ML20203G508

Requests Revision to Previously Approved Relief from ASME Section Xi,Paragraph IWA-5250 to Permit Performance of Code Repair in Fourteen Days After Discovery in Place of Structural Analysis & Use of Alternate non-destructive Exam

ML20203G508
Person / Time
Site:	North Anna
Issue date:	02/24/1998
From:	Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20203G511	List: ML20203G508 ML20203G519
References
98-037, 98-37, NUDOCS 9803030006
Download: ML20203G508 (17)

Text

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- Vimisis Ei.iri nic ANi> l'OWUH CO%WANY lticissie nsis, %cis:4 2.42<,1 February 24, 1998 '

United States Nuclear Regulatory Commission Serial No.98-037 Attention: Document Control Desk NL&OS/ETS Washington, D.C. 20555 Docket Nos. 50-338 50 339 License Nos. NPF-4 NPF-7

Dear Sir:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA P_QMER STATION UNITS 1 AND 2 BEVISION TO SERVICE WATER MIC RELIEF REQUEST NDE-32 In a February 24,1997 letter (Serial No.97-079), as supplemented on August 8,1997 and November 18,1997, Virginia Electric and Power Company requested relief from ASME Section XI paragraph IWA-5250. This relief established a monitoring program that would permit continued Service Water System operation for up to eighteen months from the date of discovery of each minor leak or indication of previous leakage attributed to microbiologicalinfluenced corrosion (MIC). The NRC approved this relief request on November 24, 1997. Since that time, we have determined several enhancements that could be made to the program. Therefore, pursuant to 10 CFR 50.55a (a) (3), we are requesting a revision to the previously approved relief from ASME Section XI, paragraph IWA 5250 to permit: 1) performance of a Code repair in fourteen days after discovery in place of structural analysis, and 2) the use of an alternate non-destructive examination technique. Minor program scope changes to correct discrepancies in the listing of the service water lines are also being made.

The current approved MIC monitoring program permits fourteen days after discovery of the leak or indication of previous leakage to perform a structural analysis of the affected line to determine operability, in numerous instances we are able to perform the appropriate Code repair within the fourteen days and not disrupt plant operations. \

Therefore, we are revising the relief request to permit either code repair of the affected i service water lines or a structural analysis of the affected line to establish operability .

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within fourteen days after discovery. The revised relief is included as Attachment 1 to U this letter.

A detailed engineering evaluation of nondestructive examination (NDE) techniques used to examine the identified MIC locations on the service water piping has been completed. The correlation between Radiography (RT) and Ultrasonic (UT) examination is very good as documented in Attachment 2 to this letter. Thus, we are revising the relief request to permit the use of either RT or UT to evaluate the MIC affected locations in the Service Water System.

9003030006 980224 n"lIF lill till',ll{l l PDR ADOCK 05000338 llt io113 11,11, lil p pop ' H. l.it l.lLllil

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In our November 18,1997 letter, a list of the service water lines included in the relief ,

request was provided to the NRC, We have identified several orrors in that listing (transposition error, incorrect line numbars, etc. ) A corrected list of the service water lines is provided in the revised relief request, including one additional service water line which should have been included in the original scope.

Each proposed change in the relief request is identified by a revision bar in the tight hand margin. Should you have any questions or require additional information, please contact us. l Very truly yours, -

3 R. F. Saunders Vice President Nuclear Eng',neering and Services Commitments made in this letter:

1. Nono Attachments cc: U.S. Nuclear Regulatory Commission Region 11 Atlanta Federal Center ,

61 Forsyth Street, SW, Suite 23T85 l Atlanta, Georgia F0303 1

Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station i

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Attachment .'

Revised Rollef Request NDE 32 Service Water MIC Monitoring Program 4

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Virginia Electric and Power Company North Anna Power Station

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Virginia lilectrie & Power Company North Anna Power Station Unit I and Unit 2 Second 10 Year Interval itequest Ihr 1(elief Number NDli 32 Itevision 3

1. IDl!NTIFICATIONOF COhiPON1!NIS Drawine il s

Service Water System 11715 Cilli 40D 2 silts.1 and 2 11715 Cllhi-78A 2 silts. I and 4 Il719 Cilhi 78112 silts. I and 3 11715 Cllhi 78C 2 Silt. 2 11715 Cilhi 780 2 Sil'IS. I and 2 11715 Cllhi 78112 SIIT.1 Components within the scope of this Request for Reliefinclude the welds and associated piping which comprise the moderate energy stainless steel piping of the Service Water System (SW). This piping system provides cooling water from the Service Water 1 Reservoir to safety related equipment and return the Service Water back to the return headers. Normal operating pressure is 100 PSIG. The design pressure is 150 PSIG and

'l the design temperature is 150*F. This is an AShil!.Section XI. Class 3 system.

