Text

Forwards Relief Requests from ASME Section XI Requirements for ISI Program,Covering Rcs,Si Sys,Chemical & Vol Control Sys & RHR Sys
	ML18152A045
Person / Time
Site:	Surry
Issue date:	06/08/1993
From:	Stewart W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	93-323, NUDOCS 9306150392
	Download: ML18152A045 (46)
	v • d • e

..

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 8, 1993 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS Serial No.

NO/ETS Docket Nos.

License Nos.93-323 RO 50-280 50-281 DPR-32 DPR-37 Surry Power Station Units 1 and 2 are presently in the third period of their second ten-year interval for inservice inspections. Examinations during this interval have been conducted to the requirements of the 1980 Edition and Winter 1980 Addenda of ASME Section XI.

Pursuant to 1 O CFR 50.55a (g) 5, relief is requested from certain requirements of ASME Section XI associated with partial examinations conducted for both Surry Units 1 and 2.

Relief requests SR-018 and SR-019 (attached) for Surry Unit 1 and relief request SR-020 (attached) for Surry Unit 2 have been provided detailing the basis of these requests.

These relief requests have been reviewed and approved by the Station Nuclear Safety and Operating Committee.

Should you have any additional questions or require additional information, please contact us.

Very truly yours, Jff(e::/~--

w. L. Stewart Senior Vic~ President - Nuclear Attachments 140042

~

9306150392 93060880 PDR ADOCK 050002 G

PDR

[t011 I I

cc:

U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station

INSERVICE INSPECTION PROGRAM RELIEF REQUESTS REC'D W/LTR DTD 06/08/93.... 9306150392

-NOTICE-THE ATTACHED FILE$ ARE OFFICIAL RECORDS OF THE INFORMATION &

REPORTS MANAGEMENT BRANCH.

THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RE-CORDS & ARCHIVES SE.RVICES SEC-TION P1..:.22 WHITE FLINT. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT

. FOR REPRODUCTION 'MUST BE RE,.

FE.RRED TO FILE PERSONNEL.

.** -NOTICE-

Surry Power Station Unit 1 ISi Examination Relief

RELIEF REQUEST SR-018 I.

IDENTIFICATION OF COMPONENTS Mark/Weld#

1-01 1-14 H003-1 H003-2 1-02 1-02 1-01 1-01 Line#

27~ 11-RC-9-2501R 12 11-SI-46-1502 12"-SI-46-1502 System RC RC SI SI CH CH CH CH RH RH Drawing#

Class 11448-WMKS-RC-R-1.2 1

11448-WMKS-0102AZ-1 1

11448-WMKS-0122D1 1

11448-WMKS-CH-E-2 2

11448-WMKS-CH-E-4 2

11448-WMKS-CH-FL-4A/4B 2 11448-WMKS-CH-E-2 2

11448-WMKS-RH-E-1A/1B 2

11448-WMKS-RH-E-1B 2

1-A01/1-B01 H001-1 System Abbreviations RC - Reactor Coolant System SI - Safety Injection System CH -

Chemical and Volume Control System RH - Residual Heat Removal System II.

IMPRACTICABLE CODE REQUIREMENTS The 1980 Edition, Winter 1980 Addenda (inclusive) of ASME Section XI in Tables IWB-2500-1 and IWC-2500-1 does not allow any limitations to the required volumetric and surface examinations.

Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%.

III. BASIS FOR RELIEF IV.

The components listed above have been examined to the extent practical as required by the Code. Due to interferences of other components or weld joint geometry the reduction in coverage for the listed components was greater than 10%.

Tables SR-018-1 and 2 are provided detailing the limitations experienced.

Amplifying sketches or drawings are also provided. Alternative components could not be substituted for examination due either to the mandatory selection requirements of the Code, or because the examination coverage attained was representative of what could be expected for that type configuration.

ALTERNATE PROVISIONS It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements.

MarklWeld#

Beam Angle 0*01 0

CO to 360 45 degrees) 45 45 45 60 60 60 60 45 & 60 45 & 60 45 & 60 45 & 60 UT Scan Direction Definitions 2

Axial scan flange side of weld 5

Axial scan head side of weld Table SR-018-1 Surry Unit 1 Examination coverage Estimates (Vessel) category B-A, Item Bl.40 Exam Area Scan Di rect ion

% Exam Reason For Partial Weld & Base 82 Proximity To Flange Weld 2

38 And Lifting Lug Weld 5

100 Interference Weld 7

100 Weld 8

100 Weld 2

19 Weld 5

100 Weld 7

100 Weld 8

100 Base 2

45 Base 5

96 Base 7

82 Base 8

82 7

Circllllferential scan, clockwise (looking down on head) 8

Circllllferential scan, counterclockwise (Looking down on head)

Sketch#lDrawing 1

11448-WMKS*RC*R-1.2

Table SR-018-2 Surry Unit 1 Examination Coverage Estimates (Piping, Vessels (< 2 11 thick) & Integral Attachments)

UT Scan Coverage%

Surface MarkLWeld#

Categor)!

Item#

~

2 7

8 Coverage%

Reason For Partial Sketch#LDrawing 1-14 B-J B9.11 99 0

100 100 N/A Valve To pipe Joint 2

Configuration/ V-path 11448*WMKS-0102AZ-1 Could Not Be Extended Due To Cast Austenitic Calibration Blocks H003-1 B-K-1 B10.10 N/A 50 Support Configuration 3

11448-WMKS-0122D1 H003-2 B-K-1 B10.10 N/A 50 support Configuration 3

11448-WMKS-0122D1 1-02(0-360°)

C-A C1.10 80*

80*

85 85 N/A Welded support Interference 11448-WMKS-CH-E-2

[1-CH-E-2]

And Inlet/Outlet Nozzle Configuration 1-02(0-360°)

C-A C1.10 80*

80*

87 87 N/A Inlet/Outlet Nozzle And 11448-WMKS-CH-E-4

[1-CH-E-4]

Flange Configuration 1-01(0-360°)

C-A C1.20 62*

56*

62 62 N/A Welded Support, And 11448-WMKS-CH-FL-4A

[1-CH-FL-4A/4Bl Inlet Nozzle 11448-WMKS-CH-FL-4B 1-01(0-360")

C-A C1.20 45*

45*

100 100 N/A Welded Support Interference 11448-WMKS-CH-E-2

[1-CH-E-21 1-A01/1-B01 C-A C1.20 79*

73*

66 66 N/A Welded Support Interference 11448-WMKS-RH-E-1A (0-360")

And Inlet/Outlet Nozzle 11448-WMKS-RH-E-1B

[1-RH*E-1A/1Bl Configuration H001-1 c-c C3.10 N/A 64 Lower Underneath Plate Weld 11448*WMKS-RH-E-1B Of Integral Attachment Inaccessible Due To Clearance Between Vessel And Concrete

- Extended V-path used to maximize coverage.

UT Scan Direction Definitions 2 - Axial scan, 180 degrees from isometric flow direction (weld.count) or on vertical vessels bottom side of weld.

5 - Axial scan, the same direction as the isometric flow (weld count) or on vertical vessels top side of weld.

