ML17286B218
| ML17286B218 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/16/1991 |
| From: | Narbut P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17286B217 | List: |
| References | |
| 50-397-91-41, NUDOCS 9112310072 | |
| Download: ML17286B218 (17) | |
See also: IR 05000397/1991041
Text
U. S.
NUCLEAR REGULATORY COMMISSION
REGION
Report
No.
Docket- No.
License
No.
Licensee:
50-397/91-41
'I
50-397
Mashington Public Power Supply System
P.
O.
Box 968
Richland,
MA
99352
Facility Name:
Mashington Nuclear Project
No.
2 (MNP-2)
Inspection at:
MNP-2 Site near
Richland,
Mashington
Inspection
Conducted:
.November
4 - 18,
1991
Inspector:
M. J.
Magner,
Reactor
Inspector
Approved by:
4vvrb~
<z/I~/.r
I
ar u,
c ang
ae,
nganeerang
ec
son
~ae
signed
Summary:
Ins ection Durin
the Period of November
4 - 18
1991
ns
ec )on
e or
Areas Ins ected:
An unannounced
routine inspection
by a regional
based
1nspec or con ucted to evaluate
the adequacy of the licensee's fire
protection/prevention
program.
Results:
General
Conclusions:
The fire protection program appears
to adequately
address
the measures
necessary
for
prevention
and detection of potential plant fires.
Additional management
attention should
be provided to expedite the removal of fire protection
impairments.
r
Si nificant Safet
Matters:
None
Summar
of Violations or Deviations:
None
0 en Items
Summar
No items were opened or closed.
9112310072
911216
ADOCH, 05000377
8
0
fj
h'
DETAILS
1.
Persons
Contacted
- J. Baker-, Plant Manager
- R. Mebring, Plant Technical
Manager
"S. Davison,
equality Assurance
Manager
- H. Fowler, Fire Marshal
~J. Kittler, Principal Fire Protection
Engineer
"D. Graham,
Fire Protection
Engineer
- K. Mise, Plant Support Engineering
Manager
L. Harold, Assistant Plant Manager
G. Brastad,
Consulting Engineer
.
R. Catlow, Fire Protection
Engineer
D.
Ker lee, Principal Quality Assurance
Engineer
J.- Roy, Senior Maintenance
Engineer
The inspector also interviewed other licensee
employees
during the
course of the inspection.
~Denotes
those attending the Exit Meeting on November 8, 1991.
2.
Fire Protection/Prevention
Pro
ram (64704)
a.
Fire Protection
Im lementin
Procedure
Review
The following procedures
were reviewed
and found to be technically
adequate
to implement the Fire Protection
Program:
Plant Procedures
Manual
(PPM) Procedure
No. 1.3. 10, "Fire
Protection program."
This procedure
establishes
programs to
provide the controls to govern the practices
related to fire
protection
system impairments,
use of ignition sources,
combustible material,
and compensatory
measures
taken for
impairments.
PPM 1.3. 19 "Housekeeping.."
This procedure
requires
Department
'anagers
to repor't monthly to the Assistant Plant Manager
regarding
housekeeping
inspection in their respective
areas.
The inspector ver'ified that these responsibilities
were being
accomplished.
Nuclear Operation Standard
No.
NOS-39 "Fire Protection
Program."
This standard identifies the basic fire protection
program requirements
including quality assurance
and individuals
responsible
for implementation of the program.
PPM 1.3.36, "Fire Protection
Program Training."
This procedure
identifies the training requirements
for fire brigade, fire
watch,
and fire fighting.
0
t'I
C.
FT
d~id
T
The licensee's
fire brigade traininq is described
in lesson
plan
80-FPT-0601-LP.
Classroom instruction is 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> in length
and
covers the following topics:
Fire Brigade Makeup/Responsibi
1 ities
Toxic and Corrosive Products of Combustion
Use of Fire Fighting Equipment
Ventilation
Fires in Radiological
Control Areas
Prefire Plans
The inspector
reviewed the annual
physical
examination
records of
all fire brigade personnel
and found them to be current.
