IR 05000400/1985045
| ML18003B188 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/03/1985 |
| From: | Hosey C, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18003B187 | List: |
| References | |
| 50-400-85-45, NUDOCS 8512230529 | |
| Download: ML18003B188 (8) | |
Text
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~O W~*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 OEC 09 $85 Report No.:
50-400/85-45 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400, Facility Name:
Harris
License No.:
CPPR-158 Inspection Conducted:
ovember 12-15, 1985 Inspector:
.
L. Trou Appr ed by:
. Hosey, Section Chief Division of Radiation Safety and Safeguards D te Signed igned e
SUMMARY Scope:
This routine, unannounced inspection entailed 22 inspector-hours on site in the area of radiation protection including management controls, training and qualification, ALARA facilities, equipment and IE Ci rculars and Notices.
Results:
Of the areas inspected, no violations or deviations were identified.
8512230529 851209 PDR ADOCK 05000400
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J.
L. Harness, Assistant Plant General Manager
- J.
R. Sipp, Manager, Environment and Radiation Control
~D.
L. Tibbitts, Director, Regulatory Compliance
'J.
W. McDuffee, Radiation Control Supervisor C. Wright, Specialist, Regulatory Compliance
- P.
W. Howard, Senior, Specialist, Regulatory Compliance Other licensee employees contacted included radiation control foreman and technicians.
NRC Resident Inspectors S.
P. Burris, Resident Inspector Operations
~Attended exit interview Exit Interview The inspection scope and findings were summarized on November 15, 1985, with those persons indicated in Paragraph
above.
Licensee representatives expressed no dissenting opinions on the findings.
The inspector described the areas inspected and discussed in detail the inspection findings.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
Organization and Management Controls (83522)
'a ~
The inspector reviewed the assignment of responsibilities for the management and implementation of radiation control, chemistry and environmental controls programs.
Implementation of the programs at the plant is assigned to the Manager, Environmental and Radiation Control (E&RC).
Other groups in the corporate structure are assigned responsibilities for assistance, review and offsite programs.
The responsibilities of Manager, E&RC and the E&RC organization are consistent with FSAR Section 12.5. Responsibilities for the programs are assigned in various documents at both the corporate and plant level.
At the corporate level, the relevant documents are the
"Conduct of Nuclear Operations Manual,"
which was approved at the Executive Vice President level, and the
"Radiation Control and Protection Manual," which was also approved at the Executive Vice President level.
The
"Radiation Control and Protection Manual" states that the Manager, E&RC is responsible for the health physics program.
The
"Conduct of Nuclear Operations Manual" contains the Corporate Health Physics Policy Statement, which was approved by the company President, and the Corporate ALARA Program.
The "Radiation Control and Protection Manual" includes the Respiratory Policy Statment.
At the plant level, the programs are implemented by a
series of procedures contained in the Plant Operations Manual, and include Administrative Procedures (AP), Plant Program Procedures (PLP),
Plant General Orders (PGO),
E&RC Procedures (ERC),
and Health Physics (HPP),
Chemistry (CRC) and Dosimetry (DP) Procedures.
The APs and PLPs assign responsibilities to members of the plant staff, consistent with the corporate documents.
No violations or deviations were identified.
5.
Training and gualifications (83523)
a.
FSAR Section 12.5. 1.3 states that the Manager, Environmental and Radiation Control, is the Radiation Protection Manager as outlined in Regulatory Guide 8.8.
FSAR Section 12.5. 1.4 states that the Radiation Protection Manager will satisfy the qualifications in Regulatory Guide 1.8.
FSAR Table 1.8-1 states that the Manager, Environmental and Radiation Control shall meet the qualifications of Section 4.4.4 of ANSI.ANS 3. 1-September 1979 (Draft).
The educational and experience
. requirements of these two documents are equal.
The inspector reviewed the resume in FSAR, Table 13. 1.3-3 and a
more comprehensive resume on file at the plant, and discussed various aspects of his experience with the Manager, E&RC.
The inspector determined that the Manager, E&RC meets the qualifications of the Radiation Protection Manager as specified in the FSAR.
b.
The inspector reviewed the qualifications of four radiation control foremen and nine technicians (RC technician III) against the requirements of ANSI/ANS-3. 1
-
September 1979 (Draft).
No discrepancies or deficiencies were identified.
C.
The inspector determined that the licensee has issued procedures for the training and qualification of radiation control technicians (TI-114)
and for the on-the-job training and requalification of the technicians (AP-506).
The licensee has also issued a procedure for the training and qualification of contractor technicians (ERC-104).
The inspector reviewed a
computerized record showing the status of
training, and procedur e qual if ication for staf f members and technicians.
No violations or deviations were identified.
6.
ALARA (83528)
a
~
The corporate program relating to the ALARA program is contained in the
"Conduct of Nuclear Operations Manual" with the policy for implementing the ALARA Program in the "Radiation Control and Protection Manual."
Both of these manuals were approved at the Executive Vice President level.
b.
The
"Radiation Control and Protection Manual" establishes the requirements for an ALARA committee sets the criteria for when a
multidisciplinary review is required for ALARA purposes, and specifies the dissemination of ALARA information.