7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow (clockwise from 0 reference on vessels).

8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow (counterclockwise from O reference on vessels).

~

45 DEGREE AND 60 DEGREE SCAN DIRECTIONS /

S --------

2~

WELD 1 Sketch #1

I I I I

I I u

- -*--***--**-------------*-----------5-----,!,.-~-:

"l ___ _L G

~___:4

_.L_ ___

3 ___

_L ___ z ___ ~----l I

F I

I I, l

,-~*

E I D

C 8

Ar---

ELEVATION VIEW - REACTOR VESSEL HF.AD cu1nncL ROD TUOE IASME SB-16"/l REACTLlil VESSEL HEHD CLAVOJl!G SECTION B-B TYPICAL coNTRO[ ROD DRIVE HOUSING PAHl!AL PENElnATION WELD DUAIL 1 SECTION C-C TYPICi\\[-CRDi-1 HOUSING HEAD PENETRATION TYPICACM~~I CLAMP

<HOUSINGS 51,53,55,57> --------,-----------

7

,*;, r: dV-llJU'l !~,: *.;;

U'.:.1~3: [ 31.J~, lJU J j I,Li",\\.JLX! I li2. lJUIJ SECTION A-A TOP VIEW-REACT~SSEL HEAD CONTROL ROD DRIVE HOUSING WELD LOCATIONS 3/,t* -

10 CAP SCREWS SA-Jq3 Gf!AIJE B-7 13 PER CLAMP!

((l"?i VIRGINIA POflEH

~ NOR TH CAROLI N,'I POWER POUER EIIGl~1-f1~11"'-'NG=-SE~n-v1-CE~S------l RICftt:ONU, V111GINJn F -

E D

C B

A

2.187" L

Weld 1-14 on Line 27\\-RC-9-2501R

--~1/2" Exam. Surface A -

8 2"

2.5" Exam. Vo I.

C-0-E-F Valve MOV -* 1595 C 1/ 3t)

~-

1/4" D~awin Not To Scale Sketch #2

F E

D C

B 7

'i. EL. II'- S 15/16" °"'v/

REACTOR

-~-~.~~-~=*/

I-RC-

...... R-1.....

(NOTE 7l 6

'i. EL.II"* S 15/16"~_.-/

/

5 REACTOR COOLANT PUMP

/***1-Rc-****...

\\.... P-IC.... /

lNOTE 9>

~

E DETAIL "E" ON

<148-WHKS-0102AZ-2

-5)

SIEAfl GENERATOR 1-RC-

.... E-IC....

INOTE Bl

.. \\/~ I 6"-AC-21-1~02-I SEE DETAIL "A" ON 11<14B-WHKS-0102AZJ IE-7J j

SEE DETAIL "I" ON j ll448*WHKS-0102Al-2 (8-IJ 3

(....... 1 I

I I

I 2

m E DETAIL "D" ON j

'4'48*WM1<S-0102AZ-2

-5) 31"X zqo q0* RED ELL SEE DETAIL "C" ON]

114'48-WHKS-0102AZ-2 (A*7J NOTE1 WORK THIS OWG WITH ll4'18-WHK5*0102AZ-2 VIRGIN I A POIIER NORTH CAROLINA POWER tt..cLEAR EMJl~ERlt<<J SERVICES Rlo.lCHl,YIRGUUA INSERVICE INSPECTION ISOMETRIC RC SYS:LOOP C REACTOR COOLANT PIPE A i-r------,-~-----rr------,-..------,--.-------r--.------1 SURRY POWER STATION UNIT 1 VIRGINIA POWER 1q-AuG-1qqz 09122 ZGSr C 355, 00 IJ01"2AZZ 11,0GN REVISED PER DC c,i.95 2

SCALE NONE lh..[5S 01tRW1SE MJT[D 2

F E

D C

B A

TYP Floor Integrally Welded Attachments H003-1 and H003-2 1/2 Sll"f. Exam.

kea A - B Sleeve t'elded To Pipe A

B A

12"-Sl-46-1502 Inaccessible Weld Penetration

[rawi tbt To S::a le Sketch #3

8 F

E D

C B

A 8

15-DEC-1992 17128 ZG51 [355,001 l0122D0011, DGN FROM 11448

-WMK5-0127 J2Z CcC-4) 7

/

6 L

AL VE BONNET BOL TIN 16 STUDS - l 3/4' 16 NUTS - l 3/4' REVISED PER 151 REVIEW REV!Sr:D PER 151 REVIEW 4

3

~EVISED PER 151 REVIEW 2

3 (CB-8>

12'-51-46-602-r-51-64-152-I REDRAWN FOR 15 I e

2 ACCUMULATOR TANK N0.2 1-SI-TK-18 VIRGINIA POWER NORTH CAROLINA POWER NJCLEM ENll11ERINII SERVICES RIC>Mllll.Y!RGIIUA INSERVICE INSPECTION ISOMETRIC SI SYS: SAFETY INJECTION LOOP B SURRY POWER STATION UNIT 1 VIRGINIA POWER l 1~!!8~:~~~~~2~'g;ER~~i:~ l-:DSllll-----+DSllll--U'Y-'-.......:.Ac.:RF......:.--+--c,o-11>_. ___

..:B.:..:l220BBl==l:,..__.----I hR===::r-r-rr-r-riF""""...:..:.:..:M:::;E5

'..:J:::;EY:_.i::::,=

..... -=--===-=--=-D::w~-l ""'

11M48-WMKS-0122DI REY.

4 6CAL£ NONE 2

F E

D C

B A

I 1---7 _,_____G _J_-5-----l!it *

...--4-----'--3

_..L._ __

2 ~I =* *____..__~

F

-[>

E C

B A

SHELL VE'.:1 c:rnm(CllU:,J

<J/4' :m~m*

1111J cour1.1Nc1

~ 1/C:,.\\ lJ.l'1U

-\\iMf,'; l1IJ;T!

(t'E-21 LElDOWN HEAT

-EXCHANGEJ~-

I-CH-

~

SHELL FLANGE ASlM A-181 GR II TUBE SHEET SHELL ASTM A-285 GR ASTM A-240 TF304 "-...,_

CH~tmEL FLANGE ASH-1 A-182 F304 2'-CH-6-602-TUBE SIDE INLET ISi CLASS 28 TUBE SIOE SHELL AS[M A-240 TP 304.375 lHICK ELLIPTICAL HEAO 25 3/4'1.0.

ASTM A -240 TYPE 304 9/16' MIN THICKNESS 7-NOV-I qoq 16, *12 as~3: r 355. 0011rnrn~0002. oGr<

UPPER SUPPO/lT (SiE s,c r ION B-8 'OH llET n11 S7

-

1 j

3/4' 3000* THO COUPLING

s=,/*~

B -

SIIELL Vl'NT CONtlEC:TION I

6"-CC-G4-151-1

~

SHELL SIDE OUl LET l.--1-0~

ISi CLASS 3A 27" 0.0.