The fire
brigade
member physical
examination
includes
a stress test for
determination of fitness for strenuous
physical activity.
The stress
test is not included in the reactor operator
physical
exami.nation,
however the inspector
was able to ascertain that fire brigade
personnel
received the required stress test
and physician
certification.
The following fire fiqhting (pre-plans)
strategies,
which are
included in the'raining program,
were reviewed
by the inspector:
Diesel Generator Building, 1B Day Tank
Room.441'eactor
Building 471'outhwest
Section General
Floor Area
Radwaste 484'able
Spreading
Room
Radwaste
Control Buildin'g 467'emote
Shutdown
Room
The fire fighting strategies
addressed
fire hazards,
extinguishments,
direction of attack (primary and alternate),
potential
hazards
(toxic
radiation), ventilation systems,
and special
operational
instructions.
Fire Protection
ualit
Assurance
The last three year independent quality assurance
audit of the fire
protection program
was conducted
in 1988 and is documented
in Audit
Report
No.88-455.
Emphasis of this audit was
on observation of
in-process
wor k, inspection of fire protection equipment,
and
assessing
performance.
A 24 month audit was conducted
October 15-
November
30,
1990. which also included assistance
from an independent
fire protection engineer;
the biennial audit results
are
documented
in Audit Report
No.90-540.
A triennial fire protection audit is
scheduled
to begin by December
1991.
d.
Plant Tour and Ins ection of Plant Fire Protection
Features
A walkdown inspection of fire protection
systems
and equipment
was
performed
by the inspector in the following areas:
circ-water
pump
house,
back-up fire protection water supply,
B diesel
generator
room, turbine building, reactor building, radwaste building, remote
lJ
l'i
~ 'i
(I
i
shutdown
room,
and the cable spreadinq
room.
Good housekeeping
practices
were observed
in all areas
inspected,
combustible
materials
were properly controlled,
emergency lights'were operable,
and all fire detection
and suppression
systems
were in Service.
A
roving fire watch was questioned
and responded satisfactorily
on
responsibilities
'and actions
taken in event of a fire.
'.
During the plant tour of the circ-water
pump house,
the inspector
noticed packing gland leakage
on the Jockey
Pump.
Although a
Technical
Evaluation
Request
was written in October
1990 to address
the problem,
no repair work had been
done
as of this inspection.
Also,
a number of fire protection
impairments
have
been in place since
May 1989 involving cable separation
issues for which compensatory
actions
were taken.
The inspector's
review of Plant Event Reports
associated
with these
impairments did not identify any impaired
safety significant circuits.
During the exit meeting,
the inspector
suggested
management
re-evaluate
existing impairments for possibly
placing
a higher priority on fixing the problem.
Subsequent
to the
exit meeting,
the inspector
learned that as
a result of management
involvement, the
number of fire protection
impairments
were reduced
by 50 percent.
No violations or deviations
were identified.
3.
~tit II tt
The inspector
met with licensee
management
representatives
denoted in
paragraph
1 on November 8, 1991.
The scope of the inspection
and
findings as described
in this report were discussed.
Documents
addressing
the fire brigade
lesson
plans
were reviewed in the regional
office on November 18,
1991 and documented
in Section 2.b of this report.
~p,g RE+(~
I4r
00
IIh
ji
p
l
)0p**4
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION V
1450 MARIALANE, SUITE 210
WALNUTCREEK. CALIFORNIAS4596 5368
0'"", i
'" )any
Docket'o.:
50-397
Washington Public
Power
Supply System
P.O.
Box 968
3000 George
May
Richland, Mashington
99352
Attention:.
Hr.
G.
C. Sorensen,
Hanager
Regulatory
Programs
Subject:
Gentl emen:
NRC INSPECTION
OF WNP-2
This refers to the inspection
conducted
by Hr.
M. J.
Magner of this office,
on
site
November
4 - 8, 1991,
and in-office on November 18, 1991, of
activities authorized
by
NRC license
No.
and to'he findings discussed
with Hr. J.
Baker,
and. other members of the supply system identified in the
enclosed
inspection report.
