ML20245A137
| ML20245A137 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/12/1989 |
| From: | Baer R, Ricketson L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20245A120 | List: |
| References | |
| 50-313-89-24, 50-368-89-24, NUDOCS 8906210114 | |
| Download: ML20245A137 (7) | |
See also: IR 05000313/1989024
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APPENDIX B
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-313/89-24
Operating Licenses:
50-368/89-24
Dockets:
50-313
50-368
Licensee: Arkansas Power & Light Company (AP&L)
P.O. Box 551
Little Rock, Arkansas 72203
Facility Name: Arkansas Nuclear One (ANO)
Inspection At: ANO site, Russellville, Arkansas
Inspection Conducted:
May 15-19, 1989
Inspector:
P
L. T. Ricketson, P.E.,IRadiation Specialist
Date
g Facilities Radiological Protection Section
Approved:
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h/P. - Protection Section V
Inspection Summary
Inspection Conducted May 15-19,1989 (Report 50-313/89-24; 50-368/89-24)
Areas Inspected:
Routine, unannounced inspection of selected areas in the
radiation protection program as set forth in the core inspection
program (83750).
Results:
No significant problems were identified in the areas of staffing,
facilities, equipment and supplies, procedures, and management support. One
apparent violation was identified concerning contamination control procedures
in areas outside of the radiological control area (see paragraph 6).
It was
alsa observed that there is a need for more health physics (HP) supervision
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oversight at some exit areas to ensure that workers follow proper contamination
control practices.
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DETAILS
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1.
Persons Contacted
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- T. G. Campbell, Vice President, Nuclear
- N. S. Carns, Director, Nuclear Operations
- L. W. Humphrey, General Manager, Qualv.y
- S. M. Quennoz, General Manager, Plant Support (Acting)
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- T. C. Baker, Manager, Technical Support
- J. D. Vandergrift, Manager, Operations
E. E. Bickel, Superintendent, HP
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G. D. Provencher, Supervisor, Quality Engineering
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T. R. Smith, Supervisor, HP
J. D. Deal, Supervisor, HP
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- D. B. Lomax, Supervisor, Plan + licensing
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J. R. Waid, Supervisor, Technical Support Training
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J. T. Pugh., Lead Trainer, (General Employee Training)
T. M. Rolniak, Lead Trainer, (HP/Radwaste)
- P. L. Michalk, Licensing Specialist
D. J. Wagner, Nuclear Quality Specialist
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N.R_C
- D. D. Chamberlain, Section Chief, Region IV
- A. T. Howell, II, Project Engineer, Region IV
- W. D. Johnson, Senior Resident Inspector
- R. C. Haag, Resident Inspector
The NRC inspector also contacted other licensee and contractor personnel
during the inspection.
- Denotes those present at the exit meeting on May 19, 1989.
2.
Inspector Observations
The following is an observation that the NRC inspector discussed with the
licensee during the exit meeting on May 19, 1989.
Observations are not
violations, deviations, unresolved items, or open items, but are
identified for licensee consideration for program improvement.
Observations have no specific regulatory requirement.
Increased Surveillance by HP Personnel
There appeared to be a need for increased HP presence and observation
in radiologically controlled areas. The NRC inspector noted numerous
m>.nor items during inspection of controlled areas such as:
individuals throwing potentially contaminated protective clothing at
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waste receptacles, individuals not following the proper undressing
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sequence, individuals not placing contaminated clothing in proper
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waste receptacles, individuals .not signing off radiation work permits
in a timely manner. Collectively, these items could be an indication
of larger problems.
In some cases HP personnel were present', but not
in sufficient numbers and often busy with other duties, or were not
aggressive enough to correct the workers. A similar observation
concerning work practices during outage activities was identified in
NRC Inspection Report 50-313/88-02; 50-368/88-02 (see paragraph 5).
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3.
Licensee Action on Previous Findings
(Closed) Violation (313/8725-01; 368/8725-01):
Failure to Perform
Radiation Surveys - This item involved the failure to perform
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catamination surveys on hand tools used in controlled areas.
The NRC
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inspector verified that an additional HP had been assigned to the
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controlled access exit point to aid in surveying items coming out of the
area. Additionally, a new automated cabinet-style frisking unit had been
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installed and was in use for items such as tools and hardhats.
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actions were consistent with the licensee', trponse to the violation.
(0 pen) Open Item (313/8725-02; 368/87Pa-02):
Dosimetry Technician-
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Training - This item involved the lack of formalized training course. for
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dosimetry technicians. The NRC inspector verified that a formalized,
in-house training course had been developed and needs only to be approved
(through the licensee's normal review process) and implemented. The
training course will be augmented by vendor training, which some
individuals have already received.
This item will remain open
until the NRC confirms that the training ccurse has been implemented.
(Closed) Open Item (313/8725-03; 368/8725-03):
Long Term Radiation Work-
Permits (RWP) - This item involved evaluation intervals for long term or
" general" RWPs and possible changing radiological conditions which could
result in more radiation exposure than originally planned. All long term
RWPs have been reviewed and are now required by procedure (1622.003
Revision 15) to be reviewed at least monthly to determine if radiological
conditions have changed. The NRC inspector reviewed several current RWPs
and verified that none were in effect for more than one month.
(Closed) Violation (313/8802-01; 368/8802-01):
Failure to Perform
Adequate Radiological Surveys - This item involved the use of survey
instruments which did not have the required sensitivity to measure lower
dose rates when iderd fyirig radiation areas outside of controlled access.
The NRC inspector ver1fied, through discussions with representatives from
the licensee's training department, that increased emphasis on the correct
instrument selection is now included in the licensee's training course
" Exposure Control," given to AP&L technicians, and in " Procedure
Requirements and Areas of Responsibility," given to contract personnel.
