ML20045H975

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Forwards Request for Relief from ASME Code,Section XI Requirements,Per GL 90-05,to Make Interim Repairs to Leak in Svc Water Sys Piping Inlet Nozzle to 3CCI*EIB Local to FW-10 as Alternative to IWA-4000/7000 Repair/Replacement
ML20045H975
Person / Time
Site: Millstone Dominion icon.png
Issue date: 07/15/1993
From: Opeka J
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
B14545, GL-90-05, GL-90-5, NUDOCS 9307220204
Download: ML20045H975 (23)
v • d • e


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NORTHEAST UTILITIES cener. Orrice, . soia n sire.t. B.,nn. cc,nn.ciicui l sYUEur .7ENrU** P.O. BOX 270 7$C* [.',"$~,,_ HARTFORD, CONNECTICUT 06141-0270 k k J w m wru w.m. (203) 665-5000 July 15,1993 Docket No. 50-423 B14545 Re: ASME Section XI GL 90-05 10CFR50.55a(g)(6)(1)

U.S. Nuclear Regulatory Commission Attention: Document Control Desk .

Washington, DC 20555  :

Gentlemen:

Millstone Nuclear Power Station, Unit No. 3 Relief Reauest From ASME Code Section XI Reouirements The purpose of this letter is to request, consistent with' the provisions of NRC Generic Letter (GL) 90-05, relief from ASME Boiler and Pressure Vessel ~

Code Section XI requirements pursuant to 10CFR50.55a(g)(6)(i). Attachment 1 provides a description of actions taken by the Northeast Nuclear Energy-  :

Company (NNECO) to make interim repairs to a leak in the service water system piping inlet nozzle to 3CCI*EIB local to FW-10 as an alternative to an IWA-4000/7000 repair / replacement.

l Consistent with the provisions of GL 90-05, NNECO is submitting ' this relief request for a tempo ary noncode repair. Code repair of the degraded piping is planned for the next refueling outage expected to begin later in July 1993.

The Resident Inspector at Millstone Unit No. 3 has been informed of this repair and, as has been our practice, we will keep the Resident Inspector fully informed of all future repairs.

  • Please contact us if you have any questions.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 0O/'N J. F. Opekal O Executive Vice President cc: T. T. Martin, Region I Administrator '!

V. L. Rooney, NRC Project Manager, Millstone Unit No. 3 P. D. Swetland, Senior Resident Inspector, Millstone Unit Nos. 1, 2,

.und 3 200081 (

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Docket No. 50-423 B14545 Attachment 1 Millstone Unit No. 3 Relief Request From ASME Code Section XI Requirements y

July 1993 l

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NORTHEAST UTILITIES TRACKING FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS MUST BE COMPLETED AND FILED WITH NRC WITHIN 30 CALENDAR DAYS UNIT: MILLSTONE UNIT 3 NCR# 393-076 DATE: 06/15/93 TIME: 0220 <

1.0 ORIGINATOR Processing Time: should not exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

1.1 COMPLETE SECTION 1 OF ENCLOSED FORM Complete 1.2 NOTIFY RESIDENT NRC INSPECTOR Person Contacted: Russ Arriahi Date: 6/15/93 1.3 FORWARD THIS FORM, NCR AND NDE MEASUREMENTS TO NUSCO SUPERVISOR, STRESS ANALYSIS ENGINEERING SECTION P

Originator: Gary Swider Date: 6/15/93 2.< , 'ESS ANALYSIS SECTION Date Received: 6/15/93 Processing Time: 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from flaw detection for preliminary operability assessment.

25 calendar days from flaw detection for final operability assessment.

2.1 PREllMINARY FLAW EVALUATION l l

Evaluation Completed By: R. E. DeContot. Date: 6/17/93 i

Notify Plant j Person Contacted : Gary Swider Date: 6/17/93 l

doc: TF3 Page 1 of 2 July 9,1993

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NORTHEAST UTILITIES TRACKING FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS 2.2 END OF CYCLE FLAW EVALUATION Evaluation Completed By: Rav DeConto Date: 7/09/93 2.3 REVIEW RESULTS OF AUGMENTED INSPECTION Completed By: Hav DeConto Date: 7/09/93 If additionalinspections are required, notify plant.