Areas
examined during this inspection are described
in the enclosed
inspection
report.
Mithin these
areas,
the inspection consisted
of selective
examinations
of procedures
and representative
records,
interviews with
personnel
and observations
by the inspector.
In accordance
with 10
CFR 2.790 of the
NRC's "Rules of Practice,"
a copy of
this letter and its enclosures will be placed in the
NRC Public Document
Room.
Should you have
any questions
concerning this inspection,
we will be pleased
to discuss
them with you:
Sincere
Enclosure:
Inspection
Report
No. 50-397/91-41
D .
F. Kirsch, Chief
Reactor Safety Branch
cc w/enclosures
Hr. J.
W. Baker,
WNP-2 Plant Manager
Hr.
A.
G. Hosier,
MNP-2 Licensing Hanager
Dr.
G.
D. Bouchey, Director, Licensing
8 Assurance
Hr.
G.
E.
Doupe,
Esq.,
WPPSS-
Hr.
A.
Lee Oxsen,
Deputy'anaging
Director
State of Washington
Hr.
H.
H. Philips,
Esq.
(Winston
8 Strawn)
t
t
L
I
I
~
',
tl
t
I
't
d
U. S
~
NUCLEAR REGULATORY COMMISSION
REGION
N
Report
No.
Docket No.
License
No.
Licensee:
Facility Name:
Inspection at:
50-397/91-41
50-397
Mashington Public
Power
Supply System
P.
0.
Box 968
Richland,
WA
99352
-Washington Nuclear Project
No.
2 (WNP-2)
WNP-2 Site near
Richland,
Mashington
Inspection
Conducted:
November
4 - 18,
1991
Inspector:
Approved by:
Summary:
M. J.
Wagner,
Reactor Inspector
4~.I,
iL/I~/r
I
ar u,
c ang
ae,
nganeenng
ec
son
~ae
agned
Ins ection Durin
the Period of November
4 - 18
1991
ns
ec
son
e or
Areas
Ins ected:
An unannounced
routine inspection
by a regional
based
snspec
or con ucted to evaluate
the adequacy of the licensee's fire
protection/prevention
program.
Results:
General
Conclusions:
The fire protection program appears
to adequately
address
the measures
necessary
for
prevention
and detection of potential plant fires.
Additional management
attention should
be provided to expedite the removal of fire protection
impairments
~
Si nificant Safet
Matters:
None
Summar
of Violations or Deviations:
None
~ddt
t %
N tt
d
d
1
d.
0
i
l
II
'
'
1.
Persons
Contacted
DETAILS
"J. Baker, Plant Manager
"R. Webri ng, Plant Technical
Manager
- S. Davison,
equality Assurance
Manager
"H. Fowler,-Fire Marshal
"J. Kittler, Principal Fire Protection
Engineer
- D. Graham,
Fire Protection
Engineer
- K. Mise, Plant Support Engineering
Manager
L. Harold, Assistant Plant Manager
G. Brastad,
Consulting Engineer
R. Catlow, Fire Protection
Engineer
D. Kerlee, Principal equality Assurance
Engineer
J.
Roy, Senior
Maintenance
Engineer
The inspector also interviewed other licensee
employees
during the
course of the inspection.
- Denotes those attending the Exit Meeting
on November 8, 1991.
2.
Fire Protection/Prevention
Pro
ram (64704)
Fire Protection
Im lementin
Procedure
Review
The following procedures
were reviewed
and found to be technically
adequate
to implement the Fire Protection
Program:
Plant Procedures
Manual
(PPM) Procedure
No. 1.3. 10, "Fire
Protection program."
This procedure
establishes
programs to
provide the controls to govern the practices
related to fire
protection
system
impairments,
use of ignition sources,
combustible material,
and compensatory
measures
taken for
impairments.
PPM 1.3. 19 "Housekeeping."
This procedure
requires
Department
Managers to report monthly to the Assistant Plant Manager
regarding
housekeeping
inspection in their respective
areas.
The inspector verified that these responsibilities
were being
accomplished.
