ML20072G160

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Rev 9 to ASME Code Section XI Inservice Insp & Testing Program
ML20072G160
Person / Time
Site: Prairie Island  
Issue date: 06/24/1983
From:
NORTHERN STATES POWER CO.
To:
Shared Package
ML20072G151 List:
References
PROC-830624, TAC-59523, NUDOCS 8306280345
Download: ML20072G160 (9)
v • d • e


Text

., _ -.

Instructions #or Entering Insert pages in the Prairie Island AS'fE Code Section XI. Inservice Insnection and Testim Drotran and Inf ormation Reoutred for MRC Review of Recitests for 9elief fron ASME Code Section XI Recuirements as follows.

REMOVE INSERT ATTACHED REVISED PACES i

i iii 111 iv iv 1.1.1-34 1.1.1-34

.1.5-75 1.1-75 2.1.1-35 2.1.1-35 2.1.1-36 2.1.1-36 2.5-58 2.5-58 o

J NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NOS. 50-282 LICENSE NOS. DPR-42 50-305 DPR-60

'ASME CODE SECTION XI INSERVICE INSPECIION AND TESTING PROGRAM AND INMRMATION REQUIRED FOR NRC REVIEW OF REQUESTS FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENTS SUBMITTED:

February 1, 1978 REVISED: Revision l' September 15,,1978 Revision 2 June 8, 1979 Revision 3 September 19, 1979 Revision 4 April 17, 1980 Revision 5 September 3, 1980 Revision 6 July 31, 1981 Revision 7 December 23, 1981 Revision 8 April 19, 1983 Revision 9 June 24, 1983 i

