IR 05000424/1990006
| ML20034A989 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 04/12/1990 |
| From: | Belisle G, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20034A987 | List: |
| References | |
| 50-424-90-06, 50-424-90-6, 50-425-90-06, 50-425-90-6, NUDOCS 9004250186 | |
| Download: ML20034A989 (8) | |
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' UNITED STATES '
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NUCLEAR HEGULATORY COMMISSION '
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REGIONil'
.g 101 MARIETTA STREET.N.W.
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ATLANTA, GEORGI A 30323
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. Report Nos.:- 50-424/90-06 and 50-425/90-06 Licensee: Georgia Power Company P. 0. Box 1295
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Birmingham, AL 35201-Docket Nos.: 50 424 and 50-425 License Nos.: -NPF-68 and NPF-81-LFacility Name:
Vogtle 1 and 2 Inspection Conducted: March 5-9 and 18-23, 1990
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Inspector:-
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/d JH. L. Whitener
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F Ddte Signed Approve by:
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G. A. Belisle, Chief (.' Date Signed-s
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Test Programs Section o
Engineerir g ' Branch Division of Reactor Safety.
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SUMMARY
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Scope:
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This-routine, announced inspection was in the areas of local leak rate testing,..
verification of containm. ant integrity, and follow-up inspection.of'open items".
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Results:
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In the areas inspected, violations or deviations were not identified.
Within the scope of this inspection, the findings indicated that th'e licensee has developed and implemented a program of controls, procedures, and testing as required by Technical Specifications-(TSs) to maintain-containment' integrity. -
Appropriate containment related systems were available and adequate procedures were. implemented to periodically verify system operability..
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4 REPORT DETAILS
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Persons Contacted Licensee Employees t
- J. Aufdenkarape, Manager, Technical Support
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- H. Beacher, Senior Plant Engineer, Technical Support J. Cash, Operation Superintendent-
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J. Davis, Senior Plant-Engineer, Maintenance J. Digby, Operations ' Local Leak Rate Test-(LLRT) Coordinator M. Brandy, Technician, Instrumentation and Control-(I&C) Maintenance J. Hopkins, On Shift Operations Supervisor
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S. Kitchens, Assistant General Manager, Plant Operations-
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T. Lamb,-Foreman, I&C Maintenance
- A. Mosbough, Assistant General Manager, Plant. Support
J. Strouse, Technician, I&C Maintenance S. Swaason, Work Planning Supervisor J. Swartzwelder, Manager, Operations
Other licensee employees contacted 'during this inspection included
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craftsmen, engineers, operators, mechanics, -security force _ members =,
technicians, and administrative personnel.
NRC Resident Inspectors R. Aiello, Acting Senior Resident Inspector
- R. Starkey, Resident Inspector
^ Attended exit interview 2.
Containment Leak Rate Testing and Integrity (61720 and 61715)
Inspection in this area was performed to verify the development and implementation of programs, controls, procedures, and ' test activities
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which ensure that containment integrity is established,. monitored-and maintained consistent with the requirements of the TSs and Code of Feascal
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Regulations.
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Local Leak Rate Testing (61720)
An important part of monitoring and maintaining containment integrity is performance of periodic local leak rate testing to verify leak tightness of containment leakage barriers.
1he purpose of the inspection activities in this area was to as certain that the licensee's LLRT program was being conducted in compliance with NRC requirements.
The inspector reviewed LLRT procedures, evaluated test results, and witnessed local leak rate testing.
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(1) Procedure Review Eleven test procedures related to Type C local leak rate _-testing of the containment leakage barriers were reviewed. These tests included the following:
- j Penetration Description Revision
Demineralized Water Supply
23 Breathing Air Supply
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40-Fire Protection Water Supply ST 42_
Accumulation Nitrogen Supply
48 CVCS Normal Letdown
49 Excess Letdown 8 Sealwater Leak Off-
50 CVCS Charging 3-
Sump Pumps Discharge 3T-
Reactor! Coolant Drain Tank Vent.
-and Hydrogen Supply
81 Instrument Air-Line
A detailed procedure review was performed for the valves in'the l
above penetrations to verify adequate alignment for venting, draining, and adequate-boundary _al.ignment for leak rate testing.
