ML20238E354

Rev a to EE-ISI-002, Condensate Line Erosion Insp Program

ML20238E354
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/07/1987
From:	Seed M, Talbott R PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20238E343	List: ML20238E341 ML20238E346 ML20238E349 ML20238E354 ML20238E360
References
EE-ISI-002, EE-ISI-2, NUDOCS 8709140291
Download: ML20238E354 (19)

Text

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EE-ISI-002 ,

Rev. A CONDENSATE LINE-EROSION INSPECTION ~  ;

PROGRAM

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l Preparec 'cy:

Engineer 7-2 d Date Verifiec Oy: Nb b b6oo O Eng1neer -

S-3-$")  !

Cate Apprevec Oy: _

Y f-7-#7 Nuciear 51te Engineering Manager Date I

1 8709140291 870909 ADOCK 050002 7 gDR

EE-ISI-0002.Rev.JA-

.Page 1 of 5.

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• 3.

CONDENSATE LINE..

EROSION INSPECTION PROGRAM Table of Contents.

SECTION' PAGE f 0bjective......................................... 2 Deterraination of Inspection Points. . . . . . . . . . . . . . . . 2 Method of Inspection.............................. 3 Acce ptance C ri teria . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . 3 R e c o rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4

! Inspection Results................................. 4 Conclusion......................................... 4 l

References........................................ 5-Attachments:

1 - Examination Locations-2 - Requested Inspection Reading Locations 3 - Procedure QCIM-39 4 - Velocity Calculations 5 - Nonconformance Report 87-186-

EE-!SI-0002 Ree. A-3

~Page 2'of 5 1 o .;m i

1 CONDENSATE LINE  !

EifdSION INSPECTION PROGRAM

-j OBJECTIVE This self-initiated program has been established to investigate the possible occurrence of undetected corrosion / erosion induced wall thinning within the Condensate System at Fort St. Vrain. The section.

of this system focused on by this program.is that piping which lies

~

i on the suction side of the Boiler Feed Pumps. -This section;of piping-is being inspected due to the concern generated by the recent failure of a similar line at the Surrey Nuclear Power Station in. Surrey,  !

Virginia. l l

Defined .within this document are the piping ~ points that are to be-  ;

inspected, the method of inspection,.and the criteria for determining i if repair,' replacement or additional inspection is required.

Depending upon the results of the inspections performed per this Engineering Evaluation it may- be necessary .to repeat these inspections at a later date. If this action is deemed necessary then 3 it shall be specified within the " Conclusion" section of this

)

Engineering Evaluation.

DETERMINATION OF INSPECTION POINTS .

l The piping which is of concern to this. inspection programiis that which makes up the suction piping for the Boiler Feed . Pumps. More' specifically, this piping is that which. lies between the Deareator Feedwater Heater (E-3104) and the Boiler Feed Pumps (P-3101, P-3102, and P-3103).

A review of this section of piping has been made to determine the- i most probable areas for corrosion / erosion during either normal or off-normal operating conditions. This determination is based on a combination of the following corrosion / erosion promoting parameters:

High Velocity; generally a concern if greater than 10 feet l per second. For this section of piping this only ' occurs  ;

at the pump intake nozzles whore'the velocity lis as much j as.11.7 feet per second. For all other locations the 4 fluid velocity remains below 9 feet per second.

(Reference Attachment 4). -1 i

Change in Flow Direction; such as elbows,. tees, reducers, l etc.. Generally of greater concern if the fittings. are j less than 10 pipe diameters apart. I l

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-EE-ISI-0002 Rev A Page 3 of 5

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Piping Material; primarily concerned' with= carbon steel piping. The material for this;section of piping is 'A106 Gr. .B carbon' steel with fittings'of A234 GR.'WPB. (See Reference 1).

Oxygen Content; _ a concern if system is deoxygenated (low ppb range). For this piping:section the oxygen content is

. generally maintained below 10 ppb. (See Reference 3:and 4).

Fluid Temperature; generally -of greater concern if-temperature lies' between 195 F . and 440 F. For this section of piping the fluid" temperature 1s approximately:

309 F during normal operation. (See Reference 2).

In consideration of the parameters stated above,..five points of inspection have been chosen. .The details of,each inspection point is provided in Attachment 1.

METHOD OF INSPECTION The wall thickness of the' pipe at each of the' inspection points.will-be measured using. longitudinal wave (" straight beam") ultrasonic- .l techniques. All ultrasonic examinations will, as a minimum, conform.

to the requirement of the PSC QC Procedure.QCIM-39 as it is presented in Attachment 3.

The quantity of readings completed at each-inspection point lshall, at' a minimum, conform to those requested in'

Attachment:

2 unless access is prevented due to local obstructions.

~

If the wall thickness at any inspection location 'is found to be. less than the manufacturer's minumum wall thickness as shown in Attachment.

1, then the inspector shall reduce the inspection grid.to a two inch by four inch matrix to determine the full extent of ' wall thickness reduction.

