ML17158A216
| ML17158A216 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/12/1994 |
| From: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| Shared Package | |
| ML17158A217 | List: |
| References | |
| NUDOCS 9404180063 | |
| Download: ML17158A216 (11) | |
See also: IR 05000387/1992099
Text
FORD I
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9404180063
DOC.DATE: 94/04/12
NOTARIZED: NO
DOCKET
ACIL:50-387 Susquehanna'team
Electric Station,
Unit 1, Pennsylva
05000387
50-388
Susquehanna
Steam Electric Station,
Unit 2, Pennsylva
05000388
AUTH.NAME
AUTHOR AFFILIATION
MARTIN,T.T.
Region
1 (Post
820201)
RECIP.NAME
RECIPIENT AFFILIATION
BYRAMiR.G.
Power
& Light Co.
SUBJECT:
Forwards
SALP Repts
50-387/92-99
& 50-388/92-99
on 920419-
940226.Plant
operational
performance
generally excellent.
DISTRIBUTION CODE:
IE40D
COPIES
RECEIVED:LTR
ENCL
SIZE:
TITLE: Systematic
Assessment
of Licensee Perfor
ance
( ALP) Repor
NOTES:
RECIPIENT
ID CODE/NAME
PD1-2
LA
CLARK,R
INTERNAL: ACRS
AEOD/DSP/TPAB
DEDRO
NRR/DRCH/HHFBPT
NRR/DRIL/RPEB
NRR/DRSS/PEPB
NRR/DRSS/RSGB
NUDOCS-ABSTRACT
OGC/HDS2
RES/HFB
EXTERNAL'G &G/BRYCE I J
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NRC PDR
COPIES
LTTR ENCL
1
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1
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1
- 1
1
1
1
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1
1
1
1
1
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RECIPIENT
ID CODE/NAME
PD1-2
AEOD/DOA
COMMISSION
NRR/DORS/OEAB
NRR/DRCH/HOLB
NRR/DRIL/RSIB
NRR/DRSS/PRPB
NRR/PMAS/ILRB
OE 'DIR
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02
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COPIES
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I:OTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.
ROOM PI-37 (EXT. 504e2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION
LISTS FOR DOCUMENTS YOU DON'T NEED!
e
.TOTAL NUMBER OF COPIES
REQUIRED:
LTTR
32
ENCL
32
APR
I 2
[9'ocket
Nos.
50-387
50-388
Mr. Robert G. Byram
Senior Vice President - Nuclear
Pennsylvania Power & Light Company
2 North Ninth Street
Allentown, Pennsylvania
18101
Dear Mr. Byram:
SUBJECT:
SYSTEMATIC ASSESSMENT
OF LICENSEE PERFORMANCE
(SALP)
REPORT NOS. 50-387/92-99 AND 50-388/92-99
This letter forwards the Susquehanna
Steam Electric Station, Units 1 and 2, SALP report for the
period April 19, 1992, to February 26, 1994.
This SALP was conducted under the revised
SALP process that was implemented by the Nuclear Regulatory Commission (NRC) on July 19,
1993.
The revised
SALP process
rates
licensees
in four functional areas:
Operations,
Engineering,
Maintenance,
and Plant Support.
The Plant Support functional area includes;
radiological
controls,
security,
emergency
preparedness,
fire protection,
chemistry,
and
housekeeping.
Overall, the NRC observed
an excellent level of performance
at the Susquehanna
Station.
Management was routinely involved in daily plant activities, exercised effective oversight, and
properly focused its attention on safety issues.
Effective communication between all of the
organizational units resulted in enhanced coordination and efficiency ofactivities.
Performance
of safety committees continued to be strong, as demonstrated
by their comprehensive
reviews,
questioning attitude, and sound safety perspective.
Self-assessment
activities were frequently
used to set performance goals, identify trends, and provide effective feedback to management.
Plant personnel
were well-trained,
knowledgeable
of plant conditions
and activities,
and
responded
to plant events in a prompt and thorough manner.
Strong performance
in the
Engineering and Maintenance areas continued during this SALP period. Performance in the new
functional area of Plant Support was also viewed as a licensee strength.
