ML19318A406

From kanterella
Jump to navigation Jump to search
Responds to IE Bulletin 80-12, Decay Heat Removal Sys Operability. Analyses of Procedures for Safeguarding Against Loss of Sys Capability Should Be Completed by 800815
ML19318A406
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 06/12/1980
From: Cavanaugh W
ARKANSAS POWER & LIGHT CO.
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
1-060-14, 2-060-19, IEB-80-12, NUDOCS 8006200489
Download: ML19318A406 (3)


Text

.

ARKANSAS POWER & LIGHT COMPANY POST OFRCE BOX 551. UTTLE ROCK. ARKANSAS 72203 [501) 3714422 WILLIAM CAVANAUGH ill June 12, 1980 Vice Prseedent Genersten & Consmxton 1-060-14 2-060-19 Mr. K. V. Seyfrit, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Comission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011

Subject:

Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 IE Bulletin No. 80-12 Decay Heat Removal System (DHRS)

Operability (File:

1510.1, 2-1510.1)

Gentleuen:

In accordance with Item 7 of the st; 4. ' bulletin, the following is provided under 10 CFR 50.54(f).

Item a.

Changes to procedures (e.g., emergency, operational, administrative, maintenance, refmling) made or initiated as a result of your reviews and analyses, including the scheduled or actual dates of accomplish-ment.

(Note:

NRC suggests that you consider the following.

(1) limiting maintenance activities to assure redundancy or diversity and integrity of DHR capability, and (2) bypassing or disabling, where applicable, automatic actuation of ECCS recirculation in addition to

[,g disabling High Pressure Injection and Containment Spray preparatory

/i to the cold shutdown or refueling mode.)

5

Response

In accordance with Items 1 and 2 of this bulletin, reviews of the Davis-Besse event and of all DHR degradation events, for which documentation exists, at ANO-1 and 2 has been completed.

In addition to these reviews, analyses of our procedures for adequacy of safeguarding against loss of DHR capability and for adequacy of responding to DHR loss events are now being perfomed. We expect to complete these analyses by August 15, 1980.

(J062004/.8Q

  • SS="'S**

"" S S'5"'

In response to Item 6, procedure revisions necessary in order to ensure that removal of decay b, eat from the RCS is accomplished as necessary will be implemented by July 7,1980.

Consideration will be given to the NRC suggestions given above in our reviews and procedure revisions.

Item b.

The safeguards at your facility (ies) against DHR degradation, including your assessment of their adequacy.

Response - ANO-1 In order 'to address Items 4, 5.-and 6 of this bulletin, the hardware capability of A10-1 to prevent DHR loss events has been and is continuing to be reviewed. Also, our letter dated August 3,1976, to D. Ziemann of your staff presented our analysis to demonstrate that the Emergency Core Cooling System and subsystems meet the single failure criterion pursuant to the requirements of 10 CFR 50.46.

Because parts of the ECCS system are also used for DHR, we feel that this analysis, plus the reviews being performed to address Items 4, 5, and 6, adequately addresses the conceras expressed in this bulletin.

Response - ANO-2 The ANO-2 FSAR states in Section 9.3.6 that:

"No single failure of an active component during residual heat remov'al will result in permanent loss of cooling capability." And:

"A single failure of a passive com-ponent in the low-pressure portion of the Shutdown Cooling System during resideal heat removal may result in the interruption of the cooldown but will not result in a loss of core c'ooling." The Safety Evaluation per-formed in support of these statements is included in Section 9.3.6.

We feel that this evaluation, along with the reviews being done in response to Items 4, 5, and 6,.is sufficient to address the concerns of this bulletin.

Very truly yours, l

s<

-,r William Cavanaugh, II s

WC: MAS:skm cc: 'Mr. Victor Stello,' Jr., Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington,.D. C.

20555 1

d__'

STATE OF ARKANSAS SS COUNTY OF PULASKI William Cavanaugh III, being duly sworn, states that he is Vice President, Generation & Construction, for Arkansas Power & Light Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Comission this Supplementary Infomation; that he has reviewed or caused to have reviewed all of the statements contained in such information, and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, infoma-tion and belief.

e

~

f A

mm/

WilliamCava3aughIII SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State above named, this /8 day of b & C 1980.

V h)Tl. -

AUJ _ - L+fn Dh' Notary Publi'c /

/

My Commission Expires:

W ****1

% *u 9/J/st i