ML19305A339

Forwards LER 79-002/01T-0

ML19305A339
Person / Time
Site:	Arkansas Nuclear
Issue date:	03/05/1979
From:	Rueter D ARKANSAS POWER & LIGHT CO.
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19305A341	List: ML19305A339 ML19305A342
References
1-039-1, 1-39-1, NUDOCS 7903130372
Download: ML19305A339 (2)

Text

• H EL PIN G BUILD ARKANSAS ARK ANS AS POWER & LIGHT COMPANY P.O. BOX 551

• LITTLE ROCK. ARKANSAS 72203

• C501) 371-4101 March 5, 1979 OONALD A. RUFTER DIRECTOR TECHN? CAL AND ENVIRONMENTAL SERVICES 1-039-1 Mr. K. V. Seyfrit, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011

Subject:

Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Reportable Occurrence Report No. 50-313/79-002 (File: 0520)

Gentlemen:

In accordance with Arkansas Nuclear One-Unit 1 Technical Specification 6.12.3.1, we have attached the subject report concerning the failure to perform a surveillance test on Nuclear Instrumentation within the prescribed time.

This Reportable Occurrence Report was changed from a 30 day report to a 14 day report and is being submitted late with the concurrence of the on-site inspector.

Very truly yours, w

Donald A. Rueter DAR:REI:tw Attachment cc: Mr. John G. Davis, Acting Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 79031303 9 1.x ...,~ a. ,~ v e s ro n own a o ( , unusea vioote sour- uTiurms sysrau

Reportable Occurrence Report No. 50-313/79-002

10. Corrective Action:

Power escalation was stopped at approximately 75% reactor power at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on 2/7/79. At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> the Nuclear Instrumentation calibration was performed per OP 1304.32, adjusting the indicated power level up approximately 2.5%. Occurrence was discussed with the Shift Supervisors and the I 6 C Supervisors.

11. Failure Data:

This occurrence is similar to 50-313/78-31, 78-14, 77-16, 77-11, 76-31, 76-23 and 76-19.

Reportable Occurrence Report No. 50-313/79-002

8. Designation of Apparent Cause of Occurrence:

Design Procedure bbnufacture Unusual Service Condition

. Including Environmental Installation /

Construction Component Failure (See Failure Data)

Operator X Other (specify)

9. Analysis of Occurrence:

Technical Specification 4.1 Table 4.1-1 requires that the Nuclear Instrumentation be calibrated every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during non-steady state operation. The calibration was required at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on 2/5/79. The limiting reactor power level used by operations for control is the highest as indicated by Heat Balance or NI indica-tion. The Nuclear Instrumentation is calibrated to agree with the plant heat balance. Therefore, there was no hazard to the health and safety of the public.

1. Reportable Occurrence Report No. 50-313/79-002 '

2. Report Date: 3/05/79 3. Occurrence Date: 2/5/79 4 Facility: Arkansas Nuclear One - Unit One Russellville, Arkansas 72801

5. Identification of Occurrence:

The failure to perform a Nuclear Instrumentation calibration within the specification limits.

6. Conditions Prior to Occurrence:

Steady-State Power Reactor Power MWth Hot Standby Net Output MWe Cold Shutdown Percent of Full Power  %

Refueling Shutdown __ Load Changes During Routine Power Operation x Routine Startup x Operation Routine Shutdown Operation Other (specify)

7. Description of Occurrence:

The unit was in startup operation following a maintenance outage.

Initial criticality was achieved at 2012 on 2/4/79. Power operation was achieved by 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> and was increased to 10% reactor power by 0000 on 2/5/79. This level was maintained until 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on 2/6/79 with the exception of a five hour period when power was increased to a

- maximum of 40% reactor power for turbine generator vibration readings.

At 1645 on 2/7/79, following a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hold at the power level cutoff of 72%, the power increase to 90% was initiated. During the Shift Supervisor's Log review, following an operator shift change, it was discovered T.S. 4.1 Tablethat the NI calibration was not performed as required by 4.1-1.