IR 05000425/1988016
| ML20151V406 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/15/1988 |
| From: | Conlon T, Hunt M, Mark Miller NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20151V401 | List: |
| References | |
| 50-425-88-16, NUDOCS 8805030053 | |
| Download: ML20151V406 (9) | |
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UNITED STATES u
', [8 NUCLEAR REGULATORY COMMISSION REGION 11
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j 101 MARIETTA STREET, N.W.
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AT LANTA, oEoRGI A 30323
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Report No.:
50-425/88-16 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket No.:
50-425 License No.:
CPPR-109
' Facility Name:
Vogtle Unit 2 Inspection Conducted: March 28-31, 1988
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Inspectors:
/f4 M s _ _ M M
N M. D. Hunt Date Signed N Md.s -
L 4 )M~}f f M. N. Miller
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Date S1'gned Approved b 9 2%
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/?'- / ('" Y T. E. Tonlon, S'ection Chief Date Signed Engineering Branch Division of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection was in the areas of electrical
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equipment, instrumentation, and licensee identified items.
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Results: No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Onntacted Licensee Employee.
- C. L. Coursey, Maintenance Superintendent
- M. D. bancan, I&C Supervisor
- L. B. Glenn, Manager, Quality Control
- E. D. Groover, QA Site Manager, Construction
"S. D. Haltom, QA Engineering Support Supervisor
- H. Handfinger, Project Start-up Manager
"A. W. Harrelson, Electrical Discipline Manager
- C, W. Hayes, Vogtle QA Manger
- M. L. Hobbs, I&C Superintendent
- R. E. Hollands, Engineering Construction Supervisor
- G. A. McCarley, Project Compliance Coordinator
- R.
H. Pinson, Vice president
- P. D. Rice, Vice President and Project Director Other licensee employees contacted included construction craftsmen, engineers, technicians, operators, mechanics, security force members, and office personnel.
NRC Resident Inspector
- R. J. Schepens
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 31, 1988, with those persons indicated in Parag aph 1 above.
The inspectors described the areas inspected and discussed in detail the inspection findings. No dissenting comments were received from the licensee.
l The licensee did rot identify as proprietary any of the materials provided i
to or reviewed by the inspectors during this inspectinn,
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3.
Licensee Action on Previous Enforcement Matters j
This subject was not addressed in the inspection.
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Unresolved Items Unres)1ved items are matters about which more information is required to
determine whether - they are acceptable or may involve violations or.
I deviations.
One unresolved item identified during this inspection is l
discussed in Paragraph 6.
-5.
Electrical Components and Systems - Work Observation (51053) and Record Review (51055)-
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The inspectors selected seven Motor Operated Valves (MOVs) for verifi-(
cation of cable installation, terminations, protecticn and installation i
records. The following MOV installations were examined-Volume Control Tank Outlet Valves LV 112 B & C
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Refueling Water Storage Tank (RWS1) Outlet Valves LV 112 0 & E
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to Charging Pumps Suction to Charging Pump A and B i
HV 8471 A & B
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Safety Injection Pump Section from RWST
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HV 9806
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Cable routing was verified from the MOV to the entry into the cable tray i
system. The raceway and conduits were identified, the MOV's were properly
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identified and inspected to ensure that the proper cable was terminated at
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the correct MOV. The connections that are internal to these valves could not be examined in all instarces due to the physical location and the fact that testing of certain systems required these valves to be energized and in a certain position. The risk of contacting the interr.al connections during removal of the cover which could cause a position change of the t
valve or a short that would incerrupt power to tho valve was considered i
and it was decided that a review of the termination records for the energized M0V's would be made.
i Discussions with the licensee representatives responsible for testing and maintenance of these MOVs regarding the compliance to the environmental
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qualifications of MOVs were held.
The licensee presented the following
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precedures for review:
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Procedure No.
CAT-E-13 Motor Operated Valves i
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l 26863-C Environmental Qualification Inspection and Compliance for Limitorque Operators
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Procedure CAT-E-13 provides instructions for the initial testing of MOVs
i and to provide a means of documenting the Construction Acceptance Testing, j
This procedure addresses the testing required before the MOV is energized
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l and operationally tested.
This procedure also references Procedure No. 26863-C which address's several items related to Limitorque MOVs.
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Procedure No. 26863-C requires documentation of qualification inspection
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of Motor Housing T-Drains, Operator Grease Relief Valve Ring Torque
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Terminal (Lug) Sizing, Internal Wiring, Control and Power Wiring Terminal
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Blocks, Torque Switch Material, Limit Switch Rotor Material, limit Switch
Finger Bvard Material, and Limit Switch Housing Material.
The acceptance i
criteria is well defined in this procedure.
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Within the areas examined, no violations or deviations were identified.
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6.
Instrument Components and Systems - Work Observation (52053)
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The inspectors selected various installed pressure and level indicators on the Main Control Panel 2-1601-QS-MC5 for examination of completed work ~and QC records associated with receipt inspection, installation, and turnover.