10 !l.\\*10

-WMV.:;-QJJ2M1

((!0-4)

'i. TUBE SIDE OUTL~T_l_ --*

SECTION A-A LOWE'~ 5UPPORT 5/8" t

2'-CH-7-602-TUBE SIDE OUTLET ISi CLASS 28 2' 3000°S.W. COUPLING TYPICAL INLET & OUTLET

-- __.£~.'i. TUBE SIDE INLET

'i. Sl>ELL SIDE OUTLET_~--

SHEE T BAFFLES SECTION B-B UPPER SUPPORT 3/8' 27 HOLES I 1/4' DRILL THAU

', HOLES DRILL & TAP THAU I J/8'-9UN-2 FOR I 1/B'DJA.

STUDS-EVERY FOURTH HOLE TAPPED 10 11448

-MKS-ll05Al

~

DETAIL I DRAIN CONIIECT IONS 3/~" 30~0* 5.11. COUPLING TYPICAL OF 7 GENERAL ELEVATION 14-_:3c...,_:l/_:::4_'._.i TYPICAL TUBE SIDE NOZZLE & FLANGE WELDS INIT JAL ISSUE 0

VIRGINIA PO'IER NORTH CAnOLINA POWER POI/ER ENGltlEF.RING SERVICES RIC,MJNO, Vl ROINIA INSERVICE INSPECTION DETAIL DRA\\o."ING LETDOWN HEAT EXCHANGER:l-CH-E-2 SURRY POWER STATION UNIT l VIRGINIA POWER CAO NO.

CHEC00002 SCALE NONE lN.ESS OTtER'il'lSE NOTED 2

F E

D C

B A

D C

B 8

7 3/4'-r.H-223* 15~2-IOUTLETl 6

Tll ll440

-,t<rS-112M?.*2 (Q[}-4) 24 NUTS 1.625 DIA.

SA-J_q4 GR 2H 5

4 J'-t:C-112-151-I

<OUILETI

/

-4' X 3' REDUCER 3

EXCESS LETDOWN HEAT 1:XCHf!NGER

!-CH-E-4

_L J/4' 300'1* H(,1.F COLIPLINS VflH PLUG CTUrlEAOEOJ

~------

I

-,\\

B 5/G' (l.U.

. I,J

"- 3/4" 3000* HALF COUPLING DRAIN PLUG CTHREAOEOI GENERAL El EVATJON lMQT[ '.'I

_U ANC 4' SCH 40 STUB

(§)

FROM 1)448

-WMKS-112AA2-I LJ'-CC-107-151- !

!INLET>

loE-41 VIRGINIA POWER NORTH CAROLINA POWER POWER ENGINEERING SERVICES RIC...a.'10,VIRGINlo>

,_I_N_S_ER_V_I_C_E_I_N_S~PE~C~TI-ON ~D_E_T_A-IL_D_R_A_W-IN~G,....,

A 1-,------~~-~-.-r~~--~~~~~-,--.-~~~--~~~~-,-,-~~~~~~~~~,,r-~~~~~~~~,-,-~~~~~~~~,

EXCESS LETDOWN HX:l-CH-E-4 SURRY POWER STATION UNIT 1 VIRGINIA POWER INITIAL ISSUE ow, CAO NO.

CH£0.J0004 0

REY, 0

SCALE NONE ltl.ESS 0Tl£RW1SE NOTED 2

G-t1ov-1qa9 rn:21 QSA3: [ 355. m,1 JCHUm0004.DSfl F1 I

I E

D C

B A

F E

D C

B A

25*JAN* lqg0 14142 QSA31 [ 3~5, 001 J CHFL004A I

DGN ISi CLASS :'B 3/4' VENT CONNECTION W

OVER PLATE SOL TING 6 - 1 1/4' 8 UNC APTlVE DOLTS

.875 MIN WALL THICKNESS INLET -

151 CLASS 28

~-----

FROM 11448

-MKS-110587 2' SCH 1605 SOCKET WELD END TO 11448

-MKS-110588

..i----cs----1 I

I I !.-

GENERAL ELEVATION

.,.- ARM LIFT ASSEMBLY 4

SEAL INJECTION FILTER 1-CH-FL-4A li_lNLET_/ **

'O' REFERENCE 2'-CH-75*1503-0UTLET - ISi CLASS 28 3

,.L'.b._.----

'+'7[,::

!J'

,-----L-+ - - -1

-.. -1

~----i--+---.i.

' ~\\).-

'.., 11r n;;,'~

ANC H003-I ANC 2

ANC BASEPLATE MOUNTING HOLES 11/8' DIA ITYP OF 41 SECTION A-A SUPPPORT DETAILS V !RGI NI A POWER NORTH CAROLINA POW=E~R--------~

POWER ENGINEERING SERVICES RJCHIO(J,VJROl~IA INSERVICE INSPECTION DETA!L DRAWING SEAL INJECTION FILTER: 1-CH-FL -4A F-E D

C B

SURRY POWER STATION UNIT 1 A

VIRGINIA POWER

]NIT ]AL ISSUE OSGN SUPY f(

CAO "°*

CHFL004AI SU<.E NONE UP<<..ESS OTHERWISE hDTEO 2

8 F

E D

C B

A 25-JAN-1990 14146 ClSA31 [ 355, 00 ! JCHFL0048 I, DGN 7

ISi CLASS 26 31 VENT CONNECTION rn OVER PLATE BOLTING 6 - I 1/4' B UNC APTIVE BOLTS

.875 MIN.

WALL THICKNESS INLET - ISi CLASS 2&

2'-CH-76-1503-FROM 11448

-MKS*1105B7 2' SCH 1605 SOCKET WELO END TD 11448

-MKS-110568 6

5 4

.i,----cs ----f te 3/4" OD ---<'!--------'

I I

I GENERAL ELEVATION SEAL INJECTION ill.ill 1-CH-FL-4B ft.INLET_/ **

'O' REFERENCE 2'-CH-76-1503-0UTLET - ISi CLASS 28 3

,.,..-b_r- **

~i'r---

~',,""'

2 ANC

--~------1 H002-1 L---r--+- - -.1,

( + ":

. -$-\\~-

'\\,

'~~

1/~' ITYPJ.....1o

'-- BASEPLATE MOUNTING HOLES 11/8' DIA ITYP OF 41 SECTION A-A SUPPPDRT DETAILS VIRGIN I A POWER NORTH CAROLINA POWER POWER El<<l I NEER I l<<l SERY, CES RICI-MHJ,YIRGINIA INSERVICE INSPECTION DETAIL DRAWING SEAL INJECTION FILTER: 1-CH-FL -48 F

E D

C B

SURRY POWER STATION UNIT 1 A

VIRGINIA POWER INITIAL ISSUE OSO< --

OSO< SUl'Y if CAO I(),

CHFL004BI Gm.E NONE lff.ESS OTH£fh'1SE NlTED 2

F 1-t>

I E

D C

B

~.

