ML20205G734
| ML20205G734 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/07/1986 |
| From: | Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20205G676 | List: |
| References | |
| 50-395-86-13, NUDOCS 8608190608 | |
| Download: ML20205G734 (8) | |
See also: IR 05000395/1986013
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA STREET.N.W.
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ATLANTA, GEORGIA 30323 -
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Report No. : 50-395/86-13
Licensee : South Carolina Electric and Gas Company
Columbia, SC 29218
Docket No. :
50-395
License No. : NPF-12
Facility Name : V. C. Summer
InspectionConduc}e
- July 1 - 31, 1986
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Inspectors :
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Richa d L. Prev tte '
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Approved by :
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Hugh C/. Dance, Section Chief
Date' Signed
Division of Reactor Projects
SUMMARY
Scope: This routine, announced inspection conducted by the resident inspectors
on site in the areas of licensee action on previous enforcement matters, onsite
followup of events and subsequent written reports, monthly surveillance observa-
, tions, engineered safety features system walkoown, monthly maintenance observa-
tion and, operational safety verification.
Results: One violation was identified:
Failure to perform timely fire watch patrols.
8608190608 860 GOB
ADOCK 05000395
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REPORT DETAILS
1.
Persons Contacted
Licensee Employees
D. Nauman, Vice President, Nuclear Operations
0. Bradham, Director, Nuclear Plant Operations
J. Skolds, Deputy Director, Operations and Maintenance
K. Woodward, Manager, Operations
M. Browne, Group Manager, Technical and Support Services
M. Quinton, Manager, Maintenance Services
A. Koon, Manager, Technical Support
G. Putt, Manager, Scheduling and Materials Management
M. Williams, Manager, Nuclear Education and Training
L. Blue, Manager, Support Services
S. Hunt, Manager, Quality Assurance Surveillance Systems
W. Higgins, Associate Manager, Regulatory Compliance
J. Sefick, Manager, Nuclear Security
B. Williams, Supervisor, Operations
L. Safely, Fire Protection
Other licensee employees contacted included engineers, technicians,
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operators, mechanics, security force members, and office personnel.
2.
Exit Interview (30702, 30703)
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The inspection scope and findings were summarized on August 1,1986, with
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those persons indicated in paragraph 1 above. The inspectors described the
areas inspected and discussed the inspection findings. The licensee did not
identify as proprietary any of the materials provided to or reviewed by
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the inspectors during the inspection. One violation was identified.
The
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licensee noted that corrective action had been implemented to preclude
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recurrence of this violation.
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3.
Licensee Action on Previous Enforcement Matters (92702)
(Closed)
Violation 85-34-02, Missing Jumpers in OPDT Circuits Allowed -
Trip Setpoint to Vary in Non-Conservative Direction on Decreasing Tave. The
licensee provided a written response to this violation in a letter to
Region II, dated February 5,1986. The inspector reviewed this response
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and found it to be satisfactory. The jumpers were installed and tested
successfully. Procedures STP 345-001, STP 345-002, and STP 345.003 were
revised to address this item. The licensees action appears to be adequate.
This item is closed.
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(Closed)
Violation 86-07-01, Inadequate Cable Tray Thermo-lag 'Installa-
tion. The licensee provided a written response to this violation in a
letter to Region II dated May 2,
1986.
The inspector reviewed the
licensee's response and procedural changes implemented by the licensee to
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prevent recurrence of this item.
The additional controls delineated in
Nuclear Quality Control Inspection Procedure (A-NQCP-5) and Station
Administrative Procedure, Design Control / Implementation and Engineering
Interface (SAP-133), appear adequate to prevent recurrence. A reinspection
of portions of the installation revealed that the installation deficiencies
have been corrected. This item is closed.
(Closed)
Potential Generic Item 86-04, Diesel Generator Field Flash
Circuits for Morrison-Knudson Diesels. The deficiency as described in the
above item is not applicable to the V. C. Summer Nuclear Station Diesels.
This item is closed.
(Closed)
Potential Generic Item 85-06, Conax Seal Body Sub-assemblies.
Only two Conax electric conductor seal assemblies are installed 'for the IC
thermocouple up grade and they are of a different design. This item is
closed.
(Closed) Unresolved Item 85-34-03, Reactor Building Spray Pump Strainers.
Reference letter dated May 7, 1986, to Mr. A. F. Gibson, Region II from
Mr. D. G. McDonnald, NRC, Subject:
Construction strainers in containment
spray system at V. C. Summer, and the safety evaluation attached thereto
addresses the concerns raised on system operability with the strainers
installed.