No additionalinspections are required.

2.4 FORWARD COMPLETED FORM TO NUCLEAR LICENSING j

Super is_or, Stress. Analy is Section:  ;

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Date : 7/09/93

/k. J. Mawsor[ ' ' i 3.0 NUCLEAR LICENSING 1

Processing Time: should not exceed 30 calendar days from flaw detection.

3.1 RELIEF REQUEST SUBMITTED By: P.G. Patton Date: 7/15 /93 Docket No. 50-423 DOC: TF3 Page 2 of 2 July 9,1993 L-

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. NORTHEAST UTILITIES  ;

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~ FORM FOR RELIEF REQUEST FROM ASME SECTION XI REUUinEMENTS' UNIT: Millstone Unit 3 'NCR # 393-076 DATE: 6/15/93-.

TIME: 0220 1.0 ORIGINATOR i

1.1 DESCRIPTION

OF FLAW .

Leak in inlet nozzle to 3CCl* E1B (high head safety injection / service water heat - ,

exchanger) local to FW-10.

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Piping / Component Drawing No.: Cl-CCl-E1B [

=t Pl&D No.: EM-133B 1.2 IMPRACTICALITY OF PERMANENT REPAIR Repair cannot be completed in 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO.

1.3 DESCRIPTION

OF PROPOSED TEMPORARY REPAIR installation of soft rubber patch weighing less than 2 pounds.

1.4 SAFETY SIGNIFICAN@ System Interaction Evaluation .,

Flooding: Pinhole laak at this time. Floor dr. i. s are adequate for drainage. y Jet Spray: Leak sprays will not affect any safety-related power supplies, j Loss of Flow: Temporary patch will prevent loss of flow.

Other Interactions: None Failure Consequences? Can be isolated.

impact to Safe Shutdown Capability? Total failure would result in loss of one train high head safetv injection (SlH).  !

1.5 ROOT CAUSE INVESTIGATION.-

Root Cause

Description:

Classic wall loss of solid 90/10 cu-ni due to turbulent flow downstream of an elbow causing locally high flow velocities. q Other Systems Affected: None- ,

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l doc: TF3 . Page 1 of 4 . July 9,1993 l o

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NORTHEAST UTILITIES FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS 1.6 AUGMENTED INSPECTION (must be completed within 15 days of flaw detection)

Assessment of overall degradation of the affected system: Leak is typical of erosion / corrosion in SWP piping. These leaks do not result from large areas ~ of damage but from very localized wall loss. An inspection program has been initiated for small bore piping.

Additional examinations required (based on root cause) - specify number of inspection locations - also specify frequency of inspections: [ ten most accessible locations for high energy piping and five for moderate energy piping systems]

Five additional locations were chosen, as listed below:

a) FW-8-1 3CCl

  • E1 B d) FW-20 3CCl*E1B b) FW-13-13CCl'E1B e) FW-22 3CCl*E1B c) FW-16-1 3CCI* E1 B Description of areas selected for augmented inspection: Small bore piping of similar configuration.

2.0 STRESS ANALYSIS UNIT 2.1 DESIGN DETAILS System: High head safety injection / service water heat exchanger Component: inlet nozzle (near FW-10)

Piping Size & Schedule: 2" / 0.083" Nominal Wall Thickness: 0.083" Safety Code Class: Class 3 Material: SB 466 No. 706 0

Design Pressure: 100 psig tube side / 35 psig shell side Design / Operating Temperature: 95 / 33 - 75 (inlet) i Code Minimum Wall Thickness: ' O.014" l I

doc: TF3 Page 2 of 4 July 9,1993

NCRTHEAST UTILITIES FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS 2.2 FLAW CHARACTERIZATION Flaw Description / Size: (i.e., flaw size, adj.: cent wall thickness, single / multiple flaw, total area examined, etc.) The flaw is highly localized. The through wall portion of the flaw is 1/8" in diameter and the adjacent wall / nominal wall is ,

0.083".