1 G

5 4

urPF n: surrnnr

. l~tf SfCTIUN B*R fOH {l[Tnll s7

~l![l I. Vf *.;J l.Ctml CTIUN n14*.m.m* 1111J cuurt.ltJ;;~ ---~L : n : //h_ SIIELL V[NT COIUIEC'IION JiLlllls=

3/4' 3000* IHLi COUPLING f l!t~I ji*1'1U

,a*H *; \\1!1.:'11 ccr-2, LElDOWN HEAT

[>:CHANGER I-CH-

~

SIIELL FLANGE SHELL ASTM A-205 GR ASH! A-181 GR II TUBE SHEET ASTM A-240 TP304 '-......,

CH~NNEL FLANGE ASTH A-182 F304 2'-CH-6-602-lU8E SIDE INLET ISi CLASS ZR

,,.,.-- I I

ti"-('(-t,4-1~1-27' 0.0.

~i SHfLL SIDE OlJlL[T

( ]~~

ISi CLASS JA 10 !l*1*1U

-WMV.:;-JJl2M1 Cci0-4l

'i_ TUBE SIDE OUTL~T_l_ --*

ANC H0~

5/8' 2'-CH-7-602-

.f SECTION A-A LOWE'l SUPPORT TUBE SIDE OUTLET ISi CLASS 28 2' 3000'S.II. COUPLING TYPICAL INLET a OUTLET 3

-- __ L~.'f. TUBE SIOF INLE,:

'i_ SltELL SIDE OUTLET-~--

SHEET BAFFLES DETAIL 1 2

SECTION 8-B LIPPER ~U?PORT 3/8' l.

27 HOLES I l/4' DRILL THAU

<, HOLES DRILL i, TAP THAU

'i_ SHELL

_L.:l~_E INLET I J/8'-9UN-Z FOR I l/8'DIA, STUDS-EVERY FGURTH HOLE TAPPED TUBE srnE SHELL ASIH A-240 10 11448

-MKS-1105AI

,___3c._cl'-/4-'-'_.., TYPICAL TUBE SIDE NOZZLE & FLANGE WELDS A

7-NDY-tqoq 16: 42 TP 30-'.375 THICK ELLIPTJCAL IIEAO 25 3/4'1,0.

ASTH A -240 TYPE 304 9/16' MIN THICKNESS us~ 3: I 355, 001 Ill lW~0002. OGll CRAIN CONIIECTIONS 3/4' 30~0' S.W. COUPLING TYPICAL OF 7 GENERAL ELEVATION INITIAL ISSUE 0

~

V!AG!N[A PO~EA 1 __ w __

-'-'N-"'OA:..:cl.:..:H-'-'C"-.A"-Fi'-"O=L.,_!N'-"A~P~O'-'Wc.:E,:..:R ________ _

POWER Er<<;IUEF.R1t<.'ING LETDOWN HEAT EXCHANGER:l-CH-E-2 SURRY POWER STATION UNIT 1

, _____ VIRGINIA POWER OC...r.N 05GH ~

CflD NO.

CHEe00002 SCl'll.E NON'E lH.CSS OTl£R'I' I SE NOTED 2

E D

C B

A

F E

D C

B A

8 SHELL HEAD 42' OD.625' THICK ASTM A-240 GR 304 18'-CC-8-121-SHELL SIDE INLET 151 CLASS 3A FROM 11448

-WMKS-0117.SI ICE-61 SHELL ASTM A-240 GR 304 18'-CC-16-121-SHELL SIDE OUTLET ISi CLASS 3A TO 11448

-WMKS-011251 lcD-6>

SHELL FLANGE ASTM A-182 F304 I

-WMKS-0117A2 I

(CE-5>

I TUBE SIDE SHELL L------

ASTM A-240 TP 30!.___/

,875 THICKNESS ELLIPTICAL HEAD 42' OD ASTM A-240 TP 304

,875' THICKNESS 07-JAN-1992 09, 18 ZG5, (355,00 I JRHE000 IA I.DGN 7

/ --.... '

6 5

141 - I 5/8' DIA. HOLES TYP. IN EACH SUPPORT PLATE

'i_ TUBE SIDE OUTLET]_.

NOZZLE REINFORCING SADDLE ASTM A-240 TP 304 ITYPICAU RESIDUAL HEAT REMOVAL EXCHANGER 1-RH-E-IA I

/'

', \\

I

\\

I I

I

/

DRAIN CONNECTIONS 13/4' 3000' S-W.

FULL COUPLING>

10'-RH-9-602-TUBE SIDE OUTLET 151 CLASS 2A 4

3 2

13' Gu~sET j 13 1/2' j__

SUPPORT f,,t.

VENT CONNECTION F

SECTION A-A LOWER SUPPORT H002-I PLATE SECTION C-C GUSSET DETAIL I~...,,

INLET

'0' REFERENCE

't_TUBE SIDE

/

INLET

!,../

10'5CH 40 r---- 'i_ TUBE SIDE OUTLET DETAIL 1 10'SCH 40 TUBE SIDE NOZZLE WELDS INITIAL ISSUE 13/4' 3000' THREADED SECTION B-8 UPPER SUPPORT VIRGINIA POWER NORTH CAROLINA POWER FULL CPLG>

lil:LEM El<<l11£ERll<<l SERVICES RICtMCNl,VIRGIIHA INSERVICE INSPECTION DETAIL DRAWING RESIDUAL HEAT REMOVAL HX: 1-RH-E-lA SURRY POWER STATION UNIT 1 VIRGINIA POWER 05CM 05CM SU'V ARF CAD hll.

RHE000IAI REY.

mvtf GTW DISPL DCII OW lJ1AWIJ<<i J<<J.

hT-r--r--r-ir-r-r-r,---r-r,1-CH(IJ----_-_::--t-LE-AO-EIDl----..:::..:::--1 11448-WMKS-RH-E-IA I

