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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 28, 1995 United States Nuclear Regulatory Commission                      Serial No. 95-176 Attention: Document Control Desk                                NO/ETS Washington, D. C. 20555                                          Docket Nos. 50-281 License Nos. DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 28, 1995 United States Nuclear Regulatory Commission                      Serial No. 95-176 Attention: Document Control Desk                                NO/ETS Washington, D. C. 20555                                          Docket Nos. 50-281 License Nos. DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS During the recent refueling outage, Surry Unit 2 completed its second ten-year interval inservice inspections. Examinations during this interval were conducted to the requirements of the 1980 Edition and Winter 1980 Addenda of ASME Section XI.
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS During the recent refueling outage, Surry Unit 2 completed its second ten-year interval inservice inspections. Examinations during this interval were conducted to the requirements of the 1980 Edition and Winter 1980 Addenda of ASME Section XI.
Pursuant to 1O CFR 50.55a (g) 5, relief is requested from certain requirements of ASME Section XI associated with partial examinations conducted during the 1995 Surry Unit 2 refueling outage. Relief requests, SR-22 through SR-26, are attached and provide the basis of this request.
Pursuant to 10 CFR 50.55a (g) 5, relief is requested from certain requirements of ASME Section XI associated with partial examinations conducted during the 1995 Surry Unit 2 refueling outage. Relief requests, SR-22 through SR-26, are attached and provide the basis of this request.
These relief requests have been reviewed and approved by the Station Nuclear Safety and Operating Committee.
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.
Should you have any additional questions or require additional information, please contact us.

Revision as of 13:33, 6 November 2019

Requests Relief from Certain Requirements of ASME Secton XI Associated W/Partial Exams Conducted During 1995 Plant Refueling Outage ISI
ML18152A356
Person / Time
Site: Surry Dominion icon.png
Issue date: 04/28/1995
From: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-176, NUDOCS 9505050201
Download: ML18152A356 (21)


Text

...PRI*ORITY 1~

.ACCELERATED RIDS PROCESSI:':G)9 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9505050201 DOC.DATE: 95/04/28 NOTARIZED: NO DOCKET#

FACIL:50-281 Surry Power Station, Unit 2, Virginia Electric & Powe 05000281 AUTH.NAME AUTHOR AFFILIATION O'HANLON,J.P. Virginia Power (Virginia Electric & Power Co.)

RECIP.NAME RECIPIENT AFFILIATION p Document Control Branch (Document Control Desk)

SUBJECT:

Requests relief from certain requirements of ASME Seeton XI R associated w/partial exams conducted during 1995 plant refueling outage ISI.

DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ) ENCL _l_ SIZE: :2-c)

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code - GL-89-04 0

. NOTES: 05000281 R RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-l LA 1 1 PD2-1 PD 1 1 BUCKLEY,B 1 1 T INTERNAL: ACRS~-- 6 6 AEOD/SPD/RAB 1 1 y

. C!~;i~D~

OGC/HDS2 01 1 1

1 1

NRR/DE/EMCB NUDOCS-ABSTRACT 1

1 1

1 1 0 RES/DSIR/EIB 1 1 1

EXTERNAL: LITCO BROWN,B 1 1 LITCO RANSOME,C 1 1 NOAC 1 1 NRC PDR 1 1 NOTES: 1 1 D 0

C u

M E

N T

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCCMENT CO!\:TROL DESK, ROOl'vt Pl-37 (EXT 504-2083) TO ELil\H:--JATE YOUR \/A\1E FRO\!

DISTRIBUTION LISTS FOR DOCLME:--JTS YOU DON'T NEED' TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 20

e -

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 28, 1995 United States Nuclear Regulatory Commission Serial No.95-176 Attention: Document Control Desk NO/ETS Washington, D. C. 20555 Docket Nos. 50-281 License Nos. DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM RELIEF REQUESTS During the recent refueling outage, Surry Unit 2 completed its second ten-year interval inservice inspections. Examinations during this interval were conducted to the requirements of the 1980 Edition and Winter 1980 Addenda of ASME Section XI.

Pursuant to 10 CFR 50.55a (g) 5, relief is requested from certain requirements of ASME Section XI associated with partial examinations conducted during the 1995 Surry Unit 2 refueling outage. Relief requests, SR-22 through SR-26, are attached and provide the basis of this request.

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,

!!ri~6or.

Senior Vice President - Nuclear Attachment 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

- -- - -

9505050201 950428 *, -. ---.,

PDR . ADOCK 050Q028 i *, *. 1

______Q___ ---*. -.. '..-.~--- -- ~~~ - -~)

.J

  • J'
  • Attachment 1 Surry Power Station Unit 2 ISi Examination Relief

'!,

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e RELIEF REQUEST SR-22 I. IDENTIFICATION OF COMPONENT Mark/Weld# Line# Drawing# Class H-006 12"-SI-247-1502 11548-WMKS-122A1 H-007 12"-SI-245-1502 11548-WMKS-122L1 II. IMPRACTICABLE CODE REQUIREMENTS The 1980 edition, Winter 1980 Addenda (inclusive) of ASME Section XI Table IWB-2500-1, examination category B-K-1, item number B10.10 does not allow any limitations to the required volumetric or 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 REL~EF The components listed above has been examined to the extent practical as required by the Code. Due to interferences from pipe support structures and the location of the supports at the point where the pipe passes through the floor, a reduction in coverage of the surface examinations of 50% was necessary. Figure SR-22-1 is provided detailing the limitations experienced. The figure is similar for both support structures. Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code.

