ML20235W841

Requests That Util Complete Encl Questionnaire on Erosion/ Corrosion Experience,Piping Design,Feedwater & Condensate Chemistry in View of Surry Pipe Erosion/Corrosion Incident in Dec 1986

ML20235W841
Person / Time
Site:	Fort Calhoun
Issue date:	07/15/1987
From:	Bournia A Office of Nuclear Reactor Regulation
To:	Andrews R OMAHA PUBLIC POWER DISTRICT
References
NUDOCS 8707230741
Download: ML20235W841 (5)

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'o UNITED STATES 8

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NUCLEAR REGULATORY COMMISSION o

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,i WASHINGTON. D. C. 20665

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JUL 3 5 tons Docket No. 50-285 Mr. R. L..A.drews Division Manager - Nuclear Pr6 ductions Omaha Public Power District 1623 Harney Street Omaha, Nebraska 68102

SUBJECT:

PWR EROSION-CORROSION QUESTIONNAIRE As a result of the Surry pipe erosion / corrosion incident in December of 1986,

]

the NRC is preparing a report that will reference existing research information available and describe the actions being taken by utilities regarding erosion /

corrosion in feedwater pipes in nuclear power plants.

Central to an understand-ing of erosion / corrosion in pipes is an accurate assessment of erosion / corrosion experience, piping design, feedwater and condensate chemistry and piping materials.

i To ensure that both the NRC and the nuclear industry have available a comprehen-sive collection of data regarding ernsion/ corrosion in feedwater pipes, the NRC will assemble a summary of utility information related to ongoing water chemistry actions in pressurized water reactors.

To accomplish this task we ask that you 1

complete the enclosed questionnaire.

The information being requested is quite extensive and will require a diligent effort on your part and ours to assure accurate and timely completion. Also, we realize that parts of the information may already be available to the NRC, but not in a convenient format which is readily accessible. Therefore, we request that you assist us by returning for each unit a single completed copy of the

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enclosed questionnaire to the Project Manager, U. S. Nuclear Regulatory

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Commission, Washington, D.C.

20555, within 60 days of receipt of this letter.

We believe the questionnaire is self explanatory; however, if questions arise or clarification is required, please contact your NRC Project Manager.

P

y

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i 1 This request is covered by Office of Management and Budget Clearance Nuraber 3150-0011 which expires December 31, 1989.

Comments on burden and dupli-

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cation may be directed to the Office of Management and Budget, Room 3208, New Executive Office Building, Washington, D. C.

20503.

Sincerely,

}

Anthony Bournia, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

PWR Erosion-Corrosion Questionnaire cc w/ enclosure:

See next page DISTRIBUTION c'. Dock.et, Fil e PDR "' ~

Local PDR PD4 Reading l

D. Crutchfield i

F. Schroeder J. Calvo P. Noonan A. Bournia 0GC-Bethesda E. Jordan J. Partlow ACRS (10)

PD4 Plant File B Wngh\\

l CO' PD4/Lh,k.

PD4/PM PD4/D /% -

PNopnaN i ABournia: sr JCalvo 7/l'i/87 7//3/87 7/(/87

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4 Mr. R.'L. Andrews Forticalhoun Station Omaha Public Power District Unit No..I cc:

Harry H. Voigt, Esq.

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, NW Washington, D.C.

20036 y,

Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, Nebraska 60008 Mr. Phillip Harrell, Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 309 Fort Calhoun, Nebraska 68023 3

Mr. Charles B. Brinkman, Manager Washington Nuclear Operations C-E Power Systems o

7910 Woodmont Avenue I)

Bethesda, Maryland 20814 Regional Administrator, Region IV

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U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011

- i 3,

Harold Borchert, Director

'l Division of Radiological Health j

Department of Health 301 Centennial Mall, South i

P.O. Box 95007 Lincoln, Nebraska 68509 j

W. G. Gates, Manager I

Fort Calhoun Station P. O. Box 399 j

Fort Calhoun, Nebraska 68023

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ENCLOSURE 3 f

I PWR EROSION-CORROSION QUESTIONNAIRE (Check or Circle All Applicable) i Utility Company:

Unit Name: _

MWe ___

Date:

Phone No.

filled by:

In service: 19....

