ML20204J688
| ML20204J688 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/25/1986 |
| From: | Brian Bonser, Bradford W, Dance H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20204J631 | List: |
| References | |
| 50-348-86-13, 50-364-86-13, NUDOCS 8608110164 | |
| Download: ML20204J688 (6) | |
See also: IR 05000348/1986013
Text
..
.
_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
.
UNITED STATES
[C. Glog'o
NUCLEAR REGULATORY COMMISSION
[
' ' ,
REGION 11
g'
j
101 MARIETTA STREET,N.W.
- -
't
ATLANTA, GEORGI A 30323
\\
/
....
Report No.: 50-348/86-13 and 50-364/86-13
Licensee: Alabama Power Company
J
600 North ~18th Street
l
Birmingham, AL 35291
)
Docket Nos.:
50-348 and 50-364
Facility Name:
Farley 1 and 2
l
Inspection Con
ted: Ju e.11 - July 10, 1986
Insp tor:
' 7 15
II
-
W. H. Bradford
Date Signed
L a /t L
,l>dec
i
Date Si'gned
B". R. Bodser
-
.
C-
M
7
N
Approved by:
H. C. Dance) Section Chief
Date Signed
Division of Reactor Projects
SUMMARY
Scope:
This routine, onsite inspection in the areas of monthly surveillance
observation, monthly maintenance observation, operational safety verification,
engineered safety feature walkdown, and onsite followup of events.
Results:
One violation was identified:
Failure to update procedures and
drawings.
%8
p
G
.
. _ . . _ _ _ . _ _ _ . . . _
.
.
REPORT DETAILS
1.
Licensee Employees Contacted:
J. D. Woodard, General Plant Manager
D. N. Morey, Assistant General Plant Manager
W. D. Shipman, Assistant General Plant Manager
R. D. Hill, Operations Superintendent
C. D. Nesbitt, Technical Superintendent
R. G. Berryhill, Systems Performance and Planning Superintendent
L. A. Ward, Maintenance Superintendent
L. W. Enfinger, Administrative Superintendent
J. E. Odom,. OpefGtions Sector Supervisor
B. W. Vanlandingham, Operations Sector Supervisor
T. H. Esteve, Planning Supervisor
J. B. Hudspeth, Document Control Supervisor
L. K. Jones, Material Supervisor
R. H. Marlow, Technical Supervisor
L. M. Stinson, Plant Modification Supervisor
J. K. Osterholtz, Supervisor, Safety Audit Engineering Review
Other licensee employees contacted included technicians,
operations
personnel, maintenance and I&C personnel, security force members, and office
personnel.
2.
Exit Interview
The inspection scope and findings were summarized during management
interviews throughout the report period and on July 11, 1986, with the
general plant manager and selected members of his staff. The inspection
findings were discussed in detail. The licensee acknowledged the violations
l
'
discussed in paragraph 7.
The licensee did not identify as proprietary any
material reviewed by the inspector during this inspection.
i
3.
Licensee Action on Previous Enforcement Matters (92702)
This area was not inspected.
4.
Monthly Surveillance Observation (61726)
The inspectors observed and reviewed Technical Specification required
,
surveillance testing and verified that testing was performed in accordance
l
with adequate procedures; that test instrumentation was calibrated; that
limiting conditions were met; that test results met acceptance criteria and
were reviewed by personnel other than the individual directing the test;
that any deficiencies identified during the testing were properly reviewed
!
I
L
.
.
2
and resolved by appropriate management personnel; and that personnel
conducting the tests were qualified. The inspector witnessed / reviewed
portions of the following test activities:
STP-1.0
- Operations Daily & Shift Surveillance Requirements
STP-24.4
- Service Water Pumos 10, 1E and 1C Annual Inservice Test
STP-9.0
- RCS Leakage Test
STP-20.0
- Penetration Room Filteration System Test
STP-20.1
- Penetration Room Filter Alignment
1-B Diesel Generator Functional Test
STP-80.1
-
STP-80.2
- 2-C Diesel Generator Functional Test
STP-71.0
- Technical Specification Valve Surveillance
STP-615.0
- Service Water Battery Charger Load Test
STP-42.0
- Turbine Trip Functional Test
STP-41.3
- N-41 Power Range Functional Test
STP-22.18
- AFW Automatic Valve Position Verification
STP-22.19
- AFW Normal Flow Path Verification
Reactor Trip Breaker Train A Operability Test
STP-33.2A
-
' ,
STP-33.2B
Reactor Trip Breaker Train B Operability Test
-
Manual Reactor Trip Greaker Trip Verification
STP-38.0
-
Containment Inspection
STP-34.1
-
Solid State Protection System Operability
STP-33.0
-
Emergency Core Cooline Valves Inservice Test and PORV
STP-10.3
-
Block Valve Stroke Test
STP-27.3
- Auxiliary and Service Water Building 125V DC Distribution
FNP-UOP 1.3 - Reactor Startup following an At Power Reactor Trip
No violations or deviations were identified.
5.
Monthly Maintenance Observation (62703)
Station maintenance activities of safety-related systems and components were
,
observed / reviewed to ascertain that they were conducted in accordance with
!
approved procedures, regulatory guides, industry codes and standards, and
l
were in conformance with technical specifications.
!
The following items were considered during the review:
limiting conditions
~
for operations were met while components or systems were removed from
service; approvals t;ere obtained prior to initiating the work; activities
were accomplished using approved procedures and were inspected as
applicable; functional testing and/or calibrations were performed prior to
,
l
returning components or systems to service; quality control records were
maintained; activities were accomplished by qualified personnel; parts and
materials were properly certified; radiological controls were implemented;
I
and fire prevention controls were implemented. Work requests were reviewed
to determine the status of outstanding jobs to assure that priority was
assigned to safety related equipment maintenance which may affect system
performance. The following maintenance activities were observed / reviewed:
Service Water Building Batteries (PCN-80-0-796)
2C Charging Pump Room Cooler
.