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

V. STATUS Pending

FLOOR MOUNTED SUPPORT

\v'ALL 2 - INTEGRAL ATTACHMENTS (1' THICK)

INTEGRAL ATTACHMENT

.-----+I-II----.

1 I 1 FLOOR PENETRATION

'---~ FLOOR PENETRATION SIDE VIE\v' TOP VIE\v' Figure SR-22-1

    • a 6 5 3

~

  • ----

0 REFERENCE ORAWINGS1 WIIM*Otl WSTtt00JSE lSO'IETll!C 12:845..34-V,,S*llZlAI WELD l'<EC>W<IOIL Sl<ETQ<

ll,.ll-c:&'1*1!186ASl<ETl rs1a.*ss:r1c11ono,.s.:u.:vrrc,i....t>G ll'°'ll<ex*es'IEISHE!fl ISICt.*SSIFICAllt,,I eo,,.:"'" [)RA11N, 115<'11..,..S*llZ*I ,lP'ES1ltESS5'<E1'"

115'8-f"P*IIA 11,._ll>fi'*l!B ltS48of"P'*12A

,11*1NC-111><G VIRGINlA POWER NORTH CAROL I NA POWER NUCLE.AR ENGlt.EERI~ SERv'icrs RICHMO!'<O, VIRGINIA INSERV!CE INSPECTION ISOME'RIC SI SYS: LOW HEAD SAFETY l~J. LOOP 3 SURRY POWER STATION UNI i 2 VIRGINIA PO'<<ER

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  • -*-***--******* *-*------*.--*------------------*------*------------------------ ****-------------------*---**

J__ . --2 ACCUMULATOR TAN!(

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rou,48

  • -S-ftC*!Z*I VIRGINIA POWER NORTH CAROLINA POWER NUCLEAR E~Gl'-E[RlNG SE~VICES 1---------RICt-.."!.J',O,VIRGJNJA INSERVICE INSPECTION ISOMETRIC SI SYS: S~FETY INJECTION LOOP I SURRY PO\..'E~ STATION UN: f 2 VIRGiN!A POWER

-~-2-j_J______ !_~_,---~__,_L__~1=-;:f-1S=~-~-:i.--H-~l~:~~}-FF.R~=Bd~Ff+4~~~HdM.~+1 I

~~&.ff~-' f~~-°-:_:J:~~~~;~

I ___., ______ _

  • RELIEF REQUEST SR-23
  • I. IDENTIFICATION OF COMPONENT Mark/Weld# Drawing# Class 1-11 11548-WMKS-CH-E-3 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1980 edition, Winter 1980 Addenda (inclusive) of ASME Section XI Table IWB-2500-1, examination category B-D, item number B3.150 does not allow any limitations to the required volumetric or 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 The component listed above has been examined to the extent practical as required by relief request SR-018 of the Inservice Inspection Program for Unit 2 Second Interval. Due to interferences from a support clamp the reduction in coverage of the surface examination was 14.6%. Figure SR-23-1 is provided detailing the limitations experienced.

Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code.

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

V. STATUS Pending

2-CH-E-3

20. 5" circurnf erence 6.5" LLtxLtxl /2 11 1 -1 1 A-A

/ A ~L------~ A Angle iron is attached to larger structure and cannot be moved. Figure SR-2Lt-l

3 2 r----S----L--.,...=-.,iR'-EG_E_N_E.JR_A_TI_V_E4....,:=.:::::,,.~.:;..........1._ _~.....,.-~...,C....L-......:.---~:::...-..L---- ---......L..--------...._----l---~

A HEAT EXCHANGER

~ 2-CH-

_5:_ ____

TU8ESHEET I E-3 .

.1 SHELL 0 7

- ... ......_..,_,,,_

_

q.25* DIA X 0.875' THICK A213 TP 304 SS CTYP OF 3l E 3" SCH 80 PIPE CTYP 2 PLACES)

. SHELL 0 8 1-16 C

ELEVATION LOOKING WEST TO 11548 SECTION °8° SECTION "A" B -WMKS-CH-8 CaF-4)

ISi ISi CLASS 2A CLASS IA VIRGINIA POWER NORTH CAROLINA POWER IIJC1EAR ENG lt£ER I tiO SERVICES Rl~,Vliwi~IA INSERVICE INSPECTION DETAIL DRAWING REGENERATIVE HEAT EXCHANGER:2-CH-E-3 A SURRY POWER STATION UNIT 2 A REV I SEO PER WALKDOWN INITIAL ISSUE VIRGINIA POWER I ND ISi REVIEW 0 OSGI SlJ'Y ARF CAO NO. CHE0000113

