ML20155A875
| ML20155A875 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/15/1988 |
| From: | Dance H, Hopkins P, Prevatte R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20155A851 | List: |
| References | |
| 50-395-88-17, NUDOCS 8810060107 | |
| Download: ML20155A875 (8) | |
See also: IR 05000395/1988017
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UNITED STATES
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NUCLEAR REGULAYORY COMMISSION
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REGION 11
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101 MARIETTA ST., N.W.
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AYLANTA GEORGIA 30323
Report No.:
50-395/88-17
Licensee:
South Carolina Electric and Gas Company
Columbia, SC 29218
Docket No.:
50-395
License No.: NPF-12
Facility Name: V. C. Summer
Inspection Conducted: August 1 - 31, 1988
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Inspector':
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/ Richard L. Prevatte
Oate Signed
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Mefl66
perry C. Hopkins
Date Signed
Accompanying Per nnelp
Stevep J. Vias (August 22 - 26, 1988)
Approved by:
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H6gh C.6 Dance, Sect n Chief
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Division of Reactor Projects
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SUMMARY
Scope:
This routine, announced inspection was conducted by the resident
'nspectors onsite, in the areas of unresolved items, monthly surveillance
observations, monthly maintenance observation, operational safety verification,
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engineered safety features system walkdown, onsite followup of events and
subsequent written reports, action on previous inspection findings, design,
design changes and modifications, and other areas.
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Results:
The licensee's periodic Jerformance of STP's has resulted in some
temporary procedure chanJes and procedure revisions.
Review by procedure
writing groups appears to satisfy procedure resiew requirements.
Too many
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changes to a procedure without reprint and study by those who perform STP's
could load to confusion and/or errors by personnel who perform test procedures.
With tho upcoming outage scheduled for September 16, 1988, there appears to
have been considerable cooperative ef forts by the several discipline groups to
produce an outtae schedule of significant detail.
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Within the areas inspected, the following violation was identified:
Failure to follow procedures, paragraph 8.
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One unrosolved item was identified involving steam path yielding potential for
postulated steam breaks, paragraph 7a.
G810060107 080916
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REPORT DETAILS
1.
Persons Contacted
Licensee Employees
- W. Baohr, Manager, Chemistry and Health Physics
K. Beale, Manager, Nuclear Protection Services
- 0. Bradham, Vice President, Nuclear Operations
C. Bowman, Manager, Scheduling and Modifications
M. Browne, General Manager, Station Support
W. Higgins, Supervisor, Regulatory Compliance
S. Hunt, Manager, Quality Systems
- A. Koon, Manager, Nuclear Licensing
- G. Moffatt, Manager, Maintenance Services
D. Moore, General Manager, Engineering Services
- K. Nettles, General Manager, Nuclear Safety
C. Price, Manager, Technical Oversite
J. Shepp, Associate Manager, Operations
- J. Skolds, General Manager, Nuclear Plant Operations
- G. Soult, General Manager, Operations and Maintenance
G. Taylor, Manager, Operations
D. Warner, Manager, Core Engineering and Nuclear Computer Services
- M. Williams, General Manager, Nuclear Services
K. Woodward, Manager, Nuclear Operations Education and Training
NRC Resident Inspectors
- P. Hopkins, Resident Inspector
R. Prevatte, Senior Resident Inspector
S. Vin , Project Manager
Other licensee employees contacted included engineers, technicians,
operators, mechanics, security force members, and office personnel.
"Attended exit interview
Acronyms and initialisms used throughout this report are listed in the
last paragraph.
2.
Unresolved Item **
See paragraph 7a for a unresolved item identified in this report.
Unresolved items are matters about which more information is required to
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determine whether they are acceptable or may involve violations or
deviations.
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3.
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
13 selected surveillance tests including all aspects of the Steam
Generator
"A" Steam Pressure (PT 474) Operability Test, (STP 303.005).
The inspectors also verified that required administrative approvals were
obtained prior to initiating the test, testing was accomplished by
qualified
personnel,
required
test
instrumentation was
properly
calibrated, data met TS requirements, test discrepancies were rectified,
and the systems were properly returned to service.
During this inspection period, personnel in general, who performed the
surveillance
procedures were knowledgeable and appeared to have
familiarized themselves with the procedures prior to the performance of a
particular surveillance procedure.
Coordination and communications
between the several disciplines required to perform STP's were adequate.
