ML20127F257
| ML20127F257 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 04/22/1985 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20127F234 | List: |
| References | |
| 50-321-85-09, 50-321-85-9, 50-366-85-09, 50-366-85-9, NUDOCS 8505200375 | |
| Download: ML20127F257 (3) | |
See also: IR 05000223/2003024
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APR 221985
ENCL 0SURE 1
Georgia Power Company
Docket Nos. 50-321 and 50-366
Hatch Units 1 and 2
The following violations were identified during an inspection conducted on
February 23 - March 24,1985.
The Severity Levels were assigned in accordance
with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).
1.
Technical Specification 6.8.1.c requires that written procedures be
established covering surveillance and test activities of safety-related
equipment.
Contrary to the above, written procedures were not established for Units 1
and 2 on February 28, 1985, to cover the following Technical Surveillance
Requirements on safety-related systems:
a.
Unit 1 Technical Specifications 4.6.0 and 4.6.E require the permanent
recording of reactor coolant temperatures in the operating loop, idle
loop, steam dome and bottom head drain prior to startop, of an idle
recirculation loop.
Retention of recorder tapes for these parameters
is 5 years vs. permanent and no other logging is specified by Hatch
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procedures.
b.
Unit 1 Technical Specifications 4.6. A and Unit 2 Technical Specifi-
cations 4.4.6.1.1 require that reactor coolant system temperature and
pressure be verified within limits at least every 30 minutes during
reactor coolant heatup and cooldown,
c.
Unit 2 Technical Specifications 4.4.6.1.2 requires that reactor coolant
system temperature and pressure be verified within limits within 15
minutes prior to withdrawal of control rods to bring the reactor
critical.
This is a feverity Level IV violation (Supplement I).
2.
Technical Specification 3.6.B requires that:
The reactor vessel shell temperatures during inservice hydrostatic or
leak testing shall be at or above the higher of the temperatures shown
on the curves of Figure 3.6-2 where the dashed line curve, RPV core
beltline region is increased by the expected shif t in RT
from
NOT
Figure 3.6-1.
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APR 231985
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Georgia Power Company
Docket Nos. 50-321 and 50-366
Hatch Units 1 and 2
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During heatup by non nuclear means, cooldown following nuclear shutdown
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or low level physics tests, the reactor vessel shell and fluid
temperatures of Specification 4.6. A shall be at or above the higher of
the temperatures shown on the curves of Figure 3.6-3 where the dashed
line curve, initial core beltline region is increased by the expected
shift in RT
from Figure 3.6-1.
NOT
During all operation with a critical core, other than for low level
physics tests, the reactor vessel shell and fluid temperatures of
Specification 4.6.A shall be at or above the higher of the temperatures
r
shown on the curves of Figure 3.6-4 where the dashed line curve,
[
fnitial core beltline region is increased by the expected shif t in
from Figure 3.6-1.
NOT
Contrary to the above, the licensee did not have a procedure issued to
implement the requirements of Technical Specification 3.6.B nor did the
licensee perform the required corrections of the stated curves.
This is a Severity Level IV violation (Supplement I).
Applicable to Unit 1
only.
3.
Technical Specification 6.8.1 requires that procedures shall be established,
implemented and maintained covering safety-related activities.
Contrary to the above:
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a.
Procedure HNP-1-3407, Suppression Chamber Delta Temperature (RCIC)
Instrumentation Functional Test and Calibration, was not properly
implemented in that on January 23, 1985 personnel placed clearance hold
tags on the Traveling Incore Probe (TIP) mode switches vs. the drive
switches as required by Procedure HNP-1-3407.
This resulted in the TIP
ball valves being unable to automatically shut upon receipt of a
Group 2 Primary Containment Isolation System (PCIS) signal as required
by Technical Specifications Table 3.7-1.
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b.
Procedure HNP-1-3417, RCIC Pump Suction Pressure Instrument Functional
Test and Calibration, and Technical Specification Table 4.2-3 Item 4,
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require monthly instrument functional test for RCIC pump suction
pressure instrument.
Proceduro HNP-1-3417 was not properly implemented
in that the required surveillance test was not performed within the
specified frequency time limits due to personnel error,
c.
Procedure HNP-2-3410, RCIC Steam Line Delta Pressure Instrument
Functional Test and Calibration, was not properly maintained in that a
revision was issued to the procedure which contained engineering errors
resulting in an improper and non-conservative set point for RCIC steam
line differential pressure.
This is contrary to Technical Specifi-
cation Table 3.3.2-2. Item 5.
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This is a Severity Level IV violation (Supplement I).
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Georgia Power Company
Docket Nos. 50-321 and 50-366
Hatch Units 1 and 2
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License Nos. OPR-57 and NPF-5
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Pursuant to 10 CFR 2.201, you are required to submit to this office within 30
days of the date of this Notice, a written statement or explanation in reply,
including:
(1) admission or denial of the alleged violations; (2) the reasons
for the violations if admitted; (3) the corrective steps which have been taken
and the results achieved; (4) corrective steps which will be taken to avoid
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further violations; and (5) the date when full compliance will be achieved.
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Security or safeguards information should be submitted as an enclosure to
facilitate withholding it from public disclosure as required by 10 CFR 2.790(d)
or 10 CFR 73.21.
A R 221985
Date:
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