ML16341E465
| ML16341E465 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 12/02/1987 |
| From: | Hooker C, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16341E466 | List: |
| References | |
| 50-275-87-39, 50-323-87-40, NUDOCS 8712210270 | |
| Download: ML16341E465 (16) | |
See also: IR 05000275/1987039
Text
'
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report
Nos.
50-275/87-39
and 50-323/87-40
Docket Nos.
50-275 and 50-323
License
Nos.
and
Licensee:
Pacific Gas
and Electric Company
77 Beale Street
Room 1451
San Francisco,
94106
Facility Name:
Diablo Canyon Units
1 and
2
Inspection at:
San Luis Obispo County, California
Inspection
Conducted:
November 9-13,
1987
Inspector:
C.
A.
oo er,
Radia ion Specialist
Da
e Signed
~Summar:
~
P.
uh
Facili ie
s, Chief
Radiological Protection Section
Da
e Signed
Ins ection
on November 9-13
1987
Re ort Nos.
50-275/87-39
and 50-323/87-40
findings, external
and internal
exposure control;
ALARA; review of licensee
audits
and reports;
and facility tours.
Inspection
procedures
addressed
included 30703,
83724,
83725,
83728,
92701,
92702,
92700
and 90713.
Results:
Of the areas
inspected,
no violations or deviations
were identified.
87>~>i 0270 871203
ADOCK 05000275
8
DETAILS
1.
Persons
Contacted
a.
Pacific Gas
and Electric
Com an
PG8E
Personnel
"J.
D. Townsend,
Acting Plant Manager
- W. B.
McLane, Acting Assistant Plant Manager,
Technical
Support
"J.
V. Boots,
Manager,
Chemistry
and Radiation Protection
(CHIRP)
"R.
P.
Powers,
Senior
CHIRP Engineer,
Supervisor,
Radiation Protection
(RP)
"T.
L. Grebel, Supervisor,
Regulatory Compliance
- J. A. Hays,
General
Foreman,
"S.
Fahey-Benson,
Nuclear Generation
Engineer
L. T. Moretti, Foreman,
R. J. Harris, Supervisor, guality Assurance
(gA), On-Site Auditing
Group
R.
M. McVicker, Lead Specialist, guality Control
(gC)
T.
L. Irving,
CBRP Engineer
D.
E. Jones,
Senior Health Physicist,
Department of Engineering
Research
(DER)
D. Bell, gC Supervisor,
Nuclear Engineering
and Construction
Services/General
Construction
b.
NRC Contacts
"P.
P. Narbut, Senior Resident
Inspector
M.
L. Padovan,
Resident
Inspector
K.
E. Johnston,
Resident
Inspector
Denotes
those present at the exit interview on November 13,
1987.
In addition to the individuals identified above,
the inspector met and
held discussions
with.other members of the licensee's
and contractor's
staffs.
2.
Licensee Action on Previous
Ins ection Findin
s
Closed
Violation
50-275/87-30-01
and 50-323/87-30-01:
This violation
involved the
RP Department's
failure to follow procedures
on the use of
Temporary Instructions (TIs).
Based
on review of the
RP Departments
TI
binder and revised procedure
RCP D-600,
Personnel
Decontamination
and
Evaluation,
and discussions
with cogniiant licensee
representatives,
the
inspector
determined that effective corrective actions
had been
implemented to prevent recurrence
as stated in PG8E's timely letter dated
September
28,
1987.
The inspector
had
no further questions
regarding
this matter.
Closed
Followu
50-275/87-30-02
and 50-323/87-30-02
This item
related to the review of the resolution
between
gC and
RP on the
requirements
for issuance
of Action Requests
(ARs) and Nonconformance
Reports
(NCRs) for licensee identified problems.
Based
on the review of
'
revised procedure
RCP D-250,
Re ortin
of Radiolo ical Occurrences,
and
a
letter,
dated
September
16,
1987,
from C.
L. Eldridge to J.
V. Boots, the
inspector
determined that the licensee
had effectively resolved this
matter.
'I
Closed)
Followu
(50-275/87-30-03
and 50-323/87-30-03):
This item
involved the
C&RP Department's
use
and control of their Required
Reading
Book regarding
acknowledgements
by personnel
who had read specific
administrative
and
RP procedures.
During this inspection the inspector
observed that the
C&RP department
had effectively implemented
new
administrative controls to ensure that acknowledgements
were
appropriately
documented for procedures
read
by C&RP personnel.