Nuclear Operation Standard
No.
NOS-39 "Fire Protection
Program."
This standard identifies the basic fire protettion
program requirements
including quality assurance
and individuals
responsible for implementation of the program.
PPM 1.3.36, "Fire Protection
Program Training."
This procedure
identifies the training requirements
for fire brigade, fire
watch,
and fire fighting.
I
il',
'
b.
Fire
Br i ade Trainin
The licensee's fire brigade traininq is described
in lesson
plan
80-FPT-0601-LP.
Classroom instruction is 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> in length and
covers the following topics:
Fire Brigade Hakeup/Responsibilities
Toxic and Corrosive Products of Combustion
Use of Fire Fighting Equipment
Ventilation
Fires in Radiological
Control Areas
Prefire Plans
The* inspector
reviewed the a'nnual
physical
examination records of
all fire brigade personnel
and found them to be current.
The fire
brigade
member
phys.ical examination
includes
a stress test for
determination of fitness for strenuous
physical activity.
The stress
test is not included in the reactor operator physical
examination,
however the inspector
was able to ascertain that fire brigade
personnel
received the required stress test
and physician
certification.
The following fire fighting (pre-plans) strategies,
which are
included in the training program,
were reviewed
by the inspector:
Diesel Generator Building,
1B Day Tank
Room
441'eactoi
Building 471'outhwest
Section General 'Floor Area
Radwaste 484'able
Spreading
Room
Radwaste
Control Building 467'emote
Shutdown
Room
The fire fighting strategies
addressed fire hazards,
extinguishments,
direction of attack (primary and alternate),
potential
hazards
(toxic
radiation), ventilation systems,
and special
operational
instructions.
C.
Fire Protection
ualit
Assurance
The last three year independent quality assurance
audit of the fire
protection program
was. conducted
in 1988 and is documented
in Audit
Report
No.88-455.
Emphasis of this audit was
on observation of
in-process
work, inspection of fire protection equipment,
and
assessing
performance.
A 24 month audit was conducted
October 15-
November 30,
1990 which also included assistance
from an independent
fire protection engineer;
the biennial audit results
are
documented
in Audit Report
No.90-540.
A triennial fire protection audit is
scheduled
to begin by December
1991.
d.
Plant Tour and Ins ection of Plant Fire Protection
Features
A walkdown inspection of fire protection
systems
and equipment
was
performed
by the inspector in the following areas:
circ-water
pump
house,
back-up fire protection water supply,
B diesel
generator
room, turbine building, reactor building, radwaste building, remote
i
I
I
li
'hutdown
room, and'he
cable spreadinq
room.
Good housekeeping
practices
were observed
in all areas
inspected,
combustible
materials
were properly controlled,
emergency lights were operable,
and all fire detection
and suppression
systems
were in service.
A
roving fire watch was questioned
and responded satisfactorily
on
responsibilities
and actions
taken in event of a fire.
~
During the plant tour of the circ-water
pump house,
the inspector
noticed packing gland leakage
on the Jockey
Pump.
Although a
,Technical
Evaluation
Request
was written in October
1990 to address
the problem,
no repair
work had been
done
as of this inspection.
Also,
a number of fire protection impairments
have
been in place since
May 1989 involving cable separation 'issues
for which compensatory
actions
were taken.
The inspector's
review of Plant Event Reports
associated
with these
impairments did not identify any impaired
safety significant circuits.
During the exit meeting,
the inspector
suggested
management
re-evaluate
ex>sting impairments for possibly
placing
a higher priority on fixing the problem.
Subsequent
to the
exit meeting,
the inspector
learned that as
a result of management
involvement, the
number of fire protection impairments
were reduced
by 50 percent.
No violations or deviations
were identified.
Exit Meetin
The inspector
met with licensee
management
representatives
denoted in
paragraph
1 on November
8,
1991.
The scope of the inspection
and
findings as described
in this report were discussed.
.Documents
addressing
the fire brigade
lesson
plans
were reviewed in the regional
office on November 18,
1991 and documented
in Section 2.b of this report.
0
II
t