Flaw Location: The flaw is located dowrstream of FW-10.

Method of Examination: UT Flaw Type: Pinhole due to erosion / corrosion Referenced UT Measurement Report: Attached to NCR 393-076 2.3 PRELIMINARY FLAW EVALUATION

SUMMARY

Preliminary Operability Assessment Details:

Method Used: Draft Code Case N513 (dated 8/13/92)

Limiting Flaw Size: Total flaw 2.375". Through wall portion of flaw 1.19"/

Minimum average wali thickness outside of the flaw must be at least 0.070 inches.

Period of Time to Reach Limiting Flaw Size: Approximately .35 years.

Eva!aation

Reference:

Memo MCE-SA-93-238 2.4 END OF CYCLE FLAW EVALUATION

SUMMARY

):

Final Operability assessment Details:

Method Used: Draft Code Case N513 (dated 8/13/92)

Estimated Erosion Rate: 0.012 in / yr Projected Flaw Size: Total projected flaw size is .50 in, total projected through wall portion is 0.375".

Periad of Time to Permanent Repair / Replacement: Permanent repair for this flaw i is scheduled for the next refueling outage (scheduled to begin on 7/31/93) l ooc: TF3 Page 3 of 4 July 9,1993

NORTHEAST UTILITIES FORM FOR RELIEF REQUEST FROM ASME SECTION XI REQUIREMENTS 2.4 END OF CYCLE FLAW EVALUATION

SUMMARY

(cont'd)-

Provide a Discussion of Evaluation of Design Loading Conditions:

Loading conditions evaluated include: pressure, deadload, thermal and seismic.

All Code stress equations were considered and were determined to be acceptable.

Evaluation

Reference:

Memo MCE-SA-93-238

.g Discussion of Augmented Inspection Results:

Five additional inspections of susceptible components were performed. These -

five inspections resulted in the generation of two additional NCRs due to wall.

thinning. The wall thinning described in the NCRs (NCR 393-070 and 084) was determined to be acceptable in Memo MCE-SA-93-237.

i 2.5 FLAW MONITORING Walkdown Frequency: (for leak monitoring) o At least once per shift.

1-Frequency of Follow-up NDE: (for erosion rate assessment)

At least once every three months.

2.6 ADDITIONAL COMMENTS (scope, limitations, and specific considerations)

None 2.7 EXCEPTIONS TO GL 90-05 / DRAFT ASME CODE CASE The evaluations were performed in accordance with GL 90-05 and the Draft Code Case N513 (dated 8/13/92) 2.8 HEFERENCES / INPUTS NCRs 393-076,070 and 084 Memos MP3-E-93-418,482, and 483 Memos MCE-SA-93-237 and 238 cc: Originator, Supervisor, Stress Analysis Engineering Section, Department Director, Nur. Mar Records doc: TF3 Page 4 of 4 - July 9,1993

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- PART 1 3Cl-CCl-E1 B (FW-10)

Objective: The objective of this evaluation is to qualify a pin hole leak in the 3CCl*E1B heat exchanger (HX) as described in NCR 393-076 for structural integrity. This evaluation qualifies the component (2" pipe) through the end of the next scheduled outage.

Parameters:The following parameters will be applied in this evaluation (Reference 1):

Design Pipe Size Outside Wall thick Pressure Temp Allowable i Nominal Dia. (in) ~ Schedule (in) - (psi) (F) Material Sh (psi) j 2 2.375 nonstd 0.083 l 100 95 SB466 706 _

8700 l 1

1.0 SCOPE This evaluation is applicable to:

a) Class 3 Section lli Subsection ND piping b) Operating conditions <200F, < 275 psig c) Pipe, tube, fittings and flanges - NO WELDING d) Structural integrity only. This does not demonstrate system operability.

e) t-adj is used throughout this calculation, t-adj is always the predicted t-adj. .

3.0 FLAW EVALUATION GL 90-05 evaluation methods do not apply to heat exchangers. However, these methods are applicable herein because the heat exchanger is fabricated from piping components.