The strainers have been removed. This item is closed.
(Closed)
Inspector Follow-Up Item 83-27-05, Operational Quality Assurance
Plan Requirements. This item addressed a concern for ambiguity in quality
assurance plans whereas the term " Calibration Standards" was not consistent
with other " Standards" in the documents. The criteria, standards and other
unclear language has been corrected in the revised Quality Assurance Plan
and through issuance of a Nuclear Quality Control Plan for Equipment
Control.
The materials inspected appear to be adequate for reasonable
understanding and clarification. This item is closed.
(Closed)
Inspector Follow-up Item 82-54-02, Leak Detection Auxiliary
Building Sump / Floor Drain Level Hi-Alarms. The electrode probe of the level
element in the auxiliary building sump was modified to indicate the proper
level. This item is closed.
(Closed)
Unresolved Item 85-46-01, Pressurizer Spray Valve Failure. The
actions taken by the licensee as reviewed by the inspectors appears to have
been adequate.
This item is closed.
4.
Monthly Surveillance Observation (61726)
The inspectors observed surveillance activities of safety-related systems
and components to ascertain that these activities were conducted- in
accordance with license requirements. The inspectors observed portions of
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selected surveillance tests including all aspects of one major surveillance
test involving safety-related systems. The inspectors also verified that
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the required administrative approvals were obtained prior to initiating
the test, that the testing was accomplished by qualified personnel, that
required test instrumentation was properly calibrated, that data met TS
requirements, that test discrepancies were rectified, and that the systems
were properly returned to service.
The following specific surveillance
activities were observed:
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STP 102-002
NIS Power Range Heat Balance
STP 112-002
Reactor Building Spray Pump Test
STP 123-002
Service Water Pump "B" Operational Test
GTP 702
Verification of "B" Olesel Generator Operability
STP 120-001
Emergency Feed Water Pump "B" Test
STP 128-043
Ccatrol Building Elevation 448' Fire Barrier Inspection
STP 114-001
Operational Leakage to Reactor Coolant Pump Seals
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STP 105-007
Accumulator Isolation Valve Verification Test
STP 114-002
Operational Leak Test
STP 108-001
Quadrant Power Tilt Ratio
STP 124.001
Electrical Power System Weekly Test
STP 128.001
Electric Fire Pump Weekly Test
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STP 128.004
Diesel Fire Pump Weekly Test
STP 125.002
Diesel Generator "B" Operability Test
STP 391-009
Reactor Building Foundation Mat Triaxial Responser-
Sprectrum Recorder Operational Test
STP 302-003
Delta T-Tavg Frotection Loop 3 Operational Test
STP 125.002
Diesel Generator "A" Operational Test
STP 115.032
Reactor Building Air Lock Door Seal. Leak Test
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No violations or deviations were identified.
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5.
Monthly Maintenance Observation (62703)
The inspectors observed maintenance activities of safety-related systems and
components to ascertain that these activities were conducted in accordance
with approved procedures, Technical Specifications (TS) and appropriate
industry codes and standards. The inspectors also determined that the
procedures used were adequate to control the act'.vity, and that these
activities were accomplished by qualified personnel.
The inspectors
independently verified that equipment was properly tested before being
returned to service. Additionally,
the inspectors reviewed several
outstanding job orders to determine that the licensee was giving priority to
safety-related maintenance and a backlog which might affect its performance
was not developing on a given system. The following specific maintenance
activities were observed:
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MWR 86C0100
Repair-Replace Mixed Bed Boric Acid Sample Valve,
XVD05774RDW
PMTS P0074115 Turbine Room Sump Pump "A"
MWR 86C0108
Repair Sterile Water System Pump, XPP0067
MWR 86C0073
Repair Radiochemistry Laboratory Sink Strainer-Drain Line
MWR 86M008
Replace Filter on the Waste Monitor Tank
MWR 86M003
Replace Filter on Waste Evaporator Feed Line
MWR 86M002
Replace Filter on the Hot Laundry-Hot Shower Tank
MWR 8601068
Adjust Air Supply Regulators to a Steam Generator IFU 3536
MWR 86Q0028
Replace Washer On Installed Bolt on Diesel Generator
MWR 86Q0312
Replace Washer, Clip and Bolt on Diesel Generator Door
MWR 86E005
Test and Repair of Emergency Lighting
MWR 8600801
Repair Standby Accumulator Pressure Gauge
MWR 8600895
Repair Steam Generator Feed Flow Instrument
MWR 8600582
Repair Valve on Recycle Evaporator
MWR 20350028
Install Computer Controllers
MWR 86C0085
Replace Flow Indicator Covers
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MWR 85E0317
Replace Torque Switch and Finger Base on Valve XVB09524A-CC,
Component Cooling Water
MWR 8600745
Repair Diesel Generator Rocker Arm Filter Leak
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MWR 8600879
Repair Accumulator Gauge
MWR 8600949
Repair Feedwater Gauge for SG "B"
MWR 8600959
Replacement of Instruments on the Feed Water System
No violations or deviations were identified.
