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{{#Wiki_filter:CATEGORY REGULAZ     INFORMATION DZSTRZBUTZO           YSTEM   (RIDE)
{{#Wiki_filter:CATEGORY REGULAZ INFORMATION DZSTRZBUTZO YSTEM (RIDE)
ACCFSSION NBR:9704160269          DOC.DATE:    97/04/09 NOTARIZED: NO                  DOCKET FATTI'5~-244 Robert Emmet        Ginna Nuclear Plant, Unit 1, Rochester              G  05000244 AU~TH'< NAME          AUTHOR  AFFILIATION MECREDY,R.C.          Rochester Gas    6 Electric      Corp.
RECIP.NAME            RECIPIENT AFFILIATION VISSING,G.


==SUBJECT:==
==SUBJECT:==
Submits relief request re class 1 ASME Section XI Category B-J to address cast stainless base metal ultrasonic weld exams.
Submits relief request re class 1
DISTRIBUTION CODE: A047D         COPIES RECEIVED:LTR         1 ENCL   i   SIZE:
ASME Section XI Category B-J to address cast stainless base metal ultrasonic weld exams.
TITLE:   OR Submittal: Inservice/Testing/Relief           from ASME Code GL-8       -04 T
DISTRIBUTION CODE:
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).                       05000244 E
A047D COPIES RECEIVED:LTR 1
RECIPIENT         COPlES                RECIPIENT           COPIES ID CODE/NAME         LTTR ENCL          ID CODE/NAME        LTTR ENCL PDl-1 LA                 1    1        PD1-1 PD                  1    1 VISSING,G.               1    1 INTERNAL: AEOD/SPD/RAB               1    1        FILE  CENTER    I      1    1 NRR/DE/EMEB             1     1       NUDOCS-A'BBTRACT         1    1 OGC/HDS3                1    0        RES/DET/EIB               1     1 RES/DET/EMMEB            1     1 EXTERNAL: LITCO ANDERSON              1     1       NOAC                      1     1 NRC PDR                  1     1 D
ENCL i
SIZE:
TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code GL-8 -04 T
05000244 E
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
ACCFSSION NBR:9704160269 DOC.DATE: 97/04/09 NOTARIZED: NO DOCKET FATTI'5~-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AU~TH'< NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSING,G.
RECIPIENT ID CODE/NAME PDl-1 LA VISSING,G.
INTERNAL: AEOD/SPD/RAB NRR/DE/EMEB OGC/HDS3 RES/DET/EMMEB EXTERNAL: LITCO ANDERSON NRC PDR COPlES LTTR ENCL 1
1 1
1 1
1 1
1 1
0 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD1-1 PD FILE CENTER I
NUDOCS-A'BBTRACT RES/DET/EIB NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 D
Oi U
Oi U
E NOTE TO ALL "RIDS" RECIPIENTS:
E NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY.,YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR               13   ENCL   12
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY.,YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 13 ENCL 12


C AND ROCHESTER GAS AND ELECTRIC CORPORATION ~ 89 FAST AVENLIE, ROCHESTER, N. Y Id&9-0001                   ARFA CODE 716 Sf6-2700 I
C
ROBERT C. MECREDY Vice President Nudear Operations                           April 9,       1997 U.S. Nuclear Regulatory Commission Document         Control Desk Attn:               Guy Vissing Project Directorate I-1 Washington, D.C.             20555
 
AND ROCHESTER GASANDELECTRIC CORPORATION ~ 89 FASTAVENLIE,ROCHESTER, N. Y Id&9-0001 I
ARFA CODE 716 Sf6-2700 ROBERT C. MECREDY Vice President Nudear Operations April 9, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy Vissing Project Directorate I-1 Washington, D.C.
20555


==Subject:==
==Subject:==
Relief   Request No. 17 Ginna Nuclear Power Plant Inservice Inspection ASME Section XI Required Examinations R.E. Ginna Nuclear Power Plant Docket No. 50-244
Relief Request No.
17 Ginna Nuclear Power Plant Inservice Inspection ASME Section XI Required Examinations R.E.
Ginna Nuclear Power Plant Docket No. 50-244


