ML20147D108
| ML20147D108 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/31/1978 |
| From: | Madsen G, Spangler R, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20147D084 | List: |
| References | |
| 50-268-78-24, 50-313-78-16, NUDOCS 7812190061 | |
| Download: ML20147D108 (6) | |
See also: IR 05000313/1978016
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U. S. NUCLEAR REGULATORY COMMISSION
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0FFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report Nos. 50-313/78-16
50-368/78-24
Docket Nos. 50-313
License No. DPR-51
50-368
Construction Permit No. CPPR-89/
Facility Operating License NPF-6
Licensee:
Arkansas Power and Light Company
P. O. Box 551
Little Rock, Arkansas 72203
Facility Name: Arkansas Nuclear One (AN0), Unit Nos. 1 and 2
Inspection At: ANO Site, Russellville, Arkansas
Inspection Conducted:
September 25 - October 22, 1978
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Inspectors:
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'T. F. Westerman,-Reactor Inspector
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" R. G. Spangler,LReactor Inspector (Intern)
Date
Approved By: h
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G. L. Madsen, Chief, R;tetor Operations and
Da'te
Nuclear Support Branch
Inspection Sunmary
Inspection During Period of September 22 through October 22, 1978 (Report
No. 50-313/ 78-16)
Areas Inspectg:
Routine, unannounced inspection of plant operations. The
inspection involved 17 inspector-hours on-site by cne NRC inspector.
Results:
Within the one area inspected, one infraction relative to jumpers /
bypasses was identified (DETAILS, paragraph 3).
Irspection During Period of September 22 through October 22, 1978 (Report
No. 50-368/78-24)
Areas Inspected:
Routine, announced inspection of the startup program; the
event of September 16, 1978; and license conditions for Modes 1 and 2
operation.
The inspection involved 36 inspector-hours on-site by the
resident inspector.
Resul t_s : Within the three areas inspected, no items of noncompliance were
identified.
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DETAILS
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1.
Persons Contacted
Arkansas-Power & Light Company Employees
G. H. Miller, Acting ANO Plant Manager
L. Alexander, QC Engineer
J. R. Anderson, Assistant Production Startup Supervisor
B. A. Baker, ANO-2 Operations Supervisor
R. L. Bata, QA Engineer
T. N. Cogburn, Nuclear Engineer
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E. C. Ewing, Production Startup Supervisor
D. R. Hamblin, QC Engineer
T. Holcomb, Scheduler '
P. Jones, Maintenance Supervisor
S. M. Strasner, QC Engineer
B. A. Terwilliger, Supervisor Plant Operations
R. Elder, Instrument Supervisor
J. Robert'on, ANO-1 Operations Supervisor
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T. Ennis, Licensing
S. Petzel, Licensing
D. Williams, Licensing Manager
F. Foster, Mechanical Maintenance Supervisor
G. Bruss, ANO-2 Shift Supervisor
M. Stroud, Electrical Maintenance Supervisor
Bechtel Employee
R. Ramey, Bechtel Startup Engineer
2.
Plant Status
Unit 1
Steady state 100% power operation.
Unit 2
Post core hot functional testing is in progress.
Problems have been
encountered in performing the flow coast down test due to the malfunction
of a D/P cell across the reactor coolant pumps.
Repair may require a
plant cooldown.
Estimated criticality date is now the week of
November 13.
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3.
Review of Plant Operations (Unit 1)
The inspector conducted a review of plant operations by:
a.
Performing a review of plant logs and data sheets for the quarterly
period of July through September; and
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b.
conducting a tour of selected areas within the plant to
observe general housekeeping and to verify selected component
configurations.
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During the review of plant logs and data sheets, the inspector found
that bypass tag numbers 77-121-1 and 77-121-2 annotated on Bypass /
Jumper log sheet No. 320 had not been verified by an individual on
their removal'on March 15, 1978.
Procedure 1005.04, Control and Use
of Bypasses and Jumpers, in paragraph 6.1.6, requires the initials of
not only the individual removing the tag but also a second individual
to verify the removal. 'The failure to properly verify the removal of .
the above tags as required by procedure 1005.04 is contrary to Technical Specification 6.8.1 and constitutes an ' item of noncompliance at the
infraction level.
Within the remaining areas of the inspection, the inspector identified
several minor discrepancies that were corrected and discussed with
licensee representatives. No further items of noncompliances or
deviations were identified.
4.
License Conditions Unit 2 for' Modes'1 and 2 (Unit 2)
The inspector reviewed the conditions identified in Attachment 2 to
Amendment No. 1 of NPF-6. The status is as follows:
a.
Mode 2 (Initial Criticality)
(1) Startup Punchlist Items
The list has been reduced to the following systems:
PlantProtectiveSystem(1)
Air and Gas Radiation Monitors (1)
Liquid Radwaste System (1)
(2) Preoperational Tests
Preoperational Test 2.083.01, Main Steam Supply and Safety
Relief Valves, has been completed.