Attachment 2 provides an identification of each piping segment within the scope of this Request foc Relief. The piping segments are identified by their line number designation which is a unique identifier. The graphics represented on the associated drawings of each piping segment along with the associated line .. amber designation provide a defining boundary for each pipe segment. The identification of piping segments as components is appreptiate as both the welds and piping forming the piping segments are subject to developing through wall leaks.

11. t hiPRACTICAllLl! CODl! Rl!QUIRiihilINTS The Service Water System has experiented through-wall leakage caused by hiicrobiological influenced Corrosion (hilC). Cher. : cal treatment of the Service Water System has not been elTective in eliminating hilC. The Service Water System is being monitored Ihr hilC. Identification of additions' through wall leakage i.< anticipated.

Through wall leakage must be located and esaluated in accordance with the requirements ofIWA 5250 of the 1983 lidition and Sumt er 1983 Addenda for Unit I and 1986 IIdition Ibr Unit 2. The specific Code requircent Ihr wnich reliefis requested is IWA 5250(a)(2).

Relief Request NDD32 Rev. 3 Page 1 of 7 (

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"lWA 5250 Corrective hicasures:

(a) The source ofleakage detected during the conduct ef a sy stem pressure test shall be l

i located and evaluated by the owner for corrective measures as fbliows:...

(2) repairs or replacements of components shall be performed in accordance with IWA 4000 or 1WA 7000, respectively,"

J Articles IWA 4000 and IWI)-4000 of AShili Section XI Code repair requirements would require removal of the flaw and subsequent weld repair.

Code repairs for through wall leaks require the line to be isolated and drained. Taking a train of service water out of se ice in some instances is a major evolution and requires entering a Technical Specification action statement. Welds and piping with through wall flaws caused by hilC can be shown to have adquate structural integrity to remain in service. This type of through wall flaw is unpredictable but normally not catastrophie. It is impractical to fbrec a Code repair within the time required by the Technical Specification 1.imiting Condition for Operation every time a through wall flaw is identitled.

Generie I.etter 90 05," Guidance for performing Temporary Non Code Repair of AShill Code Class 1,2, and 3 Piping", provides guidance ihr submitting relief requests to allow i continued operatien with a through wall flaw. Suirmitting a relief request for each instance of through wall leakage caused by hilC will be an administrative burden and cause additional reviews for the NRC. hnplementing G1,90 05 each time a through wall llaw is identified is impractical.

This relief request establishes a plan ihr continued operation with through wall flaws in stainless steel piping in the Service Water System based upon the guidance of Gl. 90 05 to the extent it is believei. practical. This relief request will be implemented upon receiving NRC appreval, in the interim, Gl 90 05 will be (bliowed fbr through wall flaws and separate ielkf requests will be submitted.

111. ISI II ASIS FOR Riii.ll!!! Rl!QUliST This relief request is submitted in a lbrmat laid out in NRC Gl 90 05. The following i information and justification is provided in accordance with the guidelines of part 11 and C oflinclosuie i to 01,90-05, s

Scone. l imitations and Specific Considerations Relief Request NDE 32 Rev.3 Page 2 0f 7

Sti!ng The scope consists of welds and stainless steel piping, pipe class 153A and 163, with evidence of possible through wallleaks in the Service Water System at North Anna Power Station Units I and 2.

lintilalii!nfi liased on radiograph e examinations and laboratory examinations of removed portions of piping frem replacements, Ncrth Anna Power Station is experiencing hilC in its stainless steel piping. The hilC caused flaws originate on the in.~er diameter of the pipe. The Service Water System i t common to both Units. As long as one Unit is in hiode 1,2,3, or 4 both trains of service water must be operable. If both Um are in hiode 5 or 6 then one train of Service Water must be operable. The intent of this reliefis to permit continued operation with the identified through wall flawa until repairs are accomplished in a scheduled service water outage.