6.
Operational Safety Verification (71707)
The inspectors toured the control room, reviewed plant logs, records and
held discussions with plant staff personnel to verify that the plant was
being operated safely and in conformance with applicable requirements.
Specific items inspected in the control room included: adequacy of staffing
and attentiveness of control room personnel; TS and procedural adherence;
operability of equipment and indicated control room status; control room
logs, tagout books, operating orders, jumper / bypass controls; computer
printouts and annunciators. Tours of other plant areas were conducted to
verify equipment operability; control of ignition sources and combustible
materials; the condition of fire detection and extinguishing equipment;
the control of maintenance and surveillance activities in progress; the
implementation of radiation protective controls and the physical security
plan. Tours were conducted during normal and random off-hour periods.
No violations or deviations were identified.
7.
ESF System Walkdown (71710)
The inspectors verified the operability of an engineered safety features
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(ESF) system by performing a walkdown of the accessible portions of the
service water, component cooling water and emergency lighting systems. The
inspectors confirmed that the licensee's system lineup procedures matched
plant drawings and the as-built configuration. The inspectors looked for
equipment conditions and items that might degrade performance (hangers and
supports were operable, housekeeping, etc.) and inspected the interiors of
electrical and instrumentation cabinets for debris, loose material, jumpers,
evidence of rodents, etc. The inspectors verified that valves, including
instrumentation isolation valves, were in proper position, power was
available, and valves were locked as appropriate. The inspectors compared
both local and remote position indications.
No violations or deviatinns were identified.
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8.
Onsite Followup of Events and Subsequent Written Reports (92700, 93702)
The inspectors reviewed the following Licensee Event Reports (LERs) and
Bulletins to ascertain whether the licensee's review, corrective action and
report of the identified event were in conformance with regulatory require-
ments, technical specifications, license conditions, and licensee procedures
and controls. Based upon this review the following items are closed.
LER 85-034
Reactor Trip With Safety Injection
LER 85-025
Overpower Delta Temperature
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Failures of G.E. Type HFA Relays in use in Class IE Safety
Systems
No violations or deviations were identified.
9.
Onsite Followup of Events at Operating Reactor (93702)
a.
On July 17, 1986, with the plant in Mode 1, the licensee, while
reviewing fire watch records identified that several fire watch patrols
had been missed between the dates of June 26 and July 17, 1986. This
is contrary to the requirements of TS 3.7.10 which requires the
licensee to establish and maintain hourly fire watch patrols for
This incident is similar to deviation
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395/85-26-17 and violation 86-06-02. This is a violation, Failure To
Perform Hourly Fire Watch Patrols, (395/86-13-01).
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The licensee took immediate action to correct this deficiency by
implementing disciplinary action against the affected individuals who
failed to perform their assigned tasks. The licensee is submitting an
Licensee Event Report (LER 86-013).
b.
On July 14, 1986, at 12:22 p.m. , with the plant . operating at 100
percent power, the 115 kV (Normal) offsite power to BUS XSWIDA was
lost. The loss of power was caused by the automatic stripping (Fault
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Protection) of one of two 115 kV power sources at the Parr sub-station,
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while the other power source was deenergized for maintenance.
The
115 kV line was restored within twenty minutes, but was kept out of
service until a cause of the failure could be determined.
The alternate
offsite power source was maintained.
Plant systems responded as
designed. The licensee will discuss these items further in LER 86-012.
c.
While operating in Mode 1, at 90 percent reactor power, on July 27, 1986,
at 1:45 a.m.,
a turbine trip occurred followed by a reactor trip.
The turbine trip occurred while PTP 102.001, Turbine Valve Testing, was
being performed. During the testing of control valve number 4, as the
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valve traveled to closed position, the main turbine tripped on low
EHC pressure, followed by a reactor trip. All systems responded as
designed. No safety injection occurred.
The cause of this event was
determined to be a loose adjustment in a pressure sensing switch.
Repairs were completed and the unit returned to power.
The licensee
is submitting a Licensee Event Report (88-014).
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