ML17164A848
| ML17164A848 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/19/1998 |
| From: | Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| Shared Package | |
| ML17164A849 | List: |
| References | |
| 50-387-98-09, 50-387-98-9, 50-388-98-09, 50-388-98-9, NUDOCS 9810260116 | |
| Download: ML17164A848 (9) | |
See also: IR 05000387/1998009
Text
~~XauUax
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9810260116
DOC.DATE: 98/10/19
NOTARIZED: NO
DOCKET ¹
~
~
FACZL:50-387 Susquehanna
Steam Electric Station, Unit 1, Pennsylva
05000387
50-388
Susquehanna
Steam Electric Station, Unit 2, Pennsylva
05000388
AUTH.NAME
AUTHOR AFFILIATION
WXGGINS,J.T..
Region
1 (Post
820201)
RECZP.NAME
RECIPIENT AFFILIATION
BYRAM,R.G.
Power
6 Light Co.
SUBJECT: Discusses
insp repts
50-387/98-09
& 50-388/98-09
on
980729-31
& forwards NOV.Insp conducted
as followp to FP
Functional
Xnsp
(FPFI) to evaluate
FPFI findings
8 determine
whether
EA was appropriate.
DISTRIBUTION CODE:
IE01D
COPIES
RECEIVED:LTR
t
ENCL
SIZE:
TITLE: General
(50 Dkt) -Insp Rept/Notice of Vino ation Response
E
NOTES:
RECIPIENT
ZD CODE/NAME
PD1-2
COPIES
LTTR ENCL
RECIPIENT
ID CODE/NAME
NERSES,V
COPIES
LTTR ENCL
05000387
0
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INTERNAL: ACRS
AEOD/TTC
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NUDOCS -ABSTRACT
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,AEOD/SPD/RAB
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NRR/DRPM/PERB
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FILE
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ZTERNAL: LXTCO BRYCE,J H
NRC PDR
NOAC
NUDOCS FULLTEZT
NOTES:
N
NOTE TO ALL "RIDS" RECIPIENTS:
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REQUIRED:
LTTR
20
ENCL
October 19, 1998
Mr. Robert G. Byram
Senior Vice President - Nuclear
Pennsylvania Power 5 Light Company
2 North Ninth Street
Allentown, Pennsylvania
18101
SUBJECT:
NOTICE OF VIOLATIONAND NRC SPECIAL INSPECTION
REPORT NOS. 50-387/98-09 AND 50-388/98-09
Dear Mr. Byram:
0
This refers to the inspection conducted on July 29- 31, 1998, at the Susquehanna
Steam
Electric Station.
The inspection was conducted as a followup to the Fire Protection
Functional Inspection (FPFI) to evaluate the FPFI findings and determine what, if any,
enforcement action was appropriate.
The inspection consisted of a review of your
July 20, 1998, letter, evaluations of physical conditions of equipment in the plant, and
reviews of prior licensing documents for the facility.
g
~~oX
Based on the information developed during the inspection and the information that you
provided in your response to the FPFI report, dated July 20, 1998, the NRC has
determined that violations of NRC requirements occurred.
These violations are cited in the
enclosed Notice of Violation (Notice) and the circumstances
surrounding them are
described in detail in NRC Inspection Report 50-3875388/98-09,
and 50-3875388/97-
201. The inspectors determined that there were inadequacies
in the implementation of
your Fire Protection Program implementation in the following areas:
Paths
1 and 3 (Automatic Depressurization
System/Core Spray) willnot meet the specific
requirement of Appendix R,Section III.L.2.bto maintain reactor coolant level above the top
of the core; 2) fire detection and suppression systems (i.e., smoke detectors and sprinkler
systems) were not installed in accordance with the code of record, and evaluations of the
deviations by qualified fire protection engineers were not available; 3) 8-hour battery
powered emergency lights were not provided in all areas of the plant where procedures
required manual actions to achieve safe shutdown conditions; 4) Violations of plant
administrative controls regarding transient combustible material and transient equipment
were identified; 5) availability of keepfill systems for preventing water hammer in fluid
systems required to achieve safe shutdown conditions (i.e., Core Spray, Reactor Core
Isolation Cooling, High Pressure
Coolant Injection, and Residual Heat Removal) were not
assured by the post-fire shutown methodology; and 6) Annual physical examinations of fire
fighting personnel were not conducted
as required by your administrative control
procedures.
