ML20236H837

Forwards 870716 Request for Info Re Plant Erosion/Corrosion Program.Encl Inadvertently Omitted

ML20236H837
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/20/1987
From:	Chan T Office of Nuclear Reactor Regulation
To:	Cockfield D PORTLAND GENERAL ELECTRIC CO.
References
TAC-65727, NUDOCS 8708050361
Download: ML20236H837 (1)

Text

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2 0 JUL 1987 DISTRIBUTION ^

M cket Filee A Docket No.: 50-344 NRC & Local PDRs PD#5 Plant GHolahan Mr. David W. Cockfield JLee Vice President, Nuclear TChan Portland General Electric Company OGC-Bethesda 121 S. W. Salmon Street EJordan/JPartles Portland, Oregon 97204 ACRS (10)

Dear Mr. Cockfield:

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SUBJECT:

TROJAN EROSION / CORROSION QUESTIONNAIRE By letter dated July 16, 1987, the staff requested information regarding Trojan's Erosion / Corrosion program. However, the referenced Enclosure was inadvertently omitted.

Enclosed is the referenced Enclosure along with the cover letter.

Sincerely, l

Oridnal signed by Terence L. Chan, Project Manager Project Directorate V Division of Reactor Projects - III-,

IV, V and Special Projects

Enclosure:

As stated cc: See next page I

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DRSP/ DV fh DRSP/PDV j TChan:cd GWKnighton l 7/20/87 7/.?O/87 0FFICIAL CORD COPY C

8708050361 870720 PDR ADOCK 05000344 P PDR l l

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1. 'o g UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION r, a wAsmNGTON, D. C. 20555

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Docket No.: 50-344 16 JUL 1987 l

Mr. David W. Cockfield 1 Vice President, iiuclear Portland General Electric Company 121 S. W. Salmon Street t

Portland, Oregon 97204

SUBJECT:

TROJAN EROSIGN/ CORROSION QUESTIONNAIRE

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

l To ensure that both the NRC and the nuclear industry have available a )

comprehensive collection of data regarding erosion / 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 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 I not in a convenient format which is readily accessible. Therefore, we request j your assistance by returning a completed copy of the enclosed questionnaire within 60 days of receipt of this letter. We believe the questionnaire is self explanatory; however, please contact me if questions arise or clarifi-cation is requhed.

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i This request is covered by Office of. Management and Budget Clearance Number -J 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.

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pp /' O T rence L. Chan, Project Manager l Project Directorate V j Division of. Reactor Projects - III, IV, V.and Special Projects

Enclosure:

PWR Erosion-Corrosion Questionnaire l

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1 Enclosure

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I PWR EROSION-CORROSION @JESTIONNAIRE (Check or Circle All Applicable) J l

i Utility Company: Unit Name: HWe i 1

Filled by: Date: Phone No.

In service: 19 .... Water Treatment: avl with annonia, morrboline, hydrazine.

Condensate polisherst none. cation, pcwdex, 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 since: 19 ...; during: operation, layup, low load soaks other....... j 1 . l l A. EROSION-CORROSION EXPERIENCE 1

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

3 2. Erosion-Corrosion of MSR Chevrons or mesh: yes, no.

1" Chevron material: stainless steel, carbon steel, other .....................

3. Erosion-Corrosion of feedwater piping: yes, no. Date found ...................

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

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

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

S. Erosion-Corrosion 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 (44 10. Inspection frequency for feedwater piping ..... years. Steam lines ..... years.

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

B. 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) ...........................................

5. Maximum flow velocity in wet stean. 71 ping ............ feet /second.

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

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

P: ..... P: ..... P: .... P: ..... P: .....

T: ..... T: ..... T: .... T: ..... 1. ..... r g " 7 .

/ y y Qy Cnndensate Pump Cond. Polishers Of Pump Steum Generators low load (typical ...% of full load): #'i P: ..... , P: ..... P: .... P: ..... P: .....

y T: ..... T: ..... T: .... T: ..... T: .....

g if 7 r gg' c , F g 4 7 Condensate Pump Cond. Polishers +/~ Bf Pump Steam Generators Pleasq_ attach cooles of the beat balance diaorams for your actual full toed and l , typical low load.

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C. FEEDWATER AND CONDENSATE CHEMISTRY

l. Please conplete the attached Table.

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

Year of oper.: 1st 1974 1976 1978 1980 1982 1983 1985 1986 1987 pH of FW maximum . . . . . . . . . . .

minimum . . . . . . . . . . .

average . . . . . . .

pH of condensate m8ximum . . . . . . . . * . .

minimum . . . . . . . . . . .

SVerage . . . . . . . . . . .

D0. ppb maximum . . . .. . . . . . . .

l minimum . . . . . . . . . . .

average . . . . . . . . . . .

Cat. Cond. uS/cm . . . . . . _. . . . .

, Spec. Cond. uS/cm . . . . . . . . . . .

NH . ppb .. . . . . . . . . . .

Nk,. ppb . ._, . . . . . . . . .

ron, ppb . ., . . . . . . . . .

Air !nleakage. -

SCFM . . . . . . . . . . .

Please send any water chemistry summary reports and data.

3. Chemical additions

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3.1 Ammonia

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

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

3.3 Boric acid: typical concentration in feedwater .... ppb as Bs, added at ..................

D. MATERIALS

1. Feedwater piping - list ASTM or other specification numbers ....................

2. Wet steam piping: ..........................

3. Attachresultsofchemicalanalysisbyyouorpibevendors.

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