ML20056A339

Rev 2 to ASME Code Section XI Inservice Insp & Testing Program,Second 10-Yr Insp Interval

ML20056A339
Person / Time
Site:	Prairie Island
Issue date:	07/31/1990
From:	Stephens B NORTHERN STATES POWER CO.
To:
Shared Package
ML20056A338	List: ML20056A337 ML20056A339
References
PROC-900731, NUDOCS 9008070037
Download: ML20056A339 (7)

Text

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l PRAIRIE ISLAND NUCLEAR GENERATING PLANT ASME CODE SECTION XI:

INSERVICE INSPECTION AND TESTING PROGRAM SECOND TEN YEAR INSPECTION INTERVAL-DECEMBER 16, 1983 - DECEMBER 16, 1993 Inservice-Inspection and Approval D---- & c => f-id f0 Prepared b h e j

- Reviewed by: <

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-- ~7 DI 90 Supt. Matl & Spec Proc Da'te

' Inservice Testing Review and' Approval Prepared by: Ben Stechens 7/29/87-Reviewed.by: Gary Miller 7/29/87 Plant Sect XI Coordinator Date Approved by: -

~7 ManagerProduc[on'PlantMdntenance Date Revision 2 7/31/90 9008070037~900731 PDR ADOCK 05000282

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- RECORDS OF REVISIONS :

nn g~( Pace No. Rev No. Pare No. Rev No. j

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' Review / Approval Sheet' 2 2.1.1-1 thru.8 0' i 1 2.1.1 9 .

'2 111 2 2.1.1-10 thru 32 0 e iii 2 2.1.1 33 1 l'.1.1-1 0 2.1.1-34 thruL38 0 1.1.1-2 0 2.1.1-39 1 l 1-1.1-3 thru 9 .

. 1 ~ 2.1.1-40 thru 45 0 i 1.1.1-10 thru 22 0 2.1.1-461 1 1.1.1-23, 24 1 2.1.1-47 thru 52 0-1.1'.1-25 thru 32 0 2.1.2-1 thru 2.1.2 5 0 1.1.1-33, 34 1 2.1.2-6 1 1.1.1-35, 36- 0 2.1.2-7, 8, 9 0 1.1.1-37 1 2.1.2-10 1 1.1.1-38'thru 51 0 241.2-11 thru 20 0 1.1.2-1 thru 5 0 2.1.3-1 thru 8 0 1.1.2-6 1 2.1.4 1 thru 6 0 1.1.2-7 0 2.2 1 1 1.1.2-8, 9 1 2.3-1 1 1.1.2-10. 0 2.3-2 1 1.1.2-11 1 2.4 1 thru 21 .1 1.1.2-12 thru 15 0 2.5 1 2 1.1.2-16 1 2.5-2 0 1.1.2-17 thru 20 0 2.5-3, 4 1 1.1.3-1 thru 1.1.3-7 0 2.5-5 0

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1.1.4-1 thru 1.1.4-6 0 2.5-6, 7, 8 1-N_,/ 1,2-1 1 2.5-9 0- 4 1,3-1 1 2.5-10 thru 12 1 1.3 2 1 ' 2.5 0 1,4-1lthru 1,4-26 1 2.5-14, 15 1 1.5-1 2 2.5-16 0

'1.5 2 0 2.5 17, 18- 1

. 1~.5-3, 4 1 2.5-19 0

'1.4-5,-6 0- -2.5-20, 21, 22 1 1.5-7 thru 1.5-24 1 2.5 23 thru 2.5631 0 1.5-25 0 2.5-32 thru 2.5 38 1 l 1.5-26 1 2.5-39, 40 0

.1 5-27, 28

. 0 2.5-41 2 1.5-29, 30, 31 1 2.5-42 deleted 1.5-32 thru 1.5-36 0 2.5 43 -0

'1.5-37 1 2.5-44 1 1.5 0

' 1.5-39, 40 1

'1.5-41, 42, 43 . 0

1.5-44 thru 1.5-50 1 1.5-51, 52 0 1.5 53, 54 1 1.5655' deleted 1.5-56 0 1.5-57 1 PI ISI/IST 11 7/31/90 2nd 10 YR PROGRAM REV 2 3

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LPRAIRIE ISLAND NUCLEAR GENERATING PLANT-RECORD OF-INRry1FICE INSPECTION AND TESTING PROGRAM REVISIONS O:

- PI ISI/IST 2nd 10 YR PROGRAM Revision Date-of Remarks (Rev) No. Issue

0 10/14/83 2nd Ten Year Update to ASME Code Requirements 1 7/13/87 Revision to 2nd Ten Year Program Revision to Requests for Relief Addition of Requests for Relief 2 7/31/90 Withdraw Request for Relief-Revise Request for Relief O

PI ISI/IST iii 7/31/90

'1 .

2nd 10 YEAR PROGRAM REV 2

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. 1 9- . 1

.. SECTION 1.5 REQUESTS FOR RELIEF FROM ASME CODE SECTION )O[

/3.1 REQUIREMENTS DETERMINED TO-BE: IMPRACTICAL 1 x ,) UNIT NO. 1 AND COMMON COMPONENTS l This section contains a tabulation of all the requirements contained in Section:XI- of the ASME Code that we have determined are impractical on Unit 1

_and common components.