~ MBL DJSPL ENOR WFM mAVIJr<<l NO.

lr.r-r--r,-r-,-,.-r-r-r-,--t---M-B-L---1-LE-AD_EHOR ___________

-l 11548-WMKS-CH-E-3 SCALE NONE l.fLESS OTI-ER'i 1SI:: NJTED 2

22-JUN-1qq2 0q,55 ZGS: C355, 0021CHE000003. OGN

.,

RELIEF REQUEST SR-24 I. IDENTIFICATION OF COMPONENT Mark/Weld# Drawing# Class 1-01 11548-WMKS-CH-FL-4A/B 2 II. IMPRACTICABLE CODE REQUIREMENTS The 1980 edition, Winter 1980 Addenda (inclusive) of ASME Section XI Table IWC-2500-1, examination category c-A, item number Cl.20 does not allow any limitations to the required volumetric or 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 The component listed above has been examined to the extent practical as required by the Code. Due to interferences from three permanent support legs the reduction in coverage of the ultrasonic examination was 35% (12 11 out of 34 11 ) . Figure SR-24-1 is provided detailing the limitations experienced.

Alternative components could not be substituted for examination due to the mandatory selection requirements of the Code.

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

V. STATUS Pending

CH-FL-4A/B 31" A A 19" 3 4 II ,__________,

--- -

O" 15" 3.5" A-A Figure SR-24-1

NOTESi

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i r-REFERENCE DRAWINGS:

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RELIEF REQUEST SR-25 I. IDENTIFICATION OF COMPONENT Mark/Weld# Line# Drawing# Class 1-09 31 11 -RC-308-2501R 11548-WMKS-RC-10~1 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1980 edition, Winter 1980 Addenda (inclusive) of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 does not allow any limitations to the required volumetric or 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 The component listed above has been examined to the extent practical as required by the Code. Due to the geometry of the weld crown the reduction in coverage of the volumetric examinations are detailed in Table SR-25-1. Figure SR-25-1 is provided detailing the limitations experienced. Substituting with another weld of the same size would not necessarily improve *the examination coverage since similar geometric conditions are expected.

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

V. STATUS Pending

Table SR-25-1 Surry Unit 2 Examination coverage Estimates 11548~WMKS=RC-10-1 category B-J, Item B9.11 UT Scan Coverage% Surface Examination Mark/Weld#

1-09

~

50 2

83

!.

72

~

72 Coverage%

100 Reason For Partial The geometry of the weld crown limits the coverage in the area of pipe to weld and weld to elbow. Material type, ASTM A-351 e

austentic steel casting, limits the use of an extended V-path examination.

UT Scan Direction Definitions 2 - Axial scan, 180 degrees from isometric flow direction.

5 - Axial scan, the same direction as the isometric flow.

7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow.

8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow.

..

'C' S/G FLOW

. . FLOW ELBOW e

PIPE

3. OS"
2. 6" 3.6" ~~
  • 31 "-RC-308-2501 R WELD 1 -09 FIGURE SR-25-1

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e RELIEF REQUEST SR-26 I. IDENTIFICATION OF COMPONENT Mark/Weld# Drawing# Class 2-05 11548-WMKS-RS-P-2A 2 II. IMPRACTICABLE CODE REQUIREMENTS The 1980 edition, Winter 1980 Addenda (inclusive) of ASME .

Section XI Table IWC-2500-1, examination category C-G, item number C6.10 does not allow any limitations to the required volumetric or 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 The component listed above has been examined to the extent practical as required by the Code. Due to interferences from a pump casing support the reduction in coverage of.the surface examination was 25%. Figure SR-26-1 is provided detailing the limitations experienced. No other alternative is available for substitution since the "B" pump has the same limitation .

    • * * * .- ....: . , * * : -~ : ....... *,r ~

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

V. STATUS.

Pending

  • .

. 1 RS-P-2A

\v'ALL SIDE VIE\J \JALL TOP VIE\J Figure SR-26-1

  • 8 7 6 5 4 J 2

, / LONGITUDIN!,L WE*. 0 F p

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OUTSIDE RECIRC SPRAY PUMP DET A D D E E TO 11548

-WMKS-0123NI DET D

~ 1DD-7l 12'SCH 8 405 PIPE 1 31**

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~DISCHARGE

. '--._ GAUGE CONNECTION D _ _ CAN DRAIN D

<l'P!Pt:I VS LC DET 8 SECT A-A

~ * ~ -

-

SEE 11448-FV-SA IOET El FOR VIBRAl!ON ~LATE DETAIL 0 RING 0

/ - 2'Xl/2'THK RING SLOTS\~

/wELOED TO CASING c:!:====!=i* ACCESSIBLE EL 12'-0'

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- . - - - -INACC.ESSIBLE - - - - - - - - - -

C C Sl lFFENING RIB ITYP *1 - - BOWL BASE LUBE LINES

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