SCALE: NONE lH..ESS 0Tt£RVISE lrl'.ITED 2

E D

C B

A

F E

D C

B 8

SHELL HEAD 42' OD.625' THICK ASTM A-240 GR 304 18'-CC-10-121-SHELL SIDE INLET ISi CLASS 3A FROM 11448

-WMKS-0112AAI COF-51 SHELL ASTM A-240 GR 304 IB'-CC-17-121-SHELL SIDE OUTLET

!SI CLASS 3A TO 11448

-WMKS-0112AAI IOE-51 SHELL FLANGE ASTM A-1B2 F304 FROM 1!448 I

-WMKS-01! 7 A2 I

7 6

5

14) - 1 5/B' OIA. HOLES TYP. IN EACH SUPPORT PLATE
'i. TUBE SIDE OUTLET] __
NOZZLE REINFORCING SADDLE ASTM A-240 TP 304 <TYPICAL>
RESIDUAL HEAT REMOVAL EXCHANGER 1-RH-E-18
__ L_S~E OEr-T-A-IL-1--~
..J.==========C I
TO 1!448 I
-WMKS-01!7A2 I
IOE-71 I
10'-RH-10-602-1 TUBE S!OE OUTLET I
ISi CLASS 2A IOE-71 I
TUBE SIDE SHELL L- - --- -
ASTM A-240 TP 304
/
.B75 THICKNESS ~
ELLIPTICAL HEAO 42' 00 ASTM A-240 TP 304
B75' THICKNESS ___ __/
A 07-JAN-1992 09:23 ZGS: [ 355, 001 JRHE000 IB l. DGN DRAIN CONNECTIONS 13/4' 3000° s.w.
FULL COUPLING!
4 3
2 H00l-l VENT CONNECTION F _
SECTION A-A LOWER SUPPORT SECTION C-C GUSSET DETAIL
rm......
INLET H002-I
'0' REFERENCE Ii.TUBE SIDE V
INLET 10' SCH 40 I
SECTION 8-8 UPPER SUPPORT 13/4' 3000" THREADED FULL CPLGI
~48 STUDS-I 3/B'
_/.' __... ASTM A-193 B7
96 NUTS - ASTM A-194 2H
[SI
!SI r----- 'i. TUBE SIDE OUTLET 10' SCH 40 DETAIL 1 TUBE-SIDE NOZZLE WELDS CLASS 2A CLASS 3A VIRGINIA POWER NORTH CAROLINA POWER lu.:LEAR ENO!IEERINO SERVICES RICIM'.Nl,VIRG!PIIA INSERVICE INSPECTION DETAIL DRAWING RESIDUAL HEAT REMOVAL HX: 1-RH-E-18 SURRY POWER STATION UNIT 1 VIRGINIA POWER ARF CAD..,,
RHE0001BI hr-,-,-,-,-r,-,-,-,-.,r.+....:..:....:..:~--+:~*:-:..:..oc.n.::*-=___!,O!!'w:__--1..,.j;'._f4;:WMKS-RH-E-IB
"'-i'*
scou: NONE LH.ESS 0Tt£RV1SE JIJTED 2
E D
C B
A
RELIEF REQUEST SR-019 I.
IDENTIFICATION OF COMPONENTS Mark/Weld#
Line#
System Drawing#
Class 1-12 27\\"-RC-3-2501R RC 11448-WMKS-OlOOAZ-1 1
1-14 27\\"-RC-3-2501R RC 11448-WMKS-OlOOAZ-1 1
1-12 27\\"-RC-9-2501R RC 11448-WMKS-0102AZ-1 1
1-04 29 11 -RC-1-2501R RC 11448-WMKS-OlOOAZ-1 1
1-04 29 11-RC-7-2501R RC 11448-WMKS-0102AZ-1 1
1-11 31 11-RC-2-2501R RC 11448-WMKS-OlOOAZ-1 1
1-11 31 11-RC-8-2501R RC 11448-WMKS-0102AZ-1 1
1-05 6 11-RC-19-1502 RC 11448-WMKS-0127J2 1
System Abbreviation RC - Reactor Coolant System II.
IMPRACTICABLE CODE REQUIREMENTS The 1980 Edition, Winter 1980 Addenda (inclusive) of ASME Section XI in Table IWB-2500-1 does not allow any limitations to the required volumetric examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%.
III. BASIS FOR RELIEF The components listed above have been examined to the extent practical as required by the Code. Due to interferences of other components or weld joint geometry the reduction in coverage for the listed components was greater than 10%. Prior to 1988 the Surry Unit 1 ISI Program contained generic relief requests concerning partial examination coverage. These relief requests SR-010 (Class 1 Category B-J) and SR-013 (Class 2 Category C-F) were withdrawn by letter serial# 88-332A dated September 30, 1988.
They were withdrawn as a result of correspondence received May 23, 1988 from the NRC, which indicated that generic relief requests could not be approved, and that specific information concerning weld/component identification, description of obstruction or limitation, and, estimate of Code coverage attained needed to be provided.
The examinations of the components above occurred in 1986 or earlier, when our procedures did not record specific scan coverage percentages. The examination record indicated what caused limitations, but not the degree of limitation in all directions. Table SR-019-1 is provided estimating the coverage experienced. This estimate is based upon values from later examinations of similar type components and geometric arrangements, and/or any information record~d for the specific examination. Alternative components were not substituted for
IV.
examination since the coverage attained was representative of what could be expected for these weld joint configurations.
ALTERNATE PROVISIONS It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements.
Table SR-019-1 Surry Unit 1 Examination Coverage Estimates (Piping)
UT Scan Coverage%
Mark£Weld#
Catesorit:
Item#
i 2
z
§ Reason For Partial Drawing#
Estimate Basis 1-12 B-J B9.11 100 100 100 Identification Tag 11448-WMKS-0100AZ-1 Unit 2 weld 1-12 And Pump Nozzle examined 4/14/91 Configuration/ V-path (similar config.
Could Not Be Extended Unit 2 A-Loop)