This evaluation is applicable to non-planar (through wall holes) and is performed in accordance with Generic Letter 90-05 and DRAFT Code Case N513 (8/13/92) (Reference 3).

S.1 tmin and t-adj Determination a) Determine tm per construction code (Reference 2).

tm = P

  • Do / (2 * (SE + Py) + A P= presssure, psig Do= outside diameter, in S= stress allowable, psi E= joint efficiency = 1.00 y= a coefficient = 0.4 ,

A= additional thickness (corrosion allowance, threading, etc...) l

= 0 for copper nickle pipe

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.(4) (Ref. 6) Remaining' tmeas Instrument

+ Calibrate l Years Wear of Life Outside tm average Tolerance Service Rate Required tadj (1) j

Diadin) (in) (in) (in) (yrs) (in/yr) (yrs} (in)  ;

2.375l 0.0136 0.078 0.004 7.21 0.0115 0.316 0.0704 Note 1) The t-adj value is the predicted remaining wall at the end of the next l scheduled refueling outage (07/31/93 to 10/09/93) .  !

Note 2) The component considered in this evaluation has been inservice since April 1986.

Note 3) The measured data is per Reference 5.

Note 4) A!! equations within this evaluation are based on the measured average wall thickness -

with the exception of the branch area reinforcement check (see section 3.2 (b)). Use of the average wall thickness for the SIF and the stress calculations is considered to be appropriate.  ;

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3.2 Branch reinforcement Evaluation Method (Reference 2) a) tadj must be greater than 2*tm

-h Pipe Size Nominal - tadj 2*tm 2 0.0704 0.0272 acceptable b) The postulated circular diameter, d, shall not exceed the pipe nominal outside diameter.

Predicted i d Maximum - Total Flaw. Predicted flaw is set Pipe Size' Outside -- Allow Flaw Circ Length equal to 0.5 inches.

Nominal Dia. (in) Length (in) (in) 2 2.375 2.375 0.50 OK The following branch connection reinforcement calculation is performed in accordance with ND 3643.3 (Reference 2).

Required reinforcement area = 1.07* tmh *di A1 = area provided by excess wall in the pipe = d2*(Th - tmh)

The mill tolerance on Th is ignored since UT is available.

Note: d2 has been set equal to the maximum allowable hole size.

Reinforce Required Excess Pipe Size tmh d1 d2 Zone- Reinforce Pipe Area ~ .

Nominal - (in) fin). (in) tadj Area, in ^ 2. A1, in ^ 2

__ 2 0.0136 2.38 2.38 0.0444 0.035 l 0.073 OK Note: The excess reinforcement pipe area is based on the rninimum area in the reinforcement zone (i.e. 0.052"). Note that the low reading of 0.048" is outside of the reinforcement zone.

c) Determination of unreinforced branch connection stresses per ND 3650 SIFPer inom tadj .

Pipe Size t-adj Figure SLP SLP Nominal tadj Rmadj h SIF NC3672.9 (psi) - (psi)1 2 0.070 1.15 0.061 5.804 2.1 715 844 tnom .

t-adj Section 'Section Pipe Size Modulus Modulus Nominal tadj_ , Rmadj__(in ^ 3) (in ^ 3) 2 0.070! 1.15 0.331 0.285 l l

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  • I The following table presents both the tnom & t-adj corrected Code stress equations:

tnom  : t-adj . Allowable t-adj Point Stress Stress '- Stress- Factor Equation Number (psi) (psi) (psi) of Safety 8

Sustained 1018/1019 1991 4936 8700 1.76 OK 9 Norm /Up Occasional 1018/1019 2972 8083 10440 1.29 OK 10 Thermal 1018/1019 4406 14135 13050 0.92 NO GOOD 11 Sus + Th 1018/1019 6397 19071 21750 1.14 OK-9 Faulted Occasional;1018/1019 3437 9575 20880 2.18 OK Failure of Eq 10 is acceptable if Eq 11 is met d) An additional limitation is placed on the through wall portion of the maximum hole size. The through wall portion of the crack may not exceed d/2 or 5 inches.

tm- 0.014 in Additional Predicted Wall Thinning 0.004 in .