Snecific Considerations System interactions, i.e. consequences of flooding and spray will be evaluated. Piping with through wall leakage that could affect plant safety related equipment will te declared inoperable and the appropriate Technical Specification action statement entered.

Welds containing evidence of through wall flaws will ')e either repaired or assessed for structural integrity within 14 days of detection. Ilutt welds and piping remaining in service aller leakage is detected for longer than 14 days and accessible to volumetric examination by Ultrasonic (UT) or Itadiographic (ItT) examination methods, will be evaluated for structural integrity for all design loading conditions, including dead weight, pressure, thermal expansion and seismic (DilE) loads. The methods used in the structural integrity analysis will consist of area reinfbreement, fracture mechanics, and limit load analysis. These methods are detailed in Attachment 1. The welds that are found to be unacceptable will be declared inoperable and the appropriate Technical Specification action statement entered.

A 3/4" hole will be postulated for any location with a through wall flaw that can not be characterized volumetrically by itT or U r, socket welds and welds that are inaccessible for itT or UT.1.aboratory examination of cut sections of hilC degraded socket weld samples indicate that flaws are enveloped within 3/4" size. A leaking socket weld location will be analyzed by treating the cross section as equivalent to the cross section of the attached pipe with a 3/4" 1. ale. The methods used in the structural integrity analysis will consist of area reinfbreemer.t. fracture mechanics, and limit load analysis. These methods are detailed in Attachment 1. J. 'hrough wall flaw size is postulated in order to perform a structural analysis. Additional monitoring is perIbrmed for a period of two (2)

Relic (Request NDD32 Rev.3 Page 3 of 7

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months on socket welds to assure the degradation meel inism is behaving in a manner expected for a MIC llaw.

The structural integrity for all welds identified with evidence of through wall leakage will j be monitored by the ibilowing methods:

o Weekly visual monitoring of through wall flaws fmm the time ofidentification until repair of the weld or completion of the structural integrity analysis. Renair of the ucld or completion of the structural analysis is required within 14 days of  ;

detecting a through wall flaw. If the welds are determined to be structurally l acceptable then the visual monitoring frequency will be decreased to once a month, o Weekly visual monitoring of through wall flaws in socket welds and butt welds inaccessible to RT or iTf examination fbr a period of two (2) months. If there is no significant change in the leakage rate the monitoring frequency will be decreased to monthly until the welds are repaired.

A significant change is defined as a 0.5 ppm increase in the leakage rate from the initial observed leakage coadition Ibr each weld, should any location reach the threshold of a significant change the weld will be reassessed fbr structural integrity and flood / spraying consequences.

o A total leakage rate limit of 1.0 ppm Ibr a single supply or return line to an individual component will be established, if this total leakage rate limit is exceeded then an evaluation will be perfbrmed to determine if design service water flow is

. available to affected components. Inadequate service water supply will cause the associated service water lines and equipment to be d<:clared inoperable and appropriate action will be taken according to Technical Specifications.

'I he temporary non-code repair will be to leave the welds as they are found, subject to monitoring and meeting the criteria ihr consequences and for structural integrity as J described above.

l: valuation Flaw lietection 1)urinu Plant Oneration and Imnracticality I)etermination The Service Water System is a common system fbr both Units at North Anna Power Station. Iloth trains are required to be operational or the appropriate Technical Specification action statement be entered. The through wall flaws on Service Water lines in service are anticipated based on the North Anna Power Station history of MIC.

Virghia lilectric and Power Company requests to evaluate the flaws and leave acceptable Relief Requeu NDIM2 Rev. 3 Page 4 of 7.

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i l through wall flaws in service in order to perform Code repairs in controlled conditions during scheduled service water outages.

I: law characteritation of hilC has traditionally been perfinmed by radiogiaphy and has wide acceptance by the industry as t.a appropriate technique. Virginia Power has also des eloped an ultrasonic technique which is as efTective as radiography for detection and length siting of hilC indications. This ultrasonic technique additionally has depth sizing capabilities. 'l he acceptabililty of ultrasonics as an alternative to radiography is documented in a report titled " Ultrasonic lixamination Technique for 1)etection of hilerobiologically Induced Corrosion in North Anna Stainless Steel Service Water '

Piping" dated December 29,1997. Virginia Power proposes to use either radiography or ultrasonics or both to characteri/c Ilaws.

