IR 05000313/1979004
| ML19269D501 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/25/1979 |
| From: | Brown G, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19269D489 | List: |
| References | |
| 50-313-79-04, 50-313-79-4, 50-368-79-04, 50-368-79-4, NUDOCS 7906040162 | |
| Download: ML19269D501 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report Nos. 50-313/79-04 Docket Nos. 50-313 50-368/79-04 50-368 NRC Operating Licenses: DPR-51 HPF-6 Facility: Arkansas Nuclear One, Unit 1 and 2 Location: Russellville, Arkansas Inspection Conducted: February 5-9, 1979 Inspector:
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Blaine Murray, Radytion Specialist
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Glen D. Brown, Chief, Fuel Facility and
/ Dats Material Safety Branch Inspection Summary
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Inspection on February 5-9, 1979 (Report Nos. 50-313/79-04 and 50-368/79-04)
Areas Inspected:
(1) ANO-1 Review of licensee's radiation protection program including posting and controls; personnel exposure records; and radiological work permits, (2) ANO-2 Review of licensee's radiation protection and radio-active waste programs during start-up including surveys; posting and control; sample collection, preparation, and analyses; effluent monitoring; test data; and procedures. The inspection involved thirty-eight (38) on-site hours by one (1) NRC inspector.
Results: One (1) item of noncompliance (INFRACTION:
failure to calibrate effluent monitors) was identified. See paragraph _6.b.(2).
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-2-DETAILS
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1.
Persons Contacted (AP&L)
- J. P. O'Hanlon, Station General Manager
- G. H. Miller, Engineering and Technical Support Manager
- B. A. Terwilliger, Operating and Maintenance Manager
- L. Alexander, QC Supervisor R. G. Carrol, Health Physics Supervisor J. L. Bates, Radiochemistry Supervisor D. J. Wagner, Assistant Health Physics Supervisor
- R. T. Elder, Instrument and Control Superintendent
- Denotes those attending the exit interview.
2.
Scope of Inspection The purpose of this inspection was to:
(1) review the radiation protection and radioactive waste systems associated with ANO-2 start-up at 20% power, and (2) review certain aspects of the AN0-1 radiation protection program.
3.
Licensee Action on Previous Inspection Findings (0 pen) Item of noncompliance (50-313) 78/17-01: This item was discussed in IE Inspection Report 50-313 78/17 and involved a radioactive gaseous release that exceeded Technical Specification limits.
The licensee's corrective action included the development of Procedure 1303.110
" Air Sampling for Reactor Building Purge" which has been submitted for approval. This item remains open pending approval of the procedure.
4.
Open Items - This Inspection (50-368) 79/04-01: An area monitor alarm set-point procedure has not been established. See paragraph 5.d.(2).
(50-368) 79/04-02:
Certain radiation levels have been identified that will apparently exceed FSAR design objectives.
See paragraph 5.a.
5.
Radiation Protection - ANO-2 (50-368)
a.
Surveys
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The inspector reviewed survey data regarding ANO-2 start-up. This included a review of Procedure 2.800.15 " Biological Shield Survey Test Procedure" data collected at 20% power. The survey data indicated that the following areas will exceed the FSAR design objectives at 100% power:
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-3-FSAR Zone Projected Dose Location Designation at 100% Power (1) Containment: 405' and 424' IV (<.100 mrem /hr) V1300 mrem /hr levels-general area (2) Containment: 335' and 357' IV (<.100 mrem /hr) evl500 mrem /hr levels-near certain pene-trations (3) Auxiliary Building: 335'
II (< 2.5 mrem /hr)
N100 mrem /hr level-hallway near let down demins.
(4) Turbine Building Extension:
I (< 1.0 mrem /hr) n>10 mrem /hr near main steam line penetrations The licensee stated that the above problem areas will be reviewed with the A/E in order to determine appropriate corrective action.
Action regarding the above items will be reviewed during future inspections.
This item is considered open.
b.
Posting and Controls The inspector reviewed posting and controls to determine compli-ance with radiation protection procedures and 10 CFR 20 require-ments.
No items of noncompliance or deviations were noted.
c.
Procedures and Facilities The inspection examined changes made to the radiation protection procedures and facilities since the previous inspection.
All changes were properly approved and documented.
No items of noncompliance or deviations were identified.
d.
Area Radiation Monitors (ARM)
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2259 122 (1) Calibration The inspector reviewed the calibration records for the ARM's to determine compliance with Technical Specification
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-4-3.3.3.1 and Procedure 2304.28:
" Area Radiation Monitoring System Calibration." The licensee's records indicated that the necessary calibrations have been completed.
No items of noncompliance or deviations were noted.
