ML20004B138
| ML20004B138 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/06/1981 |
| From: | Kellogg P, Rogers R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20004B116 | List: |
| References | |
| 50-321-81-09, 50-321-81-9, 50-366-81-09, 50-366-81-9, IEB-80-14, NUDOCS 8105270281 | |
| Download: ML20004B138 (6) | |
See also: IR 05000321/1981009
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION II
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101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, oEoRGIA 30303
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Report Nos. 50-321/81-09 and 50-366/81-09
Licensee: Georgia Power Company
270 Peachtree Street, N.W.
Atlanta, Georgia 30303
Facility Name: Hatch 1 and 2
Docket Nos.53-321 and 50-366
Inspection at Hatch site near Baxley, Georgia.
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Inspector:
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Oa'te Signed
Approved by:
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Reactor project Inspection
SUMMARY
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Inspection on February 21 - Maren
'.7, 1981
Areas Inspected
This inspection invoived 83 inspector-hours on site in the areas of technical
specification compliance, housekeeping, operator performance, overall plant
operations, quality assurance practices, sution and corporate management
practices, corrective and preventive maintenance activities, site security
procedures, radiation control activities, surveillance activities and IE
Bulletins and Circulars.
Results
Of the 10 areas inspected, no apparent violations or deviations were identified
in eight areas, two violations were identified in one area (protection of Spent
Fuel Pool High Density Racks - Paragrapn 6), one deviation was identified in one
area (Failure to conduct operability checks on SOV vent and dr ain valves as
committed
paragraph 10).
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DETAILS
1.
Persons Contacted
Licensee Employees
- M. Manry, Plant Manager
- T. Moore, Assistant Plant Manager
- T. Greene, Assistant Plant Manager
S. Baxley, Superintendent of Operations
R. Nix, Superintendent of Maintenance
C. Coggins, Superintendent * Engineering Services
W. Rogers, Health Physici .
C. Selflower, QA Site Supervisor
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Other licensee employees contacted included technicians, operators,
mechanics, security force members, and office personnel.
- Attended exit interview
2.
Exit Interview
The inspection scope and fintings were summarized on March 6,13, 20, and
27, 1981 with persons indicated in paragraph 1 above.
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3.
Licensee Action on Previous Inspection Findings
Not inspected.
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4.
Unresolved Items
Unresolved items were not identified during this inspection.
5.
Plant Operations Reviuw (Units 1 and 2)
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The inspector periodically during the inspection interval reviewed shift
logs and operations records, including data sheets, instrument traces, and
records of equipment malfunctions. This review included control room logs,
auxiliary logs, operating orders, standing orders, jumper logs and equipment
tagout records. The inspector routinely observed operator alertness and
demeanor during plant tours. During normal events, operator performance and
response actions were observed and evaluated.
The inspector conducted
random off-hours inspections during the reporting interval to assure that
operations and security remained at an acceptable level. Shift turnovers
were observed to verify that they were conducted in accordance with approved
licensee procedures.
Within the areas inspected, no violations or ceviations were identified.
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6.
High Density Storage Racks (Units 1 and 2)
The inspector reviewed documentation and procedures associated with the
licensees high de.csity storage racks.
Procurement dccuments, receipt
inspection documents, the storage condition and work and testing procedures
were inspected.
The interi., stcrage condition of the racks was not
adequate. Wind had torn away the protective plastic covering on a number of
the racks allowing dirt and debris to build up in the channels.
Sand-
blasting operations approximately fi f ty feet away contributed to the
hostile storage environment.
Further investigation revealed that a stowage level had not been assigned in
accordance wit" 2HNP-204, Equipment storage and is the subject of violation
(321, 366/81-61-01).
Also, a Nonconformance Report (No.81-223) was
initiated on February 18, 1981 describirig the inadequate protection of the
racks. When noted by the inspector on March 11, 1981, the condition had
still not been acted on.
The failure of the licensee to take prompt
corrective action to co" rect a condition adverse to quality is a violation
(321,366/81-09-02).