.J

'd REVISION OF REVISIONS Page No-Revision No Page No Revision No i

9 1.5-6' original 11 4

1. 5-7 1

iii 9

1.5-7A 1

iv 9

1.5-7B 2

1-1 4

1.5-8 thru 1.5-9 Not Used 1.1.1-1 4

1.5-10 1

1.1.1-2'thru 1.1.1-4 6

1.5-11 Original 1.1.1-5 thru 1.1.1-6 Original 1.5-12 1

1.1.1-7 1

1.5-12A 2

1.1.1-8 thru 1.1.1-10 Original 1.5-13 Original 1.1.1-11 6

1.3-14 thru 1.5-15A 8

1.1.1-12 thur 1.1.1-17 Original 1.5-16 1

1.1.1-18 Original 1.5-18 1

1 1.5-17 Original 1.1.1-19 1.1.1-20 1

1.5-18A 1

1.1.1-21 thru 1.1.1-25 Original 1.5-19 Original 1.1.1-26 thru 1.1.1-28 6

1.5-20 1

1.1.1-29 thru 1.1.1-33 Original 1.5-21 Not Used 1.1.1-34 9

1.5-22 thru 1.5-23 Original 1.1.1-35 Original 1.5-24 2

1.1.1-36 6

1.5-25 6

1.1.1-37 thru 1.1.1-39 Original 1.5-26 Not Used 1.1.2-1 4

1.5-27 thru 1.5-28 Original 1.1.2-2 thru 1.1.2-27 6

1.5-29 8

1.1.3-1 4

1.5-30 Original 1.2-1 6

1.5-31 8

1.3-1 4

1.5-32 thru 1.5-34 1

1.3-2 1

1.5-34A i

1.4-1 4

1.5-35 Original 1.4-2 1

1.5-36 6

1.4-3 thru 1.4-4 2

1.5-37 thru 1.5-39 Original l'. 4-5 4

1.5-40 1

1.4-6 1

1.5-41 Original 1.4-7 thur 1.4-8 4

1.5-42 1

1.4-9 2

1.5-43 2

1.4-10 1

1.5-44 thru 1.5-46 Not Used 1.4-11 7

1.5-47 Original 1.4-12 2

1.5-48 6

1.4-13 Not Used 1.5-49 Not Used 1.4-14 thru 1.4-15 2

1.5-50 1

1.4-16 1

1.5-51 Original 1.4-17 6

1.5-52 thru 1.5-55 6

1.4-18 4

1.5-56 3

1.4-19 thru 1.4-20 1

1.5-57 thru 1.5-58 Original 1.4-21 4

1.5-59 6

1.4-22 1

1.5-60 8

1.4-23 4

1.5-61 thru 1.5-62 Original 1.4-24 thru 1,4-34 1

1.5-63 6

~

1.5-1 2

1.5-64 thru 1.5-68 1

1.5-2 1

'1.5-69 2

1.5-3 8

1.5-70 4

1.5-3A 8

1.5-4 thru 1.5-5 8

iii-Revision 9 June 24, 1983

r P'ge No Rsvicien No Page N3

'R vision No 1.5-71 thru 1.5-72 1

2.5-5 original 1.5-73 8

2.5-6 1

1.5-74 4

2.5-6A 2

1.5-75 9

2.5-7 Not Used 1.5-76 6

2.5-8 thru 2.5-9 Original 1.5-77 7

2.5-10 thru 2.5-11 2

2.1 4

2.5-11A 2

2.1.1-1 4

2.5-12 8

2.1.1-2 6

2.5-13 Original 2.1.1-3 6

2.5-14 1

2.1.1-4 1

2.5-15 thru 2.4-20 Original 2.1.1-5 6

2.5-21 6

2.1.1-6 thru 2.1.1-7 Original 2.5-22 Not Used 2.1.1-8 thru 2.1.1-9 6

2.5-23 thru 2.5-24 Original 2.1.1-10 Original 2.5-25 thru 2.5-25A 8

2.1.1-11 6

2.5-26 1

2.1.1-12 thru 2.1.1-13 Original 2.5-26A 1

2.1.1-14 6

2.5-27 Original 2.1.1-15 3

2.5-28 6

2.1.1-16 thru 2.1.1-18 Original 2.5-29 1

2.1.1-19 6

2.5-30 1

2.1.1-20 thru 2.1.1-25 Original 2.5-31 2

2.1.1-26 1

2.5-32 Mot Used 2.1.1-27 thru 2.1.1-30 Original 2.5-33 6

2.1.1-31 6

2.5-34 Not Used 2.1.1-32 thru 2.1.1-33 Original 2.5-35 1

2.1.1-34 6

2.5-36 Original 2.1.1-35 9

2.5-37 thru 2.5-40 6

2.1.1-36 9

2.5-41 thru 2.5-43.

Original 2.1.1-37 Original 2.5-44 6

2.1.1-38 3

2.5-45 8

2.1.1-39 thru 2.1.1-41 Original 2.5-46 thru 2.5-47 Original 2.1.2-1 4

2.5-48 6

2.1.2-2 thru 2.1.2-24 6

2.5-49 thru 2.5-53 1

2.1.3-1 4

2.5-54 4

2.2-1 6

2.5-55 thru 2.5-56 1

2.3.1 4

2.5-57 4

2.3.2 Original 2.5-58 9

2.4-1 4

2.5-59 6

2.4-2 thru 2.4-4 2

2.5-60 7

2.4-5 4

3-1 thru 3-8 6

2.4-6 thru 2.4-7 1

4-1 2

2.4-8 thru 2.4-9 4

4-2 thru 4-4 Original 2.4-10 2

4-5 thru 4-6 2

2.4-11 7

4-7 thru 4-9 Original 2.4-12 thru 2.4-13 1

4-10 thru 4-13 2

2.4-14 6

4-14 thru 4-19 Original 2.4-15 4

4-20 thru 4-22 2

2.4-16 1

4-23 Original 2.4-17 6

4-24 2

2.4-18 thru 2.4-28 1

4-25 thru 4-31 Original 2.5-1 2

4-32 2

2.5-2 1

4-33 thru 4-39 Original 2.5-3 8

4-40 2

2.5-3A 8

2.5-4 8

Revision 9 June 24,1983

-iv-

NORTHERN STATES POWER CO.

TABLE 1.5 "RA!RIE ICLAND ttIT 1 TEN <EAP I N TERVAL INSPECTION SUMMara MUOR I11}l: REACTOR CORE COOIANT PUMPS 1141 O(WONINT OR SYSilli, 1 URAL INSPEC-tilCATION OR RWNIM.

