ML16341C845
| ML16341C845 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 11/15/1978 |
| From: | Sternberg D, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16341C846 | List: |
| References | |
| 50-275-78-17, 50-323-78-16, NUDOCS 7812150004 | |
| Download: ML16341C845 (8) | |
See also: IR 05000275/1978017
Text
U, S.
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION AND ENFORCE~IEIT
50-275/78-17
Report,No.
50-323/78-16
'Docket No.
50 275~ 50-323
REGION V
License
No, CPPR-39,
CPPR-69
Safeguaxds
Group
Licensee:
Pacific Gas
and Electric Company
77 Beale Street
San Francisco,
94106
Facz] ity Name
Diabl 0 Canyon Units
1
8( 2
"Inspection at:
Diablo Canyon Site,
San Luis Obis
o Count, California
Inspection
c
ucted:
ctober 1-31,
197
Inspectors:
Young, r., Resident
cto
Inspector
Date'Signed
Date Signed
'pproved
By:
Summary:
D. H. Sternberg,
Chic, Reactor Projects
Section gl
Reactor Operations
and Nuclear Support Branch.
Date Signed
ll/0 7
Inspection
on October 1-31.
1978
Re ort Nos.
50-275/78-17
and
50-323/78-16
~d:
R
i
1
P
i
fp
p
i
> 'ig
protection, plant tour, problem reports,
IE Bulletin followup, design
changes,
meeting with local officials and witnessing of testing in
progress.
This inspection involved 152 inspector-hours
onsite
by one
NRC resident inspector.
Results:
No items of noncompliance or deviations
were identified.
781.21500o't
RV Form 219(2)
DETAILS
Persons
Contacted
- R. D.
Ramsay,
Plant Supervisor
- R. D. Etzler, Project Supervisor
R.
P. Mischow, Director, guality Assurance
J.
B. Hoch, Project Engineer
- tl. N. Norem, Resident Startup
Engineer
N.
E.
Lepphe,
gA Supervisor
- J.
S.
Diammon,
gC Supervisor
- R. Patterson,
Supervisor, of Operations
- D. A. Backons,
Supervisor of tlaintenance
- J. M. Gesclon,
Power Plant Engineer
The inspector also talked with and interviewed
a number of other
licensee
employees,
including members of general
construction,
the
operations staff and
gA organization
personnel.
- Denotes those attending the exit interview.
Fire Protection
The control
room and all cable spreading
rooms of both units were
inspected.
The fire alarm, extinguishing equipment,
actuating
con-
trols and fire-fighting equipment
were verified to be operable in
the cable spreading
rooms
and
25K of the balance of the plant.
The
modification penetration
seal material
was verified not to be
flammable.
The findings of the last insurance
inspection
was
examined
by the inspector.
No items of noncompliance or deviations
were identified.
P
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 "Man on the Line, Caution,
Information and Clearance" tags'n
equipment,
and to review
with'perators
the status of various
systems
in the. plant.
During one such tour,
a worker pointed out to the inspector
some
rebar which had not been installed in accordance
with their in-
stallation drawings.
Discussions
held with gA personnel
and other
licensee
representatives
indicated that design engineering
had
been
apprised of the situation.
Subsequently,
the rebar was,re-worked
and verified by the inspector to meet the requirements
before the
concrete
was poured.
The inspector
had
no further questions
on
this subject.
No items of noncompliance or deviations
were identified.
Problem
Re orts
The requirements
of Administrative Procedure
No. C-12 (Reporting
and Resolution of Plant Problems/Nonconformances)
were examined.
, The inspector
examined
some
75 problem reports
and found the manage-
ment system to be working.
In one instance,
based
on the proposed
technical
specifications
(not a requirement at this time), the
inspector
found
a problem report which should
have triggered
a
nonconformance
report but had not done so.
If the facility had
. been in operation, this would have
been
a deviation from the
reporting requirements.
No items of noncompliance or deviations
were identified.
IE Bulletin Followu
No. 78-06
This item essentially
remains
unchanged
from that previously
r eported
(Report
Ho. 50-275/78-14).
The requisitions
have
been
received onsite
and the inspector
was informed by a licensee
repre-
sentative that another lett'er had
been sent to the
HRC with a
new
completion date for the work.
Ho .items of noncompliance
or deviations
were identified.
Desi
n Chan
es
The requirements
of Administrative Procedure
No.
C-1
(Design
Changes)
were examined.
This system addresses
design
changes
which
are minor in nature
and are within the capabilities of the onsite
staff.
The inspector found this system to be operational.
Engi-
neering
Department
Procedure
No. 3.6 (Design Changes),
which governs
design
changes
not within the capabilities of the onsite organization,
was found not to be. fully implemented
by the operations division.
A licensee
representative
stated that this procedure
would be fully
implemented prior to licensing.
In the
mean time,
a system called
"Design Comments,"
which has
been in effect for several
years is
still being used.
The inspector
examined
some
75 of the safety-
r elated
design
comments
and found them to be well researched
and in
very good detail.
The licensee
has committed to closing out all
design
comments
and having the
gA department audit that system
prior to licensing.
This is considered
to be an open item and will
be examined
by a Region
V inspector
subsequent
to the
gA department
audit.
(50-275/78-17-1)
No items of noncompliance or deviations
were identified.
Neetin
s with Local Officials
The inspector
and two representatives
from the regional office met
with local officials throughout the county to acquaint
them with
0
-3-
the mission of the
NRC; to introduce
key
NRC personnel
associated
with the facility, to discuss
lines of communications with NRC, and
to discuss
the status of the facility and related
community concerns.
The greatest
concern appears
to be the transportation,
storage,
and
disposal of high-level radioactive waste.
No items of noncompliance
or deviations
were identified.
8.
Preo erational
Testin
Portions of the following tests
were witnessed
by the inspector:
28.6
23.3
Energizing
480 Volt Switchgear
Preoperational
Testing of Auxiliary and Fuel Handling
Buildings Ventilation
19.2.12
Spent Resin
System Preoperational
Testing
39. 3
Leak Rate Test
39.1
A3
Retest of Isolation Valves
23.4 Al
Containment
Fan Cooler Testing
While witnessing the above testing (in some tests
only parts of the
test 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.
No items of noncompliance or deviations
were identified.
9.
Exit Interview
The inspector
met with a senior licensee representative
on a weekly
basis
and with the representatives
(denoted in Paragraph
1) at the
conclusion of the inspection
on October
27,
1978.
The scope
and
findings of the inspection were summarized
by the inspector.
No
other commitments aside from those in Paragraph
3,
5 and
6 were
made
by the licensee.
eI /