7.
Plant Tours (Units 1 and 2)
The inspector conducted plant tours periodically during the inspection
interval to verify that :nonitoring equipment was recording as required,
equipment was properly tagged, operations personnel were aware of plant
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conditions, and plant housekeeping efforts were adequate. The inspector
also determined that appropriate radiation controls were properly estab-
lished, critical clean areas were being cont.'olled in accordince with
proceciures, excess equipment or material is stored pre .trly and combustible
material and debris were disposed of expeditiously.
During tours the
inspector looked for the existence of unusual fluid leaks, piping vibra-
tions, pipe hanger and seismic restraint settings, various valve and breaker
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positions, equipment caution and danger tags and component positions,
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adequacy of fire fighting equipment and instrument calibration dates. Some
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tours were conducted on backshifts.
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Within the areas inspected, no violation or deviations were identified.
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8.
Technical Specification Compliance (Units 1 and 2)
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During this reporting interval, the inspector verified compliance with
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selected limiting conditions for operations (LCO's) and results of selected
surveillance tests. These verifications were accomplished by direct obser-
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vation of monitoring instrumentation, valve positions, switch positions, and
review of completed logs and records.
The licensee's compliance witn
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selected LCO action statements were reviewed on selected occurrences as they
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happened.
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Within the areas inspected, no violations or deviations were 10entified.
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9;
Physical Protection (Units 1 and 2)
The inspector verified by observation and interviews during the reg.orting
interval that measures taken to assure the physical protection of the
facility met current requirements. Areas inspected included the organi-
zation of the security force, the establishment and maintenance of gates,
doors and isolation zones in the proper condition, that access control and
badging was proper, and procedures were followed.
Within the areas inspected no violations or deviations were identified.
10.
Followup on IE Bulletins and Circulars (Units 1 and 2)
For the following IE Bulletins and Circulars, the inspector verified that
the response, if required, was timely, included the required information,
contained adequate commitments and that corrective action as described in
the written responses was completed or schedulea for completion.
For
circulars, the inspector verified that the circular was received, reviewed,
and appropriate corrective action taken or planned.
These Bulletins and
Circulars are addressed as they are issued and summarized below for record
purposes.
a.
IE Bulletins
(Closed) IES 79-02 Pipe Support Base Plate Designs Using Concrete
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Expansion Anchor Bolts. Based on reviews of licensee responses dated
July 6, September 14, and December 11, 1979 and inspections documented
in Report Nos. 321/79-07, 366/79-08, 321/79-15, 366/79-18, 321/79-27,
366/79-31, 321/79-31, and 366/79-35, this Bulletin (through Revision 2)
is closed. Anchor bolt performance during 1980 has been adequate on
both units.
(Closed) IEB 79-03A Longitudinal Weld Defects in ASME SA-312 Type 304
Stainless Steel Pipe Spools Manufactured by Youngstown Welding and
Engineering Company.
Based on review of Licensee Responses dated
April 16. June 22, and August 5,1980, this Bulletin is closed.
(Closed)
IEB 79-25 Failures of Westinghouse BFD Relays
in
Safety-Related Systems.
Based on review of the licensee responses
dated December 21, 1979, and followup by the inspector, these type
relays are not installed at the Hatch facility. This Bulletin is
closed.
(Closed) IES 79-28 Possible Malfuncation of NAMCO Model EA180 limit
switches at Elevated Temoeratures. Based on a review of the licensees
resconses dated January 8, 1980, and followup by the inspector, these
switches are not currently in use at the Hatch facility. This Bulletin
is cined.
(Closed) IEB 80-09 Hydramotor Actuator Deficiencies. Based on a review
of the licensee's response dated June 11, 1980 and followed by the
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inspector, these actuators are net installed at the Hatch facility.
This Bulletin is closed.