The inspectors verified the location, installation and correct identifi-cation of the instruments.
The instruments were furnished with the enntrol panel. The records reviewed for the instruments were contained in the "Turn 0ve'r Package" for the control panel.
The turnover package
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included certificates of compliances, Receipt Inspection Report 68905, the Electrical Equipment Installation Turnover and Inspection Report, and the Electrical Equipment QC Inspection Report, both dated August 13, 1986.
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The instruments selected for examination are identified as follows:
2PI-514A Steam Generator Loop 1 Pressure
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2PI-515A Steam Generator Loop 1 Pressure f
t 2PI-516 Steam Generator Loop 1 Pressure 2LI-517 Steam Generator Loop 1 Level
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2LI-518 Steam Generator Loop 1 Level i
j 2LI-519 Steam Generator Loop 1 Level
2PI-524A Steam Generator Loop 2 Pressure l
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2PI-525A Steam Generator Loop 2 Pressure i
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2PI-526A Steam Generator Loop 2 Pressure i
2LI-527 Steam Generator Loop 2 Level i
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l 2PL-528 Steam Generator Loop 2 Level i
2LI-529 Steam Generator Loop 2 Level
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i The inspectors performed a walkdown to examine completed work for
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instrument indicators on Shutdown Panel Train A, 2-1605-PS-SDA. Damaged
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flow, level, pressure, position, and temperature indicators were
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identified.
The damage appears as cracks on the rear cover of each indicator located inside the panel. Several indicators had cracks at the i
electrical connectio mounting studs.
The Shutdown Panel Train A had a
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"Release for Test" fag Number 2RJ02 indicating the panel was either
released for test or turned over to the test group. The licensee informed the inspectors the panel ws turned over to the test group.
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inspectors reviewed the "Receipt Inspection" and the "Electrical Equipment
Installation Turnover and Inspection" reports in the "Turnover Package"
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i for Shutdown Panel Train A since the instruments were furnish with the
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l panel.
No deficiencies were identified in the inspection and walkdown (
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reports.
Nuclear Construction System Turnover Procedure GD-A-48 contains
"Walko'own Inspection Guides" which specify that instrumentation items are to be checked for damage prior to turnover or release for test.
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It could not be determined if the damage to the instruments identified by the inspectors had occurred after the completion of the turnover
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inspection or prior to the turnover inspection and overlooked by the inspection (QC) personnel.
Therefore this item i s identified as an Unresolved Item 50-425/88-16-01, Review status of damaged indicators, until additional information is reviewed.
The. damaged indicators - are identified as:
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2FI-1640C 2LI-548A 2PI-405A 2FI-5150B 2TI-443C
- 2PI-514C
- 2LI-5018
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2LI-5048 2PL-544C
- Indicates damaged indicatorr, found by licensee after the inspectors examination.
The licensee informed the inspectors corrective action was being taken by
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the initiation of Operation Deficiency Reports (00R) Nos. T-2-88-251, 522
and 523 and a Maintenance Work Order (MWO) No. 28802828 dated March 30, 1988.
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The inspectors observed calibration activities of pressure loops for the
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accumulator tanks.
The technicians were performing pressure indicator calibrations in the control room and at Shutdown Panel Train B.
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inspectors reviewed the documentation and inspected the test equipment
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being used. The inspectors verified the technicians were performing work required by MWO 28802585 and using the latest calibration procedures listed as follows for each loop:
24775-2 Accumulator Tank #1 Pressure Loop 2P-961
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24777-2 Accumulator Tank #2 Pressure Loop 2P-963
24779-2 Accumu'tator Tank #3 Pressure Loop 2P-965 24781-2 Accumulator Tank #4 Pressure Locp 2P-967
The test equipment was properly identified with permanent numbered tags
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and had current due date calibration stickers. The inspectors noted the
i technicians were recording the data (results) during the activities.
The instrument technicians appeared to perform their work in a knowledgeable
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and professional manner.
Within the areas examined, no violations or deviations were identified.
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Instrument Components and Systems - Record Review (52055)
The inspectors examined completed calibration packages for 11 instrument loops. These records were reviewed to determine if the initial calibra-tion requirements in Construction Acceptance Test (CAT)
procedure CAT-E-08, Instrumentation, were satis;actorily completed for each loop.
The records for each calibration package contained the data sheets from the specific maintenance calibration procedure and CAT-E-08 procedure.
The inspectors verified the CAT-E-08 data sheets contained the following:
CAT test identification number:
Loop number and system designator; The wiring diagram (s) number; The instrument loop diagram number;
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The instruments calibrated and date performed; The signature of the technician who perform the calibrations; The signature of the maintenance supervisor who approved the data sheets; and The signature of the QC reviewer who reviewed the calibration package.
