ML19246B751
| ML19246B751 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/14/1979 |
| From: | Chrissotimos N, Spessard R, Wong B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19246B676 | List: |
| References | |
| 50-254-79-12, 50-265-79-10, NUDOCS 7907180455 | |
| Download: ML19246B751 (13) | |
See also: IR 05000254/1979012
Text
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U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-254/79-12; 50-265/79-10
Docket No. 50-254; 50-265
Licensee: Commonwealth Edison Company
Post Office Box 767
Chicago, IL 60690
Facility Name:
Quad-Cities Nuclear Power Station, Units 1 and 2
Inspection At: Quad-Cities Site, Cordov.2, IL 60690
Inspection Conducted: May 1-24, 1979
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Inspectors:
N. J. Chrissotimos
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Approved By:
Reactor Projects Section 1
Inspection Summary
Inspection on May 1-24, 1979 (Report No. 50-254/79-12; 50-265/79-10)
Areas Inspected:
Special, announced inspection of licensee's response
The inspection involved 148 inspector-hours
onsite by two h3C inspectors.
Results: No items of noncompliance were identified.
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DETAILS
1.
Persons Contacted
- N.
Kalivianakis, Superintendent
J. Gudac, Assistant Superintendent
T. Tamlyn, Lead Operating Engineer
K. Graesser, Administrative Assistant
- L.
Gerner, Technical Staf f Supervisor
D. Bax, Opet. ting Engineer, Unit 2
G. Conschack, Operating Engineer, Unit 1
R. Spear, Maintenance Engineer
- J. Heilman, Quality Assurance, Operations
The inspector also interviewed several other litansee employees,
including shift engineers and foremen, reactor operators, tech-
nical staf; personnel and quality control personnel.
- Denotes those present at the exit interview.
2.
Onsite Review of Operator Training
Licensee administered operating training, as described in the
licensee's response to IE Bulletin No. 79-08, did not include a
completion date. The licensee's goal for completion of this
training is July 1, 1979. This matter will be reviewed during
subsequent inspections (254/79-12-01; 265/79-10-01).
Directives for early NRC notification of serious events are
contained within the generating stations Emergency Plan Pro-
cedures. Early NRC notification is a well established practice
of the licensee. As to the continuous communications channel
the licensee's position is as stated in item nine of the response
to the Bulletin. This matter, as well as the entire licensee's
response, will be reviewed by NRR.
No items of noncompliance were identified.
3.
Onsite Inspection of Safety Features
The inspector reviewed licensee procedures and checklists
a.
against P&ID's and single line diagrams to ensure that
when implemented, valve, breaker and switch alignment
would provide adequate alignment for system operation.
Included was a review of general abnormal procedures to
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verify that safety systems once initiated are not to be
overridden.
Operators, procedurally, may take manual
control if the system has not automatically initiated.
Procedures associated with water level transients designate
prime responsibility of monitoring level parameters to the
center desk operator.
The following procedures were reviewed:
Standby Gas Treatment - QOP-7500-1
QOP-7500-2
Core Spray - QOP-1400-1
QOP-1400-2
QOP-1400-3
QOP-1400-4
Standby Liquid Control - QOP-1100-0
QOP-1100-1
High Pressure Coolant Injection - QOP-2300-1
QOP-2300-3
QOP-2300-4
DC Electrical Systems - QOP-6900-1
QOP-6900-2
QOP-6900-3
RHR/LPCI - QOP-1000-8
QOP-1000-9
Reactor Core Isolation Coolant - QOP-1300-1
QOP-1300-2
QOP-1300-3
QOP-1300-9
Diesel Generators - QOP-6600-1
QOP-6600-2
QOP-6600-4
QOP-6600-6
Maintaini ag Primary Containment Integrity - QOP-1600-11
gg 245
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Post Accident. Venting of Primary Containment - QOP-1600-13
Radioactive Waste Water - QOP-2000-6
QOP-2000-23
QOP-2000-28
Drywell Pressure Relief thru Reactor - QOP-1600-3
Building Ventilation
Torus Pressure Relief thru Reactor - QOP-1600-4
Building Ventilation
Loss of Coolant - QGA-1
QGA-2
Major Steam Leak - QGA-3
High/ Low Reactor Water Lev-1 - QGA-4
QGA-5
Reactivity Addition - QGA-6
Loss of Flow - QGA-7
QGA-9
Loss of Auxiliary Electrical Power - QGA-12
No items of noncompliance were intocified.
b.