The
inspector
had
no further questions
regarding this matter.
Closed
Followu
(50-275/87-30-05
This item involved the licensee's
clarification of requirements
for determination of the
need for a
Notification of Unusual
Event
(NUE) based
on process
monitor alarms.
Based
on review of revised procedure
EPG-l,
Accident Classification
and
Emer enc
Classification,
the inspector
determined that the licensee
had adequately clarified the classification
of NUEs based
on process
monitor alarms.
The inspector
had
no further
questions
regarding this matter.
0 en) Followu
(50-323/87-21-04
Inspection
Report Nos.
50-323/87-21
and 50-323/87-30
documented
previous inspection efforts regarding the
licensee's
Quality Hotline (QH) investigation,
No.
QCSR-87-005,
involving
radiation protection concerns of an individual working in the
radiological controlled area
(RCA) of Unit 2 during the refueling outage.
Based
on discussions
with cognizant licensee
representatives
and review
of the
C&RP Department's
response,
dated October 26, 1987, to
QCSR
87-005, it appeared
that the licensee
had adequately
addressed
the
individual's radiation protection concerns.
The
C&RP Department
calculated that the individual could have received
an additional 4.9 mrem
to the head that would not have
been indicated
by the monitoring devices
that were worn on the chest.
This item will*remain open until the
licensee's
QH has closed the matter.
Closed
Followu
50-323/87-21-02
The inspector
observed air flowing
from the licensee's
radioactive
laundry cleaning facility to the outside
yard area.
During this inspection,
the inspector
observed that
administrative controls
had been
implemented to keep specific doors
closed to ensure that the laundry facility would be maintained at a
negative pressure relative to the outside environment.
The licensee
was
also in the process
of evaluating
changes
in the ventilation system to
improve system performance.
The inspector
had
no further questions
regarding this matter.
Radiolo ical Controls
This part of the inspection
covered the areas
of:
external
exposure
control; internal
exposure control;
and
The inspector
reviewed
audits
and
QC surveillance reports,
procedures,
records of radiation
and
contamination
surveys,
select Special
Work Permits
(SWPs)
and associated
surveys,
personnel
exposure files, and
a post Unit-2 refueling outage
ALARA report.
The inspector also observed
workers in the
RCAs, held
discussions
with licensee
representatives,
and conducted facility tours
to determine
the licensee's
compliance with 10 CFR Part 20, Technical
Specifications
(TSs),
licensee
procedures
and recommendations
as outlined
in various industry standards.
Inspection
Report
Nos.
50-275/87-21
and 50-323/87-21 also
documented
previous inspection efforts in these
areas.
a.
Audits and
Sur vei llances
QA Audit Report
No.
87161T was reviewed.
The audit was conducted
June 15-July -ll, 1987, to verify that Diablo Canyon
Power Plant
(DCPP), Nuclear Operations
Support
(NOS),
and Department of
Engineering
Research
(DER) had effectively implemented
the
requirements
of the
Code of Federal
Regulations,
DCPP TSs,
Policy,
and departmental
procedures
established
for radiation
protection personnel
monitoring and dosimetry processing
programs.
The audit report documented
an extensive list of records
reviewed
and the
number of samples
examined.
The inspector
determined that
the auditors
were appropriately qualified for the audit.
No
deficiencies
were identified that resulted in Audit Finding Reports
(AFRs) being issued to
DCPP or NOS; however, four AFRs were issued
to
DER documenting minor program deviations.
The inspector
noted
that the identified deviations
were administrative in nature
and did
not represent
a significant safety problem.
Based
on an interview
with the on-site
DER representatives,
the inspector
confirmed that
corrective actions
appeared
to be appropriate.
The following QC Surveillance
Reports
were reviewed:
QCS
87-0270,
Termination of Com leted
SMP Packa
es,
performed
June 4,
1987.
QCS 87-0234,
Personnel
Airborne Ex osure Trackin
, performed
June 6-11,
1987.
QCS 87-0335,
Radiolo ical Controls for Entr
Into Areas
Havin
a Hi
h Potential for Radiation
QCS 87-0366,
Radiolo ical Controls for Unit 2 Turbine
Buildin
Buttress,
performed August 28,
1987.
QCS 87-0385,
Radiolo ical Controls Associated with Leak
Re airs of RCS-l-PCV-455B, performed
September
29,
1987.
Based
on review of the above
QC Surveillance
Reports,
the inspector
noted that
no deficiencies
were identified in report nos.