This action was consistent with the licensee's response to the violation.
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The NRC inspector reviewed selected records of surveys conducted outside
controlled access and verified that survey instruments used to perform the
surveys were of sufficiently low sensitivity to measure 0.8 mR/h. The
HP supervisor interviewed stated that a notice would be posted at the
instrument storage location advising technicians which instruments shall
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not be used outside controlled access for establishing radiat' ion areas.
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(0 pen) Open Item (313/8827-02; 368/8827-02): Health Physics Supervisor
Training - This item involved the lack of specialized training for some
supervisors. The NRC inspector verified that there has been increased
emphasis on offsite training for HP supervisors and that funds were
budgeted for several training courses in the coming months.
However, the
NRC inspector noted that at least two supervisors have still not received
any training in recent years. This item will remain open.
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4.
Audits and Appraisals
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The NRC inspector reviewed audits and selected surveillance of the
radiation protection program.
The NRC inspector reviewed Health Physics Audit QAP-3-88 performed between
May 25 and September 30, 1988, and six surveillance which supported the
audit, and concluded that the depth and scope of the audit were adequate.
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The checklists for surveillance were comprehensive and provided good
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guidance to the auditors. Qualifications of the auditors were adequate,
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with at least one former HP supervisor included as part of the audit team.
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Recommendations for improving the HP program were presented in the audit
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report and audit findings were resolved in a timely manner.
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Findings of the 1989 audit were being prepared for formal presentation to
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the HP department.
No violations or deviations were identified.
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5.
Planning, Preparation, and Outa_ge Activities
Due to an unscheduled outage to locate the source of reactor coolant
leakage, the NRC inspector had the opportunity to observe outage
operations, including planning and preparation, containment entry,
personnel dressout, and contamination control. A list of the procedures
reviewed is attached to this report.
The NRC inspector attended prejob briefings conducted by HP before entry
into Unit 1 containment and noted that the topics discussed included
expected radiation levels, protective clothing and respiratory
requirements, survey instrumentation, administrative radiation dose
limits, and dosimetry requirements. Also discussed were the symptoms
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and effects of heat exhaustion, routes to be taken by the entry teams, and
emergency rescue plan. There was a free discussion during the meeting
concerning the possible problems involved.
Representatives from
departments such as operations', safety, and maintenance were in attendance.
The NRC inspector observed entry / exit operations at the containment batch
and noted that the controlled area for undressing was smaller than for
planned outages which forced people to wait in line to undress.
Occasionally, individuals, evidently impatient at having to wait for those
in front of them to finish undressing, threw potentially contaminated
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protective clothing items into the receptacles.
Such actions bring about
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the possibility of an airborne contamination hazard.
The NRC inspector
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also noted occasional minor problems such as an individual removing his
glove liners too soon in the undressing sequence. Only one HP was present
and instructed individuals against such practices, when observed.
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However, all examples were not observed by the HP who was occupied part of
the time with other tasks such as bagging respirators and logging people
out of the area. This, along with the item discussed in the following
section, led the NRC inspector to conclude that Hp presence needs to be
increased in such cases.
The licensee had identified four examples of unknown individuals either
changing or not replacing radiological postings following entry to or
exit from radiologically controlled areas.
As a result, the licensee
issued a memorandum on May 10, 1989, discussing these practices and
warning of disciplinary action which would be taken if individuals were
found changing or not replacing radiological posting.
Labeling and
posting were inspected in areas both inside and outside of Controlled
Access and found to be adequate.
No violations or deviations were identified,
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6.
C_ontrol of Radioactive Material and Contamination
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During the course of inspecting the licensee's program of controlling
contamination, the NRC inspector observed an individual inside the high
pressure turbine housing (" doghouse"), within a controlled area.
The
individual was properly suited in " Type B" clothing consisting of paper
overalls, hood, gloves, glove liners, booties, and rubber shoe covers and
was observed to be climbing and working in the contaminated area. The
individual passed from the controlled area over a step-off pad and into a
clean area without removing potentially contaminated protective. clothing.
When these work practices were questioned by the NRC inspector, the
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individual stated that he had not seen the step-off pad and was aware of
only the step-off pad on the other side of the housing.
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Technical Specifications 6.10 and 6.11 for ANO Units 1 and 2,
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respectively, require that procedures for personnel radiation safety shall
be adhered to for all operations involving personnel radiation exposure.
Radiation Procedure 1632.002, " Access and Control of Radiologic 21fy
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Controlled Area," states that " Step-off pads are.placed at exits from more
highly contaminated areas.
The step-off pads indicate the portion of
protective clothing which should be removed when leaving the area."
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requires that, " Individuals shall observe step-off pad instructions . . . ."
The instructions on the step-off pads read, "Stop.
Remove contaminated
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clothing." The failure to follow radiation protection procedures is an
apparent violation of Technical Specification 6.10.
(313/8924-01;
368/8924-01)
No deviations were identified.
7.
Exit Meeting
The NRC inspector met with licensee representatives and NRC personnel
denoted in paragraph 1 at the conclusion of the inspection and summarized the
scope and findings of the inspection as presented in this report. The
licensee representatives acknowledged their understanding of the
inspection findings.
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ATTACHMENT
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PROCEDURES REVIEWED.
Title
Rev
. Approval
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Date
1012.005 Hot Particle Detection and Control
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1612.002 Access Control of RCAs
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10-22-87
1612.003 Radiation Work Permits
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04-14-89
1612-004 Anti-Cs
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10-16-87
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1622.003 Rad Posting and Entry Requirements
10'
11-16-88
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1622.017 Operation of a Control Point
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03-14-88
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1622.009 Requirements for Reactor Building Power Entry
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12-20-88
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