Parts, components, test equipment or materials used by test personnel
during scheduled surveillance testing activities were found to be properly
documented on the associated implementing work requests and the STP's.
No violations or deviations were identified.
4.
Monthly Maintenance Observation (62703)
The inspectors observed mair.tenance activities of safety related systems
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 in whole or in part:
MWR 8901084
Investigate and repair steam generator "A" feedwater
regulator valve
PMTS P0109921 SWS "B"
train flow operational testing
MWR 8801026
Repair switch on MCB for the high pressure turbine to the
main steam drain valve
PMTS 98203
Repair auxiliary building motor control center switchgear
room cooling fan motor (XFN0132-M0)
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PMTS 102296
Repair relief damper equipment in room 435 (XDP0234A)
PMTS 102276
Inspect and repair control room vent control damper
(XDP0021A)
PMTS 102292
Repair equipment area relief air damper (XDP0133A)
PMTS 105581
Repair and calibrate circuit breaker feeder for heat
tracing (XPC2009)
PMTS 108702
Inspect and replace spare feeder breaker (X5W1DA2)
MWR 8810218
Repair flat washers on intermediate range instrument drawer
KWR 8700053
Repair spool piece above support SFH0044 by replacing with
new gaskets
PMTS 103912
Check and repair spent fuel pit bridge crane
PMTS 103961
Lubricate spend feel pit bridge crane
PMTS 103963
Inspect spent fuel pit bridge crane for operation
KdR 8801249
Investigate and repair feedwater regulator valve (IFV00478)
MAR 88 WOO 37
Install RUSKA gauges on feedwater system to test for
moisture carry-over
KdR 20797005 Perform circuit termination for plant surveillance system
MWR 8800836
Repair fau'ty limit switch on loop "A" component cooling
pump "C"
Through observation and research conducted during this inspection it has
been determined that maintenance activities have been performed per work
request instructions and applicable procedures.
No violations or deviations were identified.
5.
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
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equipment, the control of maintenance and surveillance activities in
progress, the implementation of radiatinn protective controls and the
physical security plan. Tours were conducted during normal and random off
hour periods.
In general, the operating crews were observed to be making good use of
their time, when not occupied with the normal operating routine.
They
were observed making needed procedure changes, reviewing procedures, and
conducting on-the-job training for those standing watch under instruction.
Operations watch standing activities and the composition of control room
logs was being accomplished in Accordance with the requirements of the
controlling procedures and directives.
No violations or deviations were identified.
6.
ESF System Walkdown (71710)
The inspectors verified the operability of an engineered safety features
(ESF) system by performing a walkdown of the accessible portions of the
Component Cooling Water System.
The inspectnrs 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 thit 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.
Several deficiencies were identified, such as equipment tags missing, oil
leaking from limitorques and valves needing some type of preservation.
Responsiveness by operations to these items was prompt and positive.
No violatiors or deviations were identified.
7.
Onsite Followup of Events and Subsequent Written Reports (92700, 93702)
a.
On June 7,1988, with the plant in mode 3 the licensee was notified
by the architect engineer for V. C. Summer Nuclear Station that a
design defect may yield the potential for steam propagation, which
could affect the safe shutdown of the plant under certain postulated
steam events.
Direct steam paths through floor penetrations and more
tortuous propagational paths were identified.
Upon verification of
the potential problem the licensee changed operational modes from
mode 3 to mode 4
The licensee opened several interior plant doors
to allow for the relief of pressure build-ups.
One door was sealed
to prevent moisture intrusion in the event of the postulated steam
break.
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The licensee is performing further evaluations of this potential
problem to insure that adequate corrective actions are in place for
short and long term operations.
For furthee information see LER
88-008, dated July 7, 1988. This is an unresolved item, steam line
rupture with potential to affect safe shutdown, 88-17-02.
b.
The inspectors reviewed the following. LER's and SPR's to ascertain
whether the licensee's review, corrective action and report of the
identified event or deficiency was in conformance with regulatory
requirements, TS, license conditions, and licensee procedures and
controls.
Based upon this review the following items are closed.
LER 87-11
Lots of 7.2 kV switchgear due to degraded voltage
SPR 88-006
Failure of diesel fire pump to start on valid test
signal
SPR 86-011
keeperability of the meteorological ir.strumentation
No vinlations or deviations were identified.
8.
Action on Previous Inspection Findings (92701, 92702)
The inspectors further reviewed the July 26, 1988 reactor trip from 100*;
power, while SSPS was being tested.
