ML17279A927
| ML17279A927 | |
| Person / Time | |
|---|---|
| Site: | Columbia |
| Issue date: | 03/16/1988 |
| From: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Mazur D WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| Shared Package | |
| ML17279A928 | List: |
| References | |
| NUDOCS 8804040225 | |
| Download: ML17279A927 (4) | |
See also: IR 05000397/1988007
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION
NBR: 8804040225
DOC. DATE: 88/03/16
NQT*Rl ZED:
NO
FACIL: 50-3cij'7
WPPSS Nuclear
Pro Jecti
Unit 2i
Washington Public
Poee
AUTH.'NAME
AUTHOR AFFILI*TION
MARTINiJ. B.
Region
5i
Qfc of the Director
REC IP. NAME
RECIPIENT AFFILIATION
MAZURi D. W.
Washington Public
PoUJer
Supply
System
SUBJECT:
Foreard s
Mgt Meeting Rept 50-397/88-07
on 880301. Top ics
discussed
listed.
DISTRIBUTION CODE;
IEOID
COPIES
RECEIVED. LTR
I
ENCL J
SIZE;
TITLE: General
(50 Dkt)-Insp Rept/Notice
of Violation Response
NOTES:
DOCKET
050003zi7
RECIPIENT
ID CODE/NAME
PD5
COPIES
LTTR ENCL
1
REC IP IENT
ID CODE/NAME
SAMWORTHi R
COPIES
LTTR ENCL
2
2
INTERNAL:
IMQRISSEAUi D
NRR/DLPG/GAB10A
NRR/DREP/EPB10D
NRR/DRIS DIRWA2
&sLINB
MANiJ
REQ
F
02
5
FILE
01
DEDRO
NRR/DLPG/PEB11B
NRR/DOE* DIR11E
NRR/DREP /RP810A
NRR/PMAS/ ILRB12
1 5-9-18
RES/DRPS
DIR
1
1
1
1
1
1
1
1
1
1
1
1
EXTERNAL:
LPDR
NRC
TOTAL NUMBER QF COPIES
REQUIRED:
LTTR
22
ENCL
22
"'MR 16
1gg8
Docket No. 50-397
Washington Public Power Supply System
P.O.
Box 968
Richland, Washington
99352
Attention:
Mr.
D.
W. Mazur
Managing Director
Gentlemen:
Subject:
Management
Meeting
This refers to the Management
Meeting held with Mr. A.
L. Oxsen
and other
members of the Supply System staff at the Region
V office on March 1, 1988.
The purpose of this meeting
was to discuss
items of interest pertaining to the
activities authorized
by NRC license
Subjects
discussed
during the
meeting are
summarized
in the enclosed
meeting report 50-397/88-07.
The following topics were given special
emphasis
in our discussions
during this
meeting:
1.
We discussed
the reactor building roof overpressurization
event
experienced
on February 14,
1988 and the root cause
assessment
conducted
by your staff.
While the Supply System
appeared
to have
done
a thorough
root cause
assessment,
we expressed
concern that your management
did not
place
more emphasis
on the
human performance
aspects
of this event.
Specifically, it appeared
that the plant staff did not fully appreciate
the concept of not proceeding with an activity until anomalous
equipment
bahavior or indications are understood.
It was agreed that this concept
would be reemphasized
to the plant staff before restart.
2.
Your staff could not give assurance,
based
on thorough
system testing,
that controls,
alarms,
and protective trips associated
with the reactor
building ventilation system would perform as intended
by the design
bases.
We noted that additional
emphasis
needed to be given'to complete
end-to-end testing of system features
(such
as the high and low pressure
trips of the ventilation fans).
We agreed during the meeting that this
testing of the reactor building ventilation system would be accomplished
before plant restart.
3.
The potential
impact of balance-of-plant
system failures
was discussed
briefly.
We stated that your staff should assess
whether
other balance-
of-plant fai lures could adversely
impact the operation or integrity of
safety-related
systems.
4.
We noted that our previous meeting
on February 4,
1988
had included
a
discussion of design-related
issues
and the program you are undertaking to
correct problems identified in the design area.
The design problems
found
8804040225
88000
g031b
ADOCK 0
6
-2"
in the reactor building ventilation system,
as discussed
during our
March 1 meeting, further illustrated this concern.
In addition, the
errors identified in Anticipated Transient Without Scram
(ATWS) design
change
packages
issued for installation
have raised serious
questions
regarding the effectiveness
of your current program for performing design
and design review activities.
We intend to conduct further assessments
of
the quality of your design activities,
and encourage
you to do the
same.
5.
We expressed
continuing interest in the performance of your quality
oversight groups (the Nuclear
Safety Assurance
Group and gA/gC
organization)
and the need for these
groups to assume
a more active role
in the identification and correction of human performance
and design
problems
such
as those discussed.
Completion of the testing
and briefings discussed
in items
1 and
2 above,
respectively,
was
documented
in Mr. A.
L. Oxsen's letter dated
March 5, 1988,
which was given to our Senior Resident
Inspector
before plant startup.
We
would anticipate further discussion .of items 3, 4,
and
5 above during our next
management
meeting.
In accordance
with 10 CFR 2.790(a),
a copy of this letter and the enclosure
will be placed in the
NRC Public Document
Room.
Should you have
any questions
concerning this meeting,
we will be glad to
discuss
them with you.
Q-ibiWI6(
J.
B. Martin
Regional Administrator
Enclosure:
Inspection
Report
No. 50-397/88-07
cc w/enclosure:
C.
M. Powers,
P.
L. Powell,
R.
B. Glasscock,
G.
E.
Doupe,
Esq.,
A.
L. Oxsen,
State of WA
N.
S.
Reynolds,
Esq.,
BLCP8R
bcc w/enclosure:
Resident
Inspector
Project Inspector
D. Persinko,
G.
Cook,
RV
B. Faulkenberry,
RV
J. Martin,
RV
docket file
bcc w/o enclosure:
LFMB
M. Smith
REGION V
CCaldwe
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Phial
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3//$ /88
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3/15/88
3/7( /88
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