9810260116
981019
. PDR
ADQCK 05000387
6
R. Byram
While none of these issues were considered of such magnitude that continued operation of
the facility was questioned, they do indicate that your implementation of your fire
protection program has not received appropriate attention.
They further indicate that the
fire protection design bases of the facility have not always been properly considered when
modifications to the facility have been carried out," as evidenced by the obstruction of
sprinkler discharge patterns in the reactor buildings, and the failure to identify 8-hour safe
'shutdown lights in the "E" diesel generator building. Further, it would seem that there is
disagreement within your operating organization regarding the priority of fire protection
activities, as evidenced by the disagreement
between your fire protection staff and your
Operations Department regarding the need for annual physicals for fire fighters.
The failure
of the Path
1 and 3 post-fire safe shutdown methodologies to meet the specific
requirements of Appendix R,Section III.L.2.b, as committed in your Fire Protection Review
Report, is of particular concern since the condition was first discovered by PPRL in 1994,
and it was neither reported nor corrected.
Therefore, these violations have been
categorized in accordance with the "General Statement of Policy and Procedure for NRC
Enforcement Actions" (Enforcement Policy), NUREG-1600 at Severity Level IV.
We note that with the exception of Post-fire Safe Shutdown Paths
1 and 3 not meeting the
specific regulatory requirements, corrective actions for all the issues have already been
described in your July 20, 1998, letter.
Due consideration was given to those corrective
actions during our deliberations.
Your position regarding core cooling in the post-fire
scenario being provided
by the two-phase mixture within the core shroud, convinced us
that reduction of the severity level for the failure to meet the reactor coolant level
requirement was warranted, since a loss of the core cooling function'ould not have
occurred.
You are required to respond to violation A in the enclosure to this letter and should follow
the instructions specified in,the enclosed Notice when preparing your response.
The NRC
willuse your response,
in part, to determine whether further enforcement action is
necessary to ensure compliance with regulatory requirements.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy'f this letter,
its enclosure,
and your response will be placed in the NRC Public Document Room.
Sincerely,
ORIGINAL SIGNED BY:
James T. Wiggins, Director
Division of Reactor Safety
Docket No. 50-387, 50-388
Enclosure:
R. Byram
c w/encl:
3
R. F. Saunders,
Vice President - Site Operations
G. T. Jones, Vice President - Engineering and Support
G. Kuczynski, General Manager - SSES
J. M. Kenny, Supervisor, Nuclear Licensing
G. D. Miller, General Manager - Nuclear Engineering
R. R. Wehry, Nuclear Licensing
F. P. Arcury, Nuclear Services Manager, General Electric
C. D. Lopes, Manager - Nuclear Security
A. Male, Manager, Nuclear Assessment
Services
H. D. Woodeshick, Special Assistant to the President
J. C. Tilton, III, Allegheny Electric Cooperative, Inc.
Commonwealth of Pennsylvania
R, Byram
Region
I Docket Room (with concurrences)
Nuclear Safety Information Center (NSIC)
H. Miller, RA/W. Axelson, DRA (1)
C. Anderson, DRP
D. Florek, DRP
R. Junod, DRP
C. Miskey, DRS
W. Ruland, DRS
R. Fuhrmeister, DRS
NRC Resident Inspector
PUBLIC
- Ni
B. McCabe, OEDO
V. Nerses, Project Manager, NRR
D. Brinkman, NRR
. Inspection Program Branch, NRR (IPAS)
R. Correia, NRR
F. Talbot, NRR
M. Campion, ORA
D. Screnci, PAO
R. Zimmerman, ADPR, NRR
F. Davis, OGC
A. Nicosia, OGC
J. Lieberman, OE (OEMAIL)
D. Holody, EO, Rl
T. Walker, ORA, Rl
DOCDESK
DOCUMENT NAME: G:iEEBiFUHRMEISiSUS9809.INS
To recehre a copy of this document, indicate in the box: "C
~ Copy without attachment/enclosure
E
~ Copy with attachment/enclosure
"N
No copy
OFFICE
RI/DRS
NAME
RFuhrmeister
DATE
10/15/98
RI/DRS
WRulan
10/ '8
RI/DRP
CAnderson
6
10/
98
OFFICIAL RECORD COPY
RI/DRS
JWiggins
10/
98
10/
/98