ML19275A568

Responds to IE Bulletin 79-06C, Nuclear Incident at TMI - Suppl. Interim Action Required in Item 1 Implemented. Rept Required in Items 2 & 3 Submitted 790829.Emergency Procedure Training to Be Conducted When Guidelines Approved

ML19275A568
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/29/1979
From:	Trimble D ARKANSAS POWER & LIGHT CO.
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
2-089-18, 2-89-18, NUDOCS 7910040656
Download: ML19275A568 (3)

Text

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ARKANSAS POWER & LIGHT CCMPA., .

POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 [501)371-4000 August 29, 1979 2-089-18 Mr. K. V. Seyfrit, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Comm.

Pegion IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011

Subject:

Arkansas Nuclear One-Unit 2 Docket No. 50-368 License No. NPF-6 IE Bulletin 79-06C (File: 2-1510)

Gentlemen:

In response to Items 1 - 4 of IE Bulletin 79-06C, the fol-lowing is provided.

Item 1.

In the interim, until the design change required by the long-term action of this Bulletin has been incorporated, institute the following actions at your facilities:

a. Upon reactor trip and initiation of HPI caused by low reactor coolant system pressure, immediately trip all operating RCPs.

b. Provide two licensed operators in the control room at all times during operation to accomplish this action and other immediate and follow-up actions required during such an occurrence. For facilities with dual control rooms, a total of three licensed operators in the dual control room at all times meets the requirements of this Bulletin.

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I 2-089-18 Mr. K. V. Seyfrit August 29, 1979

Response

'e complied with this item upon receipt of the Bulletin.

Item 2.

Perfor.n and submit a report of LOCA analyses for your plants for a range of small break sizes and a range of time lapses between reactor trip and pump trip. For each pair of values of the parameters, determine the peak cladding temperature (PCT) which results. The range of values for each parameter must be wide enough to assure that the maximum PCT or, if appropriate, the region containing PCTs greater than 2200 degrees F is identified.

Response

We submit, by reference, CEN-ll5-P, which was submitted by the August 29, 1979, letter, frcn Mr. G. Liebler (Florida Power and Light) to Mr. Victor Stello.

Item 3.

Based on the analyses done under Item 2 above, develop new guidelines for operator action, for both LOCA and non-LOCA transients, that take into account the impact of RCP trip requirements. For Babcock & Wilcox designed reactors, such guidelines simuld include appropriate requirements to fill the steam generators to a higher level, following RCP trip, to promote natural circulation flow.

Response

We submit, by reference, CEN-ll5-P, which was submitted by the August 29, 1979, letter, from Mr. G. Liebler (Florida Power and Light) to Mr. Victor Stello.

Item 4.

Revise emergency procedures and train all licensed reactor operators and senior reactor operators based on the guide-lines developed under Item 3 above.

Response

In that the guidelines developed in CEN-ll5-P are not in agreement with the actions called for in Item 1 of IE Bulletin 79-06C we will not conduct training or revise exist-1101 263

t 2-089-18 Mr. K. V. Seyfrit August 29, 1979 ing procedures until our guidelines are approved. We will comply with Item 1 until this issue is resolved.

Very truly yours,

• i

, G /V/ :

,Davic C. Trimble

, Manager, Licensing DCT/JTE/ew cc: Mr. Victor Stello, Jr., Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Comm.

Washington, D. C. 20555 Mr. Harold R. Denton, Director Office of Nuclear Renator Regulation U. S. Nuclear Regulatory Commi ssion Washington, D. C. 20555 1101 264

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