ML16340A682
| ML16340A682 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 10/19/1979 |
| From: | Horn A, Morrill P, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16340A683 | List: |
| References | |
| 50-275-79-21, 50-323-79-11, NUDOCS 7912060104 | |
| Download: ML16340A682 (10) | |
See also: IR 05000275/1979021
Text
50-275/79-21
epor t go
50-323/79-1
1
U ~ S.
NUCLEAR REGULATORX COMMISSION
OFFICE
OF INSPECTION AND ENFORCEMENT
REGION V
Docket
No.
50-275
5 50-323
License
No.
CPPR-'39
5 CPPR-69
/
Licensee:
PaCifiC
GaS
and EleCtriC
COmPany
77 Beale Street
Safeguards
Group
San Francisco,
94106
Faci1ity game:
Diablo Canyon Units
1
5 2
Inspection at:
Diablo Canyon Site,
San Luis Obispo County, California
Inspection
condu
ed:
Inspectors:
Au ust 21-24 and
Se tember 24-26,
1979
/- 7
Approved By:
P. J. le rill, React r Inspector
A. J
orp,
React r Ins ectorn.HJ 8.
Bag
o, Jr.'
ctor Inspector
D.
M. Sternberg,
Chief,
eactor Project Section Pl,
Reactor Operations
and Nuclear Support Branch
ate Signed
o I'I Wc
Date Signed
Date
igned
Date Signed
Summary:
Ins ection
on Au ust 21-24 and
Se tember 24-26,
1979
Re ort Nos. 50-275/79-21
and
50-323/79-11
A~Id:
R d,
dd*p
d
I'p
p'
p<<dg,
evaluation
and verification of test results,
independent
inspection,
IE Circular
follow-up, and
a tour of the facility.
This inspection
involved'120 inspector-
hours onsite
by three
NRC inspectors.
'esults:
No items of honcompliance
or deviations were identified.
g
RV Form 219 (2)
1
DETAILS
1.
Persons
Contacted
1R.
Ramsay,
Plant Superintendent
2
1
2R. Patterson,
Supervisor of Operations
. 1'2J.
Diamonon, guality Control-Supervisor
1'2J. Shiffer, Technical Assistant to Plant Superintendent
'<tl. Norem, Resident
Startup Engineer
1
2D. Rockwell, Resident
Engineer, Electrical
'. Gisclon,
Power Plant Engineer
The inspector
also talked with and interviewed several
other licensee
employees,
including members of the construction,
engineering
and
operations staff and
gA organization personnel.
2Denotes
those attending
the exit interview on August 24, 1979.
1
Denotes
those attending
the exit interview on September
26,
1979.
2.
Prep erational
Test Pro
ram
The inspectors
examined eleven Unit 1 preoperational
test procedure
packages
that have
been turned over from the construction organization to the opera-
ting organization.
The packages
were found to contain the proper
documenta-
tion of test results
review and approval,
and resolution of test deficiencies
and problems which occurred during the testing
phase.
The test results re-
viewed were as follows:
4.3
10. 3.1
10. 3.1
10.3.1
23.10
23.10
23.10
34. 2
35.1
Main Safety Valve Setpoints
RHR System Valve Interlocks
Addendum
No. 1, Verify Separate
Power Source for SIS Valve
Position Indication and Verify Power Interlock Contactors
Addendum No. 2, Retest
Valve Interlocks
Containment
Put ge
(CHP) System
Addendum
No. 1, Air Blow Containment
Purge Lines
Following l<eld Repair
Addendum
No. 2, Check Pressure
Drop Across
CHP Filters
Fuel
Handling Tools and Fixtures
Reactor Protection
Time Response
tleasurement
35.1
35. 2
35.2
35.2
35.3
35. 3
35. 3
Addendum
No. 1,-Retest
Reactor
Protection
Time Response
After System t<odification
Reactor Protection Ope'rational
Check
Addendum
No. 1, Test Safe Failure of Reactor'rotection
System
on Loss of Power to Process
Instrumentation
Addendum
No. 2, Retest
General
Warning Reactor Trip, Trip
Status Lights and
SSPS
Slave Relays
Safeguards
Systems
Operational
Check
Addendum
No. 1, Retest Trip Status Lights P-ll
Nod and
SSPS
Slave
Relays
Addendum
No. 2, Test Containment Vent Isolation from Nevi
Rms.
