft. The bearing housing-was insulated to provide the required'
electrical insulation.
The events were-the subject of IN No. 86-26.
'
,
Trojan's Plant Engineering has investigated this IN via Operational-Assessment Review (OAR) 86-42. cAccording to the'0AR, plant t
engineering recommends that continued good maintenance practices
'
s
.~
will prevent a similar problem as discussed in IN 86-26 or a circulating current path from developing.
In conjunction with the above practices, utilizing-Plant Maintenance Procedure, MP-12-7 to guide annual maintenance on the generator bearing for insulation resistance will fulfill an adequate surveillance and thus prevent a bearing generator failure.
In conclusion, the 0AR states that Trojan's emergency' diesel generators have suitable bearings to pedestal insulation,'and present maintenance practices have provided the continued-integrity expected of the EDGs.
No further corrective action needed to improve EDG reliability.
IN 86-26 is considered closed.
B.
.(Closed) IN No. 86-52 - Conductor Insulation Degradation on Foxboro Model E Controllers This.IN describes a potentially generic problem with conductor insulation degradation on 15 conductor /24 gauge interconnection coil-cord cable sets supplied-by the Foxboro Company for use with
.Foxboro Model-E electronic controllers.
Degradation of the insulation could result in a common mode failure in that wiring of
'
the same age in various controllers may fail in certain circumstances, such as a seismic event.
The licensee's review of this IN was for information'only since they do not have Foxbore Model E controllers.
T IN 86-52 is considered closed.'
i
.C.
(Closed) IN No. 86-57 - Operating Problems with Solenoid Operated Valves at Nuclear Power Plants.
.
This IN describes a series of valve failures that have occurred recently at several nuclear power plants. The failures involved certain valves that are actuated by solenoid operated valves (S0Vs)
,
to operate properly.
These failures have adversely affected the
-
l intended functions of>the main steam isolation system, pressure
!
'
l
.
-
-
,,.-.$--
,
,
y
-
,,_y
,.,.
m
,,,
-
., -,
-
m--
.
...*
-
relief and fluid control systems.
In most cases, the cause for triggering _the event was attributed to a malfunctioning.S0V,that served as a pilot valve, which in turn resulted in the malfunction of the associated main valve.
The licensee's review of this IN'was performed per 0AR 86-64 and
~
which concluded that a revision to Maintenance Procedure (MP)-12-4, Maintenance on Air Actuators, should be issued.'
This revision will provide improved instructions and clarification of, current inspections of air actuated' valve operators. 'The revision will be issued in time for the next outage.
Based on the above revision intent of MP-12-4, this IN 86-57 is considered closed.
D.
Licensee Program to Followup ins and Bulletins The licensee's IN program was reviewed in this inspection report and in others (Inspection Report Nos. 50-344/86-05 and 50-344/86-45, and it was determined that the program meets the following criteria:
ins are distributed to appropriate licensee personnel at the corporate and site levels.
A licensee review for applicability process is instituted via the Operational Assessment Review (0AR) form for the ins.
If applicable, the scheduling or performance of appropriate corrective actions, such as changes to procedures, training, and equipment changes 'are accomplished and documented.
Management review and approval is evident throughout the program.
The licensee's IN program appears to perform the function of notifying plant personnel of potential problems as described in the particular IN.
No violations or deviations were identified in this area.
No violations of NRC requirements or deviations were identified in the insnection nf the above describad it6ms, 6.
Investigation of Familian Products Allegation RV-86-A-097 dealt with potentially fraudulent materials provided to Trojan by Familian Northwest.
As a result, the inspector in cooperation with an investigator from the Office of Investigation examined Familian products installed in safety-related systems. The inspector,.with the help of the licensee, obtained samples from selected safety-related systems for analysis if needed later.
The examined components appeared to be in an acceptable condition with no ebvious indication of abnormalities.
The inspector also reviewed associated paper work for the components and found no deficiencies in the paper wor ~
i
.f f
'
~
- ~- ~ '
'
,
.
,
'_#
l
.
-
,..
>
. v
>-; s
,
f7.
. Exit Int'erview:-
,,
'
-
. -
~
-
p
,
~
'.
'The inspector met with the licensee _re~presentatives'as noted in parag aph
,
F
~ ~
a"1 on: December 19,~ 1986 and January 9, 1987,.and. summarized the scope and'
-
'
- findings of, the.. inspection activities. - '
%
%
y
2
$.
.
y
% >
<
--
.
%
'e
.>
.
,
.
I
&
s
c b
v
+
k
-
h j
.
1