(Closed) IEB 80-10 Contamination of Nonradioactive System and Resulting
Potential for Unmonitored, Uncontrolled Release of Radioactivity to
Environment. Based on a review of licensee response dated June 19 and
July 18, 1980, and inspector folicwup onsite, the licensee has
adequately addressed the concerns raised and this Bulletin is closed.
(Closed) IES 80-14 Degradation of BWR Scram Discharge Volume Cap-
ability. Based on a review of the licensee's responses dated July 25
and August 13, 1980 and inspector onsite followup, the licensee has
appropriately addressed this item. The licensee, however, has failed
to perform the periodic checks of vent and drain valve operation
committed to in his July 25, 1980 response. This is the subject of a
deviation (321, 366/80-09-03). The Bulletin is closed.
(Closed) IEB 80-15 Possible Loss of Emergency Notification System (ENS)
with lose of Off-site Power. The inspecter reviewed the licensees
response cated October 23, 1980 and November 4,1980 and had no further
questions. This Bulletin is closed.
(Closed) IES 80-19 Failure of Mercury-Wetted Maxtrix relays in Reactor
Protective Systems of Operating Nuclear Power Plants Described by
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Combustion Engineering. Based on a review of the licensees response
dated August 29, 1980 and followup by the inspector, these relays are
not used at the Hatch facility. This Bulletin is closed.
(Closed) IEB 80-20 Failure of Westinghouse Type W-2 Spring Return to
Neutron Control Switches.
The inspector reviewed the licensees
response dated September 12, 1980 with the licensee and noted that this
type switch is not installed at the Hatch facility. This bulletin is
closed.
(Closed) IEB 80-21 Valve Yokes Supplied by Malcolm Foundary Company,
Inc. Inspector review of the licensee response dated November 26,1980
ct the site indicated that Anchor Darling Valves in safety-related
systems have yokes which were not supplied by Malcolm. This bulletin
is closed.
(Closed) IES 80-23 Failure of Solenoid Valves Manufactured by Valcor
Engineering Corporation. The inspector reviewed the licensees response
dated November 21, 1980 and followed up this item onsite. No Valvor
Solenoid Valves with the affected part numoers are onsite.
This
bulletin is closed.
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b.
IE Circulars
(Closed) IEC 79-02 Failure of 120 Volt Vital AC Power Supplies
(Closed) IEC 79-04 Loose Locking Nut on Limitorque Valve operators.
(Closed) IEC 79-05 Moisture Leakage in Stranded Wire connectors.
(Closed) IEC 79-07 Unexpected Speed Increase of Reactor Recirculation
MG Set resulted in Reactor Power increase.
(Closed) IEC 79-10 Pipefittings Manufactured from Unacceptance
material.
(Closed) IEC 79-12 Potential Diesel Generator Turbocharger Problem.
(Closed) IEC 79-17 Contact Problem in 58-12 Switches on GE metalclad
circuit breakers.
(Closed) IEC 7919 Loose Locking devices on Ingersoll-Rand Pump
Impellers.
(Closed) IEC 79-20 Failure of GTE Sylvania Relay.
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(Closed) IEC 79-21 Prevention of Unplanned releases of Radioactivity.
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(Closed) IEC 79-23 Motor Starters and Contractors failed to Operate.
(Closed) IEC 79-24 Proper Installation and Calibration of Core Spray
Pipe Break Detection Equipment.
(Closed) IEC 79-25 Shock Arrester Strut Assembly Imterference.
(Closed) IEC 80-02 Nuclear Power Plant Staff Work Hours.
(Closed) IEC 80-07 Problems with HPCI Turbine Oil System.
(Close } IEC 80-09 Problems with Plant Internal Communications Systems.
(Closed) IEC 80-14 Radioactive Contamination of Demineralized Water
System.
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(Closed) IEC 80-15 Loss of RCD Cooling and Natural Circulation Cool-
down.
(Closed) IEC 80-23 Potential Defects in Beloit Power Systems Emergency
Generators.
(Closed) IEC 81-02 performance of NRC-Licensed Individuals while on
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duty.
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