Water Treatment:

AVT with ammonia, morpholine, hydrazine.

Condensate polishers: none, cation, powdex, mixed bed;

.....% of feedwater flow; installed 19....; operated in: H-OH. NH4-OH form.

Cooling water: fresh, salt, brackish, cooling tower.

Copper alloy condenser tubing:

yes, no. Copper alloy FW beater tubes: LP. HP. none.

Boric acid used since: 19...; during: operation, layup, low load soaks. other.......

A.

EROSION-CORROSION EXPERIENCE 1.

Erosion-Corrosion identified in wet steam piping yes, no.

2.

Erosion-Corrosion of MSR Chevrons or mesh:

yes, no.

Chevron naterial:

stainless steel, carbon steel, other.....................

3.

Erosion-Corrosion of feedwater piping: yes, no.

Oate found...................

Feedwater piping materials:.................................................

4.

Erosion-Corrosion of:..... e l bows,..... T s,..... d i f f us e rs....... : reducers.

.... val ves..... or i fi ces..... other components (spec i fy)..................

S.

Erosion-Corros.lon of J-Tubes: yes, no.

6.

Erosion-Corrosion of feedwater distribution ring: yes, no.

7.

Erosion-Corrosion of turbine:

HP. LP; identify components:

8.

Erosion-Corrosion of other cycle components (identify)...................... 6*

9.

feedwater temperature range where erosion-corrosion founds from.... to..... f 10.

Inspection frequency for feedwater piping..... years. Steam lines..... years.

II.

Inspection methods used: ultrasonic thickness radiography. visual, other......

B.

PIPING DESIGN l.

Maximum feedwater flow velocity............ feet /second.

2.

No. of feed pumps operating at 100% load........ second pump On at....1 load.

3.

Maximum flow velocity when only I pump is operating............... feet /second.

4.

No. of feedwater piping components:....... elbows,...... Ts,

..... diffusers,

...... reducers....... valves,...... orifices,

...... other components (specify) 5.

Maximum flow velocity in wet steam piping............ feet /second.

6.

Feedwater pressures and temperatures (agtual (preferred) or design):

f Full load (pressure, psta/ temperature, f):

P:

P:

P:

P:

P:

T:

T:

T:

T:

T

..... r I y 3y g

gr 7

t Condensate Pump Cond. Polishers BF Pump Steam Generators r'5 low load (typical

...% of full load):

P:

P:

P:

P:

P:

T:

T:

T:

T:

T:

g' y9 Q

4 V

u y

Con ensate Pump Cond. Polishers U BF Pump Steam Generators Please attach copf es of the heat balance diagrams for your actual full load and typical low load.

kf

" $k

.y w m!-

p..

6>hn

.*n h

b M

n.>,,,

A lV

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i&.

j;

1. f C.

FEE 0 WATER AM CONDENSfle(CHEMISTRY a

g 6 <,,' s

^

jI l.

Please ccanplete the attached Table; Feedwater chemistry hlstory (average or ty >lcal valtses, final. inefeat e'r):

lh+

2.

a :;

v >'

3'980 c,

.I 12H.l.

jf8,J xtfBS 1986 1987

. [

Year of oper. {,

jp_t, l.914, 1976 1978 z(

.g pK of FW mxfrun.

Q.

mini' mum.

=._-

average._

a..

i pH of conden'dte

't.

maximum.

I

'f ml'ilmuth average._.b+j{f_g 00, ppb maxirir>e.___ii.uM idnN.

(,h ' * *. _

aYerage.g j

Caf. Cond. US/cm. 4 Spec. Cond. uS/cm.

NH ppb

.n Nh, ppb

'i Bbr8n, ps

. __ L__.

Air Inleakage,

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SCFM Please send any water chemistry summary reports and data.

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Chemical additions

3.1 Ammonia

typical concentration in feedwater.... ppbi added at...........

3.2 Hydrazine

typical concentration in feedwater.... ppbi added at.........

3.3 Boric acid: typical concentration in feedwater.... ppb as 8; added at.................

D.

MATERIAL.S 1.

Feedwater piping - l ist ASTM or other spec i ficat ion numbers....................

1 2.

Wet steam piping:

3.

Attach results of chemical analysis by vottor r.!pe vendors.

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e 70/ Doc 4 1