Due To Cast Austenitic Calibration Blocks 1-14 B-J B9.11 99 100 100 Valve to Pipe Joint 11448-WMKS-0100AZ-1 Unit 1 weld 1-14 Configuration/ V-path examined 5/26/88 Could Not Be Extended (similar config.
Due To Cast Austenitic Unit 1 C-Loop)
Calibration Blocks 1-12 B-J B9.11 94 100 100 1'/z" Nozzle And Pump 11448-WMKS-0102AZ-1 Unit 2 weld 1-12 Configuration/ v-path examined 4/14/91 Could Not Be Extended (similar config.
Due To Cast Austenitic Unit 2 A-Loop)
Calibration Blocks 1-04 B-J B9.11 100 100 100 Valve To Elbow Joint 11448-WMKS-0100AZ-1 No similar exam, Configuration/ V-path estimate from Could Not Be Extended exam record Due To Cast Austenitic Calibration Blocks 1-04 B-J B9.11 100 100 100 Valve To Elbow Joint 11448-WMKS-0102AZ-1 No similar exam, Configuration/ V-path estimate from Could Not Be Extended exam record Due To Cast Austenitic Calibration Blocks 1-11 B-J B9.11 50 50 50 Pump and Elbow Joint 11448-WMKS-0100AZ-1 No similar exam, Configuration, and estimate from Support Interference/
exam record and V-path Could Not Be visual observation Extended Due To Cast of similar joint Austenitic Calibration Blocks
Mark/Weld#
1-11 1-05 Category B-J B-J Item#
B9.11 B9.11 Table SR-019-1 (Continued)
Surry Unit 1 Examination coverage Estimates (Piping)
UT Scan Coverage%
i
2.
z
§ 50 50 50 75 75al 75 75 Reason For' Partial Pump and Elbow Joint Configuration, and support Interference/
V-path Could Not Be Extended Due To Cast Austenitic Calibration Blocks Weld Crown And Valve To Tee Configuration
- Scan was performed from this direction, coverage is unknown due to valve/pump configuration Limitation.
Note: Loop valves, pumps, and elbows made of cast austenitic material al - Extended V-path used to cover this scan direction UT Scan Direction Definitions 2 - Axial scan, 180 degrees from isometric flow direction (weld count).
5 - Axial scan, the same direction as the isometric flow (weld count).
7 - CircL111ferentiaL scan, clockwise rotation when viewing in the direction of isometric flow.
8 - Circllllferential scan, counterclockwise rotation when viewing in the direction of isometric flow.
(
Drawing#
Estimate Basis 11448-WMKS-0102AZ-1 No similar exam, estimate from exam record and visual observation of similar joint 11448-WMKS-0127J2 Drawing FP-10P, assumes no exam for 90° of 6x6x6 tee. Some coverage was attained in this region, however that extent is unknown.
8 F
E D
C B
A 8
29-AI.Xi-lqqz "814q ZG51 [355,0Gll01eeiw!l 1,DGN 7
BEarn2B VESSEL I-RC*
.-1!:t CNOTE 7l 7
6 5
SEE DETAIL "I' ON j 11448*11HKS-01'1MZ*2 IB*U REVISED PER DC,1-il5 2
GE.OR fic:-
E*lA oiifi"'i, 3
2 I
I I
I I
I I
I I
I I
I I
I Cllt.D HOT LEO LEG l NOTE, WORK THIS DllG 111TH ll448*11HKS-011l8AZ*2 l
~
VIRGINIA POWER tGTH CAROLINA POWER INSERVICE INSPECTION ISOMETRIC RC SYS1LOOP A REACTOR COOLANT PIPE SURRY POWER STATION UNIT l VIRGINIA POWER
\\1&.111 DncJIIJa IIITID 2
F E
D C
B A
8 F
E D
C B
A 8
1q-AlJG-1qqz S'h22 7
it.El-II'* q 15/16"--,/,'
I~
~
1-RC-
_J!:L INCITE 71 7
ZG51 C 355, BB I la IB2AZZ 11.0GN 6
5 REACTOR COOLA~T f1!M!5 GE.OR
~r-lfe-;-)
.P-1L INCITE q>
REVISED PER DC q1-'"
2 INCITE B>
3 2
r--.
I I
I I
I I
I I
I I
I I
I I
NOTE, WCJllC THIS OIIG WITH 11448*lll<<S*81B2AZ*2
~
VIRGINIA PINER IGTH CAR!LINA PINER ILIUM EJIIUUJIIIII IEJl'IICD 111~,IIIIIIIIA
\\
INSERVICE INSPECTION ISOMETRIC RC SYS:LOOP C REACTOR COOLANT PIPE SURRY POWER STATION UNIT 1 VIRGINIA POWER IIRAZZII 2
F E
D C
B A
F E
D C
B A
8
'IB' LR ELL FROM 11448
-WM<S-B127J5 CDF-31 23-SEP-1'18'1 ll'l:17 QSA31 I 355, BBi lB127JBB21.DGN1 7
2-lil6 6
3-11
'!Ill' LR ELL 5
4 13 3-118 3
2"-SI-85-151l2-SCK.16B LC HBB4 REDRAWN FIil ISi 2
3-05 3-06
.. VIRGINIA POWER NORTH CAROLINA POWER F011ER ENGIIEEIIIIG SERVICES RJCIKNI, YI.INIA INSERVICE INSPECTION ISOMETRIC SI SYS: COLD LOOP 2 SURRY POWER STATION UNIT 1 VIRGINIA POWER 21~!~e~~i~2~~~R~~~ i:"'""'=~---+=:;;-'=SPl.~=.c._.::...,.=_:..."'--l-""°.::....,;:..;,;r;i-:.:..,-,.,-. _....::;lll:::2::.;7J:::llll2=1'--,r=IIEY~.
LEAD....,
11448-WHKS-0127J2 2
sa>t.E NOi£ IIUSS Oll£RV1SE 1111m 2
F E
D C
B A
.J I
r... ""'
--1 A-Al"*""'
(
DIMS TYPO&. fat L~ Z *l )
LINE HOS Af>PL't Til LOOP J ONLY
=T
-~-,.
..,LO..-u:.1*
~LcL-IS'-10" ma.---~-,.~
~--*,_.....,,.am
___,_r.n.l....
NOTE~
~""LE. t**1~0"
--~ * *-.
C.ENE.PJJ.. MOlfii. R~F~RS:M(I!; Owif~~ ::!P.-1~
CHEMICAL & \\OLUME CQ\\JTROL SYSTEM REACTOR CONTAINMENT.
SH 3 J* '
I
tL.-J"'"

