ML19344E184
| ML19344E184 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/23/1980 |
| From: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 1-060-18, 1-60-18, 2-060-24, 2-60-24, IEB-79-01B, IEB-79-1B, NUDOCS 8008280012 | |
| Download: ML19344E184 (4) | |
Text
r bec to DAC:ADM:
CENTRAL FILES PDR HQ LPDh f,T4 V NSIC ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLEROCK. ARKANSAS 72203 (501)371-4422 4
June 23, 1980 WILLIAM CAVANAUGH ll1 vec president Genersoon & Construccor 1-060-18 2-060-24 Mr. K. V. Seyfrit, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
Subject:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 & 50-368 License Nos. DPR-51 & NPF-6 IE Bulletin 79-01B, Environmental Qualification of Class IE Electrical Equipment (File:
1510.1, 2-1510.1)
Gentlemen:
Our letters of 2/28/80 from Mr. D. C. Trimble to Mr. K. V. Seyfrit and 4/14/80 from Mr. William Cavanaugh, III to Mr. K. V. Seyfrit forwarded AP&L's initial responses to the subject bulletin.
In addition, the l
latter forwarded a list of outstanding items.
This letter forwards additional information and provides a schedule of completion for all remaining items.
SUPPLEMENTAL INFORMATION IE Bulletin 79-01B, Item 5:
" Identify the maximum expected flood level inside the primary containment resulting from postulated accidents.
Specify this flood level by elevation such as the 620 foot elevation.
Provide this information in the format of Enclosure 3."
l Reply:
The maximum flood levels inside the primar) containments have been calculated as follows:
1 Max. Flood Elevation Unit 1 344'-11" Unit 2 343'- 6" This information wil1 be added to the component data sheets during future revisions.
,800828oos4
Mr. K. V. Sayfrit Juna 23, 1980 REMAINING ITEMS Our eview of the outstanding items listed in our letter of 4/14/80 (Mr.
Cavanaugh to Mr. Seyfrit) has disclosed several areas where significantly more effort and analysis is required than was originally anticipated.
Therefore, a consulting engineering firm has been retained by AP&L to assist in the resolution cf these items.
A revised list of outstanding items follows along with a discussion of each.
1.
High Energy Line Break (HELB) Analysis A review of the facility FSAR's revealed that the HELB analyses contained in the FSAR's (and referenced by IE Bulletin 79-018) are not adequate for use in determining the environmental quali-fication of electrical equipment.
These analyses were restricted to the effects of pipe whip and jet inpingement resulting from pipe breaks.
Therefore, all equipment necessary to mitigate the postulated breaks was not identified and the environmental condi-tions resulting from the postulated breaks were not developed.
AP&L is currently working to develop the required information.
We estimate that this effort, including identification of affected components, calculation of post-accident environmental conditions, and researching environmental qualification data, will require approximately 1500 manhours per unit.
2.
Effects of Recirculated Fluids Outside Containment Existing information on post-accident dose rates outside the primary containment is not adequate for evaluation of equipment environmental qualification.
We are proceeding with tne re-quired analysis and estimate that this effort, including identi-fication of affected components, calculation of post-accident environmental conditions, and researching environmental qualifi-cation data, will require approximately 700 manhours per unit.
3.
Accident Radiation Dose Inside ANO-1 Containment Our previous responses listed the required radiation dose for 7
equipment qualification inside the ANO-1 containment as 2.7x10 Rads.
This was per the guidelines attached to IE Bulletin 79-01B as no plant specific data was available.
We are now proceeding to perform a plant specific analysis consistant with the assump-tions required by IE Bulletin 79-018.
The guidelines attached to IE Bulletin 79-01B are general in nature and we feel that a plant specific analysis will more accurately predict the expected acci-dent radiation dose.
We estimate that this effort will require approximately 400 manhours.
4.
Item 4 of IE Bulletin 79-01B Item 4 of IE Sulletin 79-01B requires that the qualification data for each component be evaluated against the guidelines attached to IE Bulletin 79-018.
This effort includes the evaluation of component aging.
Aging evaluations require that the materials in each component be identified.
In many cases, this information
r Mr. K. V. S:yfrit June 23, 1980 must be obtained from the component vendor, a very time consuming process.
Remaining items required to complete Item 4 include; 1) avaluation of component aging, 2) determining which components are subject to flooding, 3) determining other required information not currently available, e.g. required operating time, required accuracy, etc.
We estimate that this effort will require approximately 800 man-hours per unit to complete.
SCHEDULE AP&L recognizes the importance of resolving the issues addressed by IE Bulletin 79-018.
The extension of our efforts past the original dead-lines is due to the extensive effort required.
We are continuing to give this matter very high priority.
To date, we have expended over 5000 manhours of effort in response to IE Bulletin 79-018.
Including the work discussed above, our total effort will exceed 10,000 manhours and cost approximately $600,000.
Given the magnitude of the effort remain-ing, the following schedule represents the shortest practical completion times for each task.
Scheduled Item Completion Date 1.
HELB Analysis Unit 1 11/1/80 Unit 2 12/15/80 2.
Recirculated Fluids Analysis Unit 1 11/1/80 Unit 2 12/15/80 l
3.
ANO-1 Radiation Dose 9/15/80 4.
Item 4, IE Bulletin 79-018 12/31/80 Although Item 4 cannot be completed prior to completion of the other items, interim submittals will be made when possible.
l Very truly yours, AA f
-h.
g/r-William Cavanaugh, III' WC:ORH:skm l
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STATE OF ARKANSAS
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SS COUNTY OF PULASKI
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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 Information; that he has reviewed or caused to have reviewed all of the statements contained in such infomation, and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, informa-tion and belief.
William Ca9anaugh III I SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the l
County and State above named, thisJ 9 day of J h 6 1980.
l GJ M/
N~ tary Public ' '
o My Comission Expires:
l7",' l $ / 9 0 /
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