ML19296B836
| ML19296B836 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco, Arkansas Nuclear |
| Issue date: | 08/31/1979 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19296B831 | List: |
| References | |
| NUDOCS 8002220222 | |
| Download: ML19296B836 (1) | |
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AAKANSAS POWER & LIGHT COMPANY PUS! UFFICE BOX 551 UTTLE HOCX, ARKANSAS 72203 (501)3716 August 31, 1979
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Director of Nuclear Reactor Regulation ATTN:
Mr.
R.
W.
Reid, Chief Operating Reactor Branch i4 U. S. Nuclear Regulatory Commission Washington, D.
C.
20555
Subject:
Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No.
Long - Term Generic I'ssues Related to May 17, 1979 Order (File:
1510).
V.-.
Gentlemen:
^'
In accordance with the request of Dr. D.
F. Ross' letter of August 21',
1979, we have reviewed Enclosure 1 of that letter and provide the following responses to Items. 1, 4, 5, 7 and 8.
Item l'
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The failure modes and effects an21ysiN o'f t e Integrated Con-trol System (ICS) was provide:i - _. letter from James H. Taylor '
to Dr. D.
F.
Ross, Jr., dated A-;ust 17, 1979.
The report, entitled " Integrated Control 6;ry: 2m Reliability Analysis",
also includes a reliability asse_ ment of the ICS plant.
operating experience.
We have r r.*iewed this report and basi-cally endorse it as applicable 2.
our system.
Specific areas of difference are limited and ul 1 be addressed in our response to necessary system or procedur:2. changes, if your. review should come to that conclusion.
Our operating experience has lead us to believe the ICS it a reliable control system.
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$h]Qg 36 SACRAMENTO MUNICIPAL UTILITY oisTRICT O 6201 s street. Box 15830, sacramento, California 95313; (91 0 452 0
August 31, 1979 Mr. D. F. Ross, Jr., Director h0 0
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Bulletins and Orders Task Force' Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory'Comission Washington, D. C 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station, Unit No. 1
Dear Mr. Ross:
The Sacramento Municipal Utility District has reviewed your letter of Augusti 21, 1979 requesting information on several items.
The following provides that information which is due today and is licted by item number of enclosure 1 to your letter.
1.
On August 17, l979 Mr. James H. Taylor of B&W transmitted the Integrated Control System Reliability analysis, BAW-1564,
,. to you. We have reviewed this report and find it generally applicable to Rancho Seco Unit 1 and endorse the conclusions
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and recomendations of the report.
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4 On August 16, 1979 Mr. J. H. Taylor o' -':l provided you with a scope and schedule for the auxiliuy
.2dwater system reliability analysis. Rancho Seco U:..-. is the' lead plant for this analysis which will be avatic::.2 by the dates provided in Mr. Taylor's letter.
5.
'In response to your concerns over tha : -- al-mechanical
' conditions in the reactor vessel duri.3.ecovery from small breaks with extended loss of all feed.':::r, the District commits to have the Babcock and Wilc:
.pany perform an analysis on this subject. The result:.
this analysis shoul be available by December 21, 1979..
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7 The District ccemits to provide the information listed in Attachment A to the enclosure to yet.r letter by the following dates. These dates supersede our commitmer.t to Harold Denton on July 26, 1,979 to provide additional smil break analysis information by September 15, 1979. The required analyses will be performed by the Babcock and Wilcox 1
Company.
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AN ELECTRIC SYSTEM s ERYlN e MORE THAN Ego,000 IN THE HEART OF c A LIFO R N !
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TULECO EDISON Docket No. 50-346 LowEu. E. RCE License No. NPF-3 I.',C*$2 Serial No. 538 August 31, 1979 Director of Nuclear Reactor-Regulatica Att ention: Mr. Robert W. Reid, Chief Operating Reactors Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Reid:
This letter is in response to Mr. D. F. Ross's letter of August 21, 1979 (Log No.423 to all Babcock & Wilcox Operating Plants.
Attachment A addresses ite=s 1, & 4 re-lating to requirements of the Davis-Besse Nuclear Power Station, Unit 1 Order of May 16, 1979. Additionally, items 5, 7 and 8 of the subject letter are addressed.
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Very truly yours
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IIR/TJM L A. Capra Project Y.msage=ent Group Bulletins and Orders Task Force U. S. Nuclear Regulatory Cc=21ssion L'ashington, D. C. 20555 I
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THE TOLEDO EDrSON COMPANY EDISCN PLAZA 300 MADISCN AVENUE TOLEDO. CHIO 43652
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occket No. 50-346 1,1 cense No. NPF-3 Serial No. 538 August 31, 1979 Attachment A Items of NRC LetterNo. 423) 21,1979 (TEco Log
-August
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l re l'of the subject The item numbers ~'belo0"are consistent'with tho~se'of Enc os t d Control Systes (ICS) letter.
Item 1 - Failure Mode and Ef fects Analysis of the Integra e 17, 1979.
August The ICS Reliability Analysis (BAR-1564) was pub with the following deviations:
Page 4-1, Section 4.1.1 I
1.
i PORV setpoint is 2400 psig.
Davis-Besse Unit 2300 psig/1985 psig.
RPS tetpoints:
2 age 4-6, Section 4.2.3.1 i
above 90%
Davis-Besse rate of change is li=ited to 3% per m nute 2.
full poser and below 20% full power.
Page 4-9, Section 4.2.3.5 odulated j
During a reactor trip, the atmospheric vent valves are mits setpoi 3.
when the turbine header pressure exceedsAlso, th on loss ps.
of condenser vacuen or loss cf Circulating Water pu=
Page 4-9, Section 4.2.3.6 h
e manner The throttle pressure error signal is nodified in t e san 50/125 p as for the atmospheric vent valves but with a
.75/155 psi bias.
Page 4-11, Section 4.2.3.10 0 95% for rod Error must be greater than +0.95% or less chan 2
movement.
Page 4-11, Section 4.2.3.11 h
+10%
Feedwater demand is modified when the arror is greater t a 6.
feedwater input on a or less than -5%.. This change was te reduce load rejection.
Page 4-47, Table 4-4, Iten 5-22, Failure Mode-open b
45 to 55%
At Davis-Besse Unit 1, the feedwater valves are a outld overco 7.
open, and a signal to open these valves wou and result in a low pressure trip.
i ough to affect the
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The above deviations are noted, but are not signif cant en J
results and conclusions of this report.
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