The ALARA program for the plant is specified in PLP-501,
"ALARA Program."
The assignment of the ALARA subcommittee, the ALARA improvement program, and ALARA job evaluations are specified in Procedures AP-502, AP-509, and AP-514, respectively.
These procedures designate the membership of the committee, specify the review criteria (including pre-job estimates and post-job reviews)
and evaluation and resolution of ALARA problem reports/suggestions submitted by staff members or workers.
No violations or deviations were identified.
7 ~
Facilities (83527)
FSAR Section 12.5.2 describes the facilities to be used in conjunction with the radiation protection program.
The inspector toured the facilities with licensee representatives and reviewed the status of the following facilities:
(1)
portable instrument calibration The facility is functional and has two Cs-137 calibration systems.
Other calibration sources are being obtained.
A licensee representative stated that a neutron calibration source would not be procured; neutron survey instruments will be sent to the vendor for calibration.
(2)
equipment decontamination Decontamination equipment has been received and is in place.
However, the equipment decontamination facility will be reolcated to a
new location to service the hot machine shop.
This facility is incomplete.
(3)
respiratory protection device cleaning The facility for cleaning, sanitizing and surveying respiratory protection equipment has been designated but the equipment has not been installed.
This facility is incomplet (4)
laundry - Washers and dryers have been received and are in place.
However, the equipment has not been connected.
This facility is incomplete.
(5) first aid room - First aid facilities for treating potentially contaminated patients are being relocated to a
new location.
This facility is incomplete.
(6)
change room and personnel decontamination
- Separate facilities for men and women were provided and complete.
However, some modifications will be made as the result of changes to other adjoining facilities.
(7)
respiratory fitting A fit-testing booth and associated equipment to perform quantitative testing is installed and operable.
The licensee is conducting respirator fitting for employees.
(8)
Body Burden Analyzer The facility is set up and includes two Body Burden Analyzer chairs, each with a computer-analyzer.
The licensee is conducting baseline analyses of employees at present.
b.
In reviewing the control point to the Radiation Control Area (RCA),
a licensee representative informed the inspector that changes were planned in the area to improve the traffic flow and control at the RCA entrance.
These changes will involve relocation of walls and doors.
The inspector acknowledged but emphasized to licensee management that these changes need to be completed prior to establishing the RCA in anticipation of fuel loading to minimize both confusion in the traffic flow and cleanliness problems with the RCA.
This was acknowledged by licensee management.
As part of the respiratory protection program, air-supplied devices may be used.
A licensee representative informed the inspector that the breathing air connections and manifolds and air hoses would be equipped with distinctive fittings which are not used anywhere in the plant.
This should preclude connections of other equipment or tools to breathing air systems.
The fittings are onsite and will be installed at a future date.
The inspector had no questions at this time.
No violations or deviations were identified.
Equipment (83525, 83526, 83527)
The licensee has a partial supply of devices and accessories onsite for the respiratory protection program.
These include Self-Contain Breathing Apparatus (SCBA),
spare air cylinders, different models of respirators, air supply hoses, and air manifold assemblies.
Additional quantities are on order or will be procured, including air-supplied hoods and respirator filters.
A licensee representative stated that the projected inventory would be available prior to fuel loading.
The
I
inspector reviewed the projected inventory and had no further questions at thi s time.
b.
As SCBAs will be used during routine operations and emergency conditions, it will be necessary to periodically recharge the air cylinders.
A licensee representative informed the inspector that a
compressor capable of recharging the cylinders with respirable quality air had been procured but was not yet installed.
A suitable location will be selected so the intake is fr ee of dust and fumes, and where the compressor can be operated under accident conditions, if necessary.
The location, installation and operation of the breathing air compressor will be reviewed during subsequent inspections.
FSAR Section 12.5.2 discusses equipment and instrumentation for air sampling and radiation surveys.
The inspector reviewed the inventory on-hand and discussed planned inventory levels with licensee representatives.
The general types of instruments described in the FSAR were on-hand or being procured, with quantities generally in excess of the levels listed in the FSAR.
The final inventory will be reviewed later to determine that adequate levels are established for fuel loading'
d.
The inspector reviewed the inventory of temporary shielding materials, such as lead bricks, lead sheets and lead blankets.
These materials are onsite.
Additionally, the procedures have been prepared and issued for the installation of temporary (HPP-015).
e.
The licensee has ordered temporary ventilation units which will provide filtered exhaust from radiological areas.
This units have not been received.
No violations or deviations were identified.
9.
Circular s and Information Notices IE Circular 80-14 dealt with the radioactive contamination of plant demineralized water systems due to cross-connections with radioactive plant systems.
The inspector discussed the circular with plant personnel and verified that it had been received and reviewed.
A licensee representative informed the inspector that a Plant General Order had been drafted dealing with the circular but possible system modifications were still being evaluated.
Resolution of the actions will be completed prior to fuel loading.
This wi 1 1 be reviewed during a subsequent inspection
.
(IFI 85-45-01).
No violations or deviations were identifie ~
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