ML20083L654

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Notification of 820511 Meeting W/Util to Discuss Review Process & Preliminary Identification of Any Possible Unique Features
ML20083L654
Person / Time
Site: 05000000, Satsop
Issue date: 04/22/1982
From: Larry Wheeler
Office of Nuclear Reactor Regulation
To: Miraglia F
Office of Nuclear Reactor Regulation
Shared Package
ML082840625 List: ... further results
References
FOIA-83-575 NUDOCS 8204290657
Download: ML20083L654 (1)


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l Cocket Nos.:

50-508/509 HCMORANDUM FOR:

F. J. Miraglia. Chief. Licensing Branch No

3. DL FROM:

L. L. Wheeler. Project Manager Luensing Branch No. 3. Di SUa)[CT:

WNP 3 & 5 MEETING WITH NRC PROJECT MANAGER

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DATE & TI"E:

Tuesday. Hay 11, 1982 4

9 9:00 a.m. - 11:00 s.n

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'a ry LOCATION:

Room 130

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Phi 111pt Building

>4d"t.j Sethesda Md.

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' 7(TDj-4N PURPOSE:

Geaertl dist.oss for. of review process and pidentification of any pos WNP 3 4 5 project.

AGENDA:

WNP 3 & 5 participant presents an overview c / the pending OL application.

Any areas of iritarest that may warrant early attention use to un.que features are identified and oescribed.

PARTICIPANTS:

NRC L. Wheeler, et.al.

WNP 3 4 5 K. Cood Louis L. Wheeler, Project Manager Licensing Branch No. 3 D'

-fon of Licensing cc. See next pace.

NOTE: NRC meetings are open to interested m mbers of the pubitc to attend as observers. Mrs of the pubite who wish to attend this meeting must contact L. kneelse (301/492-7792) or F. Miraglia (301/492-7243) no later than 3:45.pm, May 7,1982.

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Post Office Boa 800

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SuSJECT: CI it.AC104 VESSEL LEVEL MEASUREME'4T SYSTEM U5!flG HEATED' JUNCT!Of THERMDCOUPLE RETERENCE: TMI Itsu !I.F.2 We have tuviesed the CE reactor vessel level measunwat system using heated Junction themecouples and. found that addttional inforr.ation is required.

I Accordingly. Please respond to the enclosed request which has been previously l

di' cussed with you by May 15, 1982.

This rquest for information is within the purview of OPB Clearence Nurbar 7

3150-0W65.

Sincerely, on::inal o!g.N tr Dennis M. Crutchfteld. Chief Operating Reactors Branch #5 Division of Licensing Encleswe:

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Palo verde Noelca-Generatine Station TTts _1. 2 & [

sir 50-C28/s29/1 LPM: E. Licitra Mr. E. E. Van Brunt. Jr.

Vice Presiden. - Nuclear Projects Arizone-Puh11c Service Cm pany Post Office Box 21666 Phoenix. Arizona -85036 Arkansas _ Units 1 and 2

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STN 50-313/3fa8 MrW_ illiam Cavanaugh. III,

LPM: B. Martin Senior Vice Pfesident. Energy Soply Department Arkansas Power;& Light Company Post office Box 551 Little rock, Arkansas' 72203 1

Calver t Cliffs Unit I and 2 STN50-3b/318

' Mr. A. E. Lundvall, Jr.

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vice President - Supply

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Balttaart Oas & Electric Company Post Office Box 1475 Baltimore. Maryland 21203 Fa111ades Plant '

<STN 50-255

  • Mr. C&vid P. Hoffman LPM: T. Wambach

'iuclear Licensing Administrator Conswers Power Company 1945 L Parmall Roid

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Jackson.~ Michigan 49201 j

j Derkins Units 1, 2 & 3 and 5erotee 1, 2 & 3 sth50aB5/489/49h 514 50-491/392/49:3 LPM: E. Licitre l

Mr. L. ' C Dail. Vice President ~

Design Engineering-DAe Power Company

  1. cs t Office Box 33189 Charlotte.-fiorth Carolina 28242 L'

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,f the response (with the ren tor.00 M--

running) of the heated junction themocouple leve! wa su remn: vst the full longth separatr.r tube, and ib ) wt th the svi:! sepaeati tube 5fstem BD plants, Also discuss the instruct 'ons to the operatr-for reetation of tM indications.