. Minimum Wall Required To Frevent Expansion'of the Through Wall Flaw 0.017 in Measured Through Wall Portion of Flawl 1/8 in Maximurn Allowed Through Wall Portion of Flaw

'(lesser of d/2 or 5 inches)- 1.188 in Predicted Through Wall Portion of Flaw (1) 0.375 in OK Note: 1) This value includes a .25 inch tolerance.

Note: 2) A wall thinning evaluation was not performed for band 3A - H (containing a 0.048" thick area). This is acceptable because the average thickness of band 3A - H is equal to the average thickness of the band which contains the hole and which was evaluated.

Additionally the separation criteria specified in GL 90-05 has been met.

References:

1) S&W Stress Calculation 12179-NP(F)-622-XD, Revision 4
2) ASME Section til 1971 Edition through the 1973 Summer Addenda
3) ASME Draft Code Case N513 (8/13/92) and GL 90-05
4) NCR 393-076
5) Attached UT data
6) Memo MP3-E-93-418 G. Swider, to: R. DeConto, dated June 15,1993 Memo MP3-E-93-438 G. Swider, to: R. DeConto, dated July 9,1993 i

Computer Storage: c:\123r3\90-05.bem\n393076.wk3  !

PARK 2 . 3Cl-CCI-E1B (FW-10) jective: The objective of this evaluation is to determine the minimum wall which will still meet all Code equations. This is an iterative process where the final tadj selected results in just meeting the limiting Code equation. An estimate of remaining life is also determined here.

Parameters:The following parameters will be applied in this evaluation (Reference 1): l Design . .

i Pipe Size Outside Wall thick Pressure Temp Allowable Nominal Dia. (in) Schedule (in) (psi) (F) Material ' Sh (qsi) >

2 2.375 nonstd 0.083 100 95 SB466 706 8700 1.0 SCOPE This evaluation is applicable to:

a) Class 3 Section lli Subsection ND piping b) Operating conditions <200F, < 275 psig ,

c) Pipe, tube, fittings and flanges - NO WELDING d) Structural integrity only. This does not demonstrate system operability.

e) t-adj is used throughout this calculation. t-adj is always the predicted t-adj.

3.0 FLAW EVALUATION This evaluation is applicable to non-planar (through wall holes) and is performed in accordance with Generic Letter 90-05 and DRAFT Code Case N513 (8/13/92) (Reference 3).

3.1 tmin and t-adj Determination f a) Determine tm per construction code (Reference 2).

tm = P

  • Do / (2 * (SE + Py) + A P = presssure, psig Do= outside diamater, in

~

S= stress allowable, psi E= Joint efficiency = 1.00 y= a coefficient = 0.4  ;

A= additional thickness (corrosion allowance, threading, etc...)

= 0 for copper nickle pipe Instrument Remaining' tmeas + Calibrate Years of Wear Life

~

Outside. tm average Tolerance Service: Ra:e Required tadj {1)

Dia. - (i_n) (in) (in) (in) (yrs) (in/yr) (yrs) (in) 2.375 0.0136 0.078 0.004 7.21 0.0115 0.316 0.0650 Instrument + Calibration Tolerance (in) 0.004 Estimated minimum average wall required (in) 0.069 USE 0.070 l Remaining Life (yrs) 0.35 USE 0.35 Note 1) The t-adj value is selected.

Note 2) The component considered in this evaluation has been inservice since April 1986.

Note 3) The measured data is per Reference 5.

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l 3.2 Branch reinforcement Evaluation Method (Reference 2) a) tadj must be greater than 2*tm Pipe Size Nominal tadj 2*tm 2 0.0650 0.0272 acceptable b) The postulated circular diameter, d, shall not exceed the pipe nominal outside diarneter.

. Predicted '

d Maximum Total Flaw '

Pipe Size _ Outside Allow Flaw Cire Length Nominal Dia. ,(in) Length (in); (in) ,

21 2.375 2.375l 0.50 OK The following branch connection reinforcement calculation is performed in accordance with ND 3643.3 (Reference 2).