(2) Alarm Set-Points A formal procedure had not been completed for establishing ARM set-points. Section '".1.4.2 of the FSAR states, in part:
"... Plant health physics personnel will specify the alarm points consistent with radiological safety controls for the area...."
Presently, alarm set-points are arbitrarily set by I&C and/or Operations personnel. The health physics staff has not been involved with review or concurrence regarding present alarm set-points. The licensee stated that a formal alarm set-point procedure will be written. This item is considered open pending completion of the procedure.
6.
Radioactive Waste Systems - ANO-2 (50-368)
a.
Test Procedures and Results The inspector reviewed test procedures and resulting data regarding chemical and radiochemical activities during start-up.
No items of noncompliance or deviations were noted.
b.
Technical Specifications (1)
Primary and Secondary Coolant Systems The inspector reviewed the sampling and analyses require-ments regarding Appendix A Technical Specifications 3.4.7, 3.4.8, and 3.7.1.4.
The licensee's records indicated that the necessary sampling and analyses have been performed.
Test results were within Technical Specification limits.
No items of noncompliance or deviations were noted.
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-5-(2) Radioactive Effluents (Liquid and Gaseous)
a.
Release Limits The inspector reviewed the sampling, analyses, and release limits to determine compliance with the following Appendix B Technical Specifications:
Liquid Technical Specification 2.2.1.1 Technical Specification 2.2.1.2 Techaical Specification 2.2.1.3 Technical Specification 2.2.1.4 Technical Specification 2.2.1.5 Technical Specification 2.2.1.6 Technical Specification 2.2.1.1 (Monitoring Requirements)
Technical Specification 2.2.1.2 (Monitoring Requirements)
Technical Specification 2.2.1.3 (Manitoring Requirements)
Technical Specification 2.2.1.5 (Monitoring Requirements)
Gaseous Technical Specification 2.2.2.1 Technical Specification 2.2.2.2 Technical Specification 2.2.2.3 Technical Specification 2.2.2.4 Technical Specification 2.2.2.5 Technical Specification 2.2.2.6 Technical Specification 2.2.2.7 Technical Specification 2.2.2.1 (Monitoring Requirements)
Technical Specification 2.2.2.3 (Monitoring Requirements)
Technical Specification 2.2.2.4 (Monitoring ' Requirements)
b.
Monitoring Instruments The inspector reviewed the test and calibration require-ments contained in the monitoring requirements for Appendix B Technical Specifications 2.2.1.4, 2.2.2.2, and 2.2.2.5.
Liquid: Technical Specification 2.2.1.4 states:
"The liquid effluent radiation monitors shall be calibrated at least quarterly by means of a known radioactive source.
Each monitor shall be tested monthly and when discharging checked daily."
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-6-Gaseous: Technical Specification 2.2.2.2 states:
"All waste gas monitors shall be calibrated at least quarterly by means of a known radioactive source.
Each monitor shall have an instrument channel test at least monthly and when discharging checked at least daily."
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Records indicated that the channel tests and release checks were conducted as specified 'in Procedure 2304.26
" Process Monitoring System Test," Liquid Waste Release Permit, and Gaseous Waste Permit procedures.
However, calibrations have not been completed as required by Technical Specifications 2.2.1.4, 2.2.2.2, and Proce-dure 2304.27 " Process Monitoring System Calibration."
The following tables show the calibration status for the various effluent monitors:
Liquid Effluent Monitors Calibration RES-2330_"BMS/WMS Liquid Discharge" Not Completed RES-4423 "Regenative Waste Outlet" Not Completed RES-1525 " Fuel Pool Heat Exchanger" Not Completed RES-1519-1 "SW Heat Exchanger" Not Completed RES-1513-2 "SW Heat Exchanger" Not Completed RES-1453 " Shut down Heat Exchanger" Not Completed RES-1456 " Shut down Heat Exchanger" Not Completed Gaseous Effluent Monitors Calibration RES-8233 " Containment Purge" November 16, 1978 RES-8542 " Radiation Waste Area Vent" Not Completed RES-8540 " Fuel Handling Area Vent" Not Completed RES-7828 " Auxiliary Building Exit Vent" Not Completed RES-8845_ " Penetration Room (North)"
Not Completed RES-8846 " Penetration Room (South)"
Not Completed RES-8231-1A "H Purge" November 13, 1978 RES-8271-2B "H Purge" November 15, 1978 As the above data indicates, several monitors have not been calibrated.
Failure to perform the required cali-brations is an apparent item of noncompliance.
7.
Exit Interview
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At the conclusion of the inspection on February 9,1979, the inspection findings were discussed with the individuals identified in paragraph 1.
The inspector sumarized the purpose and scope of the inspection. The apparent item of noncompliance and the two (2) open items were reviewed.
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