The inspector reviewed the accessible valve, breaker and
switch alignments both in the control room and in plant to
verify that their status was as indicated and were capable
of performing their intended function if necessary.
All in plant buses, motor control centers and respective
breaker position status were verified. The following
valve status was verified.
Residual Heat Removal System Valves
1001-160
1001-14
1001-161
1001-149
1001-127
1001-154
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1001-152
1001-27A-B-C-D
1001-153
1001-66A-B-C-D
1001-5A/B
1001-23A/B
1001-185A/B
1001-26A/B
1001-4A/B
1010-186A/B
1001-141A-B-C-D
1001-187A/B
1001-10A-B-C-D
1001-16A/B
1001-12A-B-C-D
1001-29A/B
1001-14A-B-C-D
1001-13A-B-C-D
RHR Service Water Pumps Valves
1001-1A-B-C-D
1001-3A-B-C-D
Standby Liquid Control Valves
All in Plant Valves except
1101 valve in Unit 2 drywell
Standby Gas Treatment Valves
7599-13
7507
7505
7503
7504
1/2 7509
7510
7559-14
Vacuum Breakers - Torus to Drywell Indication
Containment Valves
1601-62
1601-63
1601-23
1601-26
High Pressure Coolant
2301-15
2301-48
Injection Valves
1/2 2301-94
2301-80
2301-10
2301-81
2301-49
2301-33
2301-9
2301-47
2301-106A/B
2301-82
2301-93
2301-42
2301-14
2301-105
Reactor Core Isolation
1301-75
1301-61
Coolant System Valves
1301-17
1301-66A
1301-53
1301-664
1301-67C/E
1301-60
1301-62
1301-39
1301-46
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Core Spray Valves
1402-24A/B
1402-38A/B
,
1402-25A/B
1402-32A/B
1402-11A/B
1402-5A/B
1402-55A/B
1402-18A/B
1402-17A/B
1402-51A/B
1402-12A/B
ECCS Fill System Valves
1402-68
1402-69
33199-129
2301-107
1301-81
Reactor Building Closed Cooling
3799-48
3799-72
Pater System Valves
3799-49
3799-73
3799-59
3790-74
3799-62
3799-75
3799-66
3799-76
3799-68
3799-77
3799-61
3799-78
3799-64
3799-79
3799-65
3799-54
3799-81
3799-55
3799-82
3799-56
3799-84
3799-58
3799-70
3799-71
Diesel Generator Cooling Water
3999-83
Pumps Valves
3999-84
3999-79
3999-80
Manual Injection Valves - Unit 1 Drywell
Valves
Position
1402-6A
Open
1402-6B
Open
RHR/LPCI
1001-33A
Open
1001-33B
Open
Standby Liquid
1101
Open
Control
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ECCS Suction. Valves and Pump Status Verification
(In Plant)
Position
Manual Suction
HPCI 2301-22
Open
Valves from
2301-56
Open
Suppression
RCIC 1301-56
Open
Chamber
1301-30
Open
Core Spray 1402-34A
Open
1402-34B
Open
RHR/LPCI 1001-6A
Open
1001-6B
Open
Position
Breaker Status
Motor Operated
HPCI 2301-6
Open
OK
Pump Suction Valves
2301-35
Open
OK
2301-36
Open
OK
RCIC 1301-22
Open
OK
1301-25
Closed
OK
Core Spray 1402-3A
Open
OK
1402-3B
Open
OK
RHR/LPCI 1001-7A
Open
OK
1001-7B
Open
OK
1001-7C
Open
OK
1001-7D
Open
OK
ECCS Pumps
Jreaker Status
Breaker Fuse Status