QCS
87-0270,
QCS 87-0335,
QCS 87-0366,
and
QCS 87-0385.
Report
No.
QCS
87-0234 identified deficiencies
in administrative controls that
resulted in the issuance
of four ARs that required corrective
action.
The inspector 'verified that corrective actions
appeared
to
be appropriate.
No violations or deviations
were identified.
b.
External
Ex osure Control
The inspector
reviewed the licensee's
current quarter to date
radiation exposure
reports
and selected
personnel
exposure files of
workers involved with the Unit 2 refueling outage.
The inspector
noted that
Form NRC-4s,
NRC-5s
and termination letters
were
completed
and retained
as appropriate.
Updated
Form NRC-4s were
researched
prior to'xceeding
the 10'CFR 20. 101(a) limits and
no one
had exceeded
10 CFR 20.101(b) limits.
The inspector
reviewed the tollowing procedures,
documents
and
records:
Procedures
NPAP C-200
General
Re uirements for Radiation Protection
~Pro
rama
RCS-1
RCP G-100
RCP D-220
External
Ex osure Control
Radiation
Work Permits
Entr
Into Plant Areas Which Have
a Hi h
Potential for Radiation Overex osure
RCP D-600
Personnel
Decontamination
Evaluation
Documents
Records
and
Re orts
Letter from R.
P.
Powers to J
~
V. Boots
and J.
A. Sexton,
Control of 'Hot Particles't
Interim Re ort, dated
October 26,
1987.
Radiological
Occurance
Reports
(RORs) from June
2 through
November 10,
1987
'ersonnel
Contmaination
Reports
from July 2, 1987, through
November 10,
1987.
SWP 87-00677,
Re air Crack Below Valve CVCS-1-8495,
dated
November
10,
1987.
SWP 87-00675,
Char in
Pum
2-1
Mechanical
Seal
Re lacement
and
November 9, 1987.
Maintenance
Includin
All Su
ort Work, dated
Licensee
Event Report
(LER) No. 1-87-015-00,
Failure to Meet
the
Re uirements of Technical
S ecification 6. 12
Hi h Radiation
Area
When an Area Was Left Unlocked,
dated October 26, 1987,
discussed
in paragraph
4.b. of this report.
. Based
on the reviews,
observations
and interviews with workers in
the
RCAs, the inspector
determined that the licensee
was effectively
implementing their external
exposure control program.
During the inspection,
on November ll, 1987, at about 3:45 p.m.,
a
C&RP Technician, while surveying contaminated
personal
clothing that
had been
saved for decontamination
and/or disposal,
identified a
radioactiv'e particle
on the toe portion of a sock that indicated
a
count rate of 37,000
cpm with a hand held frisker.
The initial
survey of the sock
on October 30,
1987, identified only a 150
cpm
hot spot with a hand-held frisker.
The sock
had been worn by a
C&RP
technician working in the licensee's
waste sorting enclosure.
Since
the 37,000
cpm particle
had not been observed
during the initial
survey,
the licensee
immediately initiated an investigation to
identify the isotopic mixture of particle, evaluate
the potential
dose to the
C&RP Technician,
and determine
why the higher reading
had not been identified on October 30,
1987.
The licensee
informed
the inspector. of this incident on November 12,
1987, at about 9:00
a.m.
The licensee identified the particle
as being
an irradiated
fuel fragment of about 0.079 pCi.
The licensee's
draft exposure
evaluation estimated
an extremity dose of about 1.6
rem based
on
their initial investigative data.
The licensee's
final
investigation report of this matter will be examined during
a
subsequent
inspection
(50-323/87-40-01,
Open).
No violations or deviations
were identified.
Internal
Ex osure Control
The inspector
reviewed the licensee's
current exposure
report that
provided seven
day and quarter
to date
MPC-hours for radiation
workers,
selected
whole body counting records,
and
MPC work and log
sheets
from selected
SWP packages.
Based
on these
reviews
and
discussions
with licensee
representatives,
there
was
no indication
that any individual exceeded
the 40-hour control measure
requiring
an evaluation pursuant to 10 CFR 20. 103(b)(2).
During the review of air sample results
and
MPC work sheets
from
select
SWP Packages,
the inspector
noted that there were several
instances
where errors were
made when the licensee
performed
hand
calculations to determine air sample results
and
MPC fractions.
The
errors did not represent
a significant safety problem due to the low
concentrations
involved; however,
they did indicate
a lack of
attention to detail.