==Dear Mr.         Vissing:==
==Dear Mr. Vissing:==
 
The purpose of this letter is to seek approval of a relief request concerning Class 1,
The purpose of this letter is to seek approval of a relief request concerning Class 1, ASME Section XI Category B-J, to address Cast Stainless Base Metal Ultrasonic Weld Examinations. Justification and proposed alternatives are included in the attachments to this letter.           It is requested that June 16, 1997 in order to be this relief request be utilized for the upcoming approved by 1997 Outage at R.E. Ginna Nuclear Power                 Plant.
ASME Section XI Category B-J, to address Cast Stainless Base Metal Ultrasonic Weld Examinations.
This relief request deals with the employment of best effort ultrasonic examination techniques on welds associated with cast stainless components.               Due to the nature of cast stainless and associated welds, attenuation variables adversely impact the performance of ultrasonic examinations.                               The performance of other volumetric techniques, such as radiography, on associated cast components will provide little increased quantitative benefit due to the high levels of background radiation that exist for the items addressed.           Note that this relief request uses the same rationale as was used to conform with Code Case N-481 as part of the current ISI interval program. That code case was applied to RCP bowls made of cast stainless steel and was granted based on the inability of UT     measures     to be effective.
Justification and proposed alternatives are included in the attachments to this letter.
It is requested that this relief request be approved by June 16, 1997 in order to be utilized for the upcoming 1997 Outage at R.E. Ginna Nuclear Power Plant.
This relief request deals with the employment of best effort ultrasonic examination techniques on welds associated with cast stainless components.
Due to the nature of cast stainless and associated
: welds, attenuation variables adversely impact the performance of ultrasonic examinations.
The performance of other volumetric techniques, such as radiography, on associated cast components will provide little increased quantitative benefit due to the high levels of background radiation that exist for the items addressed.
Note that this relief request uses the same rationale as was used to conform with Code Case N-481 as part of the current ISI interval program.
That code case was applied to RCP bowls made of cast stainless steel and was granted based on the inability of UT measures to be effective.
Rochester Gas and Electric will continue to evaluate new emerging inspection technology as they become available for this industry problem of performing ultrasonic examinations on cast stainless components.
Rochester Gas and Electric will continue to evaluate new emerging inspection technology as they become available for this industry problem of performing ultrasonic examinations on cast stainless components.
Very       truly         yours, I
Very truly yours, j
Robert C. Mec -edy                                  @gal j    9704i6026'7,970409 PDR 8               s.
9704i6026'7,970409 PDR ADOCK,05000244 8
ADOCK,05000244 PDR
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                                                          'IIIIIII']glllllllllilllilllllll'Illillllllll
PDR Robert C.
Mec -edy
'IIIIIII']glllllllllilllilllllll'Illillllllll
@gal I


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>Attachment REJE448 xc:
Mr. Guy Vissing (Mail Stop 14B2)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector


>Attachment REJE448 xc:  Mr. Guy Vissing (Mail Stop 14B2)
l
Project Directorate I-1 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale  Road King of Prussia,  PA  19406 Ginna Senior Resident Inspector


