ML20059A351

Errata to SALP Rept 50-395/90-11 for Jan 1989 - Apr 1990

ML20059A351
Person / Time
Site:	Summer
Issue date:	08/13/1990
From:	NRC
To:
Shared Package
ML20059A349	List: IR 05000395/1990011 ML20059A346 ML20059A351
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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ERRATA SHEETS

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Pg - Line InitiJl Report Reads final Report Reads-

? coversheet- 2 INITIAL SALP REPORT- FINAL SALP REPORT

-7 .38 ...(2)replacement of

valves...

...(2) replacement of

. some cf the valves.....

16- 44 .. 1990. .. 1991..

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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 -

licensee increased the health physics (HP) staff by onverting 5

of the 10-15 semi-permanent contract HP techniciap positions to i

permanent positions, and staff turnover has bee rlow. In the  !

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 ,

performance as previously observed. l

The licensee's training program radiation protection

radwaste, and chemistry were revi ed and found to be effective '

and consistent with ANSI stand ds and licensee internal

procedures. 4 l

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 maintenance

tor S/G) licensee performed a significant

and removed amount

the resistance

of steam genert}tector

temperature de (RTD) bypass manifolds on all reactor -

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

personwas

remgood.

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 _  :

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384 person-rem, which was well under the goal of 450 person-rem.

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)

planning for the installation of a reactor head shield during

the 1991 refueling outage.

Attention and participation in the ALARA program appears to have  !

increased during this assessment period and management is

proactive in ALARA in*tiatives. Other strengths in the ALARA

/ 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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of the feedwater water hammer event were effective. Engi eering  !

identification and evaluation of high energy line brea' impact _!

on intermediate building chiller capacity were effec ve.and t

demonstrated aggressive engineering involvement in p nt issues.

Engineering evaluation and resolution of the elec o-hydraulic  ;

control relay card failure were comprehensive. .

In contrast to the good performance of engi ering on major I

issues, engineering support is not as aggre ive in response to ,

more roctine problems. Examples were the untimely technical

suppor', provided by engineering in inves} gating and evaluating .

the steam generator resin intrusion pro iem which contributed to t

- extented low power plant operation tside of recommended

chemittry limits, the condensor ext action line failure, and

root csuse determination for routi e plant trips or equipment

i failures prior to restart. s

Control of design change a t ity has been adequate with the l

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exception of deficiencies tified related to post-modification

L testing. A MOV wiring ( ication deficiency was not identified

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by post-modification t ng which resulted in the inoperability i

of one residual heat oval train. This wiring deficiency was  ;

i identified and correc d by the licensee during a post-modification

L review. Wiring err s in the main steam isolation valve test

, panel and safety r ated battery modifications were also not

!- identified by po -modification testing. Following B safety '

l related battery eli replacement, weak engineering guidance for

l post-maintena e testing snd poor work practices by maintenance,

! 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

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progr has provided improved engineering support and is well

i 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

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operator carididates with all candidates passing. This 100 per

cent pass rate which has continued since 1984 demonstrates the

i. 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 ~

for operator requalification training. _ Requalification

examinations were administered to 24 candidates with 21 passing.

The plant specific simulator was upgraded with a new computer, .

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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