E cyII$

AND LESCRIPTION OF PO.PER IDlNTIFICATION I%4tINATIm TION pgy SYSTi}l NitmER PERCDil ITI}i mW T11111D BF. EWITNFD ITilt AMXNT AND EXTINT PIRIOD 4

85.4 B-K-1 INTEGRALLY WEI.DED SUPPORTS DISQlARGE N0ZZLE AT 0

  • RELIEF NO. 47 PUMP A 3
  • S-UT SUPPORT A (450) l'SUP? ORT 100%

1v0 PT 33 0

SUPPORT B(180 ) l SUPPORT 100%

TWO PT 66 SUPPORT C(315 j i SUPP(RT 100%

TWO PT 100 0

l SUPP(iRT 1001 TilREE 100 85.5 B-K-2 SUPPORT COMPONENTS EAQi PUMP SUPPORT CON-SISTS OF A 1ATERIAL AND COLUMN COMI'ONENT AND' PUMP A EACH SUPPORT INSPECTION 1(IAT & COL)

ONE PUMP A 100%

33 SilALL INCLUDE Boni COM-COLUMN AND IATERIAL 3

V SUPPORT A (45 j)

SUPPORT B(180 SUPPORTS M

100%

66 PONENTS SUPPORTS y

SUPPORT C(315 )

suppoa7s ElREE 100%

100 F

PUMP B 7

COLUMN AND 1ATERIAL 3

V SUPPORT A (450) 1 (IAT + COL)

ONE PUMP B 100%

33 y

SUPPORTS SUPPORT B(1800)

SUPPORTS TWO 100%

66 SUPPORT C(315o)

SUPPORTS TilREE 100%

100 B5.6 B-L-1 PUMP CASING WELDS PUMP A NONE MFG-BIRDSBORO 3/N 543 PUMP S 1

S-UT ESCO PUMP CASING UIREE PUMP B 100 RELIEF NO. 63 SN561 WELDS B5.7 B-L-2 PUMP CASINGS PUMP A & B 2

V l'.S CO INTERIOR SURFACES nlREE PUMP B 50 RELIEF No. 63

$N561 85.8 B-P EXEMPTED COMPONENTS NONE N

  • Y

>RM SO c

63.

REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITEM CATEGORY REACTOR COOLANT PUMP CASING WELDS 1*

1.5 B5.6 B-L-1 CODE REQUIREMENT Volumetric and visual examinations of the pump casing weld at or near the end of the inspection interval.

BASIS 1.

Present ultrasonic examination

.6 nods would be ineffective because of the heavy wall, austenitic stainless steel cast structure of the pump body.

Present radiographic techniques are available to volumetrically examine these welds, but result in excessive radiation exposure to personnel performing disassembly, inspection, and reassembly of the pump.

2.

Pump manufacturer does not recommend disassembly of the pump for inspection only..

3.

Personnel experienced in the disassembly and assembly of pump is limited.

Significant damage or degradation may result.

[

4.

Inspection of other RCP have not detected any problems.

L La 5.

EPRI report on research project RP 2057 indicates on a generic basis that the inspection interval can be increased.

Report should be issued shortly.

ALTERNATE 1.

Monitor the RCP with the additional instruments for shaf t vibration, f rame vibration, thrust position, phase monitoring, and locked rotor.

2.

Visually 1 spect the exterior of the pump casing during the hydrostatic pressure tests required by IWB-5000.

p o;g 3.

Perform a surface examination on the external surface of the welds to the extent practicable.

55

Z 4.

If maintenance or operational problems are encountered which require the disassembly,of the pump, the pump's interior surface vill be visually inspected.

The need for volumetric examination will w,

be determined at that time.

SCHEDtILE FOR IMPLEMENTATION Six months after submittal date for revision 9

NORTHERN STATES POWER CO.