l Relief Request   No. 17 Category B-J, Cast Stainless Base Metal Ultrasonic Examination I. Components for Which Relief is Requested:
Relief Request No.
: 1. Class 1, Category B-J, Reactor Coolant Cast Pump Terminal End to Cast Elbow Circumferential Welds and Associated Longitudinal   Seam Welds.
17 Category B-J, Cast Stainless Base Metal Ultrasonic Examination I.
Weld ID                     ~Te PL-FW-XIII                   Elbow-to-Pump PL-FW-XII-LR   (XIII)       Longitudinal PL-FW-XV                     Elbow-to-Pump PL-FW-XI-LR (XV)             Longitudinal
Components for Which Relief is Requested:
: 2. Class 1, Category B-J, Reactor Coolant Inlet/Outlet Cast Elbow to Nozzle Safe End/Pipe Circumferential Welds.
1.
Weld ID                     ~Te PL-FW-I-ASW                 Elbow-to-Safe End PL-FW-IX-ASW                 Safe End-to-Elbow PL-FW-III                    Elbow-to-Safe End PL-FW-X                     Safe End-to-Elbow PL-FW-IX                    Elbow-to-Pipe PL-FW-X-BSW                  Elbow-to-Pipe II. ,ASME Requirements   for Which Relief is Requested:
Class 1, Category B-J, Reactor Coolant Cast Pump Terminal End to Cast Elbow Circumferential Welds and Associated Longitudinal Seam Welds.
Category     B-J within Table IWB-2500-1,         specifies volumetric examination requirements that are to be performed on Terminal Ends, Longitudinal welds, as well as other welds associated with required Circumferential Welds.
Weld ID
: 2. Code Case N-460 specifies   that a reduction in examination coverage on any Class 1   or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than   10%.
~Te PL-FW-XIII PL-FW-XII-LR (XIII)
PL-FW-XV PL-FW-XI-LR (XV)
Elbow-to-Pump Longitudinal Elbow-to-Pump Longitudinal 2.
Class 1, Category B-J, Reactor Coolant Inlet/Outlet Cast Elbow to Nozzle Safe End/Pipe Circumferential Welds.
Weld ID
~Te PL-FW-I-ASW PL-FW-IX-ASW PL-FW-III PL-FW-X PL-FW-IX PL-FW-X-BSW Elbow-to-Safe End Safe End-to-Elbow Elbow-to-Safe End Safe End-to-Elbow Elbow-to-Pipe Elbow-to-Pipe II.
,ASME Requirements for Which Relief is Requested:
Category B-J within Table IWB-2500-1, specifies volumetric examination requirements that are to be performed on Terminal Ends, Longitudinal welds, as well as other welds associated with required Circumferential Welds.
2.
Code Case N-460 specifies that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%.
III. Basis:
III. Basis:
Supplement scanning 4 (b)(4) of Appendix     III identifies ultrasonic requirements on Austenitic and Dissimilar Metal Welds. This paragraph further identifies that Cast items such as fittings, valve bodies, and pump casings may preclude meaningful examinations because of geometry and attenuation variables.
Supplement 4
At R.E. Ginna Nuclear Power Plant, the Reactor Coolant Pump, Westinghouse Model 93, is cast stainless (A-351 Gr CF8M). The associated fittings (elbows) are also cast stainless (ASTM A-
(b)(4) of Appendix III identifies ultrasonic scanning requirements on Austenitic and Dissimilar Metal Welds.
This paragraph further identifies that Cast items such as fittings, valve
: bodies, and pump casings may preclude meaningful examinations because of geometry and attenuation variables.
At R.E. Ginna Nuclear Power Plant, the Reactor Coolant
: Pump, Westinghouse Model 93, is cast stainless (A-351 Gr CF8M).
The associated fittings (elbows) are also cast stainless (ASTM A-


  ~ .'51   Gr CF8M) and contain longitudinal seam welds. The Reactor Inlet/Outlet   Wrought Safe     End/Pipe to Elbow Coolant circumferential welds consists of fittings (elbows) that are cast stainless (ASTM A-351 Gr CF8M). When employing optimized ultrasonic techniques on these cast/wrought welds, the techniques may detect large flaws (254 or greater through wall) 'ut   are relatively ineffective in detecting smaller flaws. Therefore, the sensitivity is less than that required by the code.
~.'51 Gr CF8M) and contain longitudinal seam welds.
Cast Stainless base metal and associated welds contain large grain structures, attenuation variables impact on performance of ultrasonic examinations. Experience has shown that these materials are not always amenable to ultrasonic examination and does not produce reliable and meaningful results.
The Reactor Coolant Inlet/Outlet Wrought Safe End/Pipe to
Currently, the industry s Performance Demonstration Initiative (PDI)   is not addressing Cast Stainless Ultrasonic Examinations.
" Elbow circumferential welds consists of fittings (elbows) that are cast stainless (ASTM A-351 Gr CF8M).
Due   to the highly attenuative characteristics of the austenitic grain structure, ultrasonic examination coverage to the extent that is specified within Code Case N-460 may not always be achievable.
When employing optimized ultrasonic techniques on these cast/wrought
Radiography   is an impractical technique to use and, alternative volumetric examinations are not if applied,  the expected to provide any meaningful increase in benefit beyond the alternative presented due to the high levels of background radiation emitting from these areas.
: welds, the techniques may detect large flaws (254 or greater through wall) 'ut are relatively ineffective in detecting smaller flaws.
IV. Proposed Alternate Method:
Therefore, the sensitivity is less than that required by the code.
None. Applicable code-required volumetric examination will be completed   to the maximum extent practical (a best effort ultrasonic examination of the cast stainless welds based on state-of-the-art techniques and associated             achievable examination coverage).       Ultrasonic examinations shall be performed from the wrought side of applicable components. We will continue to evaluate new emergingcode inspection technology as they become available.         The         required surface examinations and system leakage tests     will be performed.
Cast Stainless base metal and associated welds contain large grain structures, attenuation variables impact on performance of ultrasonic examinations.
Experience has shown that these materials are not always amenable to ultrasonic examination and does not produce reliable and meaningful results.
Currently, the industry s Performance Demonstration Initiative (PDI) is not addressing Cast Stainless Ultrasonic Examinations.
Due to the highly attenuative characteristics of the austenitic grain structure, ultrasonic examination coverage to the extent that is specified within Code Case N-460 may not always be achievable.
Radiography is an impractical technique to use and, if
: applied, the alternative volumetric examinations are not expected to provide any meaningful increase in benefit beyond the alternative presented due to the high levels of background radiation emitting from these areas.
IV.
Proposed Alternate Method:
None.
Applicable code-required volumetric examination willbe completed to the maximum extent practical (a
best effort ultrasonic examination of the cast stainless welds based on state-of-the-art techniques and associated achievable examination coverage).
Ultrasonic examinations shall be performed from the wrought side of applicable components.
We will continue to evaluate new emerging inspection technology as they become available.
The code required surface examinations and system leakage tests will be performed.


