IR 05000324/1979012
| ML19274E979 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/09/1979 |
| From: | Gibson A, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19274E977 | List: |
| References | |
| 50-324-79-12, 50-325-79-12, NUDOCS 7906070058 | |
| Download: ML19274E979 (6) | |
Text
e UNITED STAT 8.s g(pn na%q'o,,
NUCLEAR REGULATORY COMMISSION REGION 11
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o 101 MARIETTA STREET, N.W.
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ATLANTA, GEORGI A :s0303
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o, Report Nos. 50-324/79-12 and 50-325/79-12 Licensee: Carolina Power and Light Company 411 Fayetteville Street Raleigh, North Carolina 27602 Docket Nos. 50-324 and 50-325 License Nos. DPR-62 and DPR-71 i O:te ear Southport, North Carolina Inspection at Bruns 7
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7 77 Inspector:
G. L.'Trou)/ '
Date Signed 2+
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App ved by:
he d-A'T. Gityi,'Section Chief, FF&MS Branch Date Signed g
SUMMARY Inspection on March 18-22, 1979.
Areas Inspected This routine, un;...m cad inspection involved 32 inspector-hours onsite in the areas of tF refueling / maintenance health physics program and radioactive waste managennt program including respiratory protection, posting and control, surveys, exposure control, housekeeping, ef fluent monitor testing and followup on previously identified items.
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Results Of the seven areas inspected, no apparent items of noncompliance or deviations were identified in seven arcas.
7906070OTS,
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s DETAILS 1.
Persons Contacted Licensee Employees A. C. Tollison, Jr., Plant Manager
- J. M. Brown, Superintendent, Operations and Maintenance W. M. Tucker, Superintendent, Technical and Administrative D. N. Allen, Quality Assurance Supervisor
- J. A. Padgett, Environmental and Radiation Control Supervisor
- S. E. Thorndyke, Operations Supervisor R. L. Mayton, Director, Corporate Health Physics
- L. F. Tripp, Health Physicist J. L. Kiser, Engineer R. P. Cross, Engineer J. M. Petitgout, Senior Nuclear Generating Specialist J. L. McKnight, RC&T Foreman J. B. Cook, RC&T Foreman G. C. McCoy, RC&T Foreman Other licensee employees contacted included construction craf tsmen, technicians, and operators.
Other Organizations G. D. Leonard, Vice President (Site Coordinator), IRM, Inc.
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on March 22, 1979 with those persons indicated in Paragraph I above. Mr. Padgett and
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Mr. Tripp acknowledged the inspector's comments concerning the house-keeping around several radiation control points.
Mr. Brown and Mr. Padgett acknowledged the inspector's comments concerning the radiation protection program in general.
3.
Licensee Action on Previous Inspection Findings (Closed) Open Item (324/78-31-01) Unit 2 Turbine Building Exhaust Filter Charcoal Spill. The charcoal support has been repaired and the HEPA filters have been replaced. This item is closed.
(Closed) Noncompliance (78-18-01) Locking of High Radiation Doors.
The correction actions stated in CP&L letter serial:
GD-78-2785 of October 17, 1978 were verified to have been done (parngraph 7).
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-2-(Closed) Open Item (324/79-04-03; 325/79-03-03) Turbine Buildings Exhaust Flow Rates.
Revision 2 of RC&T Procedure 0007, " Stack and Building Vent Radioactive Gaseous Release Set Points," was issued to correct the flow rate for the Unit 1 Turbine Building exhaust monitor.
The monitor set points for the Turbine and Reactor Buildings monitors were also revised due to change in flow rates; monitor settings are being revised. This item is closed.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Respiratory Protection a.
The inspector reviewed the records and observed practices to verify compliance with 10 CFR 20.103. The inspector selected several individuals from the respirator issue log and verified by records review that the individuals were medically qualified to wear respirators, had completed the requisite training and satis-factorily fitted with the type of respirator which they had been issued. The inspector also reviewed logs and survey records to verify that the respirators which had been issued by serial number had been returned, had been cleaned and decontaminated and surveyed for contamination prior to being reissued.
In those cases where respirators or respirator parts had not been adequately decontaminated, the survey records indicated that they had been recleaned and resurveyed prior to being issued. The inspector had no further questions.
b.
A licensee representative informed the inspector that, in many cases, respirators have been specified based on a potential for airborne radioactivity rather than because of high airborne levels. The inspector reviewed the airborne surveys for areas for which respirators had been specified and noted that the levels were less than MPC; this has resulted in persons using
'espirators being less than the action levels of 10 CFR 20.103
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9, The inspector also observed that temporary exhaust
- ation was installed in work areas such as in the reactor 91 Unit 2 to reduce potential airborne levels.
c.
,O, power reactor facility had identified a condition where a
tvice air system, which is used for breathing air with sieline respirators, had become radioactively contaminated due to leakage from interconnected contaminated fluid systems. The licensee has issued RC&T Instruction 7018, " Airborne Radioactivity
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Analysis of Service Air" to sample the air prior to its use for breathing air and periodically while in use.
