ML16340B950
| ML16340B950 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 07/17/1981 |
| From: | Bagaglio M, Mendonca M, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML16340B951 | List: |
| References | |
| 50-275-81-13, 50-323-81-10, NUDOCS 8108040424 | |
| Download: ML16340B950 (14) | |
See also: IR 05000275/1981013
Text
.S.
NUCLEAR REGULATORY COMMISS
~
~
OFFICE
OF
INSPECTION AND ENFORCEMENT
50-275/81-13
Repor t No.
50-323/81-10
50-275
Docket No.
50-323
REGION
V
License
No.
CPPR-39
CPPR-69
Safeguards
Group
Licensee:
Pacific Gas
and Electric Company
P. 0.
Box 7442
San Francisco, California 94106
June
5 - July 3,
1981
Inspection
conducted:
Inspectors:
Mar
Bagaglio, Jr
,
Se
or Resident
Inspector
Facility
Name:
Diablo Canyon Units
1
and
2
Inspection at:
Diablo Canyon Site,
San Luis Obispo County, California
Date Signed
Ma vi
Mendonca,
Resi
nt Reactor Inspector
Date Signed
pproved
By:
D.
M. Steinberg, Ch'actor
Projects
Section
1
Reactor, Operations,Projects
Branch
Date Signed
Date Signed
Summary:
Ins ection of June
5 to Jul
3
1981
Re or t Nos.
50-275 81-13
& 50-323 81-10
~d:.1"
d:
R
1
1
p
1
1
1'ddgp1 <<,
d
bulletin/circular followups, and followup of outstanding
items.
This inspection
involved 47 inspector-hours
onsite
by two NRC resident inspectors.
Results:
No items of noncompliance
or deviations
were identified.
,( 8108040424
810717 f 'I
ADOCK 08000275~i
8
IPDR)
RV Form 219 (2)
li
l
I
i'\\
c4
r
bl
r
<APi f, yf
j
P$ 4
y
Pacific
Gas
and Electric Company
-2-
from public disclosure.
This section further requires the statement
to address
with specificity the considerations
listed in 10 CFR 2.790/b)(4).
The information
sought to be withheld shall
be incorporated
as far as possible into a separate
part of the affidavit. If we do not hear from you in this regard within the
specified periods
rioted above,
the report will be placed in the Public Document
Room.
Should you have any questions
concerning this inspection,
we will be glad
to discuss
them with you.
t
Sincerely,
~b>illa/) &Igflc4
1
g. g. g~ ~~ngea~ >8+4Pk
j Lf~~
J. L. Crews, Chief
Reactor
Oper ations Projects
Branch
Enclosure:
IE Inspection Report
Nos. 50-275/81-13
50-323/81-10
cc w/o enclosure:
J.
0 Schuyler,
PGE
J.
D. Shiffer,
PGE
M. A. Raymond,
PGE
R.
C. Thornberry (Diablo Canyon)
Sent to Reproduction,
Hg, for distribution
Distributed by RV:
RV RDR (2)
Engelken (ltr)
State of CA (Hahn/Johnson)
S, SiIver (Rpt only)
j
>
I rP f]Pq
qfw>rt<(,',g >'>f ~
f '
r
r ff'~i ~
~
f
~,It
<<f
]',.y>> >>'
.f,r,,"
.c
I C gf t f
~
I
>
>>ff
++@>>rt )>It,
+
fw>g I P
f ff"<>f~ y,>
foal fg
> >g
I
l>
l>f(
K
f
f>f
f
DETAILS
Persons
Contacted
- R. Thornberry,
Plant Manager
- R. Patterson,
Plant Superintendent
J.
S.
Diamonon,
gC Supervisor
- J.
M. Gisclon,
Power Plant Engineer
D. g. Backens,
Supervisor of Maintenance
J.
A. Sexton,
Supervisor of Operations
- J. V. Boots, Supervisor of Chemistry
and Radiation Protection
- R. T. Twiddy, Supervisor of guality Assurance
- W. B. Kaefer,
Technical Assistant to the Plant Manager
The inspectors
also talked with and interviewed
a number of other licensee
employees
including members of general
construction,
the operations staff,
and
gA personnel.
- Denotes those attending the exit interview.
Plant Tour
The inspectors
walked through various
areas
of the plant on
a weekly basis
to observe activities in progress;
to inspect the general
state of clean-
liness,
housekeeping;
and adherence
to fire protection rules; to check the
proper approval of "man on the line, caution
and clearance"
tags
on equipment,
and to review with operations
personnel
the status of various
systems
in the
plant.
The inspectors
observed that the status
of the systems
and the housekeeping
appeared
consistent with construction activities.
The reactor cavity is
still being maintained
as
a clean area.
No items of noncompliance
or deviations
were identified.
