ML20217D538
| ML20217D538 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/20/1998 |
| From: | Hannon J NRC (Affiliation Not Assigned) |
| To: | Mcgaha J ENTERGY OPERATIONS, INC. |
| Shared Package | |
| ML20217D540 | List: |
| References | |
| 50-458-97-201, NUDOCS 9803300057 | |
| Download: ML20217D538 (6) | |
See also: IR 05000458/1997201
Text
.
y
$A%t
1
UNITED STATES
.
p
g
j
NUCLEAR REGULATORY COMMISSION
2
WASHINGTON, D.C. 20555-0001
,o
March 20, 1998
Mr. John R McGaha, Jr.
'
Vice President - Operations
Entergy Operations, Inc.
River Bend Station
P.O. Box 220
St. Francisville, LA 70775
SUBJECT: FIRE PROTECTION FUNCTIONAL INSPECTION OF RIVER BEND STATION
(NRC INSPECTION REPORT NO. 50-458/97-201)
Dear Mr. McGaha:
From June 16,1997, through June 20,1997, and June 30,1997, through July 3,1997, the staff
of the U.S. Nuclear Regulatory Commission (NRC), Office of Nuclear Reactor Regulation
(NRR) with technical inspection support from Brookhaven National Laboratories (BNL), and
NRC Regions ll and IV, performed a pilot fire protection functional inspection at the River Bend
Station (RBS). The purpose of this inspection was to evaluate the adequacy of the RBS fire
protection program and its ability to prevent fires from starting; the ability to detect, control,
suppress, and extinguish fires quickly; and the capabilities of the plant to achieve and maintain
post-fire safe-shutdown conditions using systems and components that have been protected to
remain free of fire damage. In addition, this inspection evaluated the fire protection program's
adherence to the design and licensing bases as established by the Operating License NPF-47,
Condition 2.C.10; NRC safety evaluation reports; the RBS Updated Safety Analysis Report; and
the RBS fire hazards and safe-shutdown analyses. Within the areas inspected, the team's
activities consisted of selected examinations of procedures and records, interviews with plant
operations and engineering support personnel, examinations of plant equipment and structures,
and observation of simulated responses to fire events. The enclosed report presents the
detailed scope and results of this inspection.
In a letter dated July 29,1997, the NRC requested additional information to support its review of
issues found during the fire protection functionalinspection. During a meeting of
'
August 19,1997, representatives of Entergy Operations incorporated (EOI), the licensee for
RBS, met with the NRC to discuss their responses to the request for additional information
(RAl). During this meeting, the NRC staff informed the licensee that its responses did not fully
resolve the inspection issues and requested that it provide a written response to the RAI of
July 29,1997. The licensee informed the staff that it would submit its written response to the
RAI after it receives the FPFI report. The staff informed the licensee that this was acceptable.
By letter dated May 19,1997, EOl documented its corporate position conceming the design and
licensing basis of EOl plants, specifically, its compliance with Appendix R to 10 CFR Part 50
and its relationship to information Notice 92-18, " Potential For Loss of Remote Shutdown
Capability During a Control Room Fire," and multiple spurious operations. As it applies to RBS,
the inspection team reviewed the corporate positions and identified concems related to the
1
number of circuit failures that needed to be considered when identifying those associated
M\\
circuits that needed to be protected in accordance with Section Ill.G.2, of Appendix R to
\\
.
go\\
9803300057'9'dO32
i
i
ADOCK 05000458
..
. . .
.
.
.
.
.
.
.
.
.
_ _ _ _ _ _ _ _ _ _ _ _ - _
_
__
.
Mr. John R. McG h , Jr.
2
,
10 CFR Part 50, cnd tha number of firs-induced circuit failurcs (e.g., spurious equipm:nt
,
actuations) that can occur per fire event. This letter and the enclosed NRC inspection report
serve as the staff's response to the EOl letter of May 19,1997, for RBS.
From the FPFI, the inspection team determined that the operational aspects (e.g., fire
prevention program administrative controls) were satisfactory and appropriately implemented.
However, the team identified program weaknesses associated with the design of certain plant
fire protection features, fire brigade effectiveness, and certain aspects of the engineering
analyses used to demonstrate that post-fire safe-shutdown conditions can be achieved and
maintained. Specifically, the team had concerns with the design of certain fire suppression and
detection systems and their lack of con!wmance with industry fire protection standards; lack of
adequate technical basis supporting the fire resistive rating for certain fire barriers and passive
fire resistive devices; manual fire fighting equipment and extinguishing agent limitations; fire
brigade performance; fire protection related operability assessments and the implementation of
appropriate compensatory measures for conditions affecting the operability of post-fire safe-
shutdown capability; and the evaluation criteria and analysis methodology for circuits of
equipment whose spurious actuation could adversely affect post-fire safe-shutdown capability.
