ML17083B578
| ML17083B578 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/24/1985 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Shiffer J PACIFIC GAS & ELECTRIC CO. |
| Shared Package | |
| ML17083B579 | List: |
| References | |
| NUDOCS 8505090587 | |
| Download: ML17083B578 (8) | |
See also: IR 05000217/2004006
Text
AI Ii 24 1986
Docket Nos.
50-275
and 50-323
Pacific Gas
and Electric Company
77 Beale Street,
Room
1451
San Francisco,
California 94106
Attention:
Hr. J.
D. Shiffer, Vice President
Nuclear Power Generation
Gentlemen:
SUBJECT:
ÃRC INSPECTION OF DIABLO CANYON UNITS
1 AND 2
This zei rs to
a routine inspection,
conducted
by Messrs.."1.'M.."lendonca,
li. L. Padovan,
T. if. Ross,
and T. J. Polich, of this office during the period
of February
17,
1985,
through April 6,1985.
Thxs inspection
examined your
activities
as authorized
by NRC License
No. DPR-80,
and Construction Permit
No.
CPPR-69.
Discussions
of our findings vere held with fr. R.
C.
hornber'
and ~ther
memb rs of your staff, at the conclusion of the inspection.
Areas
examined during this inspection are described in the enclosed
inspection
report.
Within these
areas,
the inspection consisted
of selective
ezaminations
of procedures
and representative
records, int rviews with
personnel,
and observations
by the inspectors.
No v'olations of NRC requirements
were identified within the
scope ot this
inspectio~i.
However, your attention is invited to speciric findings in the
report pertaining to Unit 2 operations.
We recommend
you focus
on these
-'ssues
before entering
a mode of operation
where these findings become
critical.
In accordance
with 10 CFR 2.790
(a'.I,
a
copy of this 'letter,.and
the enclosures
will be placed in the
NRC Public Documen
Room.
Diablo Canyon
SSER-33
B.3-1
Appendix
B
e5050e05S7
BS0~2~
ADOCK 05000275
9
-2-
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Should you have
any questions
concerning this inspection,
we will be glad to
discuss
them with you.
Sincerely,
,('
.. ~J4 ~iI:> '!'.'..
D. F. Kcrsch; Acting Director
Division of Reactor Safety
and Projects
Enclosure:
Inspection Report Nos. 50-275/85-08
and 50-323/85-09
cc w/enclosure:
S.
D. Skidmore,
PGSE
P.
A. Crane, Jr.,
PGSE
R.
C. Thornberry,
PGGE (Diablo Canyon)
D. A. Taggert,
PGSE (Diablo Canyon)
R. steinberg,
PGSE (Diablo Canyon)
bcc w/enclosure:
RSB/Document Control Desk
(RIDS)
pink/green/docket file copies
LFMB (w!o enc)
Resident Inspector
State of CA
RV
pW
Padovan/dot
%Vs
Po~~'e~onca
It'.)~c"
4//tjfl5
4/l</85
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Diablo Canyon
SSER-33
B.3-2
Appendix
B
U. S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report Nos:
50-275/85-08
and 50-323/85-09
Docket Nos:
50-275
and 50-323
Iicense
No:
Construction Permit No:
CPPR-69
Licensee:
Pacific Gas
and Electric Company
77 Beale Street,
Room 1451.
San Francisco,
California 94106
Facility Name:
Diablo Canyon Units
1 and
2
Inspection at:
Diablo Canyon Site,
San Luis Obispo County, California
Inspection conducted:
February
14 - April 6,
1985
Inspectors:
M. M. Men onca, Sr.
esident Inspector
M. L. Padovan,
Resid nt Inspector
T. M. Ross, Resident
nspector
f /s" Fs
Date
igned
4'/I Pl
Da
e
igned
rr pr
Dat
Signed
Approved by:
T. J. Polxch, Resident Inspector
/f ff
Da
e
igned
g/P Pf
R. T.
D dds, Section Chief
Summary:
Ins ection from Februar
17
1985 throu h A ril 6
1985
(Re ort Nos. 50-275/85-08
and 50-323/85-09)
Dat
S gned
Areas Ins ected:
Routine inspection of:
Plant operations;
maintenance
and
surveillance activities; Unit 2 preoperational
test program; Unit
1 power
ascension
testing; Unit 2 systems
turnover; followup of open items
amd LERs;
reactive inspection of significant operational
events
and allegations;
independent
inspection of licensed operator shift manning,
generic concerns,
Eg program,
and
GONPRAC meeting.