Required reinforcement area = 1.07* tmh *di A1 = area provided by excess wall in tne pipe = d2*(Th - tmh)

The mill tolerance on Th is ignored since UT is available.

Note: d2 has been set equal to the maximum allowable hole size.

Reinforce Required L Excess Pipe Size tmh di d2 Zone Reinforce Pipe' Area .

Nominal - (in) (in) (in) tadj Area, in ^ 2 . A1, in ^ 2 '

2 0.0136 2.38 2.38 0.0444 0.035 0.073 OK c) Determination of unreinforced branch connection stresses per ND 3650 SIF Per. tnom tadj Pipe Size t-adj - Figure SLP SLP Nominal tadj_ Rmadj h SIF. NC3672.9 (psi) Jsi) 2 0.065L_ 1.16 0.056 l 6.129 2.1 715 913 tnom t-adj Section Section Pipe Size , Modulus Modulus Nominal tadj Rmadj (in ^ 3) lin^3)_, ,

2 0.065 1.16 0.331 0.265 1

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The following table presents both the tnom & t-adj corrected Code stress equations:

tnoni t-adj Allowable. __t-adj Point - Stress- Stress Stress Factor Equation ' Number- (psi) - (psi) - (psi) of Safety; 8

Sustained 1018/1019 1991 5559 8700 1.56 OK 9 Nor/Up Occasional 1018/1019 2972 9132 10440 1.14 OK 10 Thermal- 1018/1019 4406 16046 13050 0.81 NO GOOD 11 Sus +-Th 1018/1019 6397 21606 21750 1.01 OK 9 Faulted Occasional 1018/1019 3437 10826 20880 1.93 OK Failure of Eq 10 is acceptable if Eq 11 is met .

d) An additional limitation is placed on the through wall portion of the maximum hole size. The through wall portion of the crack may not exceed d/2 or 5 inches.

tm 0.014 in Additional Predicted Wall Thinning - 0.004 in Minimum Wall Required To Prevent Expansion of the Through Wall Flaw 0.018 in Measured Through Wall Portion of Flaw [ 1/8 in Maximum Allowed Through Wall Portion of Flaw (lesser of d/2 or 5 inches) 1.188 in Predicted Through Wall Portion of Flaw (1) 0.375 in OK Note: 1) This value includes a .25 inch tolerance.

1

References:

1) S&W Stress Calculation 12179-NP(F)-622-XD, Revision 4
2) ASME Section lli 1971 Edition through the 1973 Summer Addenda
3) ASME Draft Code Case N513 (8/13/92) and GL 90-05
4) NCR 393-076 l
5) Attached UT data .l Computer Storage: c:\123r3\90-05.bem\393076e.wk3 Prepared By:_[1 ,Ch Date: 9/9/93 RE Pe G..,b Reviewed By: ~ C O Date: 7- 9 -73 l (PREM c CcQHA)

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e Evr ULTRASONid INSPECTION ' i

_MILLSTC

~

DATA SHEET DRAWING NUMBER: . /2 / 7 9 - c/ - cc /- e/M -

i i

LINE NUMBER: J c c /

  • Era l Cnez.srcr) COMPONENT NUMDER: _ s/g COMPONENT TYPE:__ %.cr coupunc, i

$12E: 2. " SCHEDULE:

NOMINAL WALL: . o U' _.

. . . . . . . .................Al .,..

. . . . . . . . . . . . . . . . . , . . . .. . . . . . . . .T0 . . . .

. . I1 6. . . .

t r

.im..........@........<

W .-

4

.I

/ . . . .  ?.. . . . . . .

2,...

  • G. . "

ygt. 3 FLOW _

. _ . . . c ., . .

. . c

. . . . . .. ' ,......s... . . . .

Q v . 5

_ _ - - . . Q. . . .

E

..).....

  • . e ...................... ***

INSPCCTOR: m,) h/o/d DATE: /-/F U

'V.

TOTAL P.DG

% 4

  • I
  • P300 E OLC.ilBL scM41.0At Eaic Ent$$2LLD.