RIV's review of test
data is not complete.
(3) Outstanding Startup Program Test Deficiencies
The RIV review of test deficiencies is not complete.
(4) Unit Load Transient Test 2.800.01, Appendix U
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Revision 1 to this procedure was issued September 27, 1978.
This issue is considered closed.
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(5) Main Feedwater Line Break Witnin Containment Piping
Penetration Room
Required design changes are scheduled to be coupleted by
October.
(6) Radiation Protection
Calibration of radiation protection equipment is still in
progress.
Estimated completion date is October 29, 1978.
(7) Hanger Installation
Three hangers remain to be installed and work is in progress.
(8)
Independent DC Power Supplies for the Series Containment
Penetration Breakers
The Design Change Package (DCP-638) that installed this
design change has been completed by Job Order 5450 on
August 29, 1978.
This issue is considered closed.
(9) Discrepancies in Facility Operating Procedures
A permanent change to 2304.92 through 95 was being prepared
to provide for comparison of the addressable CPC constants
before and after testing.
This is the only discrepancy
remaining.
(10) Hydrogen Purge System Test
This issue remains unresolved and the necessity for maintain-
ing this system is currently under review by NRR.
(11) Low Pressure Safety Injection Pump Motor Failure
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This issue was closed in IE Inspection Report 50-368/78-23,
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paragraph 14.d.
(12) Loose Part in the Safety Injection System
The licensee had initially reported that during repair of
valve SI-18 a pin was found to be missing.
Subsequently,
during discussions with the maintenance personnel involved,
the licensee determined that the missing pin had not been
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reinstalled during earlier maintenance activities.
Actions
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have been taken by the licensee to provide instruction to
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the maintenance personnel involved to prevent recurrence.
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This issue is considered closed.
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b.
Mode l'(Power Operation)
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(1) Startup Punchlist Items
The following systems have outstanding startup punchlist
items which affect their operability.
- Control Room H&V (1)
Miscellaneous-H&V (1)
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FeedwaterSystem(1)
Fuel Pool and Auxiliaries (6).
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Waste Gas System (1)
Solid Radiation Waste System (1)
Main Steam System (2)
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(2) CESEC Code' Instrumentation
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The instrumentation for verification of the CESEC Code has
been obtained.
The inspector will verify its installation
prior to Mode 1.
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There were no items of noncompliance or deviations identified during
the inspection of this item.
5.
September -16, 1978 Incident (Unit 2)
During the period of this resident inspection report, a special
inspection was conducted of the September 16, 1978 incident involving
initiation of the Unit 2 Engineered Safety Feature Systems and spray
down of the Unit No. 2 containment building.
(SeeIEInspectionReport
No. 50-368/78-25.)
Subsequent to this inspection, the licensee had proposed the following
preliminary plant changes and testing with respect to the instrument
inverters 2Y11, 2Y13, 2Y22 and 2Y24.
a.
The input circuitry associated with fuse FU-2 which was
found blown in 2Y24 is to be verified to be in accordance with
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the vendor's recommendations for each inverter,
b.
The current and voltage pots associated with the static transfer
switch are to be adjusted to their extreme position on each
inverter, i .e. , 185-190 amps vice the present nominal 154 amps on
overcurrent, and 20-30 volts vice the present 84 volts on under-
voltage. The licensee stated that the current setting of 190 amps
should cause .the inverter to go 'to 0 volts output as the result of
the saturation of the inverter output transformer.
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Each inverter is to be tested for the following:
c.
(1) Operation on their respective DC bus with the normal
rectified 480 volt AC input de-energized.
(2) Tripping of the undervoltage coil associated with each
of the 480 volt essential buses.
This would allow the
emergency diesels to start and assume the load on each
essential bus.
(3) De-energizing the power to the DC bus battery charger and
cycling of the breaker associated with the 480 volt AC
input.
(4) Determine if transfer switch operation does occur with
energization of the battery eliminator circuits associated
with the Reactor Trip Switchgear.
This circuit draws
approximately 200 amps of starting current.
(5) Perform a load test of each inverter and verify appropriate
settings.
No items of noncompliance or deviations were identified during the
inspection of this item.
6.
Pc o Core Hot Functional Test (Unit 2)
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Tht: inspector reviewed the Test Director's Log for the period of
September 11, 1978 through October 12, 1978.
This log provides a
chronological record of the post core hot functional test program.
The inspector also reviewed the master sequence document 2.650.01
for the post core hot functional test which was in progress.
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No items of noncompliance or deviations were identified.
7.
Exit Meetings (Units 1 and 2)
Exit meetings were conducted on September 29, October 11 and
October 20, 1978 with Mr. Terwilliger and other members of the plant
staff.
The inspectors discussed the scope of the inspection and
summarized the inspection findings which are detailed in this report.
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