Performance in the
Operations area declined from its previous superior level.
Plant operational
performance
was
generally
excellent.
The operations
staff's
superior
performance contributed to the safe operation of the plant during normal operations.
Operator
training was improved and effective.
However, some aspects of performance were diminished
as a result of long-standing uncorrected
matters involving fuel handling practices
and status
control of equipment restored from maintenance,
which were revealed toward the end of the
period. The recurrent nature ofproblems in these areas indicated that management was not fully
uu~> (
9404180063 9404i2
ADOCK 05000387
6
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APR
I 2 ]ggg
cognizant of the ineffectiveness of previous corrective measures,
and generally accepting of the
conditions.
Accordingly, management oversight and control relative to root cause assessment
and corrective action effectiveness were considered
weak.
II
The
maintenance
program
was well'anaged
and
continued
to
be
a
strength.
The
implementation of the overall program was effective, and demonstrated
a strong influence of
program and site management.
However,
there were a few isolated
instances
where the
maintenance and surveillance activities did not achieve the licensee's typically high standards for
safety-related activities.
The engineering organization demonstrated
a strong and conservative
safety perspective
and
provided an effective interface with site activities. Engineering management oversight in support
of the station was very evident.
Engineering evaluations were generally found to be technically
accurate, thorough, and complete.
While several repetitive events raised questions relative to
monitoring and trending of system performance, overall the licensee's performance in this area
'as superior.
The plant support functions significantly contributed to safe plant performance.
Performance
in the radiation protection area continued to improve.
Improvements in Health Physics/worker
communications
and increased
use of shielding contributed to low station doses.
There was
continued strong performance in the emergency preparedness
area with a number of important
improvements
implemented
in preparation
for the Full Field Exercise.
Security program
performance continued to be superior.
We have scheduled a management
meeting with you, open for public observation, at 10:00 a.m.
on April20, 1994, at your Access Processing
Center.
At this meeting you should be prepared
to discuss our assessment
and any initiatives that you plan to take to address
the weaknesses
detailed in our evaluation.
We appreciate your cooperation,
Sincerely
.
Orig'"al ~~"~<<'" ~
Thomas T. Martin
Regional Administrator
Enclosure:
Systematic Assessment of Licensee Performance (SALP) Report Nos.
50-387/92-99 a!ld 50-388/92-99
APR
I 2
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cc w/encl:
H. G. Stanley, Vice President - Nuclear Operations
J. M. Kenny, Nuclear Licensing
G. T. Jones, Vice President - Nuclear Engineering
M. M. Urioste, Nuclear Services Manager
D. F. McGann, Supervisor, Nuclear Compliance
H. D. Woodeshick, Special Office of the President
J. C. Tilton, III, Allegheny Electric Cooperative, Inc.
Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
K. Abraham, PAO (23)
NRC Resident Inspector
Commonwealth of Pennsylvania
The Chairman
Commissioner Rogers
Commissioner Remick
Commissioner de Planque
Institute for Nuclear Power Operations (INPO)
APR
I 2 ioo
bcc w/encl:
Region I Docket Room (with concurrences)
J. Callan, NRR
SALP Program Manager, DRIL, NRR
bcc w/encl: (Via E-Mail)
J. Taylor, EDO
W. Russell, NRR
V. McCree, OEDO
J. Lieberman, OE
W. Scott, NRR/RPEB
R. Clark, Project Manager, NRR
C. Miller, PDI-2, NRR
Region I Staff
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bcc w/encl:
Region I Docket Room (with concurrences)
J. Callan, NRR
SALP Program Manager, DRIL, NRR
bcc w/encl: (Via E-Mail)
J. Taylor, EDO
W. Russell, NRR
V. McCree, OEDO
J. Lieberman, OE
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R. Clark, Project Manager, NRR
C. Miller, PDI-2, NRR
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bcc w/encl:
Region I Docket Room (with concurrences)
L. Reyes, NRR
SALP Program Manager, DRIL, NRR
bcc w/encl: (Via E-Mail)
J. Taylor, EDO
W. Russell, NRR
V. McCree, OEDO
J. Lieberman, OE
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- SEE PREVIOUS CONCURRENCE PAGES