Inputs
37.6
Pump Vibration Measurement
37. 7
37.7
t1ain Steam Isolation Val ves
Adendum
No. 1, Retest
NSIVs Following tlodification
37.15
Pressurizer
Level Control
37.23
Rod Control
System Functional
Test
(No Rods)
The inspectors
observed that for preoperational
test
35.1
and 37.23, the
calabration of test instrumentation verification was documented
in 1976
several
days to several
months after test completion which was contrary
to
iXemo to Startup
Engineers
834.
Licensee representatives
stated that
current plant procedures
provided for documenting
the verification of
instrument calibration at the time of the test and that additional guid-
ance to clarify the use of the "Instrument Calibration Verified" stamp
would be provided to the startup engineers.
The inspectors verified
that the instruments
used for the subject tests
were in calibration
when
used for tests
35.1
and 37.23
and that current plant procedures
provided
adequate
guidance.
No items of noncompliance
or deviations
were identified.
3. 'E Circular Follow-u
The inspector verified by discussions
with licensee
personnel
and review
of Plant Safety
Review Committee Meeting minutes that the following
circulars were r'eceived
by the licensee,
reviewed for applicability by
appropriate
personnel,
and appropriate
actions
were taken or planned.
Circular 78-19 - Manual Overrides
(Bypass) of Safety System Actuation
Signals:
Licensee
personnel
had determined that this issue
had been
considered
during the design stage of Diablo Canyon.
(Closed)
Circular 79-02
Failure of 120 Volt Vital AC Power Supplies:
Licensee
. personnel
concluded that the Diablo Canyon vital AC power supplies
.
differ in principle of operation
from those described
in the circular.
(Closed)
Circular 79-04 - Loose Locking faut on Limitorque Val've Operators:
The inspector verified the licensee's
personnel
have torqued
and staked
all locking nuts
on Unit
1 limitorque valve operators
and that
a similar
program is underway for Unit 2.
(Closed)
Circular 79-10 - Pipefitting Manufactured
from Unacceptable
Material:
The licensee's
review of receiving documents
from March 1978 through
January
1978 indicated
no defective material
(as described
in the
circular)
had
been received.
(Closed)
Circular 79-11 - Design/Construction
Interface
Problem:
The licensee's
Organization
includes operations,
design/engineering,
and construction/
startup for Diablo Canyon.
Departmental
and interface
procedures
exist
which should preclude the concerns of the circular.
(Closed)
Circular 79-12 - Potential
Diesel
Generator Turbocharger
Problem:
A
review of the Diablo Canyon
GM Diesel Turbocharger
Lube Oil System
showed
'that is is significantly different from the
ALCO turbocharger
system.
(Closed)
Circular 79-13 - Replacement of Diesel
Fire
Pump Starting Contactor's:
No Cunmins
Engines
Company diesel fire pumps are planned or used
by the
licensee at Diablo Canyon.
(Closed)
No items of noncompliance or deviations
were identified.
Plant Tour
The inspectors
toured the facility and
made the following observations:
a
~
b.
Unit
1 systems
and components
were in a layup status consistent with
'heir
construction
and testing status.
Housekeeping
and cleanliness
in Unit
1 appeared
consistent with
construction activities and applicable fire and safety requirements.
No items of noncompliance or deviations
were identified.
Exit Interview
'he
inspector
met with licensee
representatives
(denoted in Paragraph
1)
on August 24, 1979,
and on September
26, 1979.
The scope
and findings
of the inspection
were summarized
by the inspectors.