ML20138L983
| ML20138L983 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/12/1985 |
| From: | Clemons P, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20138L974 | List: |
| References | |
| 50-317-85-31, 50-318-85-26, NUDOCS 8512200158 | |
| Download: ML20138L983 (7) | |
See also: IR 05000317/1985031
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report Nos.
50-317/85-31
50-318/85-26
Docket Nos.
50-317
50-318
Category
C
License Nos. OPR-53
Priority
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Licensee:
Baltimore Gas and Electric Company
P. O. Box 1475
Baltimore, Maryland 21203
Facility Name: Calvert Cliffs Nuclear Power Plant, Units 1 and 2
Inspection At:
Lusby, Maryland
Inspection Conducted:
November 18-22, 1985
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Inspector:
P. Clemons, Radiation Specialist
' date
Approved by:
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M. Shanbaky, Chief
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PWR Radiation Safety Section
Inspection Summary:
Inspection on November 18-22, 1985 (Report Nos. 50-317/
85-31 and 50-318/85-26).
Areas Inspected:
Routine, unannounced safety inspection of the Radiation Pro-
tection Program during the outage including: external dosimetry training,
respiratory protection, exposure control, surveys, procedures, posting and
labeling, and outstanding items. The inspection involved 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> onsite by
one regionally based inspector.
Results: No violations were identified during the course of this inspection.
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DETAILS
1.0 Persons Contacted
1.1 Licensee Personnel
N. Millis, General Supervisor - Radiation Safety
J. Carlson, Assistant General Supervisor - Radiation Safety
P. Rizzo, Supervisor - Technical Training
L. Smialek, Senior Plant Health Physicist
W. Putman, Senior Quality Assurance Auditor
E. Roach, Quality Assurance Specialist
1.2 NRC Personnel
~T. Foley, Senior Resident Inspector
D. Trimble, Resident Inspector
Other licensee personnel were contacted and interviewed during the
inspection.
2.0 Purpose
The purpose of this routine safety inspection was to review the perfor-
mance of the licensee's radiation protection program during the 1985
refueling outage with respect to the following elements:
external dosimetry program;
training of outage personnel;
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respiratory protection program;
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exposure control;
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surveys;
procedures; and
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posting and labeling.
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3.0 Licensee Action on Previous Findings
(Closed) Violation (317/85-20-01 and 318/84-20-01) Failed to adhere to the
criteria of Appendix B, Part 50. The inspector reviewed the corrective
action specified in the licensee's response dated October 26, 1984. The
corrective action appeared to be adequate.
4.0 External Dosimetry Program
The licensee's external dosimetry program was reviewed with respect to the
criteria contained in 10 CFR 20, " Standards For Protection Against
Radiation."
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The licensee's implementation of the external dosimetry program was
evaluated by the following methods:
Interviews of the Dosimetry Supervisor and staff;
Review of dosimetry records of selected personnel.
Within the scope of this review, no violations were identified.
The following was noted:
The external dosimetry program was adequate and effective.
The licensee's dosimetry group was well staffed.
The licensee's External Dosimetry Program is NVLAP certified. This
certification demonstrates an acceptable level of minimum performance
in evaluating personnel radiation exposures.
5.0 Surveys
The licensee's survey program was reviewed against criteria contained in
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10 CFR 20.201, " Surveys".
The licensee's performance relative to these criteria was determined by
discussion with the Radiation Controis-Ops Supervisor and by reviewing
appropriate radiological survey records.
The licensee's records indicate that the surveys taken throughout the
Controlled Area are adequate.
Within the scope of this review, no violations were identified.
6.0 Posting and Labeling
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The licensee's program for area posting and control was reviewed against
the criteria in 10 CFR 20.203, " Caution signs, labels, signals and
Controls".
The licensee's performance relative to these criteria was determined from
a tour of the Controlled Areas and from discussions with the staff
members.
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Throughout all of the areas inspected, posting and labeling were more than
adequate.
Within the scope of this review, no violations were identified.
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7.0 Respiratory Protection Program
The Itcensee's respiratory protection program was reviewed with respect
to the criteria contained in 10 CFR 20.103, " Exposure of individuals to
concentrations of radioactive materials in air in restricted areas".
The implementation of the licensee's respiratory protection program during
the outage was evaluated by:
interviews of the personnel responsible for various aspects of the
program;
reviewing records that indicated that breathing air had been sampled
and analyzed to assure Grade D quality.
Procedures for implementing the respiratory protection program appeared
.to be adequate.
Within the scope of this review, no violations 'iere identified.
8.0 Procedures
The adequacy and effectiveness of the licensee's procedures were reviewed
against the criteria contained in Technical Specification 6.8, "Proce-
dures", and Technical Specification 6.11, " Radiation Protection Program".
Procedures reviewed included:
RSP 1-117, " Selection, Issuance And Wearing Of Respiratory Protection
Devices Used At Calvert Cliffs Nuclear Power Plant",
RSP 2-306, " Operation And Maintenance Of The. Containment And Plant
Breathing Systems",
RSP 2-301, " Respiratory Protection Device Maintenance",
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RSP 3-201, " Personnel Dosimetry",
RSP 3-202, "Special Dosimetry".
Within the scope of this review, no violations were identified.