TN 1.5 DRA!RIE !SLAND l't:IT 2 PAGE 2 op 3 TEN

  • EAR I'4 TER V AL li4SPECTION SUMMAAr M UOR I1IN: REACTt% CORE C001 ANT PUMPS EXAM (IRONIN OR SYS11N, 1UTAL INSPEC-IDCATION OR RINNINL.

cal $

AND DESCRII7 TION OF ND.PER IDINTIFICATION EXAMINATIm TION g

WM MER PM IU mW ITIN 1D BF T%WINFD T11N

  1. NT AND EXTINT Pfm0D B5.4 B-K-1 Ih1TCRALLY WELDED SUPPORTS (6)

DISQlARGE N0ZZLE AT 0 PUMP A 3

S-U.T.

SUPPORT A (45 )

-NONE-PUMP A RELIEP NO. 47 (RDIARKl SUPPORT B(1.80 )

3 SUPPORTS 100%~

PUMP A(PT EXAM ONLY) 100 SUPPORT C(315 )

1 SUPPORT 100%

PUMP A luu

+

PUMP B 3

S-U.T.

SUPPORT A (45*)

-NONE-RELIEP NO. 47 (RDIARIO SUPPORT B(180 )

1 SUPPORTS 100%

PUMP B(PT EXAM ONLY) 100 SUPPORT C(315 )

I SUPPORT 100%

TilREE PUMP B 100%

B5.5 B-K-2 SUPPORT COMPONENTS EACH PUMP SUPPORT CONSISTS OP A LATERAL AND COLUMN CatPONENT P

AND EAQI SUPPORT

,P INSPECTION SilALL M

PUMP A INCLUDE BODI O

s'OLUMN AND LATERAL 3

V SUPPORT A (45*)

1 (IAT. & COL.)

ONE PUMP A 100%

33 COMPONENTS --

SUPPORTS SUPPORT B(180*)

SUPPORTS WO 1001 66

$UPPORT C(315*)

SUPPORTS DIREE 1001 100 PUMP B COLUMN AND LATERAL 3

V SUPPORT A (45 )

1 (IAT. & COL.)

ONE PUMP B 1001 33 SUPPORTS SUPPORT B(180*)

SUPPORTS WO 100%

66 SUPPORT C(315*)

SUPPORTS

'DIREE 100%

100 B5.0 B-L-1 PimiP CASING WELDS PUMP A

  • 1 S-UT MFG ESCO PUMP CASING THREE PUMP A 100 RELIEP NO. 63 S/N 510 WELDS PUMP B
  • 1 S*lff HFG ESCO PISIP CASING TilREE PUMP B RELIEP NO. 63 S/N 515 WELDS
  • PUMP A OR B. WillCllEVER IS Tile PUMP TilAT IS DISASSEMBLED.
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REQUEST FOR RELIEF CODE PROGRAM CODE EXAM COMPONENT OR ITEM CLASS TABLE ITF!2 CATECORY REACTOR COOLANT PUMP CASINC WEl.DS 1

1.5 B5.6 B-L-1 l

CODE REOUIREMENT Volumetric and visual examinations of the pump casing weld at or near the end of the inspection interval.

BASIS 1.

Present ultrasonic examination methods would be ineffective because of the heavy wall, austenitic stainless steel cast structure of the pump body.

Present radiographic techniques are available to volumetrically examine these welds, but result in excessive radiation exposure to personnel performing disassembly, inspection, and reass,embly of the pump.

2.

Pump manufacturer does not recommend disassembly of the pump for inspection only.

3.

Personnel experienced in the disassembly and assembly of pump is limited.

Significant damage or degradation may result.

4.

Inspection of other RCP have not detected any problems.

w

,y 5.

EPRI report on research project RP 2057 indicates on a generic basis that the inspection interval can be increased.

g Report should be issued shortly.

AI. TERNATE 1.

rionitor the RCP with the additional instruments for shaft vibration, frame vibration, thrust position, phase monitoring, and locked rotor.

2.

Visually inspect the exterior of the pump casing during the hydrostatic pressure tests required by IWB-50b0.

3.

Perform surface examination on the external surface of the welds to the extent practicable.

os <:

g 4.

If maintenance or operational problems are encountered which require the disassembly of the pump, f[g the pump's interior surface will be visually inspected.

The need for volumetric examination m

will be detenmined at that time.

SCllEDULE FOR IrlPLEMENTATION Six months after submittal date for revision 9.

.

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