ML19327B867

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Responds to 890829 Request for Proposed Program for Completion of Generic Ltr 88-20 Re Individual Plant Exam (IPE) for Severe Accident Vulnerabilities.Util Intends to Submit Results of Both Units by End of 1991
ML19327B867
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 11/01/1989
From: James Fisicaro
ARKANSAS POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-1335, RTR-NUREG-CR-2300 0CAN118906, CAN118906, GL-88-20, NUDOCS 8911140107
Download: ML19327B867 (3)


Text

f h+ S Ark:nsas P:wer & Light Cimpany O j55

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TN 501377 4000 u

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a i November 1, 1989 ,

SCAN 118986  ;

U. S. Nuclear Regulatory Commission l Document Control Desk Mail Station P1-137 -

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Subjecti Arkansas Nuclear One - Unfts 1 & 2

. Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6

> Individual Plant Examination for Severe Accident n Vulnerabilities - Generi~c Letter 88-20 '!

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Gentlemen:

By. letter dated August 29, 1989 (9CNA088921) AP&L was requested to submit our proposed program for completing our Individual Plant Examination (IPE),

The requested description of AP&L's program in ' response to Generic Letter 88-20 follows.

AP&L has choosen to perform its IPE for both ANO-1 and 2 through the use of plant specific.Probabilistic Risk Assessments (PRAs). AP&L has begun a .

Level I and'11mited Level II PRA on each of the Arkansas Nuclear units. The methodology used for the Level I analysis can best be characterized as a.

, small event tree and large fault tree approach. This methodology is consistent with the general guidelines of NUREG/CR-2300. The' Level II analysis will be of limited scope utilizing existing containment analyses; but some plant specific calculations may be performed using the MAAP computer code. An internal flooding analysis with system walkdowns will also be performed. Analyses will conform to the guidance of Generic Letter 88-20 and NUREG-1335.

l' AP&L is conducting the IPEs with assistance from Science Applications t International Corporation (SAIC). AP&L Engineering, Operations and Maintenance personnel are directly involved in all aspects of the PRA effort including model development, independent review and application of the bq g results. The PRA methodology, models and results will be independently reviewed in-house with assistance from ERIN Engineering and Research l

g Incorporated. ERIN will review the methodology and coordinate the Nmo : independent in-house review.

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J- o s L 'wo AP&L's original ANO-1 PRA effort began in September of 1988. Since that hM- time we have developed system models, collected plant specific data, and began analysis of accident sequences. The ANO-2 PRA effort began in July of

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P 1989.

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. 7 Based on our progress to date, AP&L intends to complete the IPEs and submit

~w- the results of both ANO units by the end of 1991. This date differs from

5.h dates previously discussed in various presentations and our June 14, 1989 CODA - letter-(2CAN068918) on improved Auxiliary Feedwater System reliability for gof ANO-2. This difference from our previously stated completion date (late l t

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  • U. S. NRC Page 2 i November 1, 1989 L  !

1990 for both units) is due to the previously provided date being based on  ;

completion of the PRA models only. The new date is based upon the completion of the models, the addition of internal flood analyses, the need for interfacing with Operations and Maintenance Training and the Accident Management Program,. addressing identified vulnerabilities, and the proposed use of some plant specific calculations, all of which is necessary to fulfill the additional requirements of an IPE. While schedules have been developed that provide assurance of the projected finish date, firm milestone dates are inappropriate due to uncertainty in the timing of the integration and~

reiteration work that occurs as the IPE elements are. assembled. Also, in~a project of this nature.and magnitude, schedule changes can occur. If a delay in our schedule oc::urs, you will be notified.

This information is being provided under oath and affirmation pursuant to 10CFR50.54(f). If you have any questions, please do not hesitate to call.

Very truly yours, l h5L*t+s.

ames J. Fisicaro Manager, Licensing 7

'JF/MCS/1w J

cc: Mr. Robert Martin U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. C. Craig Harbuck NRR Project Manager, Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Chester Posiusny NRR Project Manager, Region IV/ANO-2 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-D-18 One White Flint North 11555 Rockville pike Rockville, Maryland 20852 1

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STATE OF ARKANSAS )

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COUNTY OF PULASKI )

~ I, James J. Fisicaro, being duly sworn, subscribe to and say that I am Manager, Licensing for Arkansas Power & Light Company; that I have full ,

i authority to execute this oath; that I have read the document numbered J t-SCAN 188912 and know the contents thereof; and that to the best of my

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knowledge, information and belief the statements in it are true.

P d.d 5 M V V ,

James J. Fisicato

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SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State above named, this M day of ,

1989. .

E i N Public My Commission Expires:

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