Pump Status
Core Spray 1-1401-1A
OK
OK
OK
1-1401-1B
OK
OK
OK
2-1401-1A
OK
OK
OK
2-1401-1B
OK
OK
OK
RER/LPCI
1-1002A
OK
OK
OK
4
1-1002B
OK
OK
OK
1-1002C
OK
OK
OK
1-1002D
OK
OK
OK
2-1002A
OK
OK
OK
2-1002B
OK
OK
OK
2-1002C
OK
OK
OK
2-1002D
OK
OK
OK
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Control Room Valve and Switch Status Verification
Units 1 and 2
Core Spray System
1402-3A/B
1402-24A/B
1402-4A/B
1402-25A/B
1402-6A/B
1402-38A/B
1402-9A/B
1402-A/B Pumps
Automatic Depres-
203-A
203-D
surization System
203-3
203-E
203-C
Drywell Pressure Reset
Switch
Reactor Core Isolation
1301-12
1301-22
1301-34
1301-50
Coolant System
1301-13
1301-25
1301-35
1301-53
1301-16
1301-26
1301-48
1301-60
1301-17
1301-32
1301-49
1301-61
Trip Throttle Valve
1331-62
Flow Controller
Turbine Vacuum Pump
RCIC Condensate Pump
1001-68A-B
1001-18A-B-C-D
System
1001-34A-B
1001-43A-B-C-D
1001-37A-B
1001-7A-B-C-D
1001-23A-B
1001-65A-B-C-D
1001-26A-B
1001-16A-B
1001-28A u
1001-33A-B
1001-29A-B
1001-4A-B
1001-49
1001 5A-B
1001-155A-B
1001-21
1001-156A-B
1001-20
1001-187A-B
1001-60
1001-63
1001-47
1001-36A/B
1001-50
Containment Cooling
1002 Pumps
Permissive Switch
RHR Service Water Start Permissive
Switch
2/3 Containment Cooling Bypass Switch
Standby Gas Treatment
7503
7506
7504
7507
7505
7510
b
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High Pressure Coolant Injection
2301-39
2301-29
2301-10
2301-32
2301-30
2301-3
2301-7
2301-64
2301-48
2301-28
2301-65
2301-6
2301-36
2301-8
2301-14
2301-5
2301-49
2301-15
2301-4
2301-35
2301-9
Flow Controller
Turning Gear Motor
Gland Seal Cooling Water Pump
Gland Seal Leak Off Blower
Gland Seal Hotwell Pump
Auxiliary Oil Pump
Emergency Oil Pump
Pressure Suppression and Containment
Isolation Valves
Main Steam Drain Valves
Tip Ball Valves
1001-60
2001-4
1601-57
1001-63
2001-3
1601-59
1001-20
2001-15
1601-58
1001-21
2001-16
1601-56
1601-62
1601-24
1601-21
1601-63
1601-61
1601-22
1601-23
1601-60
1601-55
1601-22
1601-44
Reactor Building Closed
Cooling Water System
1-13701
1-13703
1-13702
1-13706
No items of noncompliance were identified.
The inspector reviewed the licensee response to IE Bulletin
c.
No. 79-08, items 8A, 8B and 8C and reviewed the respective
procedures to assure proper " return to service" of safety
feature components. The licensee has modified outage
sheets which are used when safety systems are out of
service, to include a specific verification of return to
service / operability of the equipment.
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No items of noncomplience were identified.
d.
The following surveillance test procedures were reviewed
to verify that when completed the system was returned to
an operable condition and that acceptance criteria were
met.