-*--* --~----, -:-.-,:~~ ~-

t.,\\lll'~'lf,*, *.l *\\ F,-_.,_...... };,;:t: \\
I II o*- D',,r-lOUH D*Zl 0- D, FP*I011l£ 1*!1
.r z'!ol~--
_-.:.i.!h,-IM..
NOT£~
L K"'-LR-1:* *1'--0"
&E.NEIUJ.. NOlll.. lU!.FE.RliMCI!: ~
-:FP.-la.,t CHEMICAL & \\Ol.UME CCNTROL SYSTEM REACTOR CONTAINtENT.
SH 3
... 9'l'llllt TIIIII '11a caana,cr-.,
........ --.,..,.,.... r-.nw
-**mu--.
IIIOIQI.. -
- - COSftNl.&nDl'I
./.S
= 11~-FP-IOP~
\\
Surry Power Station Unit 2 ISi Examination Relief
RELIEF REQUEST SR-020 I.
IDENTIFICATION OF COMPONENTS Mark/Weld#
Line#
System Drawing#
Class 1-05 8"-RC-311-2501R RC 11548-WMKS-RC-6 1
1-07 6 11-RC-316-1502 RC 11548-WMKS-0122H1 1
1-12 27~"-RC-303-2501R RC 11548-WMKS-RC-12-1 1
1-13 27~ 11-RC-303-2501R RC 11548-WMKS-RC-12-1 1
1-14 27~"-RC-303-2501R RC 11548-WMKS-RC-12-1 1
1-01 CH 11548-WMKS-CH-E-2 2
1-02 CH 11548-WMKS-CH-E-2 2
1-02 CH 11548-WMKS-CH-E-4 2
H001-1 30"-SHP-102-601 MS 11548-WMKS-0101D1 2
H001-2 30 11-SHP-102-601 MS 11548-WMKS-0101D1 2
H004-1 30"-SHP-103-601 MS 11548-WMKS-0102D1 2
H004-2 30"-SHP-103-601 MS 11548-WMKS-0102D1 2
System Abbreviation RC-Reactor Coolant System CH-Chemical and Volume Control System MS-Main Steam System II.
IMPRACTICABLE CODE REQUIREMENTS The 1980 Edition, Winter 1980 Addenda (inclusive) of ASME Section XI in Tables IWB-2500-1 and IWC-2500-1 does not allow any limitations to the required volumetric and surface examinations.
Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%.
III. BASIS FOR RELIEF IV.
The components listed above have been examined to the extent practical as required by the Code. Due to interferences of other components or weld joint geometry the reduction in coverage for the listed components was greater than 10%. Table SR-020-1 is provided detailing the limitations experienced.
Amplifying sketches or drawings are also provided. Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code, or because the examination coverage attained was representative of what could be expected for that type configuration.
ALTERNATE PROVISIONS It is proposed that the examinations already completed at the reduced coverage be counted as meeting the Code requirements.
Additionally the main steam integral attachments (H001-1, HOOl-2, H004-1, and H004-2) shall be visually (VT-1) examined
1-~
for cracking and abnormal inservice induced conditions at the next refueling outage scheduled tentatively for September 1994 (10 year ISI).
Table SR-020-1 Surry Unit 2 Examination coverage Estimates (Piping and Vessels (< 2" thick) & Integral Attachments)
UT Scan Coverage%
Surface MarkLWeld#
Categorll'.
Item#
i
2.
1.
§ Coverage%
Reason For Partial Sketch#LDrawing 1-05 B-J B9.11 89 89*
100 100 N/A Valve And Pipe Joint 1
Configuration 11548-WMKS-RC-6 1-07 B-J B9.11 83*
83 100 100 N/A Valve And Elbow 2
Joint Configuration 11548-WMKS-0122H1 1-12 B-J B9.11 100 0
100 100 N/A Pump And Pipe Joint 3
Configuration/ V-path 11548-WMKS-RC-12-1 Could Not Be Extended Due To Cast Austenitic Calibration Blocks 1-13 B-J B9.11 0
100 100 100 N/A Valve And Pipe Joint 3
Configuration/ V-path 11548-WMKS-RC-12-1 Could Not Be Extended Due To Cast Austenitic Calibration Blocks 1-14 B-J B9.11 100 0
100 100 N/A Valve And Pipe Joint 3
Configuration/ V-path 11548-WMKS-RC-12-1 Could Not Be Extended Due To Cast Austenitic Calibration Blocks 1-01(0-360°)
C-A C1.20 66 66 38 38 N/A Welded Support, Extended 11548-WMKS-CH-E-2
[2-CH-E-2]
V-path Used to Maximize Coverage 1-02(0-360°)
C-A C1.10 95 95 77 77 N/A Flange/Weld Configuration, 11548-WMKS-CH-E-2
[2-CH-E-2]
Welded Support, Nozzles 1-02(0-360°)
C-A C1.10 77 77 80 80 N/A Nozzles, Extended V-path 11548-WMKS-CH-E-4
[2-CH-E-4]
Used to Maximize Coverage H001-1 c-c C3.40 N/A 80 Support Configuration 4
11548-WMKS-0101D1 H001-2 c-c C3.40 N/A 80 Support Configuration 4
11548-WMKS-0101D1
Table SR-020-1 (Continued)
Surry Unit 2 Examination Coverage Estimates (Piping and Vessels (< 2 11 thick) & Integral Attachments)
Mark/Weld#
H004-1 H004-2 Category c-c c-c Item#
C3.40 C3.40
- Extended V-path used to maximize coverage UT Scan Direction Definitions UT Scan Coverage%
i
2.
z
§ N/A N/A Surface Coverage%
57 57 Reason For Partial Support Configuration support Configuration 2 - Axial scan, 180 degrees from isometric flow direction (weld count) or on vertical vessels bottom side of weld.
5 - Axial scan, the same direction as the isometric flow (weld count) or on vertical vessels top side of weld.
Sketch#/Drawing 5
11548-\\.IMKS-0102D1 5
11548-\\.IMKS-0102D1 7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow (clockwise from O reference on vessels).
8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow (counterclockwise from O reference on vessels).
*~
Weld 1-os on Line No. a 11-Rc-311-2so1R C 1/ 3t) 0.719 C 1/ 3t)
Exam. Vol.
C-D-E-F Sketch #1
8.
F E
D C
B A
21-FEB-lqq0 21121 QSA3r [ 355, 002 l00RC0006 I, DGN 7
2'1'-RC-301-2501R-TO 11548
-IIMKS-RC-12-1 IGD-4>
6 qe* LR ELL 8'-RC-311-2501R-5 TO 11548
-WMKS-RC-6Z laC-2>
4 3
1-04
'10' LR ELL INITIAL ISSUE 2
ALVE YOKE 80L TINj 4 STUDS-2' 4 *NUTS-2'
!NOTE 3>
27 l/2'-RC-31l3-2501R-FROM 11548
-WMKS-RC-12-1 IGE-6>
..... VIRGINIA POWER
'1111111111111' NORTH CAROLINA POWER PINER ENlll£ERINI SERVICES RIDMH!,'IIIIDINIA INSERVICE INSPECTION ISOMETRIC RC SYS:LOOP BYPASS SURRY POWER STATION UNIT 2 VIRGINIA POWER 2
F E
D C
B A
la, Ill
\\.
Weld 1-07 on Line 6"-RC-316-1502
-i>
Search ~it 1 5:!arch ~it 2
\\
Elbow 0.187"
( 1/ 3t)
