ML19261B639

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Forwards Proposed Change to Tech Spec 4.2.6 Re Insp of Reactor Coolant Pump Motor Flywheels,W/Encl Required Fee
ML19261B639
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 02/22/1979
From: Cavanaugh W
ARKANSAS POWER & LIGHT CO.
To: Reid R
Office of Nuclear Reactor Regulation
References
1-029-9, 1-29-9, NUDOCS 7902280313
Download: ML19261B639 (9)
v • d • e


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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK, ARKANSAS 72203 [501)371-4422 February 22, 1979 WILLIAM CAVANAUGH lll Vice President Generation S Construction THjo N

00C[jg-.,

1-029-9 Director of Nuclear Reactor Regulation NM/TVp N8 f ATTN: b!r. R. W. Reid, Chief bS f

Operating Reactor Branch #4 I

U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Proposed Technical Specification (File:

1511.1)

Gentlemen:

Enclosed is a proposed change to the Arkansas Nuclear One - Unit 1 (ANO-1)

Technical Specification 4.2.6.

The basis for this change is discussed below.

ANO-1 Reactor Coolant Pump Flott rs (RCPhi) are an early model from Allis-Chalmers manufactured such that the flys1 eels are " shrunk-to-fit" on the shaft. The manufacturer has stated that th se flywheels were not intended to be removable and has strongly recon.nended that they not be removed from their shafts. Without removal, it is impossible to meet the present technical specification calling for complete surface examination.

In lieu of a complete surface examination of the flywheel we propose to do a complete ultrasonic volumetric examination and a surface examination of all exposed surfaces accessible through the acces: ports at approximately 10-year intervals, during the plant shut down coinciding with the inservice inspection schedule. To facilitate your review, we have enclosed RCPh!

drawings showing the flywheels and the access ports.

Inspection of RCPh! flywheels is scheduled for our upcoming refueling shut down.

We request an expedient review of this proposed change in order that we might implement the surface inspection requirements for this outage.

We have determined, in accordance with 10CFR170, this technical specification change request is a class III change request as it involves a single safety 7822080 7g VSO22803/3 MEMOEA MCOLE SOUTH UTILITIES SYSTEM

Mr. R. W. Reid February 14, 1979 issue. Accordingly, we have enclosed a check for $4000.

Very truly yours, A.-

/-rry' William Ca.'m h IIF

/

s WC: ERG:Ig Enclosure

STATE OF ARKANSAS

)

)

ss COUNTY OF PULASKI

)

Willian Cavanaugh III, being duly sworn, states that he is Executive Director, Generation S Construction, for Arkansas Power 5 Light Company, that he is authori::ed on the part of said Company to sign and fii' with the Nuclear Regulatory Co::aission this Supplementary Infornation; tha; he has reviewed or caused to have reviewed all of the statenents contain.'d in such in fo rma t ion, and that all such statements lade and matters set forth therein are true and correct to the best of his knowled ;e, inform.-

tion and i>elief-

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  • hillta.T Ca, ug;pfp Ili

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SUCbCRIiiED AND SWORN TU before me, a ';otary Public in md for the County and State above named, this Qg ay of k 19 9.

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';a tary Puolic

'!y Co:maission Expires:

1ebruar, 17, 1982

IS-261 Item Component Exception 6.4 Bolting 20 Not Applicable 6.6 Integrally h'elded Not Applicable Valve Supports 4.2.3 The structural integrity of the reactor coolant system boundary shall be maintained at the level required by the original accep-tance standards throughout the life of the station.

Any evidence, as a result of the tests outlined in Table IS-261 of Section XI of the code, that defects have developed or grown, shall be investigated.

4.2.4 To assure the structural integrity of the reactor internals throughout the life of the unit, the two sets of main internals bolts (connecting the core barrel to the core support, shield and to the lower grid cylinder) shall remain in place and under tension.

This will be verified by visual inspection to determine that the welded bolt lecking caps remain in place.

All locking caps will be inspected after hot functional testing and whenever the internals are removed from the vessel during a refueling or maintenance shutdown. The core barrel to core support shield caps will be inspected each refueling shutdown.

4.2.5 Sufficient records of each inspection shall be kept to allow comparison and evaluation of future inspections.

4.2.6 Surface and volumetric examination of the reactor coolant pump flywheels will be conducted coincident with refueling or maintenance shutdowns such that within a 10 year period after startup all four reactor coolant pump flywheels will be examined. The extent of coverage will be limited to those areas of the flywheel which are accessible without motor disassembly, i.e.,

can be reached through the access ports.

Also, if radiation levels at the lower access ports are prohibitive, only the upper access ports will be used.

r 4.2.7 The reactor vessel material irradiation surveillance specimens removed from the reactor vessel in 1976 shall be installed, irradiated in and withdrawn from the Davis-Besse Unit No. 1 reactor vessel in accordance with the schedule shown in Table 4.2.-l.

Following withdrawal of each capsule listed in Table 4.2-1, Arkansas Power S Light Company shall be responsibic for testing the specimens and submitting a report of test results in accordance with 10 CFR 50, Appendix H.

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