ML17158B666
| ML17158B666 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna |
| Issue date: | 06/10/1996 |
| From: | Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| Shared Package | |
| ML17158B667 | List: |
| References | |
| EA-96-087, EA-96-87, NUDOCS 9606200195 | |
| Download: ML17158B666 (7) | |
See also: IR 05000387/1996003
Text
,
CATEGORY 2
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
CCESSION NBR:9606200195
DOC.DATE: 96/06/10
NOTARIZED: NO
"
,
DOCKET
FACIL:50-387 Susquehanna
Steam Electric Station, Unit 1, Pennsylva
05000387
50-388
Susquehanna
Steam Electric Station, Unit 2, Pennsylva
05000388
AUTH.NAME
AUTHOR AFFILIATION
WIGGINS,J.T.
Region
1 (Post
820201)
RECIP.NAME
RECIPIENT AFFILIATION
BYRAM,R.G.
Power
& Light Co.
SUBJECT: Discusses
insp repts
50-387/96-03
& 50-388/96-03
& forwards
DISTRIBUTION CODE:
IE01D
COPIES
RECEIVED:LTR
ENCL
SIZE:
+
TITLE: General
(50 Dkt)-Insp Rept/Notice of Violation Response
NOTES:
05000387
E
RECIPIENT
ID CODE/NAME
PDl-2
INTERNAL: ACRS
EOD/g.'-R.
FILE CENTER
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TERNAL: LITCO BRYCE,J
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NRC
NOTES:
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ID CODE/NAME
POSLUSNY,C
AEOD/SPD/RAB
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NRR/DRPM/PECB
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NOTE TO ALL "RIDS" RECIPIENTS:
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I
June
10,
1996
EA 96-087
Hr. Robert
G.
Byram
Senior Vice President-
Nuclear
Power
and Light Company
2 North Ninth Street
Allentown, Pennsylvania
18101
SUBJECT:
NOTICE OF VIOLATION NO. 50-387/388/96-03-01,
96-03-02,
96-03-03
Dear Hr. Byram:
This refers to the predecisional
enforcement
conference
held
on Hay 7,
1996,
at the
NRC Region I office located in King of Prussia
PA.
The conference
was
held to discuss
apparent violations outlined in NRC inspection report
50-387/388/96-03
performed
between
December
11-15,
1995,
and March 4-8,
1996,
at the Susquehanna
Steam Electric Station
(SSES).
The inspection
focused
on
issues
important to the public health
and safety
and consisted of independent
evaluations of your engineering
program.
The enforcement
conference
involved apparent violations concerning
the high
pressure
coolant injection (HPCI) system operability,
and the identification
and correction of the susceptibility of a HPCI injection valve to pressure
locking. It also considered
the manner in which longstanding
design
deficiencies
in the reactor water cleanup
(RWCU), containment
atmosphere
'leanup
and seismic monitoring systems
were addressed
in accordance
with the
plant licensing basis.
Based
on the information developed
during the inspection
and the information
that you provided during the conference,
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 the subject inspection report.
The violations highlight the fact that your organization did not appropriately
consider the regulatory significance of design deficiencies
in the
RWCU and
seismic monitoring systems
once they were identified by plant personnel.
Further,
changes
that your organization
made to the
RWCU leak detection
and
isolation system
were not entered
into the Final Safety Analyses
Report
(FSAR)
as required
by
With regards
to the apparent violations that were considered for the HPCI
system,
we have concluded
you had responded
appropriately considering the
information that
was available at the time concerning
pressure
locking and
Your treatment of the
HPCI injection valve was consistent
with NRC expectations
outlined in the Generic Letter 89-10 program.
Accordingly,
no violation existed.
9b0b200i95
9bOb10
ADGCK 050003S7
8
gl
Robert
G.
Byram
While we believe that your response
to
a single failure in the containment
atmosphere
cleanup
system
was not timely,
we have not completed
our
consideration
on the matter of enforcement
action.
That action will be
determined after
we complete
a review of the concerns
outlined in NRC
unresolved
items 96-03-02,
96-03-03
and escalated
enforcement
item 96-03-04 of
NRC inspection report 96-03.
