ML17159A037
| ML17159A037 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/04/1997 |
| From: | Anderson C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| 50-387-97-04, 50-387-97-4, 50-388-97-04, 50-388-97-4, NUDOCS 9711130054 | |
| Download: ML17159A037 (7) | |
See also: IR 05000387/1997004
Text
CATEGORY 2
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9711130054
DOC.DATE: 97/11/04
NOTARIZED: NO
DOCKET ¹
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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
ANDERSON,C.J.
Region
1 (Post
820201)
RECZP.NAME
RECIPIENT AFFILIATION
BYRAM,R.G.
Power
6 Light Co.
SUBJECT: Refers to 970904 correspondence
in response
to 970805 ltr re
post-accident
sampling sys discrepancy, item b of Violation
4,cited in insp zepts
50-387/97-04
& 50-388/97-04.Agrees
that item b of violation 4 should be withdrawn.
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21
November 4, ]997
Mr. Robert G. Byram
Senior Vice President
- Nuclear
Power & Light Company
2 North Ninth Street
Allentown, Pennsylvania
18101
SUBJECT:
INSPECTION REPORT NOS. 50-387/97-04 AND 50-388/97-04
Dear Mr. Byram:
This letter refers to your September 4, 1997 correspondence,
in response
to our
August 5, 1997, letter.
With regard to the post-accident
sampling system discrepancy,
item b of Violation 4, cited
in the subject report, you stated that this was not a valid example of a failure to initiate a
condition report.
We note that you have provided new information regarding the initiation
of Condition Report 97-0402 in February 1997.
We are concerned that this information
was not brought to NRC's attention during the inspection.
However,. we agree that in light
of this information, item b of Violation 4 should be withdrawn.
We request that you make
every effort to research
and evaluate
NRC findings during our inspections,
and inform the
inspectors when you believe that additional effort beyond the inspection period will likely
resolve an issue.
Notwithstanding, the post-accident
sampling system is a important system that must be
maintained operable
in accordance
with your technical specification requirements.
We will
continue to monitor your effectiveness
in maintaining this system during future inspections
of your NRC licensed activities.
With regard to the Final Safety Analysis Report (FSAR) departure,
Violation 5, cited in the
subject inspection report, your response
provides additional information on the scope of
your current licensing basis (CLB) project as it relates to the implementation of the NRC
Enforcement Policy for this issue.
Specifically, you stated that discretion under Section
VII.B.3(a) of the Policy should be applied.
Section VII.B.3 (Discretion for FSAR Departures) provides that NRC-identified departures
from the FSAR may not be cited during a 2-year grace period if it is likely in the NRC's
view that the licensee would have identified the violation in light of the defined scope,
thoroughness
and schedule of the licensee's initiative (i.e., CLB project)
~
During the
subject inspection, the FSAR departure,
cited as Violation 5, was identified by the NRC.
j
PPtkL management
and staff were specifically asked whether the CLB project would have
found this departure.
The violation was cited because
your staff responded
that your CLB~
project would not have identified this error.
97iii30054 97ii04
ADOCK 05000387
8
IIIIIIIIIIIIIIIIIIIIIIIIIII!IIIIIIIIIIII
Mr. Robert G. Byram
In view of the new information provided in your response,
we concur that your CLB project
would have identified this departure,
and have changed the violation to an unresolved
item.
This item will remain open to track the progress
and timely conclusion of your CLB project.
Additional departures
may be added to this open inspection item provided that the CLB
project is expected to have identified the errors within the 2-year grace period.
Notwithstanding, we note that the NRC has subsequently
identified FSAR departures that
would not have been identified by your CLB project.
These departures
were cited in NRC
Inspection Report 50-387, 388/97-06, which also describes weaknesses
that NRC
identified in your CLB project.
These weaknesses
involved a lack of standards
for system
walkdowns and system engineer reviews.
In addition, the project implementing procedure
had not received final approval
~
Your corrective actions in response
to that report will be
considered
in determining whether future exercise of discretion for FSAR departures
is
appropriate.
Thank you for informing us of the corrective and preventive actions documented
in your
letter.
These actions will be examined during a future inspection of your licensed program.
Your cooperation with us is appreciated.
Sincerely,
Clifford J. Anderson, Chief
Project Branch No. 4
Division of Reactor Projects
Docket Nos.
50-387;50-388
CC:
G. T. Jones,
Vice President
- Nuclear Operations
G. Kuczynski, General Manager
J. M. Kenny, Supervisor,
Nuclear Licensing
G. D. Miller, General Manager
- Nuclear Engineering
R. R. Wehry, Nuclear Licensing
M. M. Urioste, 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
Mr. Robert G. Byram
Distribution:
Region
I Docket Room (with concurrences)
Nuclear Safety Information Center (NSIC)
W. Axelson, DRA
P. Swetland,
A. Keatley, DRP
NRC Resident Inspector
PUBLIC
W. Dean, OEDO
C. Poslusny,
Project Manager,
J. Stolz, PDI-2, NRR
Inspection Program Branch, NRR (IPAS)
R. Correia, NRR
F. Talbot, NRR
DOCDESK
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DOCUMENT NAME:
G:NBRANCH4XSUS9704.REP
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