ML19326C233
| ML19326C233 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/16/1973 |
| From: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8004220806 | |
| Download: ML19326C233 (5) | |
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Docket No. 50-313 N[.
!1 Mr. J. D. Phillips Vice P-esident & Chief Engineer Arkansas Power and Light Company p,
Sixth and Pine Streets Pine Bluff, Arkansas 71601
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Dear Mr. Phillips:
From the fall of 1972 into early 1973, the Regulatory staff was engaged in the safety review of the cicetrical and control systems of Arkansas Nucicar One, Unit 1.
This reviev included 1cngthy nectings with your staff both here, at the plant and in your Little Rock offices. We have tried to furnish you detailed notes and explanations to ensure that you understood our concerns. After i
extencive review of this plant we are unable to conclude that the p
clectrical and control systems are acceptable.
In our letter to you on February 7, 1973, we enumerated 18 areas of concern. Through the spring and into the sunner you gradually amended and supplemented your application with responses to these items.
In order to maintain a rethcJ1 cal review schedule for your plant we decided to issue our Safety Evaluation Report with the final electrical review outstanding. We took this course only because we felt confident that we had explained our concerns and requirenents to your staff thoroughly, and you would have ample time to complete your work and denonstrate compliance. Having spent so cuch time on your car,e already, we had to set aside your responses to cicetrical questions c.nd wait til af ter the ACRS meetings to review thca with the other matters remaining.
In October we attenpted our concluding review of your electrical and control systems and discovered continuing deficiencies and F
questions of a significant nature. We met with your staff us soon h
as possible, on October 30, 1973, to describe these problets, b
The principal concerns here were identified to you long a'o in EI.;.
s come detail; they to not new review matters. Our principal concerns are:
1.
Because of an oversight in your initial safety analysis it vas necessary for you to design a secan line break instrumentation and control system (SLBIC) to effect rapid isolation of the Ob [
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In a fresh design, at this late date, of
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a pystem directly required for accident control, your SLBIC systen does net meet the requirements of IEEE 279, the p"
basic standard for such protective systems.
2.
By your analysis, the emergency feedwater system is needed
=h for safe shutdown of the reactor; and yet we have repectedly'
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revicued this system and pointed out potentially disabling F
single failures and other aspects of the system design which l
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tishe its reliability questionable.
J en 3.
In the effort to validate your proposed use of the diesel generators for peaking service, unique features were included in the design of your offsite power connections. Our February 7, 1973 letter stated that such peaking service would not be ic" allowed and called for you to perform a design audit of the power systen to change those features which nahe it vulnerable to indiscriminate tripping of the offsite power sources and vulcrnabic to disablement by single failures. As presented to us now, in a May 23, 1973, revision of the drawing, there has been als ist no change in the design and it does not satisfy the requirements of General Design Criterion 17 as it should.
4.
As long ago as April of 1972, we expressed concern about the cables in the subfloors of the control and computer rooms.
In our February 7, 1973, letter we specifically asked you to denonstrate that this installation is acceptabic with respect to design basis events such as fire. In your Etreh 13, 1973, Ictter you stated that the PVC (polyvinyl chlorid >.)
covering on the flexible accel conduits of these cables will not support ecm.bustion.
It is our understanding that PVC uay indcod barn, releasing corrosive and toxic hydrochloric acid vapor, and that the use of PVC is being discontinued in many applications because of this. We do not know if you considered this capect in your review of the subfloor arrangement.
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We realize how close the scheduled fuel load date is and we urge you to couplete the required work in this area so as not to delay licensing action. ~I!owever, we cannot license this plant until the electrical and control system design and installation are acceptable to ensure the health and safety of the public. Consequently, we expect you to submit conclusive analyses and corrected designs by November 30, 1973.
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.m In addition, we expect you to follow this submittal with a technical presentation on December 14, 1973 which covers the details of the E
reviews and associated design changes. These dates have already been p.
discussed with your staff.
If your subnittal is satisfactory we will expect to be able to give you indication of that ' ef.'re the end of December and to publish our Safety Evaluation Rt; 'i Supp1 h at in January.
Sincerely, CMgtnat eigned by R. C. DeYoune; R. C. DeYoung, Acsistant Director
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Pressurized Water Reactors Directorate of Licensing cc: liorace Jewell, Esquire llouse, Eolms and Jewell 1550 Tower Building Little Rock, Arkansas 72201 Mr. Willica Cavanaugh, III Production Department P. O. Ecx 551 Littic Rock, Arkansas 72203 DISIRIBUTION:
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C J. D. Phillips s Uc calize how close the scheduled fuel load date is and we urge you
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s to co,lete the required work in this area so as not to delay licensing action. However, we cannot license this pl, ant until the electrical and contr 1 cystem desi n and installation are acceptable to ensure E
the health and safety of the public. Consequently, we expect you to submit conclugive analyses and corrected designs by November 30, 1973.
In addition, v6 e::pect you to follow this submittal with a technical x
presentation on Decenber 14, 1973 which covers the details of the reviews and assoc 1 ted design changes. These dates have aircady be'en discussed with your taff. If your submittal is satisfactory we vill expect to be able to ive you indication of that before the end of Decc=berandtopubliskourSafetyEvaluationReportSupplenentin January. Please notify us in 7 days of the receipt of this letter of your ability to moet the shbedule indicated.
Sincerely.
R.
. DeYoung, Assistant Director Pre urized Water Reactors Direct te of Licensing ec: Horace Jewell, Esquire House, Holms and Jewell 1550 Tower Euilding Little Rock, Arkansas M 31 Mr. Uilliam Cavanaugh, III Production Department P. O. Box 551 Little Rock, Arlansas 72203 DISTRIBUTION:
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We realiz how cloce the scheduled fuel load date is and we urge F -
you to coup ete the required work in this area so as not to delay licens g action. However, we cannot license this plant until the elec rical and control system design and installation aro acceptable ensure the health and safety of the public.
Consequently, we xpect you to subnit conclusive analyses and corrected designs November 30, 1973.
In addition, we expect you to accompany th.
subnittal with a technical presentation which covers the deta a of the reviews and associated design
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changes.
If your subuJtal is satisfactory, we will complete our review by December $1, 1973. Please notify us in 7 days of the receipt of this leb er of your ability to nect the schedule indicated.
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R. C DeYoung, Assistant Director for sPressuri::ed Water P.eactors Directhrate of Licensing
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cc: Eorace Jewell, Esquire House, Holme and Jewell y
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Little Eo:L,, Arkansas 72201 Mr. Uillian Cavanaugh, III
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Production Department ll P. O. Box 551 id Little Rock, Arl:ansas 72203
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