ML16340A408
| ML16340A408 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/06/1979 |
| From: | Johnston G, Sternberg D, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16340A409 | List: |
| References | |
| 50-275-79-04, 50-275-79-4, NUDOCS 7904190192 | |
| Download: ML16340A408 (8) | |
See also: IR 05000275/1979004
Text
~g
Repor t No
50 275/79
04
Docket
No. 50 27
U ~
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION AND ENFORCEMENT
REGION V
License
No.
Gafaduarda
Group
Licensee:
Pacific
Gas
and Electric ComPany
77 Beale Street
San Francisco
94106
FaciIity
Name ~
,
Diablo Canyon Unit
1
Inspection at:
Diablo Canyon Site,
San Luis Obispo County, California
Inspection
co
u ted;
, Fe rualy 1-'23,
1979
a
Inspectors:
T.
Youn
Jr.,
R
id nt
ctor I
6.
W. ~+hnsto
Reactor Inspector
spector
Date
igned
Da e Signed
ate Signed
Approved By:
Summary:
D.
l1. Sternberg,
Chs&g Realtor
Prospects
Sect
Reactor Operations
and Nuclear Support Branch
ion
1
ate Signed
Ins ection on Februar
1-23,
1979
Re ort No. 50-275 79-04
p
tp
1
ig.s
tour, witnessing of system verification testing
and other testing in
progress,
preoperational
test program controls
and quality assurance
for
preoperational
testing,
and review of special
report (CILRT).
This
inspection involved 82 inspector-hours
onsite
by one
NRC resident
inspector,
and
12 inspector-hours
onsite
by one regional
NRC inspector.
Results:
No items of noncompliance
or deviations
were identified.
RV Form ?19
(2
>904>so /9~
4
DETAILS
l.
Persons
Contacted
- R. D. Ramsay,
Plant Superintendent
R.
D. Etzler, Project Superintendent
- N. H. Horem, Resident Startup
Engineer
N.
E. Leppke,
gA Supervisor
- J. S.
Diamonon,
gC Supervisor
R. Patterson,
Supervisor of Operations
- D. A. Backeons,
Supervisor of Naintenance
- J. N. Gisclon,
Power Plant Engineer
- C. N. Seward,
gA Engineer
- J.
D. Shiffer, Assistant to the Plant Superintendent
The inspector also talked with and interviewed
a number of
other'icensee
employees,
including members of general
construction,
the
operations staff and
gA organization
personnel.
- Denotes
those attending
the exit interview.
2.
Preo erational
Testin
a.
Portions of the following tests
were witnessed
by the inspector:
21.2 A-1
Reflush Diesel
Fuel Oil System Lines
16.2 A-1
Reflush Primary Water Line to
\\
24.3
Purge
Gaseous
Radwaste
System
37.10
Steam
Dump Performance
Demonstration
37.4 A-1
Reactor
Coolant System Thermal
Expansion Test
b.
While witnessing the above testing (in some tests
only parts
of the tests
were being performed or redone),
the inspector
verified that the procedures
were technically adequate;
the
latest revisions
were available
and approved;
the overall
crew
performance
was adequate
and, in the case of completed tests,
the acceptance
criteria were met.
Administrative controls for
design
change
and documentation
were followed.
Ho items of noncompliance
or deviations
were identified.
Plant Tour
The inspector walked through various areas of the plant on
a weekly
basis
to observe activities in progress;
to inspect the general
state of cleanliness,
housekeeping
and adherence
to fire protection
rules; to check the proper approval of "tlan on the line, Caution
and Clearance"
tags
on equipment;
and to review with operators
the
status of various
systems
in the plant.
The inspector
noted that the status of the systems
and the house-
keeping
appeared
consistent with construction activities.
Within
the past
two weeks, extra personnel
have
been assigned
to the
cleanup
crews
and housekeeping
is improving.
No items of noncompliance
or deviations
were identified.
S stem Verification Testin
SVT
SVT (Mini Hot Function Testing)
was started
on February
20,
1979
and is scheduled
to continue approximately thirty days.
During
this period,
the plant is to be brought up to operati ng temper-
atures
and pressures.
All subsystems
and/or components
which have
had corrective maintenance
and/or modifications will be retested
to
assure their operational
status.
At the conclusion of the in-
spection,
the primary system
(RCS) temperature
had
been raised to
120'
with a pressure
of 50 PSIG and
RCS venting was in process.
Ho items of noncompliance
or deviations
were identified.
Prep erational
Test Pro ram Controls
The inspector verified by record review and/or observation
that (a)
jurisdictional controls were being observed for system turnover,
(b) tagging
was being accomplished
consistent with jurisdictional
controls of the administrative
procedures
and (c) controls were
being observed prior to and subsequent
to testing.
A schedule for
preoperational
testing is being maintained
and updated
when necessary.
Ho items of noncompliance
or deviations
were identified.
Prep erational Testin
A
The inspector
examined all
gA audit reports of preoperational
testing audits
conducted within the last three months.
The audits
were conducted
in accordance
with approved
procedures
and corrective
actions for all discrepancies
had
been
taken.
System turnover from
1l
~I
construction to startup test group and to operations division was
being conducted
in accordance
with established
procedures
and
administrative controls.
No items of noncompliance
or deviations
were identified.
6.
Review of Periodic
and
S ecial
Re orts
A review was conducted
by the inspector of the Diablo Canyon Unit
1
Reactor
Containment Building Integrated
Leak Rate Test report for
October
30 - November 1, 1978.
This report also included
a summary
analysis of the Type
B and Type
C penetration tests.
The inspector
,reviewed this report and the supportive information to ascertain
whether this information appears
technically adequate.
The following
documents
were
used in the review:
a 0
Appendix J to 10 -CFR 50, "Primary Reactor
Containment-Leakage
Testing for Hater-Cooled
Power Reactors."
b.
American National Standard
N45.4-1972,
"Leakage
Rate Testing
of Containment Structures for Nuclear Reactors."
r
c.
Regulatory
Guide 1.68, "Preoperational
and Initial Startup
Test Programs for Hater-Cooled
Power Reactors."
d.
Topical Report BN-TOP-1, Revision
1, "Testing Criteria for
Integrated
Leakage
Rate Testing of Primary Containment Structures
for Nuclear
Power Plants,"
Bechtel
Corporation.
e.
Diablo Canyon Technical Specifications for Unit l.
'I
The inspector's
independent
calculations
over the time period of
the test
(1130 on 10/31/78 to 0730 on ll/ll/78) indicate
a mass
point leak rate of 0.0225 weight percent
per day;
as
opposed
to the
licensee's
figure of 0.0219 weight percent
per day.
Both figures
are within the allowable limit of 0.0354 weight percent per day for
the case of a reduced
pressure
test for the facility based
on a BN-
TOPl test procedure.
No items of noncompliance or deviations
were identified.
7.
Exit Interview
The inspector
met with a senior licensee
representative
on a weekly
basis
and with the representatives
denoted in Paragraph
1
on
February
23,
1979.
The scope
and findings of the inspection were
.
summarized
by the inspector.
h