For two penetrations, the inspector? reviewed' the isometric i
drawings to: verify the draining al_ignments.
No. significant
- i problems were ' identified'with regard to penetration venting, i
draining, valve -identification,- valve ' alignment or system restoration. Type B testing of electrical-penetrations was also
reviewed.
The Conax electrical penetrations are Type B tested
- i at calculated accident pressure.-(Pa)- each refueling outage.
L Further, the penetration pressure -_is left at 30 psig and monitored quarterly between -outages.
The inspector discussed-the penetration design with maintenance engineering and reviewed-the penetration design drawings.
Frcm this review,. the
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inspector' concluded that the polysulfone plugs, cap.and ferrule assemblies, and the double 0-ring flange seals are being properly tested.
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The inspector verified that the following-- attributes were
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included in the procedures reviewed to ensure adequate leak: rate
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testing of containment isolation boundaries:
i (a) LLRTs were performed at the calculated peak _ accident
pressure, Pa.
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(b) The LLRT procedures utilized approved methods for testing
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containment penetration boundaries and containment
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isolation valves (CIVs).
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q (c) Penetration leakage rates were determined using the maximum pathway leakage.
(d) The criteria 'and. response for LLRTs_ and combined leakage rate failure were incorporated in the test program procedures.
(e) Repairs.or modifications-to-containment isolation boundaries and CIVs were-preceded-and followed by~ LLRTs.
(f) The correct test frequency was specified.
(2) Records Review Implementation of the LLRT-program to' establish and maintain containment leak' tight barriers was reviewed - including records of performance, identification of problems, corrective actions,-
d retests, and test acceptance.
A detailed' review. of-Type B 'and.
Type C leak rate testing was. performed for the previouss refueling -outage on Unit 1 (October - December 1988) and on-i Unit 2 (October 1988 - February 1989).
Test ~ status and data sheets for the current _ Unit I refueling outage were also reviewed.
Records reviewed included the following:
h Airlock full pressure tests
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Airlock seal tests (
Purge valve tests
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Electrical penetrations
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Isolation valves i
Total local leak rate calculation (running' summation of j
Type B and Type C leak rates)
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l Procedure 28916 (updates of total. Type B and Type C leakage j
when a component-is retested) leak rate summations, i
In the review the inspector determined that:
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Data sheets were complete and test results were within the specified acceptance limits,
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i Data was tabulated and transferred to Procedure 28916 (controlling procedure for-verification that-the total local leakage does not exceed the 0.6 La limit).
Identified problems were corrected and retesting performed.-
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Tests were performed at the frequency required by NRC regulations.
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Pre-and post-maintenance-leak rate testing was _ adequately.
controlled through the riaintenance work order system, Responsibility for verification of these tests is centered with v
the operations and maintenance coordinators, shift supervisor, and-I&C maintenance foremen.
In addition to the record review. the inspector witnessed the local leak rate test. cn containment penetration 79,. Reactor Coolant Drain Tank Vent and Hydrogen supply.-
The inspector found that test personnel were knowledgeable of the test requirements and familiar with the test sequence. -The test procedure was present at 'the job site and completed.as the
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steps were performed.
No problems were,1dentified.
Based on discussions with licensee personnel, observations.by
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the inspector, and records reviewed - the. inspectors concluded that the licensee has_. developed and implemented the procedures -
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and controls necessary. to-establish and maintain.the leak. tight.
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integrity of the containment isolation boundary.
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ContainmentIntegrity-(61715)'
.j The purpose of inspection activities in this area was to verify that j
the licensee had developed and implemented procedures'and controls to
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meet the TS requirements that are intended to ensure _the operability
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of those containment related; systems designed to prevent or mitigate the release of radioactivity from the containment post accident.
For this purpose, portions of the following containment related systems y
designed to mitigate the consequence-of a LOCA were inspected for
compliance with the plant TSs:
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Containment isolation valve alignment-checks, stroke time. and
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operability tests,
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i Containment personnel airlocks, Containment internal pressure and. temperature limits, Containment combustible gas monitoring system,
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Containment depressurization system - containment spray,
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Containment depressurization system containment spray
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additive, Containment depressurization system - containment cooling, andi Containment ventilation system.