Root Cause INtermination and I:bw Characteri/ation The Service Water System at North Anna Power Station has previously experienced hilC. Itadiographic examinations of service water welds having evidence of through wall leakage revealed small voids surrounded by exfiiliation, which is typical of hilC. Na other type ofinservice defects were identilled by the radiographs near the areas

- with through wall leaks. Additionally, a visual examination perliirmed by a Virginia

!!!ectric and Power Company staff metallurgist of a sample of piping segments removed

to repair the leaking welds confirmed the presence of h11C.

filaw livaluation Flaw evaluation liir welds with through wall leakage will be performed as described in Attachment 1. The llaws in butt welds that can be characteri/cd by itT or UT l

. examination methods will be evaluatal by three types of analyses, aiea reinfiircement, limit load analysis, and fracture mechanics using the guidance from NRC Generie i.etter 90 05. The 11aws in welds that can not be characterized by RT or UT examination. i.e.

I socket wehls and inaccessible butt welds, will be evaluated by the same analysis by assuming a 3/4" hole for each point ofleakage within a weld with through wall leakage.

, Socket welds will be analyzed by treating the cross section at the socket weld as equivalent pipe cross section.

11clicfitequest NDC 32 itev. 3 l' age 5 of 7 L

IV. AUOMIENTl!!)INSPl!CTION An augmented inspection program will monitor a sample of butt welds in the Service Water System using itT or UT examination methods will be performed every three (3) months. The frequency of examination will be assessed aller a year and may be adjusted for each location based on the results of the examinations.

V. AI.TliitNATl! PitOVISIONS As u alternative to performing Code repairs in accordance with IWA 5250(a)(2) to through wall flaws in the Service Water System the through wall flaws will be left as is.

The through wall flaws will be monitored Ihr leakage and must meet the criteria for flooding and spraying consequences. Structural integrity must be determined as described herein to remain in service tieyend 14 days from detection. If structural integrity is determined, operation in this mode will continue until the subj :ct welds are replaced. All welds identified with through wall flaws will be replaced within 18 months from the time of discovery.

The structural integrity of the Sersice Water System will be monitored by the fbilowing methods until the repairs required by IWA 5250(a)(2) are completed.

o Weekly visual monitoring of through wall flaws from the time ofidcatliication until repair or completion of structural integrity analysis, if the welds are l determined to be structundly acceptable then the visual monitoring frequency will be decreased to once a month.

o All welds identified as having through wall flaws and not repaired within 14 days of detection will be assessed for structural integrity within 14 days of detection.

Hutt welds will be examined by llT or (Tl methods,if accessible, to characterize the flaws. Socket welds and butt welds inaccessible to IIT or UT will be assessed Ihr structural integrity by assuming a conservative 3/4" diameter hole. Welds determined to be structurally adequate will be included in the above monitoring program. Identification of a structurally inadequate weld will result in the assoelated piping to be declarcJ inoperable and the appropriate Technical Specification action statement to be taken, o Weekly visual mc.; bring of through wall flaws in socket welds and butt welds inacecssible to itT or UT examination for a period of two (2) months, if there is no significant change in the leakage rate the monitoring frequency will be decreased to monthly until the welds are repaired.

A significant change is defined as a 0.5 gpm increase in the leakage rate from the init;al observed leakage condition ihr each weld. Should any location reach the Rellef Request ND!b32 Rev,3 Page 6 of 7

threshold of a significant change the weld will be reassessed for structural integrity and flood / spraying consequences.

o hionthly walkdown of the accessible stainless steel portions of the Service Water System will be perfonned. The frequency of monthly walkdowns will be assessed after a year and adjusted based on the results of monthly inspections.

o A total leakage rate limit of 1.0 ppm for a single supply or return line for an individual component will be established, if this total leakage rate limit is exceeded then an evaluation will be performed to detennine if design service water flow is available to affected components. Inadequate service water supply will cause the associated service water lines and equipment to be declared inoperable and appropriate action will be taken accordim; to Technical Specifications.

o An augmented inspection program will monitor a sample of butt welds in the Service Water System using 1(T or UT examination methods. lixaminations will be performed every three f 3) months. The frequency of examinations will be assessed aller a year and may be adjusted for each location based on the results of the examinations.

The proposed alternative stated above will ensure that the overall level of plant quality and safety will not bc compromised.

VI lh1Pl.lihil!NTATION SCill!DUI.l!