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Latest revision as of 09:48, 8 January 2025

Submits Relief Request Re Class 1 ASME Section XI Category B-J to Address Cast Stainless Base Metal Ultrasonic Weld Exams
ML17264A857
Person / Time
Site: Ginna 
Issue date: 04/09/1997
From: Mecredy R
ROCHESTER GAS & ELECTRIC CORP.
To: Vissing G
NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9704160269
Download: ML17264A857 (9)


Text

CATEGORY REGULAZ INFORMATION DZSTRZBUTZO YSTEM (RIDE)

SUBJECT:

Submits relief request re class 1

ASME Section XI Category B-J to address cast stainless base metal ultrasonic weld exams.

DISTRIBUTION CODE:

A047D COPIES RECEIVED:LTR 1

ENCL i

SIZE:

TITLE: OR Submittal: Inservice/Testing/Relief from ASME Code GL-8 -04 T

05000244 E

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

ACCFSSION NBR:9704160269 DOC.DATE: 97/04/09 NOTARIZED: NO DOCKET FATTI'5~-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AU~TH'< NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION VISSING,G.

RECIPIENT ID CODE/NAME PDl-1 LA VISSING,G.

INTERNAL: AEOD/SPD/RAB NRR/DE/EMEB OGC/HDS3 RES/DET/EMMEB EXTERNAL: LITCO ANDERSON NRC PDR COPlES LTTR ENCL 1

1 1

1 1

1 1

1 1

0 1

1 1

1 1

1 RECIPIENT ID CODE/NAME PD1-1 PD FILE CENTER I

NUDOCS-A'BBTRACT RES/DET/EIB NOAC COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 D

Oi U

E NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY.,YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)

ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:

LTTR 13 ENCL 12

C

AND ROCHESTER GASANDELECTRIC CORPORATION ~ 89 FASTAVENLIE,ROCHESTER, N. Y Id&9-0001 I

ARFA CODE 716 Sf6-2700 ROBERT C. MECREDY Vice President Nudear Operations April 9, 1997 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Guy Vissing Project Directorate I-1 Washington, D.C.

20555

Subject:

Relief Request No.

17 Ginna Nuclear Power Plant Inservice Inspection ASME Section XI Required Examinations R.E.

Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Vissing:

The purpose of this letter is to seek approval of a relief request concerning Class 1,

ASME Section XI Category B-J, to address Cast Stainless Base Metal Ultrasonic Weld Examinations.

Justification and proposed alternatives are included in the attachments to this letter.

It is requested that this relief request be approved by June 16, 1997 in order to be utilized for the upcoming 1997 Outage at R.E. Ginna Nuclear Power Plant.

This relief request deals with the employment of best effort ultrasonic examination techniques on welds associated with cast stainless components.

Due to the nature of cast stainless and associated

welds, attenuation variables adversely impact the performance of ultrasonic examinations.

The performance of other volumetric techniques, such as radiography, on associated cast components will provide little increased quantitative benefit due to the high levels of background radiation that exist for the items addressed.