Sees t 4 Cole s & Structlair: Elecinda Offcot :-S A 8 C 0 E F. C E Re#4 RMtt Oslam Are

10. hts Less 0.w4 8.cs2 8.csE 0.000 0.082 0.064 0.0018.0510.012 8. css >

8 0.080 0.844 0.0C3 0.070.0.005 0.07S 0.0810.041 0.068 0.8C& c.82 8.070, 3 0.006 0.6010.05G 8.078 0.498 0.004 0.992 4.080 0.0010.475 a.e2s 0.Osa 4 8.088 4 0810.087. I.000 0.9B7 0.ed10.0tC. 8.046 0.00L 6.083 A008 8.087 S 0.00 4.92 CA00 0.092 8.887 0.895 AMS 8.007 0.022 0.4M 0.007 8.888 8 0.006. 0.001 S.Dit 8.fM 8.NF a.886 4es4 0.0$0 0.001 6.696 0.0C1 8.000 7 0 CM 0.003 0.865 8.000 0.087 8.00fs 4.004 0.08E 0.006 8.tM C.014 4.M0 8 0.0to. 0.B:4 8.002 8.Wa 3.464 0.648 0,s57 8.006 0.000 0.067 4 006 8.900 A E C 4 ( F C u Celses C.3015.802 8.005 8.003 0.00k C.000 C.987 8.090 .s-,..,.,

Celem.O.800 0.044 8.QE3 0.675 0.086. O.873 0.0518 ML Delta 0.0210.832 0.012 0.0110.00E 0.8L10.D06 8.001 A e 0.6E7 0.000 0.osG 0.087 0.t8F 0.0010.044 s.ct?

fettfen i m m flamiam teoding - 4.085 ( F, c) Aver 4ps 0.0GT tasciam Aca4tets = 0.063 ( E, C) 31sndard Owleth , 0.005 Tetal Rosategs ,sa THE A%r vAcuns ARE NcT ( om >h>st.E D To 4E. LEG I6 L E. ,

THE F O t t u ~ W C= W r48ER3 w 2 A E l TI%d ste.18 E D F Rm TttE AhE VALuE.5 AMD W E4 C VCA FJ ED FoR- Ac m stAc%

A B C D E F G H AVERAGE

^

1 0.086 0.088 0.084 0.092 0.086 0.080 0.082 0.084 0.0853 2 0.080 0.084 0.063 0.079 0.086 0.076 0.081 0.083 0.0790 3 0.086 0.091 0.086 0.075 0.088 0.084 0.082 0.088 0.0850 4 0.088 0.091 0.087 0.090 0.087 0.083 0.086 0.086 0.0873

.5j 0.087 0.089 0.090 0.092 0.087 0.085 0.085 0.087 0.0878 6 0.086 0.091 0.093 0.090 0.088 0.086 0.086 0.088 0.0885 7 0.090 0.090 0.095 0.090 0.087 0.085 0.086 0.088 0.0889 8 0.091 0.092 0.092 0.092 0.091 0.089  : 0.087 0.090 0.0905 l AVE l 0.087 l 0.090 l 0.0861 0.088 l 0.0881 ).084 l 0.084 l 0.087 l

+ ,

f

. . (-- -

c . .,

I FIGURE 2 Y C-

$ Sepec,k n on P8e 9 o- c,5 ULTRASONIC THICKNESS MEASUREMENT 3g MANUAL /MAPPlHG SHEET 724ty, O > 7 x,og ,jg//

COMPONENT ID/N4E7' CbvP4/4 fw to COLUMN - CIRCUMFERENTIAL LOCATION h E \~ G N WGLb w y A E CL

,y r ,

l i  !.

r  :

7 1 I

- 4 ' ' ,\

FL L. ,.. . . . ...

.. I O 5 \

I

\

W --

\

l

' f A-ROW - AXIAL g W, l LCCATION J- Q s ' '

{g ,

2

~ . /%'%

5 [osfW l i l WELD

, og ., ,,y g Q) h g,,l, p ,,gt ,, g, g,3 7g m- '

+e gy' df

i.

l NOTE: 1.oW AREAC t4 cat *

,D 30, f l .