This alternative to Code requirements will be followed upon receiving NRC approval foi the remair. der of the second ten > /ar inspection intervals. The Unit I second ten-year inspection interval will end on December 24,1998 and the Unit 2 second ten year interval will end on December 14,2000, Attachments:

1,1: law livaluation hiethods and Results

2. Drawing /l.ine Number Designations

References:

1. USAS 1131.1 Power Piping 19L7 lidition

2. l!PRI Report NP-6301 D," Ductile Fracture llandbook"

3. Nuclear Regulatory Commission Generic 1.etter 90 05 " Guidance for Perfomiing Temporary Non-Code Repair of AShil! Code Class 1,2, and 3 Piping" Relief Request NDD32 Rev. 3 Page 7 of 7

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l Attachment i Flaw livaluation Methods and Results IntntdRil.011 a

liutt welds identified as having possible through wall leaks will be volumetrically exan.ined by Radiographic (11T) or Ultrasonic (UT) examination rnethod s, if accessible. Flaws in butt welds that are inaccessible for examination will be postulated as e 3/4" hole for each area identified with a through wall flaw. All butt welds will be analyzed f or structural integrity by three methods, area reinforcement, limit load analysis, and linear clastic fracture mechanics evaluation.

Flaw size in socket welds identified as having possible thrcugh wall leaks cannot be characterived by nondestructive examination. A conservatively large hole,3/4", will be postulated for each area identified with a through wall llaw. The postulated flaw will be analyzed for structural integrity by treating the cross secti on as equivalent to the cross section of the attached pipe.

drea Reinforetmtnt Analysis The area reinforcement analysis is used to detennine if adequate reinforcing exists such that ductile tearing would not occur. The guidelines of ANSI 1131.1 paragraph 104.3.(d) 2 (reference

1) are used to determine the Code required reinforcing area. The actual reinforcing area is calculated and is checked against the required reinf orcement area.

The Code required reinforcement area in square inches is defined as:

1.07(in ,)(di )

Where in ,is the code minimum wall, and d i is the outside diameter The Code reinforcement area required is provided by the available material around the flaw in the reinforcing zone.

1.imit 1 oad Anallsh ,

The structural integrity of the piping in the degraded condition will be established by calculating the minimum margin of safety based upon a 1.imit Load Analysis. These methods are documented in liPRI report NP 6301-D (Ductile Fracture llandbook)(reference 2).

Relicf Request NDI.7-32 Rev. 3 pageIor3 Attachment I

The limit load analysis of the postulated flawed sections will be performed with a material flow stress representing the midpoint of the ultimate strength and yield point stress. The flawed sections will be subjected to deadweight, thennal, and seismic Dilli loading.

The allowable lim:t load is given by, hi, = 2 sritm* t-(2cos(b) sin (Q))in lbf ,

i s, - flow stress = 0.5 (S, + S.) psi Sy a yield stress psi S, = ultimate stress psi It, = mean radius of the pipe 11 *(R!* P)+F l1 =2 B+

4*aj eR,et 11, = internal radius of the pipe P = pressure psig F = axial load in Ibs t = pipe thickness = inches D = Outside diameter inches f Q = half angle of the crack (radians) = gnick leneth 2Il m hilt = 11esultant hioment MR = d Ml' + MW + T*'

hiY = llending hioment h1Z = llending hioment T = Torsion The calculated flictor of safety is,

_ FS = 4 (h111)

The minimum factor of safety of 1 A is required to be qualified for continued operation.

Fracture hicchanics Evaluation Relief Request NDii 32 Rev. 3 Page 2 of 3 Attachment I u

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A linear clastic fracture mechanics analysis will be perfonned for circumferential through wall crack using the guidance provided in NRC Generic 1.etter 90 05. The structural integrity of the piping in the degraded condition was established by calculating the minimum margin of safety based upon a Fracture hiechanics evaluation. This method is documented in l!PRI report NP-6301.D (Ductile Fracture llandbook)(reference 2).

A through wall circumferential crack will be postulated for every area containing hi!C. The cracks will be t.ubjected to a design pressure loading in addition to the deadweight, normal operating thermal and seismic Dilli loadings. For the purpose of this evaluation a generic allowable stress intensity factor of K i c = 135 ksioin will be used for the stainless steel material per NRC GI,40 05.

