ML20214M781
| ML20214M781 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/15/1987 |
| From: | Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20214M768 | List: |
| References | |
| 50-395-87-11, NUDOCS 8706010426 | |
| Download: ML20214M781 (8) | |
See also: IR 05000395/1987011
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 18 ;
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101 MARIETTA STREET,N.W.
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ATLANTA, GEORGI A 30323
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Report No.:
50-395/87-11
Licensee:
South Carolina Electric and Gas Company
Columbia, SC 29218
Docket No.:
50-395
License No.: NPF-12
Facility Name: V. C. Summer
Inspection Conducte : April 4 through May 4, 1987
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Inspectors:
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Rfchard L. Pr patte
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Perry C. Hopkiris
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Approved by:
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Hugh C. Tance, Sec61on, Chief
D6te Signed
Division of Reactor Projects
SUMMARY
Scope: This routine, announced inspection was conducted by the resident
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inspectors onsite, in the areas of licensee action on previous inspection
findings, onsite followup of events and subsequent written reports, monthly
surveillance observations, monthly maintenance observation, operational safety
verification, calibration, refueling activities, physical security and other
areas.
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Results: One violation was identified: Failure to verify that steam generator
tubes were properly plugged (Paragraph 9).
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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
G. Soult, 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
K. Woodward, Manager, Nuclear. Education and Training
L. Blue, Manager, Support Services
S. Hunt, Manager, Quality Assurance Surveillance Systems
K. Beale, Manager Nuclear Protection Services
W. Higgins, Associate Manager, Regulatory Compliance
B. Williams, Supervisor, Operations
Other licensee employees contacted included engineers, technicians,
operators, mechanics, security force members, and office personnel.
2.
Exit Interview (30702,30703)
The inspection scope and findings were summarized on May 4, 1987, with
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 the inspectors during the inspection. One violation was
identified.
Violation 87-11-01, Failure to plug correct steam generator tubes.
The
licensee offered no objections to the violation.
3.
Licensee Action on Previous Inspection Findings (92701, 92702)
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(0 pen) Licensee Identified Item, 80-29-01, Charging pump minimum flow:
long term fix in progress, see SCE & G's letter to Denton, dated,
January 22, 1982.
Report 87-08, paragraph 3, stated that the licensee
would submit a report to Nuclear Reactor Regulation (NRR) on the above.
The licensee submitted this information in a letter to NRR dated,
April 24, 1987. The office of NRR will review the response for adequacy.
This item remains open.
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 listed below including all aspects of at
least one major surveillance test involving safety related systems. The
inspectors also verified that 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 Technical Specification (TS) requirements, that
test discrepancies were rectified, and thot the systems were properly
returned to service. The following specific surveillance activities were
observed:
STP 115.033
Safety Injection / Chemical and Volume Control System
Valve Leak Test
STP 105.004
Residual Heat Removal Pump Test
STP 310.004
N.I.S. Intermediate Range (N-36) Calibration
STP 147.001
Reactor Building Penetration Test
STF 102.001
Source Range Analog Channel Operational Test (N-31, N-32)
STP 110.001
Pre-core Alterations Verification
STP 134.001
Shutdown Margin Calculation
STP 118.006
Reactor Building Purge and Exhaust Refueling Weekly Test
STP 401.002
Main Stream Line Code Safety Valves ASME Section XI Test
STP 150.012
Main Steam / Steam Generators Leak Test
STP 149.079
Service Water "B" Train Discharge Hydrostatic Test
STP 146.002
Reactor Makeup Water System Refueling Alignment
Verification
STP 125.004
Diesel Generator Load Rejection Test
STP 134.001
Shutdown Margin Calculation
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STP 128.004
Diesel Fire Pump Weekly Test
STP 115.020
Nuclear Drains System Valve Leakage Test
STP 145.003
Gaseous Radwaste Treatment Ventilation Exhaust
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Treatment Systems Operability Test
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STP 122.002
Component Cooling Pump Test
STP 125.002
Diesel Generator Operability Test
No violations or deviations were identified.
5.
Monthly Maintenance Observation (62703)
The inspectors observed maintenance activities of safety related systems
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and components to ascertain that these activities were conducted in
accordance with approved procedures, TS and appropriate industry codes and
standards. The inspectors also determined that the procedures used were
adequate to control the activity, 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:
MWR 21045007
Install new platform in the control room for the control
room supervisor
MWR 8700526
Repair leak on service water outlet expansion joint
MWR 8700547
Repair service water pipe IPX045068
MWR 8700528
Repair leak of socket weld where the line taps on to
the service water inlet piping to "B"
chiller
MWR 32356003
Perform installation work and post modification testing
per MRF 32356 and MSI 32356-2, on chiller XHS0001B
MMP 300.012
Agastat replacement on chiller XHX00018
MWR 87T0099
Disassemble valve to reset nozzle ring settings on
XUS 02806HMS
MMP 290.002
Main steam safety relief valve maintenance and testing
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;
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control room logs, tagout books, operating
orders,
jumper / bypass
controls; computer printouts and annunciators. Tours of other plant areas
were conducted to veri fy 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.
Onsite Followup of Events and Subsequent Written Reports
(92700,93713,93702)
The inspectors reviewed the following Licensee Event Reports (LER's) to
ascertain whether the licensee's review, corrective action and report of
the identified event or deficiency was in conformance with regulatory
requirements, technical specifications, license conditions, and licensee
procedures and controls. Based upon this review the following items are
closed.
