IR 05000369/1980002
| ML19323B931 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 03/31/1980 |
| From: | Gibson A, Millsap W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19323B923 | List: |
| References | |
| 50-369-80-02, 50-369-80-2, NUDOCS 8005140431 | |
| Download: ML19323B931 (7) | |
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UNITED STATES Oi NUCLEAR REGULATORY COMMISSION
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o 101 MARIETTA ST., N.W., SUITE 3100 o
ATLANTA, GEORGIA 30303
APR -1 1980
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Report No. 50-369/3fi02 Licensee: Duke Powe.r Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire Nuclear Station, Unit 1 Docket No. 50-369 License No. CPPR-83 Inspection at McGuire Nuclear Station, near Charlotte, NC Inspector:
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W. J.
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Date Signed Approved by:
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A. F. Gibson, Section Chief, FFMS Branch Date Signed SUMMARY Inspection on February 25-29, 1980 Areas Inspected This routine, unannounced inspection involved 40 inspector-hours on site in the areas of followup on previous inspection findings, health physics organization, initial and refresher health physics training, health physics procedures, facili-ties, instruments and equipment, and respiratory protection.
Results Of the seven areas inspected, no apparent items of noncompliance or deviations
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DETAILS 1.
Persons Contacted Licnesee Employees
- D. J. Rains, Superintendent of Haintenance
- T. L. McConnell, Superintendent of Technical Services
- W. M. Sample, Technical Services Engineer
- T. J. Keane, Station Health Physicist D. M. McGinnis, Health Physics Supervisor H. F. Cole, Health Physics Supervisor T. E. Parker, Training Supervisor T. McGee, Health Physics Specialist
- Attended exit interview 2.
The inspection scope and findings were summarized on February 29, 1980, with tht>e persons indicated in Paragraph 1 above. A licensee representative made those commitments discussed in paragraphs 5.a, 5.c, and 10.a.
3.
Licensee Action on Previous Inspection Findings (0 pen) Open Item (78-41-03) ALARA Review of the Mixed-Bed Demineralizers a.
and the Resin Batching Tank. This item was first discussed in Region II Report 50-369/76-41 and later discussed in Region II Report 50-369/
79-12.
In response a meeting held on January 5,1979, between NRC officials and Duke Power Company officials, a letter, dated March 21, 1979, from W. O. Parker, Jr., Vice President, Steam Production, Duke Power Company to J. P. O'Railly, Director, NRC Region II delineated responses to specific concerns relating to ALARA considerations of the CVCS demineralizer arrangement. The following lists several of the specific concerns, actions to be taken and the inspectors observations on the state of completion of these commitments:
(1) Concern (a) Description Exposure to personnel during valve maintenance work in the Chemical and Volume Control System (NV), Boron Recycle System (NB), and Boron Thermal Regeneration System (NR)
demineralizer rooms.
(b) Action A cylindrical shield containing lead shot has been erected around the NV and Recycle Evaporator Feed (NB) demineralizers.
Shields have been designed to reduce dose rates to less than
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IR/hr, assuming an undischarged resin bed. No shields have been erected around the NR demineralizers because of much lower radiation levels and the number and flexibility of redundant demineralizers in this system.
(c) Inspector's Review The inspector toured the NV and NB demineralizer rooms and noted that in all cases the required shielding was present; this portion of this item is closed.
(2) Concern (a) Description Exposure to personnel entering demineralizer rooms.
(b) Action Water above the demineralizer resin beds provides adequate shielding to allow personnel access. A grating, designed to support one inch equivalent of lead, is attached to the top of each demineralizer shield. Temporary shielding, if necessary, can be laid on the grating prior to work in the upper areas of each demineralizer room.
(c) Inspector's Review The inspector toured the NV and NB demineralizer rooms and noted that in all cases the required gratings were present; this portion of this item is closed.
(3) Concern (a) Description Exposure to personnel from scatter radiation off of the dtmineralizer room floor.
(b) Action The demineralizer shield's lowest elevation is 18 inches from the floor. Scatter radiation does not contribute significantly.to the total dose. However, the demineralizer shield design allows for the easy erection of temporary shielding.
(c) Inspector's Review During the tour of the demineralizer rooms, the inspector noted that the design features to allow for easy erection of l
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-3-e temporary shielding (essentially hooks) were not present; a licensee representative stated that these hooks are to be added to the shields. This portion of this item remains open.
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(4) Concern (a) Description
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Valve location within demineralizer rooms.
(b) Action Valves will be located outside of the demineralizer shields.
The resin discharge valves on the NV demineralizers will be moved from the rooms into an adjacent valve gallery and appropriately shielded.