Thc applied stress intensity factor for bending, Km,is found by:

Km = isic(p Rm -Q)"] F,,

The applied stress intensity factor for internal pressure, Ku., is found by:

Kn. = s,,c(p Rm -Q)" Fm The applied stress intensity factor for axial tension, Kn is found by: ,

s Kn = sc(p R -Q)" F i The stress intensity factor for residual stresses, Km is found by:

Km = S-(p Rm-Q)" F i Total applied stress intensity K iincludes a 1.4 safety factor and is calculated by:

K i= 1.4-(Km + Ku' + kn) + Km The allowable stress intensuy factor is taken from Generic Letter 90-05.

Kati, = 135 ksioin Stress Intensity Factor Ratio is dermed as:

SR = K1.

K ai.t.

The stress intensity factor ratio shall be less than 1.0 for continued operation.

Relief Request NDE 32 Rev. 3 l' age 3 of 3 Attachment 1

NITACllMl!NT 2 1 ist of drawings containing the Service Water System and the associated line number designations for pipe class 153A and 163.

DRAWING 11715 C1111040D-2, SilEliT 1 1 1/4"-WS-G37-153 A-Q3 4"-WS 001 163-Q3 3/4" WS i T 4"-WS F99-163-Q3 3/4" W5 182-i- ')3 DRAWING 11715 C1111040D 2 SilElIT 2

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l l/4" WS II?8-1$3A-Q3 1 1/4" W59181 153A-Q3 DRAWING 11715 CllM 078A 2, $11EET 1 3/4" WS G31-163-Q3 3/4" W5 F67163-Q3 3/4"-WS 1177163-Q3 40WS F64-163-Q3 4" WS 1176163-Q3 3/4"-WS F80163-Q3 3/4" WS 030163-Q3 3/4" WS F68163-Q3 3/4" WS-339 163-Q3 4"-WS F65-163-Q3 3/4"-WS G36163-Q3 3/4" WS F69163-Q3 3/4" WS 930-163-Q3 8"-WS. 93.I 63-Q3 1/2"-WS F61 163-Q3 8"-WS- 94-163-Q3 2" WS D72163.Q3 4"-WS F62-163-Q3 3/4" WS F78163-Q3 3/4" WS F66-163-Q3 4"-WS F63163-Q3 3/4"-WS-F79 163-Q3 4"-WS-G35-163-Q3 3/4" WS F81 163-Q3 l j DRAWING ll715 CllM 078. -2, SilEET 4 8"-WS 515163-Q3 8"-WS-516 163-Q3 8"-WS-513 163-Q3 8"-W S-514 163-Q3 4" WS-1148 163-Q3 3/4"-WS F64163-Q3 3/4"-WS Il52163-Q3 3/4"-WS 1153163-Q3 4"-WS 1150-163-Q3 3/4"-WS Il66163-Q3 3/4"-WS Il54163-Q3 4" WS Il51 163-Q3 3/4"-WS-Il67-163-Q3 3/4"-WS 1155163-Q3 3/4" WS 032163-Q3 3/4"-WS G33163-Q3 8"-WS 115-163-Q3 8"-WS-116163-Q3 8"-WS-113 163-Q3 4"-WS- 46-163-Q3 4"-WS- 47-163-Q3 2"-WS-926-163-Q3 3/4"-WS-Il60- t o3-Q3 3/4"-WS-Il61 163-Q3 3/4"-WS 1162-163 Q3 3/4"-WS 1163163-Q3 4"-WS Sr ' 63-Q3 4"-WS- 57-163-Q3 Relief Request NDD32 Rev. 3 Page i of 5 Attachment 2

4" WS 1149163-Q3 3/4" WS 1165153-Q3 8" WS 114163-Q3 DitAWING 11715 CllM 078112. Sill!!!T I l 1/2" WS 346 !63-Q3 1" WS 347163-Q3 1"-WS G06163.Q3 l-l/2"-WS 347-163-Q3 1-1/2"-WS 348163-Q3 1" WS 349163-Q3 1" WS 005-163-Q3 1 1/2" WS 349163-Q3 1 1/2" WS 350163-Q3 1" WS 351 163-Q3 1" WS G04163 Q3 1 1/2" WS-351-163-Q3 1 1/2" WS 352163-Q3 1" WS 353163-Q3 1" WS G03163-Q3 1 1/2" WS 353163-Q3 DI(AWING 11715 CllM 078112 SIIEl!T 3 1 1/2" WS-724 163-Q3 1" WS 725163 Q3 1" WS-933163-Q3 1 1/2"-WS 725163-Q3 1 1/2" WS ' %163-Q3 1"-WS 727163-Q3 1"-WS ~ $4163-Q3 1 1/2"-WS 728-163-Q3 1" Wh//29163.Q3 1"-WS-935 163-Q3 1 1/2" WS 729163-Q3 1-1/2"-WS 730-163 Q3 1"-WS 731 163-Q3 1" WS 936-163 Q3 1 1/2" WS 731-163-Q3 1 1/2"-WS 727-163-Q3 DitAWING 11715 CllM 078C 2, SIIEl!T '.