The maintenance calibration data sheets were reviewed for each instrument in the loop to ensure each contained the following:
The maintenance procedure number; The cabinet or location of the instrument; The description (name) of the instrument; The model and serial numbers; The required calibration input signals; The expected output signals and the high and low limits for the acceptance criteria; The correct "as left" calibration data; The test equipment used with the identification number, model number and calibration due date; and
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The signatures of the technician who perform the calibration, the reviewer and the approving supervisor (with each dated).
The instrument loops, maintenance calibration procedure numbers, CAT test numbers and date completed are identified as listed.
Loop Maintenance Procedure CAT Test Number Date Completed 2F-415 24786-2 87-2832 03/04/88 Reactor Coolant Flow - Loop 1 2F-425 24787-2 87-3344 03/J7/88 Reactor Coolant Flow - Loop 2 2 F-446 24787-2 88-407 03/04/88 Reactor Coolant Flow - Loop 4 2P-456 24526-2 87-2260 03/06/88 Pressurizer Pressure 2L-459 24493-2 87-2259 02/28/88 2L-461 24531-2 88-0370 03/25/88 Pressurizer Level 2F-917 24311-2 88-0455 03/07/88 BIT Charging Pump Flow
- 2L-990 24806-2 87-2410 03/05/88
- 2L-991 24807-2 88-0168 03/02/88
- 2L-992 24808-2 87-2275 03/05/88
- 2 L-993 24809-2 87-2409 03/03/88
- Refuelirg Water Storage Tank Level Loeps Within the areas examined, no violation or deviations were identified.
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Licensee Identified Items (10 CFR 50.55(e))
(Closed) CDR 82-24, Unit 2, Reactor Coolant System (RCS) Wide Range Pressure Transmitters.
This item was reported as the result of Westinghouse Electric Corporation's Letter GP-5846 dated April 20, 1982, and involves the high inaccuracies of the wide range pressure transmitters located in High Energy Line Break (HELB) environments. The wide range pressure transmitters provide an input into the following functions:
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Cold Overpr(ssurization Mitigation System (COMS)
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RHRS' Initiation Permissive Interlock
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~RCS-Pressure Monitoring
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This system has been designated as a Pos+.-Accident Monitoring System (PAMS) channel-in Vogtle FSAR.
The~ COMS function is only required in a benigri environment, therefore,-the HELB caused inaccuracies do not affect this system. The other functions that are provided inputs by these wide range transmitters require greater accuracies than can be supplied by the transmitters if they are expcsed to the HELB environment.
In order to ensure the functional capabilities of these transmitters, the licensee had taken the folicwing measures:
leave two pressure transmitter (0-3000 psig or greater) inside
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containment to provide an input for the COMS.
locate four pressure transmitters (0-3000 psig greater) outside
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containment in a non-HELB environment.
These transmitters will provide inputs for the RHRS Initiation Permissive Interlock, PAMS, and the Post-Accident RCS Pressure Monitoring.
The inspectors reviewed the following documentation and drawings for wide range pressure transmitters pts-403, -405, -408, -418, -428, and -4.18:
Engineering Inspection Checklists
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Specification for Electronic Pressure Transmitters
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Turnover Documentation
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Drawii.gs 2X5054A07, Rev. 3, 2X5DS4007, Rev. 2, 2X5DS3A04,
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Rev. 5, 2X5DS3G06, Rev. 6 The corrective actions taken by the licensee appears to be adequate to insure that the wide range pressure transmitters will provide accurate information in the event of an H2LB inside conatinment.
This item is closed.
(Closed) CDR 83-53 - Control Level Electrical Penetration Protection, (EPA). This item was reported on December 19, 1983, and identified 22 containment penetrating non-safety-relatea circuits which did not have adequate backup electrical protection to protect the feed-through parts of the respective EPA's.
The inspectors verified the addition of the required fuses / breakers were installed in the following circuits which are fed from the indicated boards:
Unit No - Board ID - Compartment No 2-NBS-13 2-NBS-17 2-NBS-19 2-NBF-33 2-NBF-30 2-NBF-29
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-2-NBR-17 2-NBR-19 2-NBR-13 t
2-N9R-16 2-NBE-29 2-NBE-33
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Based on the above sample, it appears that the corrective actions are '
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adenuate and records indicate all modification are complete. This item is closed.
(Closed) 85-COR-87, Limitorque Valve Motor Operators.
This item was reported on October 11, 1985 and involved possible damage to internal wiring caused by the close proximity or untact with the operator limit switch compartment space heater or the heater mounting bracket. During this insoection the. inspectors reviewed the special inspection packages developed to examine this condition.
Records were also available to identify the' MOVS. which required internal-wiring replacement due to theraal daniage or discoloration. One unit located in the warehouse was
examined by the inspectors. Other MOV's were examined as discussed in.
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The corrective action to re.iove the power from the beating r
element, inspect and replace the internal wiring as necessary appears
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adequate. This item is closed.
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