As with all NRC inspections, we expect that you will evaluate the applicability of the results and
specific findings of this inspection to other systems, components and programs throughout the
plant. We understand that the EOl response to the RAI of July 29,1997, will be combined with
your response to the enclosed inspection report. You are requested to respond to the
inspection report findings and the RAI within 60 days from receipt of this letter. In your
J
response to the inspection findings, you should document any specific actions you have taken
in response to the inspection. After reviewing your response to the inspection findings and the
RAl, the NRC will determine whether further NRC enforcement action is necessary to ensure
!
compliance with NRC regulatory requirements.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the
NRC public document room. Any Enforcement action resulting from this inspection will be
handled by NRC Region IV and addressed by separate correspondence. Should you have any
questions concerning this inspection, please contact the project manager, David L. Wigginton,
at (301) 415-1301, or the inspection team leader, Patrick M. Madden, at (301) 415-2854.
Sincerely,
i
ORIGINAL SIGNED BY:
John N. Hannon, Director
Project Directorate IV-1
Division of Reactor Projects ill & IV
Office of Nuclear Reactor Regulation
Docket No.: 50-458
License No.: NPF-47
Enclosure: NRC Inspection Report 50-458/97-201
cc w/ encl.: standard River Bend service list
SEE DISTRIBUTION LIST ON NEXT PAGE
DOCUMENT NAME: A:\\TRANS.LTR
- SEE PREVIOUS CONCURRENCE
- SPLB:DSSA
- SPLB:DSSA
- SPLB:DSSA
- DSSA:NRR PD:NRR
PMadden
KSWest
LBMarsh
GMHolahan JNHannon
03/06/98
03/06/98
03/06/98
03/20/98
03p98
OFFICIAL RECORD COPY
j
,
Mr. John R. McGaha, Jr.
2
,
,
'
Fro ths FPFI, tha inspection ts:m d t:rmin:d that ths operational aspects (e.g., fire
preve. tion program administrative controls) were satisfactory and appropiiately implemen
Howev r, the team identified program weaknesses associated with the de sign of certai
lant
fire prot tion features, fire brigade effectiveness, and certain aspects of the enginee g
analyses sed to demonstrate that post-fire safe-shutdown conditions can be achi ed and
maintaine
Specifically, the team had concerns with the design of certain fire s pression and
detection sy ems and their lack of conformance with industry fire protection s ndards; lack of
adequate tec ical basis supporting the fire resistive rating for certain fire b riers and passive
fire resistive de 'ces; manual fire fighting equipment and extinguishing ag it limitations; fire
brigade performa ce; fire protection related operability assessments a
the implementation of
appropriate com
satory measures for conditions affecting the oper ility of post-fire safe-
shutdown capability, nd the evaluation criteria and analysis metho ology for circuits of
equipment whose sp ious actuation could adversely affect post- re safe-shutdown capability.
As with all NRC inspecti
s, we expect that you will evaluat
e applicability of the results and
specific findings of this ins ction to other systems, comp ents and programs throughout the
plant. We understand that e EOI response to the RAI
July 29,1997, will be combined with
your response to the enclose inspection report. You re requested to respond to the
inspection report findings and e RAI within 60 day rom receipt of this letter. In your
response to the inspection findi
s, you should do ment any specific actions you have taken
in response to the inspection. Aft reviewing y r response to the inspection findings and the
RAI, the NRC will determine wheth further N C enforcement action is necessary to ensure
compliance with NRC regulatory req ~ emen
In accordance with 10 CFR 2.790(a), a c y of this letter and the enclosure will be placed in the
NRC public document room. Any Enfor
ent action resulting from this inspection will be
handled by NRC Region IV and addr sed b separate correspondence. Should you have any
questions concerning this inspectio , please c tact the project manager, David L. Wigginton,
,
I
at (301) 415-1301, or the inspecti
team leade , Patrick M. Madden, at (301) 415-2854.
Sincere
John N. Han
n, Director
Project Director e IV-1
Division of React Projects ill & IV
Office of Nuclear R ctor Regulation
Docket No.: 50-4
License No.: N
-47
Enclosure: N C Inspection Report 50-458/97-201
cc w/ encl.:
andard River Bend service list
SEE DIS
IBUTION LIST ON NEXT PAGE
'
1
DOCU ENT NAME: A:\\TRANS.LTR
N c/ '[
- SEE PREVIOUS CONCURRENCE
f
'
.,
I
- SPLB:DSSA
'SPLB:DSSA
SPLB:DS
DSSA:MRR
PD:NRR
PMadden
KSWest
LBMarsh
GMHolahan JNHannon
03/06/98
03/06/98
03/0/98
03/,/98
03/gQ98
'
OFFICIAL RECORD COPY
I
Mr. John R. McGrha, Jr.
2
-
.