The inspector discussed
this matter with the
C&RP management staff who acknowledged
the inspectors
observations.
During facility tours the inspector
observed respiratory
equipment
being properly used, air sampling being performed
as required
and
areas
posted pursuant to 10 CFR 20.203(d)(2).
No violations or deviations
were identified.
'
'
d.
The inspector
reviewed the licensee's
Unit 2 first refueling outage
ALARA report.
This 22 page report was very detailed
and compared
the difference in the person-rem
accumulated,
with supporting data
for each major refueling outage activity of Unit 1 and Unit 2.
The
report also discussed
the benefits of reactor coolant system forced
oxygenation.
The report outlined problems encountered,
lessons
learned,
and reasons
that exposures
were reduced or additional
exposure
incurred.
The report
summary
showed
a comparison of
exposures
of various Unit 2 outage activities with national
outage
exposures
for the major repetitive high dose jobs at Pressurized
Water Reactors.
The licensee
determined that Unit 2 exposures
were
only about
43X of the national
average.
The licensee
had not confirmed their ALARA goals for 1988;
however,
a tentative
goal of 620 person-rem
was being considered.
In 1988
the licensee will experience
a refueling outage for Unit 1 and Unit
2, completion of .the Unit 1 spent fuel pool rerack operation,
commencing
about
November 16, 1987,
and the complete
spent fuel pool
rerack operation for Unit 2.
The licensee's
ALARA goal
achievements
were discussed
in Report Nos.
50-275/87-21
and 50-323/87-21.
No violations or devi ati ons were identi fied.
4.
Licensee
Re orts
Semiannual
Radioactive
Release
Re ort
The licensee's
Semiannual
Radioactive
Release
Report for the period
of January
1, 1987,
through June
30, 1987,
was reviewed in-office.
This timely report was issued
as required
and
TS 6.9. 1.6,
and included
a summary of the quantities of radioactive
liquid and gaseous
effluents
and solid waste released
as outlined in
The report also included the off-site
dose
due to releases
of radioactive liquids and gaseous
effluents.
Administrative procedure
changes
to the Process
Control
Program,
Environmental Monitoring Procedure
(A-7), and the Offsite Dose
Calculation Procedure
(CAP A-8) were also discussed
in the report.
No errors or anomalies
were identified (50-275/87-SA-02
and
50-323/87-SA-02,
closed).
b.
LER
LER 87-015-00,
Failure to Meet the
Re uirements of Technical
S ecification 6. 12
Hi
h Radiation Area
When an Area was Left
Unlocked was reviewed in-office and on-site during the inspection.
The inspector verified that the reporting requirements
were met,
causes
were identified, corrective actions
appeared
appropriate
and
had been
implemented to prevent recurrence.
The inspector also
determined that no individual had received
any additional or unsual
radiation exposure.
Based
on the guidance provided in 10 CFR 2,
Appendix C, Part V.A., a Notice of Violation will not be issued.
The inspector
had
no further questions
concerning this matter.
c.
NCR No.
DC1-87-TC-N114 was reviewed during the on-site inspection.,
This
NCR involved an unplanned,
monitored release
of gaseous
radwaste
from Gas
Decay Tank No. 1-3 on October
22,
1987.
The
licensee
determined that the cause of the release
was
due to a
valving misalignment following minor maintenance
on the Boric Acid
Evaporator.
The licensee
determined that
a total of 0.715 curie of
gaseous activity was released
via the plant vent.
The release
was
not significant and'epresented
about
0. 104K of the
TS release
rate
limit.
Based
on review of the licensee's
evaluation
and discussion
with cognizant plant staff, the inspector
had
no further questions
regarding radiologi.cal
concerns.
The inspector toured various
areas
of the auxiliary and fuel handling
buildings of Unit 1 and Unit 2, the waste storage building and the
laundry facility.
The inspector
made independent
measurements
using
an
NRC RO-2 portable ion chamber,
S/N 2691,
due for calibration
on January
8, 1988.
In addition to the observations
discussed
in other sections
of this
report, the inspector
observed that all radiation areas
and high
radiation areas
were posted
as required
and access
controls were consistent with TS 6. l2 requirements
and licensee
procedures.
No violations or deviations
were identified.
6.
Exit Interview
The inspector
met with the licensee
representatives
(denoted
in paragraph
1) at the conclusion of the inspection
on November 13,
1987.
The scope
and findings of the inspection
were summarized.
The inspector
informed the licensee
representatives
that
no apparent
violations or deviations
were identified.