LER 85-008 Reactor trip failure of the secondary fuses
Three pressurizer safety valves were sent to Wyle Laboratories and one to
Crosby Valve and Gage Company in March, 1987, to veri fy proper set
points. On March 31, 1987, Wyle Laboratories notified the licensee that
the valves were tested and found that the as-found set points were outside
the technical specification limits of 2485 +/- 1% psig.
Preliminary
analysis by the licensee indicates differences of as-set and as-found
set points to be a function of methods utilized to simulate in plant
environmental conditions.
Further testing of the pressurizer safety
valves will be conducted by the licensee at hot plant
onditions, using
the steam medium and a calibrated pressure assist device, with a test
method which simulates actual plant conditions. The licensee has reported
the event to the NRC in LER 87-05.
No violations or deviations were identOied
8.
Calibration (56700)
The inspectors conducted a detailed review and evaluation of the
licensee's calibration program to determine its conformance with license
requirements, technical specifica', ions, licensee commitments and industry
guides and s'.andards.
To accomp'ish the above, the inspectors completed
the following:
a.
Conducted a review of licensee records and verified that the
calibration frequences of equipment met the requirements of technical
specifications.
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b.
Reviewed a sample of 30 completed tests to establish that
documentation was complete; acceptance criteria had been met; approved
test procedures were used and the personnel conducting the tests were
qualified,
c.
Examined the technical content of 13 surveillance test procedures for
adequacy.
d.
Examined the technical content and adequacy of 10 instrumentation and
control maintenance procedures used to calibrate safety equipment
not addressed in technical specifications,
e.
Reviewed the backlog of past due calibrations.
f.
Observed and evaluated the performance of 2 components undergoing
calibration.
The results of the above indicate that the licensee's calibration program
has been properly implemented.
Procedures are properly reviewed and
approved prior to implementation.
Procedures contain steps that require
signatures after each item is completed; second verification of
critica steps is required; corrective action is taken and proper notifi-
cation is made when equipment is found out of calibration; test equipment
is identified and tracked; and limiting conditions for operators are
addressed. A review of the calibratior backlog indicates that management
is notified and action is taken on past due calibrations.
Based on this review it appears that the licensee's program is implemented
by adequate procedures, has adequate administrative controls, and is
staffed by trained and qualified personnel.
No violations or deviations were identified.
9.
Refueling Activities (60710)
The
inspectors
continued
to
review
the
licensee's
activities
associated with the current refueling outage which began on March 7, 1987.
The activities consisted of (1) testing of refueling equipment prior to
use, (2) the movement of fuel into the reactor core, (3) fuel inspection,
(4) drainage of the refueling canal, (5) reactor make up water system
refueling alignment verification and (6) reactor head replacement.
The
inspectors verified that the periodic testing required by technical
specifications and station administrative procedures were completed within
the prescribed time limits.
The inspectors also observed the conclusion of work being performed on
the steam generators.
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On April 14, 1987, while performing maintenance and inspection, the
licensee discovered that two steam generator tube plugs had been installed
in the incorrect tubes in steam generator "C", cold leg. A review of this
item by the licensee, discovered that this problem had occurred in or
about November 21, 1985, during the second refueling outage.
Further
review of the item revealed that after eddy current testing had determined
which tubes required plugging, a template had been designed and
constructed with drilled holes to match the tubes which required plugging.
In addition to the template holes drilled to allow tube plugging, two
pilot holes were drilled to attach a suspended tube plug basket. This
device performed adequately and the correct tubes were plugged on the hot
leg side. When the template was installed in the cold leg side of the
steam generator, the basket was not attached, and the Subsequent error
resulted in the plugs being installed through the template holes that would
have been used to suspend the tube plug basket.
This deficiency was not
identified in the subsequent verification inspection.
This failure to
identify this deficiency is contrary to the requirements of 10 CFR 50,
Appendix "B",
Criterion X and the South Carolina Electric and Gas
Company's Operational Quality Assurance Plan that requires this is a
violation: Failure to plug correct steam generator tubes (87-11-01). The
licensee has corrected this deficiency and performed an analysis which
indicated that the incorrect plugging had no adverse effect on steam
generator operation.
The licensee is currently evaluating plugging and
verification inspection procedures for steam generator tube plugging,
in order to strengthen the current procedures and methodology. The
licensee is preparing a LER on this subject.
Other than the above, no violations or deviations were identified.
10.
Physical Security (71881)
The inspectors verified by observation, review of documentation of
records and personnel interviews that appropriate measures are taken to
assure the physical protection of the facility. The physical security
plan (PSP) provides adequate instructions to insure that the required
number of guards, search equipment and search procedures are in place.
Verification of adequate patrols, central control television monitors
and alarm stations are in place.
Areas inspected included the
organization of the security force, the establishment of maintenance of
gates, doors and isolation zones.
That access control and badging was
proper, that search practices were appropriate and that escorting and
communications procedures were followed.
The inspectors received an anonymous concern in regards to the lack of
management
and
supervision
fulfillment
of established
security
procedures. A review of records, safeguards information, and storage of
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security records was performed, and in addition, interviews with
selected individuals and other random personnel, failed to support or
substantiate the concern.
Unless there is more definitive information
forth coming. This item is considered closed.
No violations or deviations were identified.
11. Other Areas
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Senior resident and resident inspectors respectively, from the H.B.
Robinson plant visited V.C. Summer for orientation and familiarization
to fulfill requirements for onsite backup inspectors.
The Regional Administrator visited V.C. Summer and met with plant staff
on April 16, 1987. He participated in a reception and presented Nuclear
Regulatory Commission Senior Reactor Operator and Reactor Operator
Licensees to personnel who had recently completed the training and
examination program.
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