ML20236D104

Requests Assistance in Completing Encl Questionnaire Re Erosion/Corrosion in Feedwater Pipes in Nuclear Plants.Nrc Preparing Rept That Will Ref Existing Research Info as Result of Surry Pipe Erosion/Corrosion Incident in Dec 1986

ML20236D104
Person / Time
Site:	Prairie Island
Issue date:	07/16/1987
From:	Diianni D Office of Nuclear Reactor Regulation
To:	Musolf D NORTHERN STATES POWER CO.
References
NUDOCS 8707300304
Download: ML20236D104 (4)

Text

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JllL 1 e 1997

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l Docket Nos. 50-282 DISTRIBUTION l

and 50-306 2 Docket J11esh DWigginton Local PDR GHolahan Mr. D. M.LMusolf, Manager NRC PDR PKreutzer Nuclear Support Services PDIII-3 r/f DDiIanni Northern States Power Company PDIII-3 s/f OGC-Bethesda l

414 Nicollet Mall EJordan JParlow j

Midland Square, 4th Floor ACRS (10) 1 Minneapolis, Minnesota 55401-i d

Dear Mr. Musolf:

j As.a result of the Surry pipe erosion / corrosion incident in Dacember of 1986, i

the NRC is preparing a report that will reference existing rerearch 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 /corrison

. experience, piping design, feedwater and condensate chemistry and piping materials.

To ensure that both the NRC and the nuclear industry have available a comarehen-sive collection of data regarding erosion / corrosion in feedwater pipes, t1e NRC will assemble a summary of utility information related to ongoing water chemistry i

actions in pressurized water reactors. To enable us to accomplish this task, 1

we ask that you 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 i

realize that parts of the information may already be available to the NRC, but not in a convenient format which is readily accessibh.

Therefore, we request 1

that you assist us by returning for each unit.a singh completed copy of the i

enclosed questionnaire to the Project Manager, U. S. Nuclear Regulatory Commission,-Washington, D. C.

20555, within 60. days of 7ceipt of this letter.

We believe the questionnaire is self explanatory; howa

, if questions arise or clarification is required, please contact your NRC Prsject Manager.

1 This request is covered-by Office of Management and Budget Clearance Number 3150-0011 which expires December 31, 1989. Comments on burden and duplication may_be directed to the Office of Management and Budget, Room 3208, New Executive Office Building, Washington, D. C.

20503.

Sincerely, i

8707300304 870716 Dominic C. Dilanni, Project Manager PDR ADOCK 05000292 Project Directorate III-3 i

P PDR Division of Reactor Projects o

Enclosure:

PWR Erosion-Corrosion Questionnaire h

cc: See next page 0ffice:

LA/PQIII-3 PM/PDIII-3 PD/PDIII-3 Surname: PKredtzer DDilanni/tg DWigginton Date:

07/q/87 07// 9/87 07/t//87 j

i

'i, i

L Mr. D. M. Musolf Prairie Island Nuclear Generating j

l' Northern States Power Company Plant

]

cc.

.j Gert.1d Charnoff, Esq.

Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.

Washington, DC 20037 Dr. J. W. Ferman l

Minnesota Pollution. Control Agency 520 Lafayette Road-St. Paul, MN 55155

)

a Mr. E. L. Watzl, Plant Manager.

1 Prairie Island Nuclear Generating Plant j

Northern States Power Company Route 2 Welch, Minnesota 55089 s

Jocelyn F. Olson, Esq.

Special Assistant Attorney General J

Minnesota Pollution Control Agency 1935 W. County Road, B2 1

Roseville, Minnesota 55113

{

U.S. Nuclear Regulatory Commission Resident Inspector's Office 1719 Wakonade Drive East Welch, Minnesota 55089 l

l Regional Administrator, Region III U.S. Nuclear Regulatory Commission j

Office of Executive Director for j

Operations 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. William Miller, Auditor 1

Goodhue County Courthouse l

Red Wing, Minnesota 55066 l

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l ENCLOSURE 3 PWR EROSION-CORROSION QUESTIONNAIRE (Check or Circle All' Applicable) l Otility Company:

Unit Name NWe i

filled by:

Date:

Ptene No.

l In service: 19....

Water Treatment:

AVT with annonia. morpholine. hydrazine.

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

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

Cooling waters fresh, salt, brackish, cooling tower.

Copper alloy condenser tubing: yes, no. Copper alloy FW heater tubes: LP. HP. none.

Boric acid used sint:e 19... during: operation, layup, low load soaks. other.......

A.

EROSION-CORROSION EXPERIENCE l.

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

i 2.

Erosion-Corrosion of HSR Chevrons or mesh: yes, no.

l Chevron materials stainless steel, carbon steel, other......................

l 3.

Erosion-Corrosion of feedwater piping:

yes, no.

Date found..................

l Feedwater piping materials:

4.

Erosion-Corrosion of:..... elbows...... Ts...... diffusers.......: reducers.

.... valves,.... orifices..... other components (specify)..................

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)...................... 3 9.

Feedwater temperature range where erosion-corrosion found: from.... to..... F

^

10.

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

II.

Inspection methods usedt ultrasonic thickness, radiography. visual, other......

8.

PIPING DESIGN 1.

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

2.

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

.....% load.

3.

Maximum flow velocity when only 1 pump is operating............... feet /second.

4.

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

...... diffusers.

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

...... other components (specIfy)

S.

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

6e feedwater pressures and temperatures (agtual (preferred) or design):

Full load (pressure. osla/ temperature, f):

P:

P:

P:

P:

P:

T:

T:

T:

T:

T:

U 9

y y

l g

y Condensate Pump Cond. Polishers 8F Pump Steam Generators low load (typical

...% of full load):

O P:

P:

P:

P:

P:

T:

T:

T:

T:

T:

U P

(

g y

Q P

4 7

Concensate Pump Cond. Polishers BF Pump Steam Generators Please attach cooles of the heat tyalance diaorams for your actual full load and typical low load.

-g-

b C.-

fEEDWATER ANQ CONDENSATE CHEMISTRY 1.

.Please complete the attached Table.

' 2.

Feedwater chemistry history (average or typical values.. final feedwater):

Year of oper.:

1st

-1974 ~ 'l976 1978 1980 1982 1983 1985 1986 1987 k-pH of FW maximum.

minimum.

)

average.

.pH of condensate maximum.

minimum'.

i average.

D0. ppb maximum.

minimum.

average.

Cat. Cond. uS/cm.

Spec. Cond. uS/cm.

NH. ppb N,4,. ppb

_Mron, ppb Air inleakage.-

SCFM Please send any water chemistry sunnery reports and data.

I

(

3.

Chemical additions 3.1 Ammonias typical concentration in feedwater".... ppb; added at...........

3.2 Hydrazine

typical concentration in feedwater.... ppb; added at.........

{

3.3 Boric acid typical concentration in feedwater.... ppb as B; f

added at..................

i D.

NATERIALS 1.

Feedwater piping - IIst ASTM or other specification numbers....................

2.

Wet steam piping:

3.

Attach results of chemical analysis by you or pib vendors.

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