ML19207B942

Submits Info Re Failure Mode & Affects Analysis of Integrated Control Sys,Auxiliary/Emergency Feedwater Sys, Reliability Upgrade & thermals-mechanical Conditions in Reactor Vessel,In Response to 790821 Ltr

ML19207B942
Person / Time
Site:	Crystal River
Issue date:	08/31/1979
From:	Moore G FLORIDA POWER CORP.
To:	Ross D NRC - TMI-2 UNRESOLVED SAFETY ISSUES TASK FORCE
References
3--3-A-3, 3-0-3-A-3, NUDOCS 7909060188
Download: ML19207B942 (4)

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2 Florida Power A st 31, 1979 File. 3-0-3-a-3 Mr. D. F. Ro ss , J r .

Director Bulletins and Orders Task Force Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Identification and Resolution of Long-Term Generic lesues Related to the Commission Orders of May 1979

Dear Mr. Ross:

On August 23, 1979, Florida Power Corporation received your letter of August 21, 1979, identifying eight long-te rm issues related to the C which must be re-solved for Crystal River Unit 3 and the other B&W Operating r_ '

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These eight (8) items were identifica and briefly discussed in Enclosure 1 of your letter. In your discussion of Items 1, 4, 5, 7, and 8, you requested Florida Power Corporation to provide additional information and our schedule for resolution of these five (5) items by August 31, 1979.

In that regard, Florida Power Corporation hereby submits, as Attachment 1 to this le t te r , our response to your August 21, 1979, request for additional information.

If you require further discussion concerning our response, please 'ntact us.

Very truly yours, FLORIDA POWER CORPORATION

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G. C. Monre Assistant Vice President Power Production GCMekcF06(D5)

Attachment 7900060/88! OJ.'o fS General Office 320i Tnatsounn sneet soutn . e o Box N O R St Pe'erstva h a FB 80 eu; SW

STATE OF FLORIDA COUNTY OF PINELLAS G. C. Moore states that he is the Assistant Vice President, Powe r Productisn, of Florida Power Corporation; that he is authorized on the part of said caapany to sign and file with the Nuclear Regulatory Commission the inf onnation attached hereto; and that all such statenents made and matters set forth therein are true and correct to t he best of his knowledge, infonnation and belief.

, , r G. C. Moore Subscribed and sworn to before me, a Notary Public in and for the State and County above nam e d , this 31st day of August, 1979.

Notary Public Notary Public, State of Florida at Large, My Commission Expires: August 24, 1983 (CrockettNotary2 D12) r) ,, y r. . r3 ss % A;s a co

ATTACICIENT 1 Response to Ross Let ter of August 21, 1979 Item _1 - Fai lure liode and Affects Analysis of the lutegrated Control System On August 17, 1979, B&W subuitted to you for your review, co p i es of tho report entitled ~BAW--1564, Int egrated Cont rol System (ICS) Rel iabi li ty Ana l ys is .

This letter is to advise you that this report is applicable to Crystal River l'n i t 3. Although this was a generic re po r t developed by B& W , and there are dif-terences i n t he secondary system designs at the va r io us B&W plants, we feel that the conclust.ons reached in this report can be applied to Crystal River linit 3.

Florida Power Corporation is presently reviewing the recommendations listed in Section 3 of this re po r t to det ine what possible changes are neem sa ry at Crystal River Unit 3 to enhance reliability and safety.

l_ tem fi - Auxi 1 la ry/ Eme rgency Feedwate r Sys t em Re I labi 1 i t y lipg rade This letter is to intorn you of Florida Power Corporation's c omm i t me nt to the AFW/EFW System Reliability Study proposed by B&W and discussed with you and your staff on July 19, 1979, and August 9, 1979. The dra f t re po rt f or Cr: 4tal River Unit 3 will be submitted by October 22, 1979, and the first report will be submit ted by December 3, 1979.

Item 5 - Detailed Analysis of the Thermal-Mechanical Conditions in the Reactor Vessel During Recovery f rom Small Breaks With i:xt ended Los , of All Feedwater The above analysis will be submit ted by December 21, 1979.

Item 7_ - Small Break LOCA Analysis The following is our schedule of response to the six (6) items contained in Attachment A of your letter:

1) A. Re po rt will be submitted on December 1, 1979.

B. Report will be submitted on September 30, 1979.

2) A. Report wiIl be submitted on Septembe r 30, 1979.

B. In response to this request, we are proposing three (3) op t. i o n s e in preference of o rd e r :

1) Provide a statement by September 30, 1979, that no suall break with auxiliary teedwater will pressurize the systen to' the PORV setpoint.

2) Provide by Decembe r 30, 1979, a <lua l i t a t i ve as se ,sment of the transient.

3) Provide core analysis by February 1, 1980, using li.01 iL 2 break with no AFW available, i

Ue a re presently proceeding with option dl, nules, ot hersise notified by the NRC by September 7, 1979.

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3) A. Report wl1I be submitteil on September lu, 1979.

B. Report wiiI be submitted on Oc t obe r ll, 1979.

C. Report wili be submitLed on September 30, 19/9.

D. Report will be submitted on October 31, 1979.

4) An analysis of the first 100 uinutes of the T:il-2 acc ident will be submi tted by Se ptembe r 30, 1979.

5) Re po r t will be subai t ted on Septeiaber 10, 19/9.

6) Report will be submi tted on riay 1,1980.

Item 8 - Analysis for Losr, of Feedwater and Othe r An t ic ipa t ed lransients

" Analysis of loss of f eedwater and other antic ipated transients origina lly . tis-cussed by fillREG-0560, Section 8.4.I has been expanded and superseded by NUREG-0578,Section 2.1. 9. On August 9, 1979, B&W and t he B&W ownors Group dis-cussed a conceptual program with the NRC staff to address the Lessons Learned Task Force item. The desc ribed prograu enta i ls the integration of analysis, simulation and plant event response evaluation developing svuptom ba s e d guide-lines f or station operators to evaluate a bno rm a l transients. L,ur letter indi-cates qualified acceptability of the pro;; ram. The se ve n transients selected for prepara tion extend into all areas of plant response requi ri ng de t,i led coord ina-tion between NSSS vendor and architech engineer equipuent as well as the cuny plant specific interactions that must be considered. To prov ide this integra-tion and provide a truly meaningful result, se ve ra l details of the program are being f urther def ined that will affect the quality of the evaluation but also impact schedule. Therefore, consistent with a discussion tetween Mr. R. Capra and Arkansas power and Light Company on August 27, 1979, we wi1I defer subalt-ting a detailed schedule until September 14, 1979.*

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