This inspection effort required
357 inspector-hours
for Unit 1, and 303
inspector hours for Unit 2 by four resident inspectors.
Diablo Canyon
SSER-33
B.3-3
Appendix
B
20
These procedures
reference plant drawing 050909 which lists all
electrical
and
IGC devices
by manufacturer,'odel
number,
design
class,
Q listing reference,
seismic qualification,
and enviromental
qualification.
From drawing 050909,
environmental qualification
requirements for selected
equipment were noted
and verified to be
consistent with the requirements
for preventive maintenance
and
surveillance testing of selected
equipment.
This program further requires
any
EQ e'quipment,
work, and
documentation to be specifically labeled
as
EQ; additionally,
the'rogram
required training in the
EQ procedures,
as well as,
updating
and failure trend analysis.
The licensee
has planned for full
implementation of the
EQ program by March 31,
1985.
This date is
consistent with an understanding
between
the NRC's Office of Nuclear
Reator Regulation licensing project manager for Diablo Canyon
and
PG&E cognizant engineering
group.
e.
Station Batte
Installation
0 eration and Maintenance
J.
M. Taylor's
(NRC) February 26,
1985,
memo to the
NRC Regional
Administrators
on the subject of "Station Battery Operation
and
Maintenance," identified several deficiencies previously existing in
the installation, operation
and maintenance
of station batteries at
several nuclear facilities.
In response
to this memo, the inspector
evaluated
the condition of the Unit
1 station battery.
Items
evaluated
included
1) the physical installation (such
as battery
supports, battery fluid level, cleanliness,
cell integrity, lack of
terminal corrosion
and cell sediment, etc.)
and 2) battery records
(such as float voltages,
performance of service tests,
specific
gravity measurements,
equalization
charges, full capacity tests,
etc.).
Additionally, the inspector witnessed
the performance of STP
M-11A "Measurement of Station Battery Pilot Cell Voltage and
The inspector verified that 1) the acceptance
criteria of STP M-llA was met, 2) the requirements
of Technical
Specification Surveillance
Requirement
4.8.3.1 "Electrical Power
Systems - D.
C. Sources"
have been complied with, and 3) the
recommendations
contained in J.
M. Taylor's
memo are being
instituted for the Diablo Canyon Unit 1 station batteries.
No violations or deviations
were identified.
10.
Alle ation Followu
Task:
Allegation or Concern
No.
152
ATS No:
RV-84-A017
a ~
Characterization
Concerns with installation of P 1331 conduit clamps.
Three specific
concerns
were identified: 1)
P 1331 inner bolts cannot be torqued to
the specified torque;
2) the torque relaxes after several
days;
and
3) the torque values specified are excessive.
Diablo Canyon
SSER-33
B.3-4
Appendix
21
b.
Im lied Si nificance to Plant Desi
n
Construction
or 0 eration
Improper installation of P 1331 conduit clamps might result in
raceway supports
being incapable of performing their intended
functions.
c.
Assessment
of Safet
Si nificance
The staff verified that, prior to this allegation,
the licensee
had identified electrical raceway supports that were no< torqued
to values required for seismic design conditions.
The licensee
subsequently
issued
1625 torque modification packages
for Unit 2
raceway supports
to correct these deficiencies.
During the
implementation of the torque modification program,
the licensee
identified 159 torque modifications that could not be accomplished
as originally specified.
Additional engineering analysis
was required
on these
modifications,
78 of which involved
P 1331 clamps. Original torque
modifications required all clamp bolts regardless
of position, inner
.or outer, to be torqued to the value required for the critical
load-bearing bolt or bolts on the clamp.
Subsequent
modifications identified the specific bolts that required torquing
and either an alternative
method to torque the inner bolts if they
were load-.bearing or other methods to accomplish seismic hardening
of the clamps
such as increasing
the torque
on other bolts, or
welding.
The staff reviewed the revised torque modifications
on a
sampling basis to ensure that the inner bolt torquing concern
was
identified and adequately
addressed
by the licensee.
The staff determined that the second
concern regarding bolt
relaxation
was addressed
by the licensee prior to implemention of.
original torque modifications.
The licensee
contracted
ANCO
Engineers
Inc. to conduct tests to determine
the slip-resistance
capacity of bolted connections for various nut types
and bolt
These test results
were utilized by the licensee in
preparing the original torque modifications.
The inspector
reviewed portions of the
ANCO Engineering's
Test Report which
verified no significant bolt relaxation
was observed
during testing.