(c) Inspector's Review During the tour of the demineralizer rooms the inspector noted no valves inside the shields and also verified that the NV discharge valves had been removed from the demineralizer rooms and shielded; this portion of this item is closed.
(5) Concern (a) Description Exposure to personnel inspecting hydraulic piping restraints in demineralizer rooms.
(b) Action All hydraulic " snubbers" in the NV, NB, and NR demineralizer rooms will be changed to mechanical " snubbers".
(c)
Inspector's Review During the tour of the demineralizer room, the inspector noted hydraulic snubbers in NV demineralizer rooms A and B and NB demineralizer room B; at the time of the exit interview, a licensee representative stated that these snubbers would be removed. This portion of this item remains open.
b.
(Closed) Open Item (78-19-01) Beta Calibration Factor For Portable Survey Instruments. This item was first discussed in Region II Report 50-369/78-19 and later discussed in Region II Report 50-369/78-41.
The inspector verified that the source needed to perform beta calibrations of portable survey instrument was on site and discussed its use with a licensee representative who stated that the appropriate procedures were being revised to include beta calibrations. ~This item is closed.
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(Closed) Open Item (79-12-10) Lint /Trasn Trap For Radwaste Laundry Washers. The inspector verified that this trap is present and a licensee representative stated that it is functional. This item is closed.
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Health Physics Organization
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a.
The inspector reviewed with a licensee representative the present
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organization of the Health Physics Section as well as certain organi-
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zational changes soon to be implemented and compared these against the organizational structure discussed in FSAR section 12.3.1.
The licen-see's organization reflected the general requirements discussed in the FSAR with the exception that the major subunits of the Health Physics Section are presently supervised by Health Physics Supervisors not by Assistant / Associate Health Physicists as the FSAR states; at the time of the exit interview, a licensee representative stated that the FSAR would,be amended to reflect the current organization (80-02-01).
i b.
The inspector discussed with a licensee representative the present staffing level of the Health Physics Section. At present, the section includes 48 members with the senior positions filled and with several openings available for learners and experienced technicians. The inspector had no further questions concerning staffing.
The inspector discussed with a licensee representative the need to c.
define those job functions requiring a " technician" in the sense of Paragraph 4.5.2 of ANSI N18.1-1971, " Standard for Selection and Training of Personnel For Nuclear Power Plants" to which the licensee is committed in FSAR section 13.1.3, " Qualifications of Station Personnel". At the time of the exit interview, a licensee representative stated that this s
matter would be considered and addressed in some manner in the Station Health Physics Manual (80-02-02).
d.
During a previous inspection (see Region II Report No. 50-369/77-9) a licensee representative agreed to revise FSAR section 13.1.3.2 to reflect the qualifications of the then new Station Health Physicist and to provide a policy statement regarding the responsibility and
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authority of the Station Health Physicist in either the health physics
procedures or the Station Directives Manual. The inspector verified that Revision 24 to the FSAR reflected the qualifications of the current Station Health Physicist and that the policy statement con-cerning the responsibility and authority of the Station Health Physicist j
has been included in Section 1 of the Station Health Physics Manual.
The inspector had no further questions concerning these matters.
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Initial and Refresher Health Physics Training
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The inspector discussed with a licensee representative the initial and a.
j refresher health physics training required for individuals who enter the Radiation Control Area. The inspector reviewed the outline of the
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initial training as well as the annual refresher training; the inspector also reviewed examples of the initial training and refresher training examinations given at the end of the training periods. A licensee representative explained the means used by the station to ensure that all persons are given the proper training; this includes the use of individual training records and frequent review of these records to ensure that no one is behind in his training. A licensee representative stated that each person must receive initial health physics training
prior to unescorted access to the restricted area and that each such
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person must receive annual refresher training; the licensee representa-tive further stated that the initial and refresher health physics
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training program has been implenented. The inspector had no further questions concerning this matter.
b.
The inspector chose, from a plant organizational chart, ten persons including persons from each major organizational group and reviewed their health physics training records; in all cases, the records showed up-to-date training. The inspector had no further questions concerning this matter.
7.
Health Physics Procedures The inspector reviewed with a licensee representative the state of comple-tion of those procedures listed in the Health Physics Procedure Index. The inspector noted that almost all procedures have been completed and properly approved, however, a small number are still outstanding. The inspector had no further questions concerning this matter.
8.
Facilities The inspector chose several facilities listed in FSAR section 12.3.2,
" Facilities and Equipment," toured them with a licensee representative and discussed, with this representative, their functioning and state of comple-tion. The following is a listing ce these facilities and a brief statement concerning their state of completion:
First Aid Room - This room is out fitted to accept and treat contaminated a.
patients; it is complete.