4"-WS 46163-Q3 1"-WS- 85 163-Q3 3/4"-WS A47163-Q3 1"-WS 485163-Q3 1"-WS81-163 Q3 1" Wh-487-163-Q3 1"-WS- 77-163-Q3 1"-WS-489 163-Q3 1"-WS-477-163-Q3 1"-WS-491-163-Q3 1"-WS-48 l- 163-Q3 3" WS 75163-Q3 3"-WS 73-163-Q3 3"-WS- 76163 Q3 4" WS- 47-163-Q3 3/4"-WS 79163-Q3 3/4"-WS A49-163-Q3 3/4"-WS 381-163-Q3 1"-WS- 82 163-Q3 2"-WS- 80-163-Q3 1"-WS78-163 Q3 3/4"-WS 83163-Q3 1"-WS-478 163-Q3 3/8"-WS-383 163-Q3 1"-WS-482 163-Q3 3/8"-WS 382163-Q3 3"-WS- 74 163-Q3 2"-WS 376-163-Q3 4" WS- 56-163-Q3 3/8"-WS W 163-Q3 3/4"-WS A48163-Q3 3/8"-WS 398-163-Q3 Relief RequestNDE 32 Rev.3 Page 2 of 5 Attachment 2

11715 Cithi 078C 2, SilEET 2 (Cont'd) 1" WS. 9016.1-Q3 2" WS 377163 Q3 3/4" WS C06163-Q3 3/8" WS C01 163-Q3 1" WS 92163-Q3 3/8" WS 399163-Q.1 1"-WS 86163.Q3 3/4" WS 378163-Q3 3/4" WS C01 163.Q3 2"-WS 84163-Q3 1" WS-488 163-Q3 3/4" WS 379163-Q3 3/4" WS 913163-Q3 1" WS 88-163-Q3 1" WS 490163 Q3 3/4" WS 380-163-Q3 1" WS 78163-Q3 3/4" WS 83163-Q3 3/8" WS 383163-Q3 1" WS 492163-Q3 3/4" WS A50163 Q3 4" WS- 57163-Q3 1" WS 89163-Q3 3/4" WS 773163-Q3 3/4" WS 400163-Q3 2" WS 772163-Q3 3/4" WS 774163-Q3 3/8" WS 910-163 03 2" WS 775163-Q3 3/8" WS 914163.Q3 3/8"-WS 913163-Q3 2" WS-776163 Q3 3/8"-WS 915-163-Q3 1/8" WS 916163-Q3 3/4" WS 779163-Q3 2" WS 777-163-Q3 3/4" WS 909163-Q3 1" WS 486163-Q3 3/8" WS 912163-Q3 DitAWING ll715 Cilhi 0780 2, S' zT 1 2" WS D46153A-Q3 2" WS C88153A-Q3 1" WS D50-153A-Q3 2"-WS C81 153A-Q3 3/4" WS D39-153A-Q3 2"-WS C87-153A-Q3 1"-WS l>30153A-Q3 2" WS 63163-Q3 3/4" WS D41 153A-Q3 3/4" WS-D61 163-Q3 3/4" WS D55163-Q3 2" WS 62163-Q3 '

1" WS D31-153A-Q3 2" WS-C80-153 A-Q3 3/4" WS D43-153A-Q3 3/4"-WS C67-153A-Q3 3" WS- 73-163-Q3 3/4"-WS C73153A-Q3 2" Wh. 54 163-Q3 3/4" WS C76153A-Q3 2"-WS 5216.1 Q3 3/4" WS-C70153A-Q3 3/4" WS D67163-Q.1 2" WS-C86153A-Q3 2" WS 50163-Q3 25.WS- 79.l >3 A-Q3 3" WS 74163-Q3 2"-WS C85153A-Q3 2"-WS. 55-163-Q3 3/4"-WS D62-163-Q3 3/4"-WS D54-163-Q3 2" WS- 60-163-Q3 2" WS- 53163-Q3 3" WS- 75-163-Q3 3/4" WS D68163-Q3 3/4"-WS-D69 163-Q3 2" WS Sl 163-Q3 2"-WS 61 163-Q3 11715 Cllht 0780 2, SilEET 1 (Cont'd)