Acceptance
Date Performed
Surveillance
U-1
U-2
U-1
U-2
U-1
U-2
Operations Daily
N/A
N/A
OK
OK
4-7-79
4-7-79
Summary QOS-005
Containment Oxygen
N/A
N/A
OK
OK
4-15-79
4-15-79
5% QOS-1600
OK
OK
OK
OK
4-15-79
4-15-79
RHR Door Closure
QOS-020
Station Batteries
N/A
N/A
OK
OK
4-19-79
4-19-79
(k'eekly) QOS-6900
Core Spray Pump
OK
OK
OK
OK
3-24-79
3-3-79
Operability
QOS-1400-S3
Core Spray Valia
OK
OK
OK
OK
3-24-79
3-3-79
Valve Operability
QOS-1400-S2
RHR/LPCI Pump Oper-
OK
OK
OK
OK
4-1-79
3-17-79
ability QOS-1000-S2
RER/LPCI Valve Oper-
OK
OK
OK
OK
4-1-79
3-17-79
ability QOS-1000-S3
HPCI Pump Operability OK
OK
OK
01
3-27-79
3-22-79
QOS-2300-S2
HPCI Valve Operability OK
OK
OK
OK
3-27-79
3-22-79
QOS-2300-S3
RCIC Pump Operability OK
OK
OK
OK
3-27-79
3-22-79
QOS-1300-S2
RCIC Valve Operability OK
OK
OK
OK
3-27-79
3-22-79
QOS-1300-S3
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Unit I and 2 Diesel
OK
OK
OK
OK
3-29-79
3-22-79
Generator Operability
QOS-6600
Unit 1/2 Diesel Gen-
OK
OK
OK
OK
3-22-78
N/A
erator Operability
~
Torus /Drywell Vacuum
OK
OK
OK
OK
3-25-79
3-19-79
Breaker Operability
QOS-1600
OK
OK
OK
3-21-79
3-26-79
Recycle Test QoS-1100
Standby Gas Treatment OK
OK
OK
OK
3-20-79
' 20-79
j-
Operability QOS-7500
Core Spray Flow Rate
OK
OK
OK
OK
2-25-79
1-3-79
Test QOS-1400
RHR/LPCI Flow Ra+.e
OK
OK
OK
OK
2-25-79
3-17-79
Test QOS-1000
RHRS/CCW Flow Rate
OK
OK
OK
OK
4-1-79
3-17-79
and Pump Operability
QOS-1000-S4
RHRS/CCW Valve Oper-
OK
OK
OK
OK
4-1-79
3-17-79
ability QOS-1000-S5
HPCI Flow Rate Test
OK
OK
OK
OK
2-27-79
1-3-79
QOS-2300
RCIC Flow Rate Test
OK
OK
OK
OK
2-27-79
2-22-79
QOS-1300
Normally Open Iso-
OK
OK
OK
OK
2-18-79
2-23-79
lation Valve Exercise
QOS-1600
250 VDC Batteries
OK
OK
OK
OK
3-17-79
4-19-79
QOS-6900
125 VDC Bat:.eries
OK
OK
OK
OK
3-18-79
4-19-79
24/48 VDC Batteries
OK
OK
OK
OK
3-17-79
4-19-79
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Torus /Drywell
P
OK
OK
OK
OK
1-6-79
9-26-78
Test QOS-1600
Reactor Building to
OK
OK
OK
OK
2-24-79
2-23-79
Torus Vacuum Breaker
Test QOS-1600
Manual Operation of
OK
OK
OK
OK
10-26-78
9-30-78
ADS Q05-201
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No items of noncompliance were identified.
The inspector determined trat the licensee utilizes "indepen-
e.
dent verification" of system alignment following extended
outages.
Following maiatenance activities, verification
of system alignment is accomplished by testing to ensure
that the affected system will perform its intended function.
After satisfactory completion of the test, the system is
then declared operable.
The licensee on a daily basis independently verifies
accessible manual ano motor operated emergency core cooling
system suction valve aligaments with breaker, fuse and
pump status included.
The licensee implements a "S" lock control over essential
manual valves. Keys are available only by permission of
the Shift Engineer who logs the appropriate information on
release and return of keys.
No apparent inadequacies were identified in the administrative
controls to assure return to operability at the conclusion
of extended outages.
No items of noncompliance were identified.
4.
Onsite Assessment of Operating Procedures
Reactor Core Isolation and/or High Pressure Coolant Injection
systems are not required to assist in level control of the
reactor during routine operational event induced reactor level
Tagging practices on control panels do provide a potential I i
obscuring status indicators. However, recent operator practice
is to manipulate tags so as to climinate obscuring the visual
status of essential safety equipment.
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5.
Exit Interview
The inspector met with licensee representatives (denoted in
Paragraph 1) on May 24, 1979.
The inspector sumarized the
scope and findings of the inspection.
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