You will be notified of our conclusions
regarding
these
issues later in separate
correspondence.
Although your organization's
problem identification capability is superior,
we
are concerned that your organization did not resolve the design
issues
in the
RWCU leak detection
and seismic monitoring systems
in a timely manner.
Further, your organization did not appropriately consider the regulatory
'ignificance
of these
design deficiencies.
Accordingly, the operability of
the
RWCU leak detection isolation system
was questionable
from 1989-1996.
Further,
the location of seismic monitoring instrumentation
has not been in
compliance with the plant Technical Specifications
since the start of
commercial plant operation.
We note the
RWCU leak detection
and isolation system consists of diverse
isolation components.
Since the design deficiency concerned
only one portion
of the
RWCU isolation system,
and other components
were operable,
the safe'ty
consequence
of the
RWCU design
weakness
was low because
other
RWCU isolation
system
components
could perform
an equivalent isolation function if required.
Additionally, the safety consequence
of the inappropriately located seismic
monitoring instrumentation
is also low since the information provided by the
monitors is only part of the information that would be used
by your
organization to assess
plant response
to
a seismic event.
Therefore,
these
violations have
been categorized
in accordance
with the "General
Statement of
Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy),
tune 30,
1995) at Severity Level
IV .
You are required to respond to this letter and should follow the instructions
specified in the enclosed
Notice when preparing your response.
In your
response,
you should document
the specific actions
taken
and
any additional
actions you plan to prevent recurrence.
After reviewing your response
to
this Notice, including your proposed corrective actions
and the results of
future inspections,
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 of the
NRC's "Rules of Practice,"
a copy of
this letter, its enclosure(s),
and your response will be placed in the
NRC
Public Document
Room (PDR).
To the extent possible,
your response
should not
include
any personal
privacy, proprietary,
or safeguards
information so that
it can
be placed in the
PDR without redaction.
Robert
G.
Byram
The response
directed
by this letter and the enclosed
Notice are not subject
to the clearance
procedures
of the Office of Hanagement
and Budget
as required
by the Paperwork
Reduction Act of 1980,
Pub.
L. No. 96.511.
'incerely,
Oocket Nos.
50-387;
50-388
License
Nos.
Enclosure:
James
T. Wiggins, Director
Division of Reactor Safety
cc w/encl:
G. T, Jones,
Vice President
-, Nuclear Engineering
G. Kuczynski, Plant Hanager
J.
H. Kenny, Supervisor,
Nuclear Licensing
G.
D. Hiller, Hanager - Nuclear Engineering
R,
R. Wehry, Nuclear Licensing
H.
H. Urioste,
Nuclear Services
Hanager,
General
Electric
C. 0.
Lopes,
Hanager - Nuclear Security
W. Burchill, Hanager,
Nuclear Safety Assessment
H. 0, Woodeshick,
Special Office of the President
J.
C. Tilton, III, Allegheny Electric Cooperative,
Inc.
Nuclear Safety Information Center
(NSIC)
Commonwealth of Pennsylvania
0
Robert
G.
Byram
Distribution w encl:
Region
I Docket
Room (with concurrences)
K. Gallagher,
NRC Resident
Inspector
PUBLIC
Distribution w encl:
(Via E-Mai 1)
W. Dean,
OEDO
C. Poslusny,
Project Manager,
J. Stolz,
PDI-2,
Inspection
Program
Branch,
( IPAS)
R.
Zimmerman,
ADPR,
J.
Goldberg,
J.
Lieberman,
(OEMAIL)
D. Holody,'I
DOCUMENT NAME:
A: EA96087.SUS
To receive a copy oF this document, indicate in the hox: "C"
Copy~thout attachment/cn
ur
~ Copy with attachment/enclosure
"N'
Yo copy
OFFICE
R I/OE
RI/DRP
RI/DRS
RI/DRS
NAME
JJoust
.
WPascia~
MHodes
JWi
ins
DATE
06/03/9
06/ ")/96
06/
9
OFFICIAL RECORD
COPY
06/
/96
06/
/96