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Decontamination Room - This room is complete with the exception of the piping for three ultrasonic sinks (80-02-03).
Change Room and Hot Showers - These facilities are complete; however, c.
a modification has been requested in order to increase their utility (80-02-04).
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Cask Decontamination Facility - This facility is complete.
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Hot Laundry - This facility is complete and functional.
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Instruments and Equipment
The inspector reviewed with a licensee representative the present and a.
ordered inventory of portable radiation detection equipment and noted that the inventory met the requirements for portable instruments stated in section 12.3.2.4 of the FSAR. The portable instruments
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present include the following types: neutron REM meters; thermal and j
fast neutron detectors; low and high range ion chambers; Geiger counters
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to measure exposure rate; Geiger counters to measure beta-gamma contami-nation; extended probe Geiger counters; and alpha scintillators. The inspector discussed with a licensee representative the adequacy of the present inventory for plant start-up; the licensee representative stated that he felt that the present inventory was adequate for this purpose. The inspector had no further questions concerning this matter.
b.
The inspector discussed with a licensee representative the present inventory of portable air sampling equipment; the present inventory consists of 12 grab samplers, 4 continuous air samplers and 2 continuous air monitors. The 16 air samplers are functional and calibration equipment is on site; of the two continuous air monitors, one is not functional and neither is calibrated (80-02-05). The inspector discussed with a licensee representative the use of lapel samplers to better assess the exposure of workers to airborne radioactive material; the licensee representative stated that present plans include the use of lapel samplers but the make had not been decided upon and no purchase orders had been written (80-02-06).
The inspector discussed with a licensee representative the sources c.
presently available to calibrate portable radiation detection instruments.
The licensee representative stated that the 3 Ci Co-60 source, the 1 aCi Co-60 source and 5 Ci Pu-Be neutron source discussed in section 12.3.2.4 of the FSAR are available onsite; the inspector examined the
Tc-99 beta calibration standards and the Pu-239 alpha calibration standards and noted that they are of a type generally used in the i
industry. The inspector had no further questions concerning this matter.
d.
The inspactor discussed with a licensee representative certain aspects of personnel dosimetry. First, the present inventory of self-reading dosimeters was considered. The licensee presently has over 2,000 of these dosimeters most of which are of the 0-500 mR range; however, higher ranged dosimeters are available if needed. Secondly, personnel
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neutron dosimetry was discussed; a licensee representative stated that
present plans called for the use of a neutron REM meter and stay-times to determine personnel neutron exposure. The iaspector had no further questions concerning this matter.
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10.
Respiratory Protection Program The inspector discussed with a licensee representative his respiratory a.
protection program and reviewed it in the light of the guidance provided by the following paragraphs of the Regulatory Position of Regulatory Guide 8.15, " Acceptable Programs For Respiratory Protection":
1, 2, 3, 4(a-h), 5, 6, 7, and 8(a-e). Regarding the above items, the licensee's program is satisfactory with the following exceptions:
(1) Paragraph C.1 of the Regulatory Guide requires a written policy statement on respirator usage from a high management level. The licensee's policy statement is contained in Section 4 of the Ftation Health Physics Manual; however, it does not address all of the subjects required by Paragraph C.1; for instance, it does not address relief from respirator use. At the time of the exit interview, a licensee representative stated that the policy statement would be revised to include all required subjects (80-02-07).
(2) Paragraph C.2 requires that respiratory protective equipment be selected and used such that the average concentration of radioac-tive material in the air that is breathed, during one period of use, does not exceed the values specified in Table 1, Column 1 of Appendix B to 10 CFR 20.
Although this aspect of respirator selection is discussed in Section 4.3 of the Station Health Physics Manual, the inspector stated that the instructions should be strengthened to make the selection process more explicit; in particular, the protection factors for the respirators being used should be listed. At the time of the exit interview, a licensee representative agreed to strengthen those instructions as needed (80-02-Od).
b.
The inspector discusced with a licensee representative his present inventory of respiratory protection equipment as well as the equipment on order. At present, there are 22 SCBAs on site with 8 on order; approximately 140 full face air purifying respirators onsite; and approximately 140 full face airline respirators onsite.
Spare parts and consummable items such as filter cartridges are either onsite or on order. Region II Report 50-369/78-19, paragraph 10.b, states that licensee representative previously stated that there would be approx-a imately 40 self-contained breathing units and 150-200 full face respir-ators for use with supplied air or with filters. The inspector discussed this with a licensee representative who stated that this was an early estimate and that a detailed consideration of respirator needs has shown the above inventory to be adequate; the inspector agreed. The item is closed and the inspector had no further questions.
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