Valve 2-Sl-239 1/4" D.187" C 1/ 3t) 1.125" Exam. Vol.
C-D-E-F
[)"awl ng t-bt To Sea I e Sketch #2
"'-,----8---1 7
6 5
F E
2-06 6'-Sl-24'1-1502-B A
23-NOV-1'1'12 15,47 ZG51 [355,002l0122H001 I.OGN SENSITIZED PIPING
~
54 55 56 57 58 5'1 60 61 62 63 64 4
2'1'-RC-301-2501R-TO 11548
-WMKS-RC-12-1 CGB-41
~
2-24 2-23 2-22 2-21 2-1'1 2-16 2-14 2-11 2-10 2-0'1 2-0B 3
I!!....J!M 2-26 12 BENDS>
2-24 2-23 2-22 2-21 C2 BENDS>
2-18 C2 BENDSI 2-16 12 BENDS>
2-13 12 BENDS>
2-11 2-10 2-0'1 2
It EL. 1-110'-6'\\
FROM 11548
-WMKS-0122Kl-2 IGB-51 I
e VIRGINIA POWER NORTH CAROLINA POWER IU:LEM EIIOll£ER1NI SERVICES Rl~oVIROINIA INSERVICE INSPECTION ISOMETRIC REVISED PER IS! REVIEW.
INITIAL ISSUE SI SYS: LOW HEAD SAFETY INJECTION *1
. SURRY POWER STATION UNIT 2 VIRGINIA POWER DSOII --
DSOII Sll'V ARF 11122Hllllll 0
IIEY.
l SCU NONE LN.£SS OTIOVISE IIITED 2
F E
D C
B A
i\\'l, I*'
t...
l ;
t*
2. 187" Welds 1-12, 1-13 & 1-14 on Line 27~-RC-303-2501R
-i>
C F
1/ 4" Sketch #3
-i>
2.0" 2.5" Exam. Vol.
C-D-E-F D-awin Not To Scale E
', \\'
Va Ive or Purrp As ilppl icable 0.729" (1/]t) 1/ 4"
8 F
E D
C B
A 20-FEB* l'l'll!I 23147 7
/
It_ EL.11'*'1 15/16' ---1*
REACTOR VESSEL 2-RC-R-1
!NOTE 7)
QSA31 [355, 002J00RC0012 I. DGN 6
J J
5 REACTOR COOLANT PUMP
/""2-=i:ic-. \\
\\... P-lA... 1 CNOTE 'll m
EE DETAIL A ON 1548*WHKS*RC*l2*2 aE-6>
J
/
4 GE~OR 2-RC-E-1A
1NOTE 0 8l 0
J TD 11548
WHKS*0117AI-I IGE-7>
FROM 11548
WHKS*0122HI laE-4>
INITIAL ISSUE 3
r*****-,
I I
I I
I I
I I
I
- I I
I I
I J
2 SEE DETAIL I ON J 11548*WHKS*RC*l2*2 IG8*2>
l'*RC*436*1502*
TO 11548
WHKS*RC-38 laE-21 l'*RC-437*1502*
TO 11548
WHKS*RC-38 la >
..'~EE DETAIL C ON J 11548*WHKS*RC*l2*2 IGB-7)
NOTE, WORK THIS DWG WITH 11448*WHKS*RC*l2*2 e VIRGINIA POWER
~TH CARCLINA POWER POIIEJI EICIIIEERIICI liERY ICES AIDtlNJ,Yllllllllill INSERVICE INSPECTION ISOMETRIC RC SYS:LOOP A REACTOR COOLANT PIPE SURRY POWER STATION UNIT 2 VIRGINIA POWER lllllRCllli!l21 2
F E
D C
B A
F E
D C
B A
8 7
6 Ll'PER SU'PORT CSEE SECTION B-B FOR DETAILS7 S1£\\.L VENT CIHIECTIOII 8 t t 8 13/4' 3000* TICJ COl.l'LINGI ---=---_.:._: :,,,-:___..;..--.
S1£LL SIDE INLET ISi CLASS 3A FROM 11448
IIMKS*ll112ALI IIIE-61 LETDOWN HEAT EXCHANGER SHELL FLANGE ASTM A-181 GR II TU8E S1£ET ASTM A-24111 TP304 CHANNEL FLANGE ASTM A-182 F31l4 2'-CH-306-602-TUIE SIDE INLET ISi CLASS 28 2-CH-E-2 ELLIPTICAL HEAD 25 3/4'1.D.
ASTM A *240 TYPE 304
'l/16' MIN THICKNESS 27" 0.0.
DRAIN CONNECTIONS 3/4' 3000° S.W. COUPLING TYPICAL OF 7 GENERAL ELEVATION TO 11448
-IIMKS-llll2AKI (Cl*-51 DIIA!rf' CONNECTIONS 5
3/4' 31lee* s.w. COUPLING ~
TYPICAL OF 7 ~
t 4
ANC SECTION A-A LOWER SU'PORT 2'-CH-307-602-TUBE SIDE OUTLET ISi CLASS 28 2' 300ll0S.W. COUPLING TYPICAL INLET &. OUTLET I
1.,
I I
I 3 J/4' 3
2
{ S1£LL SIDE 0UTLE1:_~--
DETAIL l SECTION 8-8 l.l'PER SU'PORT 3/8' 27 HOLES I 1/4' CRILL THRU
'I HOLES DRILL &. TAP THRU I I/ a*-euN-2 FOR I 1/B'OIA.
STUDS-EVERY FOURTH HOLE TAPPED TYPICAL TUBE 51[)1; NOZZLE &
FLANGE WELDS INITIAL ISSUE e
VIRGINIA POWER NORTH CAROLINA POWER POWER El<<llNEERING SERVICES Rl!HINJ, YIROIIUA INSERVICE INSPECTION DETAIL DRAWING LETDOWN HEAT EXCHANGER:2-CH-E-2 SURRY POWER STATION UNIT 2 VIRGINIA POWER DOON osa,......,n CMI l"l.
CHE00llll02 llMt MBL Dl!R DOI (b.\\ I:_
(JIAWUCJ NJ.
F£Y.
LtllD DOI 115-18-WMKS-CH-E-2 0
SDOI.E NONE lN.ES'S 0TlRIIISE ICJTED 2
F E
D C
B A
Ir 8
F E
D C
B A
8 12-FEB-l'lql!I 12104 7
3/4'-CH-423-151*
3/4'THICIC ELLIPTICAL 1£AD IOUTLETI OSAJ1 [ 355, e02JCHE000004, ~GN 6
TO 11548
VM<S-1!111253 18£-21 ISi a.ASS 2A CLASS 3A 24 MJTS 1.625 DIA.
SA-1'14 GR 2H 5
4' SCH 411 4
3/4' 31!1BB* HALF COl.f't.lNG DRAIN PLUG ITlflEAOEOJ GENERAL ELEVATION 3
2
~1~5~ieRi8~
8 5/8' 0.0.
INITIAL ISSUE 2-CH-E-'4 3/4' 31!10B" HALF COLPI.ING VENT PLUG ITHREAOEOI 3'-CC-187*151*
ONLETI FROM 11548
VM<S*l!11253 18£-2>
~
VIRGINIA POWER
,...., NORTH CAROLINA POWER PIIIIER EIGIIEEIUIIG &ERYICES Rl~,YIAIIINIA INSERVICE INSPECTION DETAIL DRAWING EXCESS LETDOWN HX:2-CH-E-4 SURRY POWER STATION UNIT 2 VIRGINIA POWER t.JrLE'S'S OltERWISE fCJTED 2
F E
D C
B A
A
/30"-SHP-1 02-601 -SPRING CAN INACCESSIBLE WELD AREA EXAMINED AREA
~~
8" OF INSIDE GUSSET INTEGRAL ATTACHMENT WELD EXAMINED A-A INTEGRAL ATTACHMENTS HOOl-1 AND HOOl-2 (TYPICAL)
DRAWING NOT TO SCALE Sketch #4
,,~, I
8 F
E C
B STEAM GENERMOR 2-RC-E-IB 7
TO 11548
-WMCS-l!lll3A2-2 rac-11 6
~
BIOLOGICAL SHIELD WALL 5
INSIDE REACTOR CONTAlfi.tENT 3
A t-r-------...,...,,--------"T'"°..-----------.--r---------.-.--------..... ---------t ISEO PER 151 REVIEW INITIAL ISSI.£ 8
7 6
31-AUG-1'1'12' ll811l8 ZG'5, [3!1!5,llil2lllllllDl!l811.00N 2
~
VIRGINIA POWER NmTH CARCLINA POWER IDIDIIEEIIIIII IEIIVICES 111~¥11111IIIA IN ERVICE INSPECTION ISOMETRIC SHP SYS:MAIN STEAM LINE LOOP B SURRY POWER STATION UNIT 2 VIRGINIA POWER
_,111111.
11548-IMCS-BJSIDI I
2 F
E D
C B
A
l I
.A I J r30"-SHP-1 03-601
('
-,__SPRING CAN INACCESSIBLE WELD AREA
-r 3" i.-
13" 1 14" 1 7 /8" BOLTING A-A INTEGRAL ATTACHMENTS H00-4-1 AND H00-4-2 (TYPICAL)
DRAWING NOT TO SCALE Sketch #5
8 F
E D
C B
A lrl-SEP-1'1'12 ll'h 16 ZG5,C355,llll2Jel"21l01!111.DGN 7
2-RC-E-lC 6
STEAM GENERATOR TO 11548
-WHKS-811l3A2-3 IGC-2>
5 Ii. EL 41Y-4' -~./
I OUTSIDE REACTOR
. CONTAINMENT INSIDE REACTOR CONTAINMENT REVISED PER ISi REVIEW.
3 INITIAL 1551£ 2
..... VIRGINIA POWER
~
NIJITH CNQ..INA POWER INSERVICE INSPECTION ISOMETRIC SHP SYS: MAIN STEAM LINE. LOOP C SURRY POWER STATION UNIT 2 VIRGINIA POWER APS CID IG.
11~1 2
F E
D C
B A
ll<Y, I

ML18152A045

Text

Navigation menu

Search