Relief Request NDE 32 Rey,3 Page 3 of 5 Attachment 2

l l 3/4" WS IX ,163-Q3 3/4" WS D70163-Q3 l

2" WS C83153A-Q3 3" WS 76163-Q3 2" WS CH9153A-Q3 2" WS C78153A-Q3 3/4"-WS D60163-Q3 3/4" WS C66153A-Q3 2" WS 64163-Q3 3/4" WS C72153A-Q3 j 2".WS- 65 163-Q3 3/4"-WS C75153A-Q3

2" WS C82153A-Q3 3/4" WS C69153A-Q3

=

3/4" WS C68153A-Q3 2" WS C84153A-Q3 i

3/4" WS-C74 153 A-Q3 3/4"-WS C77153A-Q3 3/4"-WS C7l l53A-Q3 1

DilAWING ll715 CDM 0780 2. SilEl;T 2

2" WS D46153A-Q3 3/4" WS D65163-Q3 3/4" WS D71 153A-Q3 3/4" WS D66-163-Q3 1" WS D47153A-Q3 3/4" WS 934153A-Q3 3/4" WS D33153A-Q3 2"-WS 948153A-Q3 3/4" WS D51 163-Q3 3/4" WS 940153A-Q3 1" WS D48153A-Q3 1 1/2" WS 976153A-Q3 3/4"-WS D35153A-Q3 1 1/2" WS 982153A-Q3

, 3/4"-WS D52163-Q3 3/4" WS 943153A-Q3 1" WS-D49153A-Q3 3/4" WS 937153A-Q3

. 3/4" WS D37-153A-Q3 2" WS 954153A-Q3 3/4"-WS D53163-Q3 2"-WS 947153A-Q3 l 3" WS- 73163-Q3 1 1/2" WS 977153A-Q3 3/4"-WS D63-163-Q3 1 1/2" WS-963-153A-Q3 3" WS 7J 163-Q3 2" WS 953153A-Q3 2"-WS 454163-Q3 3/4"-WS D58-163-Q3 2"-WS 455163-Q3 2"-WS-462-163-Q3 2" WS 452163-Q3 2"-WS-463 163-Q3 2" WS-453 163-Q3 2" WS 946-153A-Q3 2"-WS 450163-Q3 1-1/2"-WS 979153A-Q3 2" WS-451 163.Q3 1-1/2"-WS 978-153A-Q3 2"-WS 949153A Q3 2"-WS 952153A-Q3 1-1/2"-WS 981 153 A-Q3 2" WS 945153A-Q3 l-l/2"-WS 965-153A-Q3 1 1/2"-WS 980153A-Q3 2"-WS 955153A-Q3 1 1/2" WS 961 153A-Q3 3/4"-WS D57163-Q3 2"-WS-460 163-Q3 2"-WS 464163-Q3 2"-WS-945 153A-Q3 2"-WS 465-163-Q3 2" WS 944153A Q3 3"-WS- 75 163-Q3 1 1/2" WS 975153A-Q3 3"-WS. 76163 Q3 1 1/2"-WS 971-153A-Q3 3/4"-WS D59163-Q3 2" WS 950153A-Q3 d

2"-WS 461 163 Q3 2" WS 951-153A-Q3 l Rdief Request NDD32 Rev.3 Page 4 of 5 Attachment 2 i

1)RAWING 11715 CllM 078112, Sill!!!T I 1" WS. 9163 1". WS 10163 3/4" WS l!03 163 3/4" WS 1745163 3/4" WS 1744163 2" WS l!64163 1" WS G07163 1/2"-WS l!68163 3/4" WS l!08163 1".WS 1)97163 i

. 1" WS 947163 2" WS 1)91-163 1" WS 050163 1"-WS Il84163 1" WS OS2163 i

3 l

I I

a I

T T

ReliefRequcstNDE 32 Rev.3 Page 5 of 5 Attachment 2 t

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