Note that this relief request uses the same rationale as was used to conform with Code Case N-481 as part of the current ISI interval program.

That code case was applied to RCP bowls made of cast stainless steel and was granted based on the inability of UT measures to be effective.

Rochester Gas and Electric will continue to evaluate new emerging inspection technology as they become available for this industry problem of performing ultrasonic examinations on cast stainless components.

Very truly yours, j

9704i6026'7,970409 PDR ADOCK,05000244 8

s. -

PDR Robert C.

Mec -edy

'IIIIIII']glllllllllilllilllllll'Illillllllll

@gal I

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Pi~ 'V

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I I

>Attachment REJE448 xc:

Mr. Guy Vissing (Mail Stop 14B2)

Project Directorate I-1 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector

l

Relief Request No.

17 Category B-J, Cast Stainless Base Metal Ultrasonic Examination I.

Components for Which Relief is Requested:

1.

Class 1, Category B-J, Reactor Coolant Cast Pump Terminal End to Cast Elbow Circumferential Welds and Associated Longitudinal Seam Welds.

Weld ID

~Te PL-FW-XIII PL-FW-XII-LR (XIII)

PL-FW-XV PL-FW-XI-LR (XV)

Elbow-to-Pump Longitudinal Elbow-to-Pump Longitudinal 2.

Class 1, Category B-J, Reactor Coolant Inlet/Outlet Cast Elbow to Nozzle Safe End/Pipe Circumferential Welds.

Weld ID

~Te PL-FW-I-ASW PL-FW-IX-ASW PL-FW-III PL-FW-X PL-FW-IX PL-FW-X-BSW Elbow-to-Safe End Safe End-to-Elbow Elbow-to-Safe End Safe End-to-Elbow Elbow-to-Pipe Elbow-to-Pipe II.

,ASME Requirements for Which Relief is Requested:

Category B-J within Table IWB-2500-1, specifies volumetric examination requirements that are to be performed on Terminal Ends, Longitudinal welds, as well as other welds associated with required Circumferential Welds.

2.

Code Case N-460 specifies that a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted provided the reduction in coverage for that weld is less than 10%.

III. Basis:

Supplement 4

(b)(4) of Appendix III identifies ultrasonic scanning requirements on Austenitic and Dissimilar Metal Welds.

This paragraph further identifies that Cast items such as fittings, valve

bodies, and pump casings may preclude meaningful examinations because of geometry and attenuation variables.

At R.E. Ginna Nuclear Power Plant, the Reactor Coolant

Pump, Westinghouse Model 93, is cast stainless (A-351 Gr CF8M).

The associated fittings (elbows) are also cast stainless (ASTM A-

~.'51 Gr CF8M) and contain longitudinal seam welds.

The Reactor Coolant Inlet/Outlet Wrought Safe End/Pipe to

" Elbow circumferential welds consists of fittings (elbows) that are cast stainless (ASTM A-351 Gr CF8M).

When employing optimized ultrasonic techniques on these cast/wrought

welds, the techniques may detect large flaws (254 or greater through wall) 'ut are relatively ineffective in detecting smaller flaws.

Therefore, the sensitivity is less than that required by the code.

Cast Stainless base metal and associated welds contain large grain structures, attenuation variables impact on performance of ultrasonic examinations.

Experience has shown that these materials are not always amenable to ultrasonic examination and does not produce reliable and meaningful results.

Currently, the industry s Performance Demonstration Initiative (PDI) is not addressing Cast Stainless Ultrasonic Examinations.

Due to the highly attenuative characteristics of the austenitic grain structure, ultrasonic examination coverage to the extent that is specified within Code Case N-460 may not always be achievable.

Radiography is an impractical technique to use and, if

applied, the alternative volumetric examinations are not expected to provide any meaningful increase in benefit beyond the alternative presented due to the high levels of background radiation emitting from these areas.

IV.

Proposed Alternate Method:

None.

Applicable code-required volumetric examination willbe completed to the maximum extent practical (a

best effort ultrasonic examination of the cast stainless welds based on state-of-the-art techniques and associated achievable examination coverage).

Ultrasonic examinations shall be performed from the wrought side of applicable components.

We will continue to evaluate new emerging inspection technology as they become available.

The code required surface examinations and system leakage tests will be performed.

0 I

v 11