-.
-
--
- _ _ -
.
-.
- -
-
-
-
--
.
.
3
2C Charging Pump Alignment
FCV- 122 (Unit 2)
4160V ACB Preventative Maintenance Program
Unit 2 Post Accident Hydrogen Analyzer MWR 135596
Unit 2 MDAFW pump to 2C Steam Generator check valve
No violations or deviations were identified.
6.
Operational Safety Verification (71707)
The inspectors observed control room operations, reviewed applicable logs
and conducted discussions with control room operations during the report
period.
The inspectors verified the operability of selected emergency
systems, reviewed tagout records, and verified proper return to service of
affected components.
Tours of the auxiliary building, diesel building,
turbine building and service water structure were conducted to observe plant
equipment conditions, including fluid leaks and excessive vibrations. The
inspector verified compliance with selected Limiting Conditions for
Operations (LCO) and results of selected surveillance test. The verifi-
cations were accomplished by direct observation of monitoring instrumen-
tation, valve positions, switch positions, accessible hydraulic snubbers,
and review of completed logs, records, and chemistry results.
The
licensee's compliance with LC0 action statements were reviewed as events
occurred.
The inspectors routinely attended meetings with certain licensee management
and observed various shift turnovers between shift supervisors, shift
foremen and licensed operators. These meetings and discussions provided a
daily status of plant operations, maintenance, and testing activities in
progress, as well as discussions of significant problems.
The inspector verified by observation and interviews with security force
members that measures taken to assure the physical protection of the
facility met current requirements.
Areas
inspected
included the
organization of the security force; the establishment and maintenance of
gates, doors, and isolation zones; that access control and badging were
proper; and procedures were followed.
'
No violations or deviations were identified.
7.
Engineered Safety Feature System Walkdown (71710)
The inspector verified the operability of the 125V DC auxiliary building
distribution system by performing a complete inspection of the accessible
portions of the system. The inspector verified the positions of breakers,
operability of local and remote instrumentation where possible, the
condition of equipment, and compared the licensees' system checklist with
the systems drawings and actual position of breakers. During the inspection
the following inadequacies were identified:
,
_
_
_
,_
_
_
__
.
.
4
The following drawings, which are controlled referenced material used by
plant operators in the control room, had not been revised to reflect changes
in plant design:
.
a.
Unit 1 DC Distribution System drawing D-177082 shows SPACE at breaker
- 26 on 125V DC Distribution Panel ID. Breaker #26 actually supplies a
terminator cabinet.
b.
Unit 2 DC Distribution System drawing 0-207082 shows breaker #22 on
125V DC Distribution Panel 28 supplying the Auxiliary Feed Water
Turbine Control Panel. Breaker #22 is a spare breaker,
c.
Unit 2 DC Distribution System drawing 0-207083 shows breaker #21 on
125V DC Distribution Panel 2D as a spare breaker. Breaker #21 actually
supplies a termination cabinet.
i
A Temporary Change Notice on Unit 2 was not issued to cover a pen change
made to FNP-2-SOP 37.1 125 Volt DC Auxiliary Building Distribution System
checklist, to show breaker #22 on 125V DC Distribution Panel 2E is a spare
breaker and not a SPACE as indicated in the 50P checklist.
Unit 1 DC breaker LB-15, a supaly to a security inverter, is not included in
the system checklist in FNP-1-SOP 37.1, 125 Volt DC Auxiliary Building
Distribution System.
The above examples are identified as a violation (348,364/86-13-01) of
Technical Specification 6.8.1 as implemented by Administrative Procedures
(AP) 1 and 8.
AP-1, Review and Approval of Plant Procedures, requires
reviews of procedures for current conditions and adequacy and the issuance
of a temporary change notice for pen changes.
AP-8, Design Modification
Control, requires procedures and drawings to be updated after modifications.
Several minor discrepancies were identified by the inspector which are not
considered to be part of the violation. The license has implemented prompt
corrective action.
a.
Unit 2 DC breaker LA-06 is described in the FNP-2-SOP 37.1 battery bus
2A checklist and on the nameplate of the local control panel as Diesel
Generator 2C Control Panel . The breaker nameplate and DC Distribution
System drawing D-207082 list Diesel Generator 1C Control Panel.
b.
Unit 2 DC breaker LA-1? is described in the FNP-2-SOP 37.1 battery bus
2A checklist as SKVA Inverter 28. The DC Distribution System drawing
D-207082 and the nameplate on the local control panel list a 7.5KVA
inverter.
c.
In the FNP-2-SOP 37.1 system checklist breaker #16 on distribution
i
panel 2B is described as reactor trip switchgear control power to Unit 1
"A" bypass breaker and "A" reactor trip breaker. Unit 2 does not supply
Unit 1 DC power.
d.
In the FNP-2-SOP 37.1 system checklist breaker #13 on distribution
panel 20 was listed twice with different loads specified. There is
only one breaker #13. Both entries were signed off in the checklist
completed prior to Unit 2 startup.
-
- -___
-- -
_
_ _ _
_.
_
_ __
_
._
-
._
-
l
.
.
5
8.
Follow up of Plant Events (93702)
On July 2,1986 at 3:15 p.m., Unit 1 tripped from 99% reactor power on a
negative rate trip. The trip was caused by a short in control rod . F14
stationary gripper coil circuit in the containment penetration resulting in
blown fuses and control rod F14 dropping into the core. All systems
functioned as designed. The cabling for control rod F14 stationary gripper
coil circuit was rerouted through spare conductors in the same penetration.
1
. . . . . . . . . . . .