'9.0
Training
The licensee's training program was reviewed against criteria contained in
10 CFR 19.12, " Instructions to Workers" and ANSI N18.1, 1971, " Selection
and Training of Nuclear Power Plant Personnel".
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The licensee's performance relative to these criteria was determined by
discussion with a Training Instructor, and by review of documentation.
The lesson plans used in providing training for the Contractor Health
Physics Technicians appeared to be more than adequate.
Within the scope of this review, no violations were identified.
10.0 Exposure Control
The licensee's external exposure control program was reviewed against cri-
teria contained in 10 CFR 20.202, " Personnel monitoring". The licensee's
program for controlling personnel exposure and maintaining exposure ALARA
during the 1985 Refueling Outage was evaluated by:
Interviews of the ALARA and Radiation Control Supervisors and
selected members of their staff;
Review of procedure RSP-106, "Special Work Permit"; and
Review of activities and documentation associated with nozzle dam
installation and removal.
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Within the scope of this review, the following was identified:
The inspector determined that 15-20 licensee employees participated
in the nozzle dam operations during this outage.
The licensee's
exposure records indicated that this job was accomplished with the
expenditure of 9.9 man-rem.
This represents a significant reduction
in exposure in performing this job. According to the Radiation
Control - ALARA Supervisor, the lowest exposure received in doing
this job, prior to this outage, was 47 man-rem.
The licensee is to.be commended for the tremendous effort that resulted in
this significant reduction in exposure.
Within the scope of this review, no violations were identified.
11.0 Control Room Habitability
Combined Inspection Report Nos. 50-317/85-27 and 50-318/85-25 provided
the results of a review of Control Room Habitability at the Calvert Cliffs
Nuclear Station, Units 1 and 2.
Since the issuance of this inspection
report, additional findings relative to the acceptability of Control Room
Habitability at Calvert Cliffs have been identified by the NRR Review
Group. These additional findings are stated below along with NRC
requested action.
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Additional Findings
-(a) Leakage was measured (1000-2000 cfm) through the isolation dampers
with the system in the recirculation mode and flow (10-25% of rated
flow) was measured through the charcoal absorber unit when it was
isolated.
(317/85-31-01)
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The licensee should provide the following:
the results'of the current evaluation to establish total inleakage
rate for the Control Room envelope, and
the date as to when the identified deficiencies will be corrected.
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(b) Missing screws and bolts were evident and, as a consequence, ducting
seam leakage was noted.
Additionally, several holes were found at
stress points on the fabric expansion joints.
It was stated that
inspection and repair of this system was needed to minimize inleak-
age during an accident. (317/85-27-01 and 318/85-25-01)
The licensee should provide the following:
status of maintenance deficiencies that have been corrected,
results of the evaluation of the walkdown of effected duct work, and
the date when all activities including identified deficiencies will
be corrected.
(c) Technical Specification 4.7.6.1.e.2 requires both isolation valves of
each outside air intake to close on a control room high radiation
test signal. At Calvert Cliffs, only the butterfly damper on each
intake closes on high radiation signal.
(317/85-31-02)
The licensee should provide the following:
corrective actions to be taken, and
the date when the deficiencies will be corrected.
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12.0 Exit Interview
The inspector met with the personnel denoted in Section 1 at the conclu-
sion of the inspection on November 22, 1985. The scope and findings of-
the inspection were discussed at that time.
The licensee was given a copy of the NRR findings of the Control Room
Habitability Study that was performed in September, 1985. A copy of the
material provided to the licensee is attached to this inspection report.
No other written material was provided to the licensee.
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Attachment to Combined Inspection Report 50-317/85-31; 50-318/85-26
Control Room Habitability Findings
Leakage was measured (1000-2000 cfm) through the isolation dampers
with the system in the recirculation mode.
Flow (10-25% of rated flow) was measured through the charcoal
absorber unit when it was isolated.
The licensee representative knowledgeable about the control room
HVAC system was from BG&E headquarters.
His understanding of the
system and its mode of operation differed from the manner in which
the system operated.
Missing screws and bolts were evident and, as a consequence, ducting
seam leakage was noted. Additionally, several holes were found at
stress points on the fabric expansion joints.
Technical Specification 4.7.6.1.e.2 requires both_ isolation valves of
each outside air intake to close on a control room high radiation
test signal. At Calvert Cliffs, only the butterfly damper on each
intake closes on high radiation signal.
The location where equipment temperature was monitored to show
conformance with Technical Specification 4.7.6.1.a was not near
such equipment but on a control room wall.
The manner in which the control room HVAC system is operated and its
configuration is quite different from that which would be concluded
from Calvert Cliffs III.D.3.4 submittal.
Laboratory testing of charcoal should be at 30 C rather than 130 C
consistent with ASTM D3803-1979 and the allowable penetration for
this test should be 1% in accordance with Table 2 of Regulatory Guide 1.52.
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The cooling load for the control room is 116.5 tons. The capacity
-of the safety grade system is 96 tons. After a series of cooling
problems in 1980 a new non-safety grade system was added to handle
control room cooling during normal operation. The adequacy of the
revised HVAC system has not been analyzed.
The 19 cfm of inleakeage used by the licensee in the III.D.3.4
analysis has never been verified.
The leak rate assumed in the III.D.3.4 evaluation was based upon
factory test data and anticipated performance of the butterfly and
louvered dampers.
The actual performance of the dampers shows
substantially greater leakage.
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