F3 mpg 5 40 pguen;  ! l l l!

F N j 3 MD C. 2.-J APPCAP,.45 1 l ll } -

l.oV UZ6 Mens My ,

l l l I ' '

doMrN6L W4U. IS Foo@ [ '

IMNCAbIA7If y ouT31bc *ndt - -

l ll A Rear.

1 l j. l 1

)

g q-

- - I l ) , I ,

i -

l EX, AMINE .- .) . ._ LEVE . _ /- - OATE_[(-/f-U i BEVIEWEB p[ !pi Wf~ LEVEL M/d DME_d"/I'E5 -

.. 0 ,. -

Rev:

8 --

- Procedup NU.UT 30 Page. to of to u2em.m '

8 l

i i i  ! I

6

.,g...

i.

IiNHrl'HEAST LFFIEJTIIHi g_

9

  • <ci

.n, ncewa .<=. - '

cwmi.uw- $

appteILRt UTE848 M5NCE DDepakt saceressiast auctgas tmalM touement

.g

' June 15.1993 Mrd-E-93-418.

To: Ray DeConto-MCE/SA - Berlin From: a wider Unit 3 Engineering .

Subject:

Accuracy of UT Measurement Systerns Used on Salt Water Systems -

The ultrasonic thickness measurements on the following Service Water piping as referenced on NCR 393-076 were taken using a Stresstel T-Scope (S/N CL 730) with'a Stress-Tel $ mhz probe. The inspection had an accuracy of 0.003" over the entire range inspected. Calibration sheets documenting the above accuracy and calibration have been attached to the NCR.

If you have any questions, please call me at MP3 extension 5381.

cc: D. R. MacNeill NCR 393-076 h '.

-k', '

'l q

( .-.

. na s seostrusarrumrnes

- s a '""*~'*"

5 .

t w 9 a _- ._.T.2'*""

~

'sumunnus July 9,1993 MP3.B-93-483 i

To: Ray DeConto MCE/SA- Berlin s

Pan: Gary ' der ,, ..e Unk 3 Engfricerfog -MIllsone: '

Subject:

In Service Datas for SWP Piping and Other Infonnation The piping identified in NCRs 393470,393 0 6, and 393 084 is all original piping which was placed in service at t!m end of Service Water system testing in July 1985.

Additionally, I have reviewed the attached data for NCR 393-076 and it is identical to the original data shed attached to the NCR.

If you have any questions, please call me at MP3 extension $381.

cc: W. V. PJchter M./ ACHE 3 f5pt. ,

NCR 393-070 NCR 393 076 ,

NCR 393 084 e

l g erv.m oo .

TOTAL P.01 i

~

n w

, c:.;. '

~

d 'r','~ : r ';i * , w.:;;,g.g,y;pygpiggg gg,grg ygg ggy,.g,gy,,,y. ,gy

. /.r4 0.006 0.088 0.084_ 0.092 0.086 0.080 0.0B2 E084 0.0853 E - . f .- R2 0.0e0 -0.o84 aoss ao7e o.08s -o. ore 0. cat o.oss F.onRT

' e ,-. g 0.00s o.091 aoss nors o.5 0.084 0.0a2 o.oss 7.'6555' am av4f:o.0es o55TT657 tow ~Tos7 T6sa ooes oose

")::4e

. o.os7 c.ose - 0.000 acef 0.0s7 c.oss c.1lilir o.asy nos78

. ; . ; - dwm o oet - ACE 555 aoss oW is; ooss o.oes d2iiFe Roses"

. . . wiz : o.000 t o.000 0.00s o,000 T687 d'555 ~ o.06~o.o88 0.0881T

,. jZ/g o091

_ . 0.092 o.002 o.002 0.001 0.089 a.ost, o.000 -0.5555'

, , ', . LAVE l 0.087l 0.090l o.o86l o.088l o.088l 0.064I c.084l o.087]

+

y ..

.4 i..,- . .

't 4 4 4.

+

t 4

=

. /:

.. r 4 y ,-

TOTAL P.01 C __ _1t .
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