Subsequent to the June 1,
1988
reactor trip, while performing an SSPS logic test, the licensee made
changes to STP 345.074, SSPS actuations logic and master relay test, for
train "B",
to insure that the breaker would be closed locally instead of
from the MCB.
Personnel failed to follow the procedure
in that the
breaker was closed from the MCB inst ad of locally at the RTB as
specified. The solid state protection system actuation logic and master
relay test for train B, STP 345.074, was initiated and channel
"B"
was
placed in test at approximately 9:00 a.m.,
on July 26, 1988.
A reactor
trip occurred at 9:24 a.m.
At approximately 4:30 p.m. , a relief shif t
supervisor entered the control room and discovered that SSPS train "B" was
still in test.
The channel was returned to normal at approximately
5:30 p.m.
STP 345.074, precaution step 3.9 limits the time that a
channel may be bypassed for testing to two hours. The procedure was not
followed in that operations allowed the SSPS train "B"
to remain in bypass
for over eight hours. During the time "B"
train was in test no protection
signal could have been generated by that channel. Step 3.10 of the above
procedure also requires that if the test was terminated prior to
- ompletion it must be returned to normal.
This is an additional example of
the above violation for failure to follow procedures, 88-17-01.
See. Report
No. 50-395/88-14 and LER 88-009 for further information,
9.
Design, Design Changes and Modifications (37700)
The inspectors reviewed four design changes,1.'sted belnw not previously
approved by NRR, to assure that the changes had been reviewed and approved
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in accordance with the Technical Specifications (TS) and 10 CFR 50.59.
During the review, the inspectors verified (1) that the design changes
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were reviewed and approved in accordance with TS and established QA/QC
controls, (2) that design changes were controlled by established
procedures, (3) that the licensee conducted a review and evaluation of
test results and that these test results were within previously
established acceptance criteria and that any test deviations tere resolved
and necessary retesting was accomplished as appropriate, (4) that
operating procedure modifications were made and approved in accordance
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with TS, and (5) that as-built drawings were changed to reflect the
modifications.
The inspectors ot> served (1) that change activities were
conducted in accordance with the appropriate specifications, drawings, and
other requirements, (2) that acceptance and startup testing of modifi-
cations were conducted in accordance with technically adequate and
approved procedures, and (3) that appropriate controls were implemented,
(e.g. , firewatch, portable fire fighting equipment, welding and cutting
permit, etc.). Additionally, the inspectors reviewed the outstanding
facility change requests (FCR's) and determined that an excessive backlog
was not developing.
Design changes reviewed were:
M F 21097
Installed spare pump concept for swing systems
No violations or deviations were identified.
10.
Other Areas
Other activities related to the inspection program are noted:
a.
The Assistant Director for Region II Reactnr Projects, the Director,
Reactor Projects Directorate 11-1 and the Region II Deputy Director
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for Reactor Projects, visited and toured the plant NTC and EOF on
August 3, 1988.
b.
The Senior Resident Inspector assisted Region II in conducting an OPA
of the Vogtle Nuclear Plant during the week of August 8 and d , 198S.
c.
The Regional Project Engineer for V. C. Sumner assisted the Resident
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Inspectors during the week of August 22, 1988.
11.
Exit Interview (30703)
The inspectirn scope and findings were summarized on August 31, 1988, with
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those persons indicated in paragraph 1 above.
The inspectors described
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the areas inspected and discussed the inspection findings. No dissenting
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comments were received from the licensee.
The licensee did not identify
as proprietary any of the ' materials provided to or reviewed by the
inspectors during the inspection.
Item Number
Description and Reference
88-17-01
Violation - Failure to Follow Procedures,
paragraph 8.
88-17-02
URI - Steam Line Rupture with Potential to
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Affect Safe Shutdown, paragraph 7.
12.
Acrenyms and Initialisms
Emergency Operating Facility
Engineered Safety Feature
LER
Licensee Event Report
MCB
Main Control Board
MWR
Maintenance Work Request
NRC
Nuclear Regulatory Commission
Nuclear Reactor Regulation
NTC
Nuclear Training Center
Operational Performance Assessment
PMTS
Preventative Maintenance Task Sheet
Quality Assurance
RTB
Reactor Trip Breaker
SPR
Special Procedures Report
SSPS
Solid State Protection System
Surveillance Test Procedures
Service Water System
TS
Technical Specifications
Unresolved Item
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