IR 05000313/1979026
| ML19294B183 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/04/1980 |
| From: | Spangler R, Westerman T, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19294B180 | List: |
| References | |
| 50-313-79-26, 50-368-79-25, NUDOCS 8002270486 | |
| Download: ML19294B183 (6) | |
Text
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND EhTORCEMENT
REGION IV
Report Nos. 50-313/79-26 50-368/79-25 Docket No. 50-313 License No. DPR-51 50-363 hTF-6 Licensee: Arkansas Power and Light Company P. O. Box 551 Little Rock, Arkansas 72203 Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2 Inspection At: ANO Site, Russellville, Arkansas Inspection Conducted: December 17-20, 1979
//[/[U Inspectors:
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T. 'G. Spatygler,' Reactor Inspector
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L. A. Yandell, Reactor Inspector Date Revieued By:
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T. F. Westerman, Chief, Reactor Projects Section
'Date Inspection Su= mary Inspection Conducted during the period of December 17-20, 1979 (Report No. 50-313/79-26)
Areas Inspected: Routine, unannounced inspection of previously identified items, calibration of license specified instrumentation and calibration of general safety-related instrumentation. The inspection involved 39 inspector-hours on-site by two (2) NRC inspectors.
Results: Within the three areas inspected, no items of noncompliance or deviation were identified.
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Inspection conducted during the period of December 17-20, 1979 (Report No. 50-368/79-25)
Areas Inspected:
Routine, unannounced inspection of previously identified items, calibration of license specified instrumentation and calibration of general safety-related instrumentation. The inspection involved 26 inspector-hours on-site by two (2) NRC inspectors.
Results: Within the three areas inspected no items of noncompliance or deviation were identifie.
DETAILS 1.
Persons Contacted Arkansas Power & Light Company Employees J. P. O'Hanlon, ANO Plant Manager B. A. Baker, Operations Superintendent T. N. Cogburn, Nuclear Engineer E. C. Ewing, Production Startup Supervisor P. Jones, Maintenance Supervisor B. A. Terwilliger, Operations and Maintenance Manager R. Elder, I&C Supervisor 2.
Inspection Follow-up on Previously Identified Items (Closed) Open Item 368/7906-01 (Inspection Report 79-06, paragraph 12):
Review of Design Change Packages for " Millstone Syndrome" Problem:
The time delay setting for relays 162/309-1 and 162/409-1 was corrected on March 12, 1979 under job order 2-5832-79-1.
A sample of fourteen additional relays installed for this design change were found to have been set correctly.
The inspector therefore considers this item resolved.
3.
Calibration of Instrumentation (Units 1 and 2)
The inspector selected a sample of various instruments to determine that the frequency of calibration required by each license had been met.
In addition, these calibrations where reviewed to determine:
a.
That they were performed using approved procedures; b.
That the procedure setpoints agree with the applicable technical specifications; and c.
That selected test equipment utilized by the procedure had been properly calibrated.
The calibration procedures shown below were reviewed for Unit 1.
Procedure Title Item No, in Table 4.1 of Technical Specification,'irequency 1304.41 Paragraph 7.8 RCS 7/ Refueling (R)
Channel A Temp Calibration
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1304.26 Process Radiation 28/ Quarterly Monitors 1304.41 Paragraph 7.9 RCS 8/R Channel A Pressure 1304.11 Makeup Tank Level 27/R 1304.24 Reactor Building 46/R Sump Level 1304.73 Steamline Break 32/R Instrument and Control System No items of noncompliance or deviations were identified.
For Unit 2 only, those calibrations with a specified interval less than
" Refueling" were sampled.
The inspector detere.ned that the d
operation logs contain entries to verify on a daily basis (above 15% Power) that the CPC delta T power and Nuclear Power agree with the computed heat balance and to verify each shift (above 70%
Power) that CPC calculated RCS flow agrees with flow calculated from the heat balance.
In addition, procedure 2304.100 was reviewed as noted above. This procedure verifies the stability of the linear power subchannel gains for excore nuclear instrumentation.
No items of noncompliance or deviation were found.
4.
Calibration of Safety and License Related Instrumentation (Units 1 and 2)
The inspector determined that a calibration program was established and implemented for safety or license-related instrumentation having no license specified frequency of calibratien.
In addition, a sample of these calibrations were selected for review to determine:
a.
That they were performed using approved procedures; b.
That the procedures appear to be technically acceptable; and c.
That selected test equipment utilized by the procedure had been properly calibrated.
The following Unit 1 instrumentation was selected for review:
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.
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Pressurizer Level (1304.22)
Boric Acid Tank Level and Temperature (1304.18)
Diesel Generator Fuel Oil Sa=pling (1605.42;.44)
Diesel Generator Air Compressor Auto Start Switches (1303.39)
Emergency Feedwater Flow and Pressure (1304.05)
CRDM Position Indication (1304.36)
Containment Hydrogen Concentration Instrumentation D 20'.30)
The selected instrumentation for Unit 2 was:
Pressurizer Level (2103.13)
Boric Acid Addition Tank Level and Temperature Diesel Generator Fuel Oil Sampling Diesel Generator Air Compressor Auto Start Switches Emergency Feedwater Flow and Pressure CRA Position Indication Reactor Building Hydrogen Concentration The inspector determined that the calibration of the above instrumentation is administratively controlled by either a refueling frequency surveillance test procedure or the Preventive Maintenance (PM) Program.
Indeed, almost all Unit 1 instrumentation required to determine compliance with license Limiting Conditions of Operation are included in a refueling surveillance procedure.
On the other hand, most of this type of Unit 2 instrumentation is scheduled and performed as part of the FM program.
The inspector found that the plant instrumentation and controls group was several months or more behind on performing scheduled Preventative Maintenance activities.
For example, the following instrumentation is scheduled for annual calibration under the FM Program:
Instrument No. and Name Date Last Calibrated 2LT4625 Pressurizer Level April 18, 1978 2 LIT 4906 Boric Acid Addition Tank Level November 17, 1978
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2 TIC 4906, 4907, Boric Acid Addition June 22, 1977 (all)
4908, 4912 Tank Temperatures 2PSHL2803 D. G. Air Compressor October 20, 1978 Start (Unit 2)
PSL5231, 5232, D. G. Air Compressor September 26, 1978, 5233 Start (Unit 1)
October 2, 1978, October 2, 1978 2FT-0713, 0717 Emergency F.W. Flow October 13, 1978 0718 September 22, 1978 October 13, 1978 2PIS-0789,0795 Emergency F.W. Suction October 4, 1977; Pressure September 9, 1978 2PT-0713 Emergency F.W. Discharge January 27, 1978 Pressure These instruments range from one month to over one year overdue for calibration.
The inspector was not able to determine during this inspection either the licensee's progress in correcting this backlog, nor the estimated time required for this effort.
Pending further review, this item will remain as an unresolved item (368/7925-1).
No further findings were identified in this area.
5.
Unresolved Item Unresolved items are catters about which more information is required to ascertain whether they are acceptable, items of noncompliance or deviations.
The unresolved item identified during this inspection is described in paragraph 4.
6.
Exit Interview An exit meeting was conducted on December 20, 1979 with Mr. J. P. O'Hanlon (Plant Manager) and other members of his staff.