It was also determined that the third concern stating the torque
values specified are excessive
was addressed
by the licensee prior
to receipt of this allegation.
When the higher "excessive"
value of
85 ft-lbs was required by engineering analysis,
a Design
Change Notice
(DCN)was issued
which included
a hardware
change to
bolts that had been tested for both slip-resistance
and torque
relaxation at this higher torque.
The inspector verified that the
DCNs included
such hardware
changes.
d.
Staff Position
The staff found that the licensee properly identified and
dispositioned
these installation concerns prior to the allegation
Diablo Canyon
SSER-33
B.3-5
Appendix B
22
and there is acceptable
assurance
that raceway supports
were
properly installed.
Furthermore, in Section
6 of Supplemental
Safety Evaluation Report No. 29, March 1985, the staff concluded,
that the methods
used by the licensee
to evaluate electrical
raceway
supports including actual bolt torque levels,
were acceptable.
No further action is required.
Task:
Allegation or Concern Nos.
1652 and
1653
ATS NO:
RV-84-A122
a.
Characterization
Installation, inspection
and testing of seals in crane wall (inside
containment)
and auxiliary building penetrations
were performed by
personnel
who were not properly trained.
Indoctrination records
were falsified.
b.
Im lied Si nificance to Plant Desi n
Construction or 0 eration
The subject penetration
seals
perform one or all of the following
functions:
1) radiation shielding,
2) hydrostatic/air sealing
and
3) fire barrier sealing.
Unsatisfactory penetration shielding could
result in increased
personnel
radiation exposure
or unanticipated
damage to safety related
equipment
(as
a result of fires or steam
line breaks).
C ~
Assessment
of Safet
Si nificance
In responding to a Hot-Line concern,
as documented in Quality
Concern
Summary Report-110,
the licensee
held additional
conversations
with the concerned individual.
The individual
indicated that he did not intend to imply that training records
were
falsified.
Instead,
he clarified that training of Promatec
installation, inspection
and testing personnel
was not adequate.
The licensee's
findings from their review of the individual's
concern concurred that further onsite training and indoctrination of
Promatec craft personnel
was necessary.
Accordingly, all Promatec
personnel
were directed to attend
QA orientation classes.
Additionally, specific instruction in procedures,
regulations,
methods, responsibilities,
and personnel interfacing,
as applicable,
was provided to Promatec personnel.
The staff reviewed records to
verify attendance
at this training.
Conversely,
the licensee's
review also determined that Promatec
personnel
were well trained
and knowledgeable.
The staff
established,
from a review of the Promotec procedures,
that
OC hold
points were required to be implemented.
The staff determined that
the licensee verified that
QC hold point inspections
had been
performed
as specified in the seal installation process.
Therefore,
Diablo Canyon
SSER-3
B.3-6
Appendix B
assurance
is provided that previously installed penetration
seals
are satisfactory.
d.
Staff Position
The staff finds that the concerns identified above
have been
responsibly dispositioned
by the licensee.
No further action is required.
No violations or deviations
were identified.
ll.
0 en Item Followu
a.
Vendor Problems Trackin
S stem
(
en Item 84-03-01
Closed)
The licensee
has instituted
a new commitment control module as part
of the plant information management
system that is used to track
vendor problem reports.
Additionally, responsibilities
have been
defined for Westinghouse
Technical Bulletins,
NRC Bulletins and
Notices, Nuclear Operations
Maintenance
Information Service
information, and INFO's Significant Operating Experience
Reports
and
information service.
This item is closed.
No violations or deviations
were identified.
12.
Licensee
Event
Re ort (LER) Follow-u
(Unit 1)
Circumstances
and corrective actions described in the following LERs were
examined.
Review of the LERs, and reporting to NRC within required time
intervals by the licensee,
was verified by the inspectors.
The
inspectors
also ensured
appropriate
corrective actions
were established
and applicable
events
were accurately described.
Accordingly, the
following LERs are considered
closed:
LER 85-04:
Nonfunctional fire barriers
were acceptably
reported
and
addressed
by the licensee.
LER 85-03;
LER 85-06;
LER 85-07;
LER 85-09:
These four LERs were discussed
in Inspection Report Number
50"275/85-01
and were verified to have been acceptably
reported
by the licensee.
LER 85-11:
The manual reactor trip on loss of feedwater is discussed
within this report; it was also acceptably
addressed
and
reported
by the licensee.
No violations or deviations
were identified.
Diablo Canyon
SSER-33
B.3-7
Appendix B