ML19343C654
| ML19343C654 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/09/1981 |
| From: | Kellogg P, Rogers R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19343C641 | List: |
| References | |
| 50-321-81-04, 50-321-81-4, 50-366-81-04, 50-366-81-4, NUDOCS 8103240848 | |
| Download: ML19343C654 (10) | |
See also: IR 05000321/1981004
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 30303
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Report Nos. 50-321/81-04 and 50-366/81-04
Licensee: Georgia Power Company
270 Peachtree Street, N.W.
Atlanta, GA 30303
Facility Name: Hatch I and 2
Docket Nos. 50-321 and 50-366
Inspection at Hatch ne
Baxley, Georgia
Inspector:
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R. F. R3gers
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Oate Signed
Approved by:
P. Kellogg, Section Chief, Reactor Project 2B
Date Signed
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SUMMARY
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Inspection on January 10, - February 20, 1981
Areas Inspected
This inspection involved ~108 inspector-hours on cite 'in the areas of technical
specification compliance, reportable occurrences, housekeeping, operator per-
formance, overall . plant Loperations, c,uality a'ssurance practices, station and
corporate management practices, corrective and preventive maintenance activities,
site security -procedures, radiation control activities and surveillance
activities.
Results
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Of the eleven areas inspected, no apparent violations or deviations were identi-
fled in' ten areas,-two violations were identified in one area (inoperability of
the core spray system
paragraph 5).
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DETAILS
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1.
Persons Cortacted
Licensee 81ployees
- M. Manry, Plant Manager
- T. Moore, / ssistant Plant Manager
- T. Greene, Assistant Plant Manager
S. Baxley, Superintendent of Operations
R. Nix, Superintendent of Maintenance
C. Coggins, Superintendent of Engineering' Servides
W.. Rogers, Health Physicist-
C. Belflower. QA Site Supervisor
Other licensee employees contacted included technicians, operators,
mechanics, security force members, and office personnel.
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized.on January 30, -February 6
and February 20, 1981 with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings
'a.
Noncomp1.iance
(Closed) (321, 366/80-14-01):
Excessive Radiation Levels in a truck
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HNP-8016,'. . Shi pment of. Radioactive Material, .was' acceptably
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' revised on 10/27/80 to ' address this concern. This item is' closed.
(Closed) (321, ~ 366/80-17-01)!
Violations of ' secondary containment
integrity. ' A design change has been implemented on secondary contain-
ment doors which assures that containment integrity is maintained.
This item is closed.
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(Closed) (321, 366/80-19-04):
Failure of SRB to Audit Emergency
Implementing Procedures as required by T.S.
The required audit has
been completed and the report issued. This item is closed.
-(' Closed) (366/80-35-01):
Inoperable SDV high level scram switches.
The~li,censee has modified h.is procedures to require a functional test
' .following each scr'am. . This item is. closed..
(Closed) (321, 366/80-42-01):
Failure- of workers to follow HP
procedures.
The licensees corrective . action of providing more sur-
veillance of HP activities in this area has been adequate. This item is
closed.
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(Closed) (321, 366/80-42-02):
Failure of HP Technicians to follow
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procedures.
The licensees corrective actions have been effective.
This item is closed.
b.
Unresolved Items
(Closed) (321/77-1/1): Analysis of RPV Transients. HNP-1-3981 Rev. 4,
Commulative Fatigue Usage Factor Monitoring, was issued on 12/19/80.
This item is closed.
(Closed) (321, _366/80-19-01):
Failure of plant manager to attend
emergency duty officer training.
Required training was completed on
5/30/80. This item is closed.
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(Closed) (321, 366/80-19-03): QA Audit of emergency plan open items.
The referenced open items have been closed. This item is closed.
_(Closed) (321/78-29-03, 366/78-37-03):
HNP-809, Plant Modifications, revised to address this concern. This
item is closed.
.(Closed) (366/78-22-01): Improper breaker alignment in a MCC'. Unit 1
and 2 MCCs have been modified to address this issue. This item is
closed.
c.
Open Items
(Closed) (321, 366/80-06-02): Classification of Operating Procedures.
This item ,is closed.
(Closed) (321,,366/80-06-05): ,' Sm'allbreak (OCA Procedure. ' HNP-1902,
'
'
' Pip'e Break Inside' ~~ Primary Containment, sas suitably ' revised on
12/19/80. This item is closed.
(Closed)-(321, 366/80-19-02): . Emergency operating procedure reviews
' not 'compl ete. All required reviews complete as of 11/21/80. This item
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is closed.
(Closed) (321, 366/80-06-03):
Training deficiencies in emergency
training of operators. These have been corrected. ,This item'is closed.
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4.
Unresolved Items,
Unresolved items we.re not identified during this inspection.
5.