ACCEPTANCE CRITERIA The primary criteria that will be used for acceptance is the manufacturer's minimal wall thickness. The manufacturer's' minimum wall thickness is equal to the nominal wall thickness minus 'the manufacturer's. tolerance of 12.5 percent as specified in the ASME B&PV code,.Section II, Part'A. The. minimum wall thickness ~for each inspection point is provided in Attachment 1.

If the wall thickness.is less than the manufacturer's minimum wall thickness, Engineering will evaluate on a case-by-case basis' whether j!

the wall thickness has been reduced' to a point where.' repair or ';

replacement is required. The following guidelines shall be' used in .

i making this determination.

l j

ss-isi-Uuu2 nev. ' A Page 4 of 5-

.. c, Is the . wall thickness less than the design minimum wall thickness (TDM)? The thickness, Tgg, is the minimum wall I thickness required for the design pressure and temperature per ANSI B31.1, 1967, Section 104.

Will the wall thickness, TDM, be reached before the next refueling outage?

In addition to wall thickness acceptability Engineering shall also determine if an increase in inspection points is warranted or if additional inspection is required in light of any detected wall reduction.

RECORDS All examinations shall, as a ' minimum, be recorded per the requirements of QCIM-39 as it is presented in Attachment 3. These records shall include .all the applicable signatures and shall be permanently stored at the Fort St. Vrain Record Center.

INSPECTION RESULTS Through the inspections performed per this Engineering Evaluation, a wall thickness below manufacturer's minimum wall thickness.was found at inspection points 70. and 71. This reduced wall thickness was-evaluated via Nonconformance Report (NCR)87-186, This evaluation determined that a significant factor of safety still exists and that no threat of failure exists within the near future.. Due to the uncertainty as to the actual cause of this pipe wall reduction the information obtained will be utilized as baseline data for a repeat inspection.

CONCLUSION The inspection performed per this Engineering Evaluation has confirmed the present integrity of the Condensate /Feedwater piping between the Deareater Feedwater Heater and the Boiler Feed Pumps.

l l Due to the detection of reduced wall thickness and the possibility that this wall thickness reduction is a result of an - ongoing phenomena, this inspection program shall be repeated after approximately one year of service and again after an additional year j of service to determine the rate and cause of this wall thinning l (Reference NCR 87-186). If additional wall reduction is' detected by the subsequent inspections then Engineering shall evaluate the situation to determine the corrective action required.

l I

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EE-ISI-0002 Rev., A Page 5 of 5 o :s REFERENCES

1) Specification 1-N-2 for class 021 piping

2) Process Flow Orawing PF-31-3

3) System Description 50-31

4) Procedure WCP 302, Issue 3

5) Institute of Nuclear Power Operations (INPO), Significant Operating Experience Report (SOER) 82-11

6) Virginia Electric and Power Company (VEPCO) Report, "Surry Unit 2 Reactor Trip and Feedwater Pipe Failure Report" Rev. 0

7) IE Information Notice No.86-106 (Including Supp. 1 and 2):

Feedwater Line Break l

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FORT ST. VRAIN NUCLEAR GENERATING STATION  !

Service

• PUBLIC SERVICE COMPANY OF COLORADO tft EE -ThT -M CHECK LIST OF DESIGN VERIFICATION

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QUESTIONS FOR DESIGN REVIEW METHOD N

• ffM YES NO N/A  !

I U 1. Were the inputs correctly selected and incor'porated ir.to design?

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2. Are assumptions necessary to perform the design activity adequately described and reasonable?

Where necessary, are the assumptions identified for subsequent re-verifications when the detailed design activities are completed?

l d U 3. Are the appropriate quality and quality assurance requirements specified?

{ ] 4. Are the applicable codes, standards and regulatory requirements including issue and addenda properly identified and are their requirements for design met?

U 5. Have applicable construction and operating experience been considered?

[ 6. Have the design interface requirements been satisfied?

d 7. Was an appropriate design method used?

bUU 8. Is the output reasonable compared to inputs?

dUU 9. Are the specified parts, equipment, and processes suitable for the required application?

g 10. Are the specified materials compatible with each other and the design environmental conditions to which the material will be exposed?

)

2 11, Have adequate maintenance features and requirements been specified?  !

[)) 12. Are accessibility and other design provisions adequate for performance of needed maintenance and repair?

4 7][ 13. Has adequate accessibility been provided to perform the in-service inspection expected to be required during the plant life? l i

14. Has the design properly considered radiation exposure to the public and plant personnel?

[J"( R 7 15. Are the acceptance criteria incorporated in the design documents sufficient to allow verification that design requirements have been satisfactorily accomplished?

g Fi-] 16. Have adequate pre-operational and subsequent periodic test requirements been appropriately specified? j l

U 17. Are adequate handling, storage, cleaning and shipping requirements specified?

2 18. Are adequate identification requirements specified?

19. Are requirements for record preparation review, approval, retention, etc., adequately specified?

NOTE: If the answer to any question is no, provide additionalinformation and resolution below.

l RESOLUTION OF DESIGN DEFICIENCIES UNCOVERED DURING THE DESIGN VERIFICATION PROCESS l bdo d CieAC(65 owk LA. 1 0 A S a M V 1 l

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