Procedure
Review
The procedure
on emergency boration,
was reviewed.
This procedure
calls for an optional boration which requires closing of the centrifugal
charging
pump recirculation valves.
These valves
are required to be open
to assure
adequate
coolant flow through the centrifugal charging
pump on
pump startup.
The licensee
has
been apprised
that the operator
may need
to open these
valves
on
a safety injection signal to assure
centrifugal
charging
pump function.
This issue will be<carried
as
an open item until
resolved.
Additional Procedures
Reviewed:
1-
Malfunction of Reactor
AP C-4sl
(see
below)
Makeup Control
, Jumpers
and Lifted Circuit Log
1
1
~
~
'l
II
~
'
'%
~ AI
~ 8
r
6
I
r
P
,I
v
V
4.
I
ps,g
'J
C-104
Independent verification'of Operating Activities (see below),
and
Numerous Procedures'on-Exercising
Valves in ECCS,
Auxiliary Feed
System
and Related
Systems
No items of noncompliance'or 'deviations
wet e idehtified'.,
rP>>
~l
'
IE Bulletin/Circular Followu
"'-
"
!.>'fl
An inspector
reviewed
licensee~",actions, related to IE,Bulletins and Circulars.
Inspection findings were
as follows:
IE Bulletin 80-24: Prevention of Damage
due to Hater leakage
inside
Containment
(closed).
Although not required to respond to this bulletin,
the applicant reviewed potential
sources
of ',water leakage into contain-
ment addressed
by the bulletin."
Th'e applicant's:rev'iew went beyond the
scope of the bulletin and demonstrated
in each
instance
where
an alarm
condition and/or routine surveillance
performed
on
a shift basis
would
detect the subject "leakage.
The cooling water systems
inside contain-
ment are closed
systems
and have not experienced
any leakage
problems
to date.
Based
upon discussions
with a licensee representative
and
review by the inspector of an applicant's written investigation into this
problem area,
the applicant
has
met the intent of the bulletin and it
is considered
closed.
No items of noncompliance
or deviations
were identified.
C
5.
Fuel
Load (FL)/Full Power
(TAP) items were reviewed during the course of
- this inspection:
a ~
Tap I.C.6. - Guidance
on Procedures
for Verifying Correct Performance
'f
Operating Activities (FL requirement)
Summary:
It is required
(from NUREG-0737) that licensees'rocedures
be reviewed
and revised,
as necessary,
to assure that
an effective
system of verifying the correct performance
of operating activities
is provided
as
a means of reducing
human errors
and improving the
quality of normal operations.
This will reduce
the frequency of
'occurrence
of situations that could result in or contribute to accidents.
Such
a verification system
may include automatic
system status monitoring,
human verification of operations
and maintenance activities independent
of the people performing the activity (see
Recommendation
5),
or both.
Findings
and Conclusion:
An inspector
has reviewed Nuclear Plant
Administrative Procedure
(NPAP) C-104,
Independent Verification of
Operating Activities.
In NPAP C-104, the applicant
has specified the
sequence
to be followed by plant personnel
conducting
independent
verifications.
The applicant
has also delineated
time limits to perform
independent verifications
and individuals who may make initial and
0
1
~
~
li" 'v
i
J
4
a'
/
t
~ I
pl
I
sl
1,'i
4
a,
'I
1
1
t
't
I'
\\
t,
t
Il
I
1(
restoration
lineups of systems,-
NPAP C-104 complements
several
other
applicant administrative procedures
used to perform maintenance
and
surveillance tests of preventive maintenance.
Based
upon review of
NPAP C-104
and its integration with existing directives, this
TAP
is considered satisfied
and closed.
il
b.
TAP II.K.l - IE Bulletins on Measures
to Mitigate Small
Break
and Loss of Feedwater
Accidents
(FL prerequisite)
NUREG 0737 addresses
seven
items under this
TAP that
need to be satisfied
prior to fuel load.
Of these
seven,
four are applicable to Babcock
and Wilcox plants
and are hence
not applicable to Diablo Canyon.
Accordingly, the following paragraphs
discuss findings regarding the
three applicable items.
(1)
Summary:
TAP II.K.l, Item 5, which corresponds
to
IE Bulletin 79-06A,
Item 5.
For facilities for which the auxiliary
system is not automatically initiated, prepare
and im-
plement immediately procedures
which require the stationing of an
individual (with no other assigned
concurrent duties
and in direct
and continuous
communication with the control room) to promptly
initiate adequate
auxiliary feedwater to the steam generator(s)
for those transients
or accidents
the consequences
of which can
be limited by such action.
Findings
and Conclusion:
system is auto-
matically initiated at Diablo Canyon.
This portion of the subject
TAP is closed.
(2)
Summary:
TAP II.K.1, Item 10,which corresponds
to
IE Bulletin 79-06A,
Item 10.
