IR 05000313/1988014

Insp Repts 50-313/88-14 & 50-368/88-14 on 880502-06.No Violations or Deviations Noted.Major Areas Inspected:Unit 2 Startup Testing from Refueling Outage 2R6

ML20155B031
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/31/1988
From:	Kelley D, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20155B024	List: IR 05000313/1988014 ML20155B020
References
50-313-88-14, 50-368-88-14, NUDOCS 8806130060
Download: ML20155B031 (5)

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION l REGION I ;

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NRC Inspection Report: 50-313/88-14 Operating Licenses: DPR-51 ;

a 50-368/88-14 NPF-6 :

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Dockets: 50-313 50-368

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Licensee: Arkansas Power & Light Company (AP&L)

j P.O. Box 551 ,

Little Rock, Arkansas. 72203  ;

Facility Name: Arkansas Nuclear One (ANO), Units 1 and 2 Inspectior At: ANO, Russelville, Arkansas Inspection Conducted: May 2-6, 1988 j  !

Inspector: u,f ad s:r[ W [

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D. T. Kelle9, React)r Inipeptor, Test Programs Da'te'

Section, Division of ReaMor Safety  ;

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Accompanying  !

, Personnel: R. A. Azua, Reactor Inspector, Test Programs

Section, Division of Reactor Safety j 1 i Approved

#4 f/

l W. C. Seidle Chief, Test Programs Section Date

Division of Reactor Safety

Inspection Summary

Inspection Conducted May 2-6, 1988 (Report 50-313/88-14)

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Areas Inspected: No inspection of Unit 1 was conducted

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i Results: Not applicable.

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1 Inspection Conducted May 2-6, 1988 (Report 50-368/88-14)  !

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Areas Inspected: Routine, unannounced inspection of the ANO, Unit 2 startup i testing from Refueling Outage 2R l l l l Results: Within the area inspected, no violations or deviations were identifie I i l i l 2 8806130060 880602 l PDR ADOCK 05000313 j Q DCD j

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DETAILS Persons Contacted AP&L

• S. M. Quennoz, Plant General Manager

• D. R. Howard, Licensing Manager

• R. Lane, Engineering Manager

• Smith, Superintendent, Reactor Engineer

• L. W. Humphrey, General Manager, Nuclear Quality

• P. Michalk, Licensing Specialist

• D. Lomax, Plant Licensing Supervisor NRC

• Johnson, Senior Resident Inspector

• Denotes those present at the exit intervie The NRC inspectors also contacted other plant personnel, including operators, technicians, and administrative personne . Startup Testing - Refueling Outage 2R6 (72700)

In preparation for the startup of AN0 2 from the present refueling outage, the NRC inspectors performed reviews of prestartup procedures and test results, and post-startup test procedures. These reviews were conducted in conjunction with other reviews conducted by the resident inspectors in preparation for Unit 2 startup. The review and evaluation of the post-startup testing results will be documented in a subsequent NRC inspection report due to a delay in the Unit 2 startup. A brief discussion of the delay appears in paragraph 4 of this repor The prestartup activities fall into two categories; RTD calibration, and rod drive and rod position indication verification. The procedures were reviewed for methodology, technical accuracy and adherence to requirements and commitments of Technical Specifications (TS) and license condition ,

and to verify that the purpose and acceptance criteria were clearly defined. In addition, the procedural steps were reviewed to verify that when performed, the procedure would yield valid and verifiable result The procedures were also examined for signoffs and quality assurance / quality control (QA/QC) hold points where require The completed RTD test procedures, listed below, were reviewed for completeness and the calculations were examined to verify accurac Additional reviews were conducted to detennine if any procedural deficiencies or deviations were identified, and if so, that the resolutions were accurately documented and technically correc . . . .

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OP-2302.006, RTD Response Time Penalty Calculation OP-2304.045, Response Time Testing of RC RTD OP-2304.041, Plant Protection System Channel A (B, C,-D)

Calibration ( .105. .106. .107)

OP-2312.008 Calibration of RTO Transmitters for CPC ( .009, .014 .015)

The results of completed Test Procedure OP-2304.002, "Control Element Assembly Repatch & Verification," were examined for completeness and to determine if any discrepancies or procedural deviations were identified, and if so, that their resolution were documented and technically accurat The procedure was also examined to verify that the intent of the testing had been accomplished which was to ensure that the cabling was attached to the correct connector and the control element assemblies would indicate *

correct position when move Procedure OP-2302.021, "Sequence for Low Power Physics Testing Following Refueling," was also reviewed. This procedure is the controlling document for the conduct of low power physic testing. The review consisted of verifying that the proper testing procedures were included, the correct sequence of testing was identified and any hold points were specifie No violations or deviations were identifie . Procedure Review - Post-Critically The post-critical procedures are core physics / core performance test procedure Criticality was not achieved during the time frame of this report. The data for these core physics / core performance tests will be examined and evaluated during a subsequent NRC inspectio In preparation for the post-critical testing, the NRC inspectors performed detailed review of the core physics / core performance test procedures. The specific categories and associated test procedures are listed below. The procedures were reviewed for methodology, technical accuracy and to verify that they addressed the requirements of the TS, applicable ANSI standards, core reload analysis reports and license comitment Surveillance of Core Power Distribution Limits (61702)

OP-2302.039, Core Power Distribution Following Refueling Nuclear Instrumentation Calibration (61705)

OP-2302.001, Incore Detector Channel Check OP-2302.100, Excore Instrument Channel A.(B, C, D) Test ( .101, .102,

.103)

OP-2304.104, Ecore Instrument Channel A (B, C, 0) Calibration ( .105

.106. .107)

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OP-2304.032, Fower Range Linear Amplifier Calculation at Power OP-2304.146 Startup Channels 1 and 2 Calibration Core Thermal Power Evaluation (61706)

OP-2302.023, Low Power Physics Base ^ Power Level Determination GP-2302.035, Nuclear Themal Power Calculation Determination of Reactor Shutdown Margin (61707)

OP-2302.028, Determination of Critical Boron Concentration and Inverse Borcn Worth OP-2103.015, Reactivity Balance Calculation

' Isothermal and Moderat::r Temperature Coefficient Determination (61708)

OP-2302.026 Isothermal Temperature Coefficient Measurement Total Power Coefficient of Reactivity at Pressurized Water Mactors (61709)

OP-2302.009, MTC Power Control Rod Worth Measurements (PWR) (61710)

OP-2302.003, Determination of CEA Group Worth by Exchange OP-2302.024, Control Element Assembly Symmetry Test OP-2302.025 Determination of CEA 6-1 Worth OP-2302.017 Determination of Group P Integral Worth OP-2302.029, Determination of Regulating CEA Group Worth Nonoverlap OP-2302.030, Sequential Worth Measurement of CEA Regulating Group No violations or deviation were identifie . Startup Delay (93702)

During the performance of the precritical rod drop time test, the licensee discovered that 11 rods did not meet the minimum TS drop time of 3000 milli.econds. Preliminary investigation suggests that the new test method of hopping all the rods simultaneously, ? ice one at a time as the previous testing specified, had increased the holding coil decay time. The details of the licensee's investigation were still in progress at the conclusion of this inspection and will be documented in the next resident inspector's monthly repor . Exit Interview (30703)

The Region IV reactor inspectors conducted an exit interview on May 6, 1988, with licensee representatives identified in paragraph 1. The NRC i

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inspectors sumarized the scope and findings of the inspection. The licensee did not identify as proprietary any of the information provided to, or reviewed by, the NRC inspector l l

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