The inspector reviewed the radioactivity sample recor6, as well as the sample
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t-3-records to verify that the air quality meets Grade "D" levels, and verified that the air met the requirements.
A licensee representative discussed the contamination problem with the inspector and stated that the licensee would review both the service air and instrument air systems to identify areas where contamination was possible and initiate corrective actions.
6.
Housekeeping and Contamination Control During tours of various areas of the plants, the inspector noted instances where the housekeeping did not appear to be consistent with good contamination control practices. In two areas (the entrances to the Unit 2 condenser room and the Unit 2 Turbine Building breezeway),
anti-contamination clothing, poly bags and assorted paper were observed strewn around the areas. A licensee representative acknowledged these conditions and stated that efforts would be made to improve the condi-tions and assure that good contamination control and work practices were observed.
7.
Locking of High Radiation Area Doors This item was originally identified in RII Report Nos. 50-324/78-18, a.
50-325/78-18, paragraph 4 as an item of noncompliance in that a high radiation area was not locked as required by Technical Specification 6.12.2 when the dose rate was greater than 1,000 mrem /hr. Additional examples were discussed in RII Report Nos.
50-324/78-23,50-325/78-20, paragraph 4.
The licensee's corrective actions are discussed in CP&L letter serial:
GD-78-2785 of October 17, 1978; the letter stated that corrective actions would be completed by March 1,1979.
b.
The inspector observed several doors in the plants which provide access to high radiation areas when the units are at power and verified that the corrective actions had been completed. The inspector also discussed the corrective actions with licensee representatives and reviewed the status of the corrective actions.
A licensee representative stated that the actions were complete except for one door. This door has not had the lock changed due to work being performed to modify the wall configuration; the licensee representative stated that the lock would be changed during the modification. The inspector informed licensee manage-ment that this item was closed for record purposes and the final door would be verified during a subsequent inspection.
8.
Surveys 10 CFR 20.201(b) requires that the licensee shall make such surveys as necessary to comply with the regulations of 10 CFR 20. The inspector
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t-4-reviewed records of airborne, radiation and contamination surveys performed at specific work areas and in general plant areas to demon-strate compliance with 10 CFR 20 and the licensee's procedures.
Surveys were also taken for "before and after" conditions when temporary shielding was installed or removal of equipment occurred. The inspector noted that certain of the surveys required by RC&T Instructions 7002, 7004, 7005 were not being performed. A licensee representative stated that these were gener.nl surveys for operation and that more frequent surveys were being performed in some areas due to outage work. The inspector had no further questions.
9.
Posting and Control a.
The inspector toured various areas in the Turbine Buildings, Reactor Buildings and outside areas to observe the posting and control of areas and materials.
The inspector took radiation dose rate measurements with an NRC instrument to verify that radiation areas were identified and posted in accordance with 10 CFR 20.203(b) and that high radiation areas were identified and posted in accordance with 10 CFR 20.203(c) and Technical Specifi-cations 6.12.2.
No unidentified or improperly posted areas were identified.
b.
The inspector reviewed randomly selected contamination surveys taken during the month of March for various areas in the plants and determined that contaminated areas were identified and posted in accordance with section 6.3 of the Radiation Control and Protection Manual. The inspector also observed the posting of contaminated areas and compared the posting of selected areas with the contaminated areas identified in the surveys.
The inspector had no further questions.
c.
The inspector observed the storage of radioactive materials in various areas of the plant. Waste was collected and stored in drums labeled as radioactive material; bags or specific pieces of equipment were stored in areas posted as radioactive material areas. The inspector took radiation dose rate measurements on several bags of waste which may have been radioactive waste outside of posted storage areas; no readings above background levels were identified. The inspector had no further questions.
d.
10 CFR 20.207 specified the requirements for storage of licensed radioactive material in unrestricted areas. Licensee representa-tives informed the inspector that radioactive materials were stored in outside areas of the restricted area but that no licensed radioactive material was stored in unrestricted areas. During tours of the plant areas, the inspector observed no radioactive material stored outside of restricted areas; the inspector had no further questions.
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I L-5-10.
Testing of Standby Gas Treatment System Filters and Adsorbers As discussed in RIl Report Nos. 50-324/78-31; 50-325/78-33, paragraph 6.b, the test results for the standby Gas Treatment System heater were being held pending clarification of Technical Specification 4.6.6.
Amendment 44 to the Technical Specification revised the testing require-ment for the heater. The inspector reviewed the test results for the SBGT heaters for both units conducted on February 10, 1979 and determined that the test results met the Technical Specifications requirements and that the results were reviewed and approved in accordance with the licensee's procedures. The inspector had no further questions.
11. Effluent Monitor Testing Environmental Technical Specifications 3.5.1. f and 3.5.2.d require that liquid and gaseous effluent monitors, respectively, shall be calibrated at least quarterly and functionally tested at least monthly.
The inspector re n wed the calibrations for 4th quarter, 1978 and 1st quarter, 1979 and Je monthly tests for October-December, 1978 and January-March, 1979 and verified that the calibrations and functional tests were performed at the required frequencies or greater frequencies.
The inspector had no further questions.