2.

Pro 1rlda 42 analysis of the response of the hea ted junc t ion t herttu w leal measgrement system with a brea6 in the upper head (a with the lenstf stparater tube, and (b) with the al1? upara tor tube ir. the s:e Plants.

Also discuss the instructions y tne op.<ator for interpretr 'm 40 indications.

3-Providefan analysis of the response of the heated junction the.m ua levelarasurement system after a large break t OCA in particular how m:

1evelt inside that separator. tube compare witn the :ne' outside tak uc m

accmt~ the dra14 rete of the' separator tube.

Wne instructions w11^ ne m vided the optrater for laterpretation of the indi: a er0 UM 4.

Describe the' effects of failure of the follo q components of the hec J., c,.[p junction tiemecevale level measurevnt system wit respec t to measuremnt

  • A systan response; information presented to the opera n r. and effects or re.

M.'f free 'an ahneraal'trarsient.

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1) Slagle thereocouple failure in a sing;e sensor.

The therm -

couple.ts assumed to. fall by a creak in at least one thermoelamen-s-

would result ~1n antepen circuit.

a. Jould the estematic checking procedure detect the fau;*

before the QSPD$ continued to record data?

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What wold happen to the differential output?

2) Hester failure fin a single s e sor. The heater is assumec tn f.-

by a brtek in the hester element that would result in an oper -irc/-

a. _Would t.he 4 Weestic checkisg procedure detett tne fa.i!

before tne QSPD$ continued to rgord data?

b-What unuld be the effect on the other hea ters ' n the av 3} Ast.arx a rupture in the sensor sheath se mat toolset i s adm :

into the senior.

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Would the automatic checking procecce detect the fao the QSPDS continued to record data?

b.

What would be the effect on the heate-in !"e a t 'ec tr and other heaters in the san.e string'

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Eequest for Mditional

-Z-i Informtion RVLMS B.

Prebe l) Reactor vessel seal failure.

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Cables l

1) Assume failure of connector.

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Complete failure of connector.

b.

Partial ~ failure (only some of ti e connections foil ).

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Severed cable.

3) Wet connector.

4). Incorrect wiring at connectors (or any other location inside

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conttirunent).

A'consoon error. In large installations is the incorrect wiring of the

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F themocouple extension cables by cor,r,ection of the Asumel e> ten-m:

sion lead to the Chromel thermoelement et cetera.

Under stable hi containment conditions this could produce an offset.

If the 27 temperature of the containment were to rise, much larger temper-p' ature errors could result.

This situation should be ar.elyzed for J >,

the effect on. both the thermocouple signals from the individaal

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thermocouples and the differential signal;.

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.1) If the heater supply is designed for fast response, rapid fluctua-h*

tions in the cor. trol signal can induce oscillations la the heater

}f supply output. This in turn eculd cause heater failure by overheating 4

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or fatigue.

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""I' Vice Pres. dent Advanced Systems & Technology flcrida Power & Light Company Post Cffice Box $29100 Miami, Florida 33152 ya3erford steam Electric " aion.

STN r.0 3E2 Unit 3 LFM: S. Black Mra L..V. Aaurin Assistant Vice President -

Nuclear Operations Louisiana Power 1 Light Company 142 Delarende Street New Orleans Louisiana 70174 Maine Yankee STN 50-309 Mr. John H. Garrity, Senior of reciar Nuclear Engineering and Licensir.:

Maine Yankee Atomic Power Compan) 83 Edison Daive Augusta. Maine 04336 1

1 Millstone Unit 2 STN 50-336 LFM: M. Conner Hr. W. G. Counsil Nuclear Enginc4 ring and Operations Ecrtheast Nuclear Energy Coepany-Post Office Box 270 Hartford, Connecticut 06101 Ft. Calhoen 5..,.,a - d, c on.

a I* 49 Mr. W. C. Jones DTvision Manage.

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January 27, 1982 Y'.

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