ML19209C999
| ML19209C999 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/30/1979 |
| From: | Dance H, Rogers R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19209C997 | List: |
| References | |
| 50-321-79-26, 50-366-79-30, NUDOCS 7910180567 | |
| Download: ML19209C999 (4) | |
See also: IR 05000321/1979026
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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101 MARIETTA ST., N.W., SulTE 3100
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ATLANTA GEORGIA 3o303
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Report Nos. 50-321/79-26 and 50-366/79-30
Licensee: Georgia Power Company
270 Peachtree Street, N. W.
Atlanta, Georgia 30303
Facility Name: Hatch I and 2
Docket Nos. 50-321 and 50-366
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Inspection at Hatch Site near Baxley, Georgia
Inspector:
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pate Signed
Approved by:
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H. C. Dance, Section Chief, RONS Branch
Dste S'igne'd
SUMMARY
Inspection on July 4-August 3, 1979
Areas Inspected
This inspection involved 110 inspector-hours onsite of the Unit I refueling
outage, Unit 2 startup testing, technical specification compliance, IE Bulletins
and Circulars, reportable occurrences, housekeeping, operator perforuiance,
overall plant operations, quality assurance practices, station and corporate
management practices, corrective and preventative maintenance activities, site
security procedures and radiation control activities.
Results
Of the thirteen areas inspected, no apparent items of noncompliance or devia-
tions were identified.
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79101806Q
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DETAILS
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1.
Persons contacted
Licensee Employees
- H. 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 of Engineering Services
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W. Rogers, Health Physicist / Radiochemist
C. Bellflower, QA Site Supervisor
Other licensee employees contacted included technicians, operators, mechan-
ics, security force members, and office personnel.
- Attended exit interview.
2.
Exit Interview
The inspection scope and findings were summarized on July 13, 20, 27 and
August 3, 1979 with those persons indicated in paragraph I above.
3.
Licensee Action on Previous Inspection Findings
Not inspected.
4.
Unresolved Items
Unresolved items were not identified during this inspection.
5.
Tours of the Plant (Units 1 and 2)
The inspector conducted plant tours periodically during the inspection
interval to verify that monitoring equipment was recording as required,
equipment was properly tagged, operations personnel were aware of plant
conditions and were alert, and plant housekeeping efforts were adequate.
Some tours were conducted on backshifts and on weekdends.
6.
Review of Nonroutine Events Reported by the Licensee (Units I and 2)
The following licensee event reports (LERs) were reviewed for potential
generic problems, to detect possible trends, and to determine whether
corrective actions appeared sppropriate. Events which were reported
immediately were also reviewed as they occurred to determine that technical
specifications were being met and that the public health and safety was of
utmost consideration.
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50-321/79-27
5/7/79
Valve Seat Leakage Excessive
50-321/79-28
5/17/79
Valve Seat Leakage Excessive
50-321/79-32
5/30/79
Cable Spreading Room Sprinkler
not Seismic
50-321/79-33
5/24/79
RHR Valve Leakage Excessive
50-321/79-36
5/30/79
Reactor Sample Valve Solenoid
not Environmentally Qualified
50-321/79-42
7/10/79
SBLC Inboard Isolation Valve
Leakage
50-321/79-43
7/3/79
Radwaste Sump Discharge Line not
Seismic
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50-321/79-45
7/12/79
SBLC Relief Valve Lifted Low
50-321/79-47
7/27/79
RCIC Torus Suction Line not Seismic
50-321/79-48
7/30/79
MCC Breakers Undersized
50-366/79-36
5/30/79
Cable Spreading Room Sprinklers
not Seismic
50-366/79-56
7/10/79
Torus Level High
50-366/79-57
7/10/79
Loss of Service Water to Drywell
Cooling
50-366/79-61
7/13/79
RCIC Condensate Pump Trip
50-366/79-64
7/13/79
RCIC Inadvertent Isolation
50-366/79-65
7/18/79
RBM "A" Downscale Setpoint High
50-366/79-69
7/30/79
RCIC Inbosrd Isolation Valve Galled
50-366/79-70
8/1/79
Drywell Pressure Switch Set High
50-366/79-71
8/1/79
Drywell Airlock Handwheel Leak
50-366/79-22
8/1/79
Controller For RHRSW Pump
Inoperative
7.
liigh Pressure Coolant Injection and Reactor Core Isolation Cooling Malfunc-
tions and Test Programs (Units 1 and 2)
As a result of the simultaneous failures of the High Pressure Coolant
Injection system (HPCI) and the Reactor Core Isolation Cooling system
(RCIC) in June, the licensee completed an extensive test program on Unit 2.
This program was described in detail in IE report 50-321/79-24 and
50-366/79-28. The test program commenced on July 6, 1979 and was completed
on August 3, 1979. The test series consisted of approximately twenty five
automatic starts of HPCI and RCIC turbines under various plant operating
conditions. All starts were successful and four were observed by the
inspector.
Special instrumentation indicated that both systems sensed an
elevated steam flow D/P spike on system startup which approached the high
steam flow D/P isolation setpoint. The occurrence of this spike would
normally be expected under system initiation conditions. The licensee has
installed 3 second time delay relays in the isolation initiation logic
circuits for both HPCI and RCIC to further enhance system reliability. NRC
is evaluating this modification. Unit I will conduct a similar but abbre-
visted test program on HPCI and RCIC during post refueling testing to
assure that Unit I systems are operable and if circuitry modifications are
warranted.
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The Resident Inspector will continue to follow this item.
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8.
Technical Specification Compliance (Units 1 and 2)
During this reporting interval, the inspector verified compliance with
selected limiting conditions for operation (LCO's) and results of selected
surveillance tests. These verifications were accomplished by direct observa-
tion of monitoring instrumentaiton, valve positions, switch positions, and
review of completed logs and records. The licensee's compliance with
selected LCO action statements were reviewed on selected occurrences as
they happened.
9.
Voltage Regulator Problems (Unit 2)
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On August 3, 1979, Unit 2 tripped from full power due to rapid change in
load on the transmission grid.
It appeared that the excitation portion of
the voltage regulation circuit for the generator field had failed to re-
spond properly to the grid disturbance. The licensee has initiated an
investigation with General Electric, the generator manufacturer, to deter-
mine the cause.
10.
Followup on IE Bulletins
For the following Bulletins, the inspector verified that the response was
timely, included the required information, contained adequate commitments,
and that corrective action as described in the written responses was complet-
ed.
IEB 78-10, Bergen-Patterson Hydraulic Shuck Suppressor Accumulator
a.
Springs
The inspector verified that this concern had been addressed by the
licensee for Unit I during the current outage. Affected snubbers have
been repaired. This item is closed.
b.
IEB 79-11, Faulty Overcurrent Trip Devices in ECCS Circuit Breakers
The inspector reviewed the licensee's response dated June 19, 1979
which indicated that these circuit breakers are not in use in either
unit at Hatch. This item is closed for both units.
11. Followup on IE Circulars
For the following circulars, the inspector verified that the circular was
received, reviewed, and corrective actions taken or planned if appropriate.
IEC 78-14, HPCI Turbine Reversing Chambcr Hold Down Bolting
IEC 78-19, Manual Overide of Safety Systems
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