(
'
From thu FPFI, the inspection team determined that the operational aspects (e.g., fire prevention
program administrative controls) were satisfactory and appropriately implemented. However, the
team identified program weaknesses associated with the design of certain plant fire protection
features, fire brigade effectiveness, and certain aspects of the engineering analyses used to
demonstrate' at post-fire safe-shutdown conditions can be achieved and maintained.
j/
Specifically, th eam had concems with the design of certain fire suppression and detecti
systems and thei ack of conformance with industry fire protection standards; lack of ad uate
technical basis sup orting the fire resistive rating for certain fire barriers and passive
resistive
devices; manual fire ~ hting equipment and extinguishing agent limitations; fire bri
performance; fire prote ion related operability assessments and the implementat;t-fire safe-
dn of
i
appropriate compensato measures for conditions affecting the operability of p
shutdown capability; and t
evaluation criteria and analysis methodology for arcuits of
equipment whose spurious a uation could adversely affect post fire safe-s tdown capability.
As with all NRC inspections, we
pect that you will evaluate the appli
ility of the results and
specific findings of this inspection
other systems, components and ograms throughout the
plant. We understand that the EOl r ponse to the RAI of July 29,
97, will be combined with
your response to the enclosed inspecti
report. You are request
to respond to the inspection
report findings and the RAI within 60 day from receipt of this let}er. In your response to the
inspection findings, you should document
y specific actions you have taken in response to the
inspection. After reviewing your response to he inspection findings and the RAI, the NRC will
)
determine whether further NRC enforcement
ion is necessary to ensure compliance with NRC
regulatory requirements.
In accordance with 10 CFR 2.790(a), a copy of this 'tter and the enclosure will be placed in the
NRC public document room. Any Enforcement a son esulting from this inspection will be
handled by NRC Region IV and addressed by s parate
rrespondence. Should you have any
questions concerning this inspection, please
ntact the oject manager, David L. Wigginton, at
(301) 415-1301, or the inspection team lead r, Patrick M. , dden, at (301) 415-2854.
Sincerely,
John N. Hannon, Directo
Project Directorate IV-1
Division of Reactor Projects I & IV
Office of Nuclear Reactor Regu tion
Docket No.: 50-458
License No.: NPF-47
Enclosure: NRC Inspe on Report 50-458/97-201
cc w/ encl.: standard iver Bend service list
SEE DISTRIBUTl
LIST ON NEXT PAGE
DOCUMENT
ME: A:\\TRANS.LTR
DSSA
SPLB:DSSA
SPLB:DSSA
-
/ 'PMadden
KSWest
LBMarsh
JNHannon
03/'/98
03/(9/98gL
03/ /98
03/ /98
OFFICIAL RECORD COPY
ga7 7 7MI
.
...
p'. 9
.
~ Mr. John R. McGaha, Jr.
3
DISTRIBUTION
PUBLIC
Central '
<-' Docket File -
So- 45&
CERossi, AEOD
SPLB R/F
Regional Administrators
PIPB R/F
Deputy Regional Administrators
SPSB R/F
EELB R/F
ACRS (3)
BSheron
OGC (3)
EAdensam
JHannon
DWgginton
)
GHolahan
)
SNewberry
"
LMarsh
KWest
PMadden
EConnell
PQualls
.
MSalley ..
LWhitney
WHRuland, Rl
ABelisle, Rll
RGardner, Rlli
TStetka, RIV
Plant R/F
SPLB R/F
p
.
o
.
.,
. a*
w
Mr. John R. McGaha .
Entergy Operations, Inc.
River Bend Station
ec:
Winston & Strawn
Executive Vice President and
1400 L Street, N.W.
. Chief Operating Officer
Washington, DC 20005-3502 .
Entergy Operations, Inc.
P. O. Box 31995
Manager- Licensing
Jackson, MS 39286
Entergy Operations, Inc.
River Bond Station
General Manager- Plant Operations
P. O. Box 220
Entergy Operations, Inc.
St. Francisville, LA 70775
River Bond Station
P. O. Box 220
Senior Resident inspector
St. Francisville, LA 70775
P. O. Box 1050
St. Francisville, LA 70775
Director- Nuclear Safety
Entergy Operations, Inc.
President of West Feliciana
River Bend Station
Police Jury
P. O. Box 220
P. O. Box 1921
St. Francistville, LA 70775
St. Francisville, LA 70775
Vice President - Operations Support
. . . Regional Administrator, Region IV
Entergy Operations, Inc.
U.S. Nuclear Regulatory Commission -
P. O. Box 31995
611 Ryan Plaza Drive, Suite 1000
Jackson, MS 39286-1995
Arlington, TX 76011
Attomey General
Ms. H. Anne Plettinger
State of Louisiana
3456 Villa Rose Drive
P. O. Box 94095
Baton Rouge, LA 70806
Batnn Rouge, LA 70804-9095
Administrator
Wise, Carter, Child & Caraway
Louisiana Radiation Protection Division
P. O. Box 651
P. O. Box 82135
Jackson, MS 39205
Baton Rouge, LA 70884-2135