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i For selected TS requirements _on these systems,.the inspector reviewed'
surveillance test procedures and records for 1989 (except-for daily or weekly tests which were reviewed for one month) to verify that:
Surveillance test procedures Lare establishedLwhich address the TS requirements.
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The test procedures / contain instructions, acceptance criteria, and limits rappropriate to the TS requirements.
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The surveillance tests' were performed at the frequency l required ~
by the TSs.
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Corrective ~ action and retest' were performed when problems were i
identified.
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The sample cf surveillance' records reviewed by the inspector included -
the following:
14475-1, Containment Integrity Verification -' Valves Outside Containment (Frequency:
Monthly).
54055-1, Train A Diesel Generator and_ Engineered Safety Features Actuation Test (Frequency: '18 Months).
24905-C, Personnel Airlock Leak Rate Test _ (Frequency:
When Required).
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14000-1~, Operations Shift and. Daily Surveillance Logs-(Frequency:
Daily) (Containment Temperature a.1d Pressure).
14485-1, Containment Spray System Flow Path Verification, j
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Monthly).
54070-1, Train A Containment Spray System-Automatic Actuation Test (Frequency:
18 Months).
14490-1, Containment-Cooling' System Operability Test (Frequency:
Monthly).
24551-1, Containment Hydrogen Monitor Train A-(Frequency:
Monthly / Quarterly).
14970-1, Hydrogen Recombiner Functional Test (Frequency:
Months).
24955-1, Containment Local Leak Rate Test - Penetration 83, (Frequency:
3 Months) (Purge Valves).
'14825-1, Quarterly Valve Inservice Test.
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28916-1, Containment Type A, B, a C Leakage Totalization Based on this sample review, th'e inspector concluded that the licensee has established-and. implemented periodic test procedures to ensure that the operability requirements specified in the TSs for
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containment systems designed to mitigate the consequences of an
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accident are maintained.
Within areas inspected, no violations or deviations were identified.-
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IE Bulletin and Supplement 81-02 Follow-up (92701).
(Closed) 50-424/81-BU-02:
Failure of-Gate Type Valves. to Close Against Differential Pressure.-
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The purpose of this Bulletin and Supplement are to request all licensees e
to investigate and' correct the failure for motor-operated gate valves to fully close at design differential pressure.
A letter dated September 20, 1989, from Westinghouse Electric Corporation-
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to Georgia Power Company summarizes the corrective action taken. in response to Bulletin 81-02 and Supplement 1. for' their-electro-mechanical
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division motor-operated gate valves supplied to Georgia Power Corporation, Vogtle Unit 1.
The inspector reviewed the corrective actions taken for specific valves'.-
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Corrective actions included increasing torque switch settings, replacing the spring pack with a stiffer spring pack. increasing actuator gear ratics, and setting up valves to limit close-in lieu of torquing close.
The inspector considered that actions taken in response to-Bulletin 81-02 and its supplement to be adequate for Unit 1.
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Action on Previous Inspection Findings (92701)-
(Closed) Inspection Followup Item (IFI) (424/89-31-03-and 425/89-36-03):
Questions Regarding Pressurizer Safety Valve Setpoint Test Methods Furmanite's pressure assist device, one method utilized by the licensee to determine pressurizer safety valve.setpoint, differentiates between simmer and actual setpoint by evaluating the strip chart recorder's output in conjunction with monitoring for a loud noise.
For simmer the strip chart output slope change is not as distinct nor does a loud noise occur.
Wyle's, set pressure test method..another method utilized by the' licensee to determine pressurizer safety valve setpoint. ' differentiates between simmer and actual setpoint by measuring the pressurizer safety valve disk lift and steam pressure.
The magnitude of the disk lift is much less for simmer than actual setpoint.
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The reason for the offset between set pressure and disk' lif t graphs was due to a three millimeter programmed offset between the two graphs.
Set-
-t pressure, in reality, occurs at the same time a: disk lift but lags on the
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chart because of the three millimeter offset, s
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Exit Interview
i The inspection scope and results were. summarized on March 23, 1990,'with
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those persons indicated in paragraph-1.
The inspector described the areas inspected and discussed in detail the. inspection results listed below.
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Proprietary information is not contained in this report.
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