- Plant' Operations 'R$ view '(Uriits 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
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records of equipment malfunctions. 'This review included control room logs,
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auxiliary. logs, operating orders, standing orders, jumper logs and e_quipment-
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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.
On January 26, 1981, with the Unit 2 refueling outage in progress, prepara-
tions were being made to perform the RPV Hydro Procedure, HNP-2-1230, when
Technical Specification 3.5.2.1.b.2
was inadvertently violated
for
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approximately'seven'(7) hours. This specification requires both subsystems
of th.e core spray (CS) to:be operable when the torus is drained. The manual
isolation valves, 2E21-F007A&B, were closed as part of the valve lineup
procedure for HNP-2-1230.
The hydro itself was not to be performed until
the torus was filled and core spray was not required.
Because the valve line.up was commenced . prior to filling the torus (not
normally the case) and the procedure did not contain a caution or condition
for making CS inoperative, the technical specification was violated.
The
-condition was identified by a shift supervisor who was checking the system
lineup and noted that the valves should not be shut.
It was properly
reported to the NRC by the licensee. Had the same situation developed on
Unit 1, it would not have been a. problem because of different technical
specification requirements. The failure to comply with T.S.3.5.3.1.b.2 is a
violation'(366/81-04-01) and the failure of the Plant Review Board (PRB) to
adequately review HNP-2-1230 as required by T.S. 6.8.2 is also a violation
(366/81-04-02).
6.
Plant Tours (Units 1 and 2)
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The ' inspect'or codducted' plant ' tours ~ periodically during the inspection
interval to verify that monitoring equipment was recording as required,
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equipment was properly ! tagged, operations personnel were aware of plant
conditions, and plant housekeeping efforts were adequate.
The inspector
also_ determined that appropriate radiation controls were properly
established, critical clean areas were being controlled in accordance with
procedures, excess equipment or material is stored properly and combustible
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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-
positions, equipment caution and danger tags and component positions,
adequacy of fire fighting equipment and instrument calibration dates. Some
tours were conducted on backshifts.
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'Within the a'reas "inspec'ted 'no violation orl deviations were identified.
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-7.
Technical Specification Compliance (Units 1 and 2)
During - this. reporting interval, the inspector verified compliance with
selected limiting conditions for operations (LCO's) and results of selected
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surveillance tests.
These verifications were accomplished by direct
observation of monitoring instrumentation,
valve positions,
switch
positions, and review of completed logs and records.
The licensee's
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compliance with selected LCO action statements were reviewed on selected
occurrences as they happened.
Within the areas inspected no violations or devi-tions were identified.
8.
Physical Protection (Units 1 and 2)
The inspector. verified by. observation and interviews during the reporting
interval that measures taken to assure the physical protection of the
facility met current requirements. Areas inspected included the organiza-
tion 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.
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9.
Review of Nonroutine Events Reported by the Licensee (Units 1 & 2)
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The following Licensee Event Reports (LERs) were reviewed for potential
generic impact, to detect trends, and to determine whether corrective
actions appeared appropriate. 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 were of utmost con-
sideration.
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LER No.
Datd of Report
Description
50-321/80-8';
l'/30/80.
Secondary containment violation
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/80-21
3/13/80
Secondary containment violation
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/80-22
3/11/80
Door annunciation to cableway
/80-23
3/10/80
HPCI Inoperative
./80-28
4/1/80
Secondary containment violations
/80-33
4/30/80
Seal on Unit 2 CST Slab
/80-40
5/15/80
Drywell to Torus Low 0/P
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- /80-5'5' . 76/11/80 '
MechanicaU snubber failures
/80-58
7/8/80
CRD Accumulator problem
/80-62
6/25/80
PSW pipirJ backfill
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/80-69-
7/10/80
High D/P HPCI isolation
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/80-70
7/22/80
Snubber failure
/80-74
7/24/80
RCIC failure
/80-76
7/14/80
RHR suction seismic supports
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/80-78
7/15/80
0xygen 4% on 2 occasions
/80-79
7/17/80
Smoke detector problems
/80-80
7/17/80
RWCU System cracks
/80-82
7/30/80
LPCI . inverter failure
- /80-83
8/5/80
ADS functional test 0/D
/80-84
'8/26/80
. Faulty HPCI amplifier
/80-85
8/7/80
Chloride analysis
/80-86
8/4/80
Instrument air supports
/80-89
8/14/80
Stripped gear in printer
/80-91'
8/12/80
Fan motor failure
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/80-92
8/29/80
LPCI inverter trip
/80-93
8/19/80
Torus level recorders inoperative
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..)80-96'-
9/23/8'O
.High. temp,in torus /drywell
/80-99
8/28/80-
Room unlocked
/80-87'
8/5/80
RCIC ~ pump discharge anchor
/80-100
9/5/80
D/W cooler service water
/80-101'
9/9/80
Missed standing order
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/80-102. -9/9/80
. Inverter trip-
/80-102
9/9/80
Snubber failure
-/80-105
~10/2/80- .-
Vibration in RHRSW p' ump
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./80-108
L10/14/80-
HPCI system trip
-/80-109
10/16/80
Overnead fire doors-
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/80-111-
11/24/80
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/80-113
12/16/80
Nitrogen tank low
/80-115
11/11/80
Masonry block wall stress
/80-118
1/6/81-
RHR inboard injection valve
/80-119
12/30/80
Fission product monitor setpoint drift
/80-120
12/19/80
N2 tank level low
/80-121
12/30/80
D/W temperature high
./80-122
12/30/80
Sprinkler hangers inadequate
/80-123
1/15/80
/80-124
1/15/81.
