ML20059A351
| ML20059A351 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/13/1990 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20059A349 | List: |
| References | |
| 50-395-90-11, NUDOCS 9008230002 | |
| Download: ML20059A351 (4) | |
See also: IR 05000395/1990011
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ENCLOSURE-2:-
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final Report Reads-
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INITIAL SALP REPORT-
FINAL SALP REPORT
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ENCLOSURE
INITIAL SALP REPORT
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U. S. NUCLEAR REGULATORY COMMISSI
(NRC)
REGION 11
SYSTEMATIC ASSESSMENT
CENSEE PERFORMANCE
INSPECTION
ORT NUMBER
S/90-11
SOUTH CAR 0ll g
CTRIC & GAS COMPANY (SCE&G)
V. C SUMMER NUCLEAR STATION
JANUAR
1, 1989 THROUGH APRIL 30, 1990
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implement effective programs.
During the assessment
riod, the
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licensee increased the health physics (HP) staff by onverting 5
of the 10-15 semi-permanent contract HP techniciap positions to
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permanent positions, and staff turnover has bee rlow.
In the
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latter part of the assessment period, the Asso
ate Manager of
.
He61th Physics vacancy was rapidly filled
a qualified
1
(Regulatory Guide 1.8, September 1975) per
n. from corporate
health physics.
Under new leadership, th radiation protection
program appeared to be functioning at t
same high level of
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performance as previously observed.
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The licensee's training program
radiation protection
radwaste, and chemistry were revi
ed and found to be effective
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and consistent with ANSI stand ds and licensee internal
procedures.
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The licensee has implemeniib
an excellent program to control
radiation dose to work
The collective dose 'n Nrson-rem
for the years 1987,
, and 1989 was 560, 511, and 52,
respectively,
in
he annual goal was to be under 23
pe' son-rem.
Howe
he licensee experienced five unscheduled
outages that resul
in 29 additional per;on-rem. 1he collec-
tive doses from Muary through April 1990 was 314 person-rem.
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During this perip' (the licensee performed a significant amount
d
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tor S/G) maintenance and removed the resistance
of steam genert}tector (RTD) bypass manifolds on all reactor -
temperature de
coolant loopf.
The licensee performance against goals of 124
person renyTor RTD bypass line removal and 187. person-rem for
S/G main
Actual collective dose for RTD work
was 10 )tnance was good.
person rem and 96 person-rem for S/G maintenance.
!
Altho b the refueling outage 5 ended one month after this
ass
sment period most collective dose was acquir9d prior to
A
1 30, 199*).
Licensee overall collective dose reduction
rformarce was good.
The licensee completed the outage with _
384 person-rem, which was well under the goal of 450 person-rem.
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Additional collective dose reduction measures in progress are:
(1) the reduction of mesh sizes of filters to decrease the
amount and size of radioad1
particles in the reactor. coolant
system, (2) replacement of .. ves containing stellite, and (3)
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planning for the installation of a reactor head shield during
the 1991 refueling outage.
Attention and participation in the ALARA program appears to have
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increased during this assessment period and management is
proactive in ALARA in*tiatives.
Other strengths in the ALARA
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program included, the annual continuing training of HP personnel,
the discussion of dose goal performance as part of each person's
performance appraisal, and improved general worker knowledge of
ALARA conrepts and awareness of the need to minimize exposure.
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16
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of the feedwater water hammer event were effective. Engi eering
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identification and evaluation of high energy line brea' impact
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on intermediate building chiller capacity were effec ve.and
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demonstrated aggressive engineering involvement in p nt issues.
Engineering evaluation and resolution of the elec o-hydraulic
control relay card failure were comprehensive.
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In contrast to the good performance of engi
ering on major
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issues, engineering support is not as aggre ive in response to
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more roctine problems.
Examples were the untimely technical
suppor', provided by engineering in inves} gating and evaluating
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the steam generator resin intrusion pro iem which contributed to
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extented low power plant operation
tside of recommended
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chemittry limits, the condensor ext action line failure, and
root csuse determination for routi e plant trips or equipment
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failures prior to restart.
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Control of design change a t
ity has been adequate with the
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exception of deficiencies
tified related to post-modification
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testing. A MOV wiring (
ication deficiency was not identified
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by post-modification
t ng which resulted in the inoperability
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of one residual heat
oval train. This wiring deficiency was
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identified and correc d by the licensee during a post-modification
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review.
Wiring err s in the main steam isolation valve test
panel and safety r ated battery modifications were also not
,
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identified by po -modification testing.
Following B safety
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related battery eli replacement, weak engineering guidance for
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post-maintena e testing snd poor work practices by maintenance,
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resulted in
ttery installetion with reverse polarity.
The.Syste
Engineering program which tae previous SAlp report
identif d as incomplete has been fully. implemented.
This
e
progr
has provided improved engineering support and is well
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plan d and implemented.
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T ' licensed operator training program continued to be a strong
rogram.
Initial examinations were administered to 5 reactor
operator carididates with all candidates passing.
This 100 per
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cent pass rate which has continued since 1984 demonstrates the
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high quality of the V. C. Summer licensed operator training
program.
Significant resources were dedicated to the
development of the licensed operator requalification program.
This program was upgraded to meet established NRC requirements
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for operator requalification training.
_ Requalification
examinations were administered to 24 candidates with 21 passing.
The plant specific simulator was upgraded with a new computer,
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during this assessment period and is scheduled for certification
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in 1990.
A rotational policy is being established to rotate two
SR0's from on-shift duties to the training group on a two year
,
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