ML20041B361
| ML20041B361 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/01/1982 |
| From: | Greger L, Miller D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20041B356 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM 50-373-82-03, 50-373-82-3, NUDOCS 8202230571 | |
| Download: ML20041B361 (4) | |
See also: IR 05000373/1982003
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U.S.-NUCLEAR REGULATORY CG2ISSION
REGION III
Report No. 50-373/82-03-
Docket No. 50-373
License No. CPPR-99
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Licensee: Commonwealth Edison Company
Post Office Box 767
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Chicago, IL 60690
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Facility Name:
LaSalle County Nuclear Station, Unit 1
Inspection At: LaSalle Site, Seneca, IL
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Inspection Conducted: January 14-15, 1982
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Inspector:
D. E. Miller
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Approved By:
-L. R. Greg
Chief
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Facilities Radiation
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1.
Protection Section
Inspection Summary:
Inspection on January 14-15, 1982 (Report No. 50-373/82-03)
Areas Inspected: Routine, unannounced preoperational inspection of radi-
ation protection procedures, open SER items, response to -IE Circular 79-21,
and completed systems demonstrations.- The inspection involved 11 inspector-
hours onsite by one hTC inspector.
Results: No items af noncompliance or deviations were identified.
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DETAILS
1.
Persons Contacted
- R. Bishop, Assistant Superintendent, Administrative and
Support Services
C. Schroeder, Technical Staff Supervisor
F. Lawless, Rad / Chem Supervisor
G. Watts, AIR Coordinator
S. Shepley, Resident Inspector, NRC
The inspector also contacted several engineering assistants during
the inspection.
- Denotes those presen at the exit meeting.
2.
General
This preoperational inspection, which began at 8:30 a.m. on January 14,
1982, was conducted to examine radiation protection procedures, response
to IE Circular 79-21, open SER items, and completed systems demonstrations.
No significant probleme were identified.
3.
Radiation Protection Procedures
The inspector revieted the following new or recently revised radiation
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protection procedures. They appear to be compatible with regulatory
requirements and FSAR commitments:
LRP 1250-2
Revision 1
Exposure Control
LRP 1350-23
Revision 0
Deployment of the Eberline SAM-2
LRP 1820-9
Revision 0
Performance Test of the Eberline
Sam-2 Stabilized Assay Meter
LRP 1820-10
Revision 0
Calibration of the Eberline Sam-2
Stabilized Assay Meter
4.
SER Open Items
The following licensee responses to SER open items were reviewed during
the inspection.
a.
(Closed) SER Open Item (373/81-00-13): Concerning availability
of a gamma detector that would function in the event of a LOCA
or after seismic alarm. Proper studies have been performed, and
procedure changes made, to assure and verify function of contain-
ment gamma detectors after the above stated events. No problems
were noted during the inspector's review of the licensee's response
to the SER concern.
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b.
(Closed) SER Open Item (373/81-00-63):
Concerning the need to
include in ALARA procedures the criteria for implementing Regu-
latory Guide 8.8 recommendations.
Commonwealth Edison has
developed a formal ALARA program titled " Policy and Procedures
for Maintaining Occupational Radiation Exposures As Low As
Reasonably Achievable (ALARA)." This formal program includes
methods of implementation similar to the guide's recommendations.
Several station procedures have been developed to implement the
station's portion of the CECO program. No problems were noted
during the inspector's review of the licensee's response to the
SER concern.
c.
(Closed) SER Open Item (373/81-00-87): Concerning implementation
of NUREG 0737, Item II.B.3 " Post Accident Sampling Capability."
This matter will be reviewed under open items 373/81-14-22 and
373/81-14-28.
d.
(Closed) SER Open Item (373/81-00-94): Concerning additional
accident monitoring procedures to be implemented in accordance with
NUREG 0737, Item II.F.1.
This matter will be reviewed under open
item 373/81-14-28.
(Closed) SER Open Item (373/81-00-101):
Concerning followup on
e.
commitment to reduce leakage outside containment.
In response to
this item, several procedures concerning development of a formal leak
reduction program and program implementation have been written. No
problems were noted during the inspector's review of the licensee's
response to the SER concern.
5.
IE Circular No. 79-21
The licensee's actions in response to IE Circular No. 79-21,
" Prevention of Unplanned Releases of Radioactivity," were reviewed.
In response to the circular, the licensee reviewed 40 plant systems
to identify potential release paths of radioactive fluids via nonradio-
active systems. The licensee identified 19 potential release paths
during the review. These potential release paths include temporary and
permanent crosa-ties between systems, and possible drainage of contami-
nated liquids to nonradioactive sumps. After the review, the licensee:
a.
Developed a program which establishes the requirements for sepa-
ration of components, systems, and buildings while Unit 1 is
operational and Unit 2 is under construction.
b.
Initiated several design change authorizations; engineering and
field alterations are in progress,
c.
Added the identified needed changes to the licensee's deficiency
status program to assure completion and verification.
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These actions are considered adequate response to this Circular,
(373/79-38-04)
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6.
Preoperational Systems Demonstrations
The following systems demonstration packages have been completed and-
reviewed by the licensee. The inspector reviewed'the completed packages.
Minor outstanding deficiencies appear to be adequately addressed by
facility change requests. No significant problems were noted.
SD-WE-101B
Floor Drain Reprocessing System
SD-WE-101D
Chemical Waste System
7.
Exit Meeting
The inspector met with a licensee representative (denoted in Section 1)
at the conclusion of the inspection on January 15, 1982. Discussed
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were the scope and findings of the inspection.
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