' Control room air valve timing
/80-126
1/16/81
Low N2 pressure
/80-127
1/13/81
Valve inspections
/80-128
1/27/81
High D/W pressure relay failure
/81-01
1/15/81
HPCI pressure switches
-/81-02
1/27/81
High leakage in the D/W
50-366/80-17
3/13/80
Vacuum pump failure
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/80-22
3/13/80'
'MSIV leakage high-
/80-24:
3/31/80
"D" RHRSW pump low flow
/80-45
4/15/80
ADS leak test
/80-54
6/17/80
Containment purge pressure switch
-/80-55
5/29/80
RCIC outboard steam valve.
/80-73
~5/20/80
- Hydrogen recombiner problem
/80-96
7/9/80
Reactor building to torus vacuum -
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/80-97
7/15/80
HPCI steam line' flow high
/80-98
7/14/80
HPCI suction gage out'of calibra-
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7/17/80
D/W Hydrogen - oxygen ' analyzer
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'-/80-100
7/8/80-
ECCS switches out of calibration
/80-101-
7/29/80
Injection valve failure
/80-102
8/5/80
' Late surveillance
/80-103
7/17/80.
. ADS switches out of calibration
/80-104' - 8/5/80-
-Switchgear 2F breaker trip
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/80-105
9/19/80
/80-106
. 8/26/80-
Chemicals on DN shield
/80-107
8/4/80
. Jet pump integrity
'/80-108
8/6/80
Torus to D/W vacuum breaker _
/80-110- ' 8/4/801
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SDV valve found shut
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/80-111
8/19/80
_HPCI inboard, isolation valve shut
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/80-112
' 8/19/80:
HPCI DP switch inoperative
c/80-113- ' 8/25/80
SDV high level _ switches inoperative
!
- /80-115 ~ 8/20/80
-2C,0/G failure
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-/80-116 ^8/19/80:
. Torus' temperature high
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-/80-117- - 8/19/80:
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- RCIC failed reset
~/80-118- 8/19/80.
failure
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'/80-119
8/29/80
Fire barrier penetration-
/80-120
8/21/80
. Recirc pump trip
/80-121
8/9/80
Pressure switch drift.
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iHigh RX' press _ switch.out ofc
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calibratiori-
/80-123
8/29/80
RCIC outboard isolation valve
J/80-124
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Torus-D/W vacuum breaker indica-
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/80-125
9/11/80
MSIV leakage control system
/80-126
9/9/80
inoperative
/80-127
9/23/80
2C D/G failure
/80-128
-9/23/80
Rx press inst. ou' of calibration
/80-129
9/30/80
Torus - D/W vacuum breaker
failure
./80-130
9/30/80
Hydrogen - oxygen analyzer inop
/80-133
10/9/80
Reactor level switch tripped high
/80-135
10/16/80
High conductivity
/80-136
10/14/80
Seismic PSW support
-/80-137
10/21/80
HPCI exhaust pressure switch
./80-139
10/21/80
D/W drain line not seismic
/80-140
10/23/80
D/W Vacuum breakers not tested
/80-141-
11/4/80-
HPCI D/P switch set high
/80-142
'1'1/7/80
~ Break in fire wall
/80-l'45' ~:11/26/80
Standby service water pump flow and
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head low
/80-146'
11/24/80~ ~
"B" D/G B1ower failure
/80-147
'11/13/80
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inoperative
/80-148
.11/13/80
Low level in torus
/80-149
11/26/80
- RFR pump suction valve leak
/80-150
'11/20/80
HPCI isolation low pressure
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- 180-151'
12/6/80-
FW isolation valve leakage.
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/80-157
1/6/81-
Hoist inspection not done
/80-159
12/19/80-
2C D/G failure.
/80-161-
12/16/80
.SRV surveillance failures
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/80-163
12/23/80
Reactor head insulation not seismic
/81-02
1/29/81
RCIC isol. switches out of cali-
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