!The Requests for Relief are numbered sequentially with the following _;

exemptions: j Recuest for Relief No. Remarks .

t 6 Withdrawn 10 Withdrawn 1 15 Withdrawn 17 Withdrawn 18 - 20 Withdrawn 22 Withdrawn 32 Withdrawn -i c 34 Withdrnwn 36 - 39 Withdrawn l 44 Withdrawn 46 47 Withdrawn s- 49 Withdrawn z(' - 3 51 Withdrawn Withdrawn-

, 53 55 . Withdrawn '

57c Withdrawn 58 Withdrawn 62 Withdrawn 64 - 65 Withdrawn 67 Withdrawn-l 1

PI ISI/IST Section 1,5-1 i 2nd 10-YR PROGRAM REV 2 7/31/90  ;

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2 l PRAIRIE ISLAND NUCLEA9 GENERATING PLANT- . UNIT TABLE 3.1 TEN YEAR INTERVAL-EXAMINATION

SUMMARY

PAGE- 3 OF '3 ,

ITEM NDE TOTAL EXAMINATION INSPECTION RUNNING .

~4 NO. COMPONENT OR SYSTEM IDENTIFICATION DESCRtPTION METHOD ITEMS AMOUNT & EXTENT PEROD - .% REMARKS HEAT EXCHANGERS' REGENEP.ATIVE HEAT EXCHANGER i

33.150 N0ZZLE T0-VESSEL WELDS NONE --- --- --- --- --- --- ----

• 33.160 N0ZZLE INSIDE RADIUSED VOL (6) --- --- --- ---

RELIEF NO 66-SECTION W-471R 2-ISI-138 1 --- --- --- ---

W-491R 1 --- --- --- ---

W-S0IR 1 --- --- --- ---

W-53IR l' --- --- --- ---

W-54IR 1 --- --- --- ---

W-56IR 1 --- --- --- ---

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ronu u-sm PI ISI/IST 2.1.1- PI ISI/IST 2.1.1-9 4 2nd.;10-YR PROGRAM REV 2 7/31/90

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-SECTION 2.5 REQUESTS FOR RELIEF FRD;I ASME CODE SECTION XI

'/\ REQUIREMENTS DETERMINED TO BE-IMPRACTICAL 3 ; ,/ UNIT NO. 2

-This-section contains a tabulation of all the requirements' contained in Section XI-of the ASME Code that we have determined are impractical on Unit 2 -

components.. <

The numbering system used parallels Section 1.5 of this report (Unit No. 1 Requests for Relief) with the following exceptions:

i Reauest for Relief No. Remarks 4 Not used 6 V':hdrawn 10 Not used 15 Not used 17 Withdrawn

^

18 - 20 Withdrawn 22 Withdrawn 23 Not used 24 Withdrawn 25 26 Not used-30 .31 Not used  !

32- Withdrawn

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34 Not used i l

35 Withdrawn  :

36 - 37 '

. Not used l- 38' 39 Withdrawn l 40 41 Not used i l 42 Withdrawn o 46 - 47 Withdrawn 49 Not used 51 Withdrawn 53 _

Withdrawn 55 ' Withdrawn 57c Withdrawn 58 Withdrawn 61 Not used 62 Withdrawn 64 - 65 Withdrawn 67 Withdrawn l

lc h"L PI ISI/IST Section 2.5-1 a

2nd 10-YR PROGRAM REV 2 7/31/90 1

9 n . . ,,3 .

66.' REQUEST FOR RELIEF G ".-

COMPONENT OR ITEM CODE PROGRAM CODE . EXAM .'

• CLASS TABLE - ITEM CATFGORY

. STEAM GENERATORS - PRIMARY INLET /0UTLET N0ZZLES I 3.1 B3.140 B-D- ,.

l MAIN STEAM & FEEDWATER N0ZZLES II 2.10 C2.22 C-B PRESSURIZER - RELIEF, SURGE, SPRAY & SAFETY N0ZZLES I 3.1 .B3.120 :B-D REGENERATIVE HEAT EXCHANGER N0ZZLES I 3.1 B3.160 B-D ACCUMULATOR N0ZZLES II 2.10 C2.22 C-B  :

CODE REQUIREMENT Volumetric (ultrasonic) examinations for the nozzle inner radius sections shall be conducted in-accordance.with Articles IWB-2500 and IWC-2500 for Code'. Class I and II, respectively. -

BASIS The code required volume will not be examined based .on the following criteria:

A. These nozzles do not experience high ' cyclic temperature gradients during normal operation, therefore the conditions for producing.a thermal fatigue mechanism are not applicable. ..

B. Presently, there is no comprehensive inspection technique available, nor guidance for such in the ASME Code, which would provide a conclusive assessment of the code required volumes of the inner radii, particularly since no pre' service results are available for comparison.

C. Upon consideration of the above factors, a best effort examination approach to these rozzle inner radius sections is not consistent with standard ALARA' practices. An estimated 8 to 10 man-REM expo-.

sure rate over the interval, per unit, (at the present radiations levels), would be experienced'in attempting to perform such-inconclusive examinations.

ALTERNATE The steam generator feedwater nozzles-(Table 2.10) and the pressurizer spray nozzle (Table 3.1) may be suscep-tible to a thermal fatigue mechanism due to the potential for high cyclic temperature gradients,-therefore an attempt will be made to' ultrasonically examine these inner radius areas. If service defects are detected by these examinations, the nozzles listed in the above table shall be assessed for similar examinations. Mean-while, if a more comprehensive technique 1.s developed and qualified, it will be implemented. a SCHEDULE FOR IMPLEMENTATION December 21, 1984 FI ISI/IST 2.5-41 2nd " 10-YR PROGRAM - REV:2 7/31/90

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