Review and modify as necessary
maintenance
and test procedures
to ensure that they require:
(a)
Verification, by test or inspection, of the operability of
redundant safety-related
system from service.
(b)
Verification of the operability of all safety-related
systems
when they are returned to service following maintenance
or
testing.
(c)
Explicit notification of involved reactor operational
personnel
whenever
a safety-related
system is removed from and returned
to service.
Findings
and Conclusion:
The, following applicant administrative
procedures
have
been reviewed:
NPAP A101, Supplement'
NPAP C3, Supplement
1
Relieving the Watch
Surveillance Testing
and
Iqspection
4
1
1
~
1
y/p
"~ (
) ~ ' 'P
'1
~l('
'
~
'l
i l
.
",%g 'j~
>1 ~ L%
4
L1
1
(L 'I
C;
~
~
~
~
~g, ~'
g
~
'
-4-
~l
F-
l9>t
ie
'r
(3)
NPAP
C4
'
',. '
Bypa'ss~ofwSafety
Fun'ctions
and
,'
", ;...;.,'Contr~ol of
Jumpers,'PAP
C4, Supplement
1"
'~Temporar'y Modifications, Jumpers,
- and
- Lifted Circuit Log Clearance
NPAP C-6,"Supplement:
1
', Clearance
Request.~Procedure
~,4',
~
These
procedures,aJdr'e'ss
'satisfactorily, each'f
the requirements
cited in the
Summary, above.",Accopdingly,
this'<portion of the
subject
TAP is closed;
L
Summary:
NUREG 0737,',TAP 'II.K..l, Item 17, which corresponds
to
IE Bulletin 79-06A,
Item 3.
For,facilities that use pressurizer
water level coincident with pressurizer
pressure for automatic
initiation of safety injection into the reactor
coolant system,
trip the low pressurizer
level setpoint bistables
such that,
when
the pressurizer
pressure
reaches
the low setpoint,
safety injection
would be initiated regardless
of the pressurizer
level.
In addition,
instruct operators
to manually initiate safety injection when the
pressurizer
pressure
indication reaches
the actuation setpoint
whether or not the level indication has
dropped to the actuation
setpoint.
Findings
and Conclusion:
The applicant
has modified the installed
protective
system
such that pressurizer
pressure
signals
alone
are
used to automatically generate
one of the many engineered
safeguard
features
(ESF) actuations.
An inspector
has reviewed
EP OP-O, Reactor Trip with Safety Injection,
and
pated Transient Without Trip.
The procedures
direct operators
to manually initiate ESF upon reaching
the
ESF low pressure
act-
uation set point.
This portion of the subject
TAP is closed.
Since the applicant
has satisfied all applicable portions of this
TAP, it is considered
closed.
c.
TAP I.D."5, Procedure for Feedback of Operating
Experience to Plant
Staff.
NUREG 0737 required that,
"Each applicant for an operating license shall
prepare
procedures
to assure that operating
information pertinent to
plant safety originating both within and outside the utility organization
is continually supplied to operators
and other personnel
and is incor-.
porated into training and retraining programs."
We have reviewed
Nuclear Plant Administrative Procedure
C-14, Supplement
1, Dissemination
of Operating Experience,
and based
on this review find that the applicant
has complied with the requirement.
This
TAP item is, therefore,
closed.
No items of noncompliance or deviations
were identified.
I
~
6 r
- ~
~
~
~ "~
)
g
f
~ I
)f)
Q
"
4
~
I
~
V
s
I
6.
Prep eration Test Pio ram Controls
The inspectors verified by record review and/or observation that:
(a) juris-
diction controls were being observed for system turnover,
(b) tagging
was
being accomplished
consistent
with jurisdictional controls of the adminis-
trative procedures,
and (c) controls were being observed prior to and
subsequent
to testing.
A schedule
is being maintained for preoperational
testing
and updated
when necessary.
No items of noncompliance
or deviations
were identified.
7.
A for Preo erational Testin
The inspectors
examined all gA audit reports of preoperational
testing audits
conducted within the last three months.
The inspectors verified that the
audits
were conducted
in accordance
with approved
procedures
and that cor-
rective actions for all identified discrepancies
had
been taken.
System
turnover from construction to the startup test group
and to the operations
division was conducted in accordance
with established
procedures
and admin-
istrative controls.
No items of noncompliance or deviations
were identified.
8.
Exit Interview
An inspector
met with senior licensee representatives
on a weekly basis
and
with the representatives
(denoted
in Paragraph
1)
on July 9,
1981.
The
scope
and findings of the inspection
were summarized
by the inspector.
~
~
~
V
~
)
t
'I
~
1
II
I)
PW)
P
g
~
)
gg
f) q/
fl
El
C
I
P
Jl
1