L-98-126, Forwards Response to 980416 RAI Re Plant Third ten-yr ISI Plan & Associated Relief Requests,Submitted on 970917
| ML20249C341 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/18/1998 |
| From: | Jain S DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-98-126, NUDOCS 9806290084 | |
| Download: ML20249C341 (41) | |
Text
fI ei Beave Vaney Power Station l Shippingport. PA 15077-0004 s
- SUSHIL C. JAIN (412) 393-5512 r., <7243 e43.sosa
,S,*2',) ,*,Prf ,ce. '"' L-98-126 Nuclear Power Dwision U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Response to Request for Additional Information Regarding Review of the Third 10-Year Interval Inservice Inspection (ISI) Program Plan and Associated Relief Requests (TAC No M99673)
This submittal forwards the Duquesne Light Company response to the NRC request for additional information (RAI) dated April 16,1998, regarding the Beaver Valley Unit No.1 (BV-1) Third Ten-Year ISI Plan. The RAI resulted from the NRC review of the September 17, 1997 submittal of the BV-1 Third Ten-Year Interval ISI Plan and associated relief requests.
The enclosure provides the restatement of the NRC questions (RAI Items A through J), followed by a response to each.
If you have any questions regarding this submittal, please contact Mr. S. Hobbs at (412)393-5203.
Sincerely, Sushil C. Jain \ ,
}
c: Mr. D. S. Brinkman, Sr. Project Manager 3 Mr. D. M. Kern, Sr. Resident Inspector ho\
Mr. H. J. Miller, NRC Region I Administrator J Mr. M. T. Anderson, INEEL Research Center DELIVERING l
Q U A L I T V, 98062900s4 M 99061s .
p ADOCK O 4 gggggy
1a ,s ENCLOSURE
, Response to NRC Request for Additional Information Third 10-Year Interval Inservice Insnection Pronram Plan and Associated Relief Reauests Question A:
1 The licensee's Program submittal includes an implementation schedule for performance of examinations as required by IWA-2420(b). To determine compliance with Tables IWB- )
2412-1, IWC-2412-1, and IWD-2412-1, it is necessary to know the total number of )
components eligible for examination as well as the total number of components to be j examined. Provide an examination summary that includes each examination category, the total number of components in each category, and the total number of examinations to be performed in periods 1,2 and 3 for each category.
f Response A: )
See attachment titled, " Beaver Valley Power Station Unit 1 ASME XI Percentage Reconciliation," dated 12/17/97.
Question B:
Provide a list of all ultrasonic calibration blocks to be used during the third 10-year interval, including identifications, material specifications, and sizes. Also, provide a list of all procedures that will be used in the implementation of the ISI Program Plan, including the procedure identification (e.g., number), title and a general description of the components to which it applies.
Response B:
See attachment titled, " Response B." Included are calibration blocks and NDE procedures.
Question C:
IWB-1220, IWC-1220, and IWD-1220 of ASME Section XI provide rules for exemption from examination of certain Class 1,2 and 3 components. Appendix F gives nonmandatory guidance for inspection plan development. F-2500(b) states that inspection plans should include the specific exemptions applied to each system covered by Section XI. To complete the review of the Beaver Valley Power Station, Unit 1, Program Plan, provide the specific exemption criteria applied to each exempt system. j Response C:
See attachment titled, " Response C." This attachment includes a matrix identifying the exemptions ofIWB-1220, IWC-1220, and IWD-1220 that have been applied to systems covered by Section XI.
' Enclosure Response to NRC Request for Additional Information Third 10-Year Interval Inservice Inspection Program Plan and Associated ReliefRequests Page 2 .,
Question D:
Augmented examinations have been established by the NRC when added assurance of structural reliability is deemed necessary. Examples of documents that address augmented examinations are:
(1) Branch Technical Position MEB 3-1, High Energy Fluid Systems, Protection 1 Against Postulated Piping Failures in Fluid Systems Outside Containment; (2) Regulatory Guide 1.150, Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations.
. Address the degree of compliance with these documents and any other augmented examinations that may have been incorporated in the third 10-year Interval ISI Program Plan.
Response D:
The following augmented examinations, in excess of ASME XI requirements, are included in the BV-1 Ten-Year Plan (ITYPP-3) for ease of administration:
a High Energy Line Break Inspection Program, based on UFSAR Appendix D.3.2; the Ten-Year Plan includes the examinations specified in this Section of the UFSAR for postulated high energy line break points. !
I a Regulatory Guide 1.150, Ultrasonic Testing of Reactor Vessel Welds During l Preservice and Inservice Examinations; DLC will ensure compliance with this RG at i the time of the reactor vessel examination. The impact ofimpending rulemaking activities and ongoing Code changes shall be included in the evaluation for compliance to this RG.
m Reactor Coolant Pump Flywheel Examinations; these examinations are based on the NRC letter from B. W. Sheron to S. C. Jain dated September 12,1996.
The Program Description Section of the Plan shall be revised to include this information.
i !
,. ,s Enclosure Response to NRC Request for AdditionalInformation Third 10-Year Interval Inservice Inspection Program Plan and Associated Relief Requests Page 3 ,
. Question E: l Provide the staffwith the status of the augmented reactor pressure vessel examinations required by 10 CFR 50.55a(gX6XiiXA), effective September 8,1992, 3 and a technical discussion describing how the regulation was/will be implemented at Beaver Valley Power Statian Unit 1. Include in the discussion a description of the approach and any specialized techniques or equipment that was/will be used to complete the required augmented examination. Also, provide the percent of the volume examined for each weld. It is required by 10 CFR 50.55a(gX6XiiXAX2) that essentially 100% of the volume of each weld be examined. Confirm that " essentially 100%" of each Examination Category Bl.10 weld (RPV shell welds) has been examined, or that an alternative has been submitted for staffreview.
' Note: Plants with greater than 40 months remaining in the interval on the effective date of the rule were required to perform the augmented examination in that interval.
Response E:
The BV-1 augmented reactor pressure vessel examinations, required by 10 CFR 50.55a(gX6XiiXA), were completed in IR11 (1996). AllItem Bl.10 welds of Examination Category B-A " Pressure Retaining Welds in Reactor Vessel," were examined as required by the 1989 Edition of ASME XI. Essentially 100% of the required volume was examined on all but one of the welds. The lower head circumferential weld (RC-R C-8) was limited due to four radial support keyways. The keyways are welded to the !
inside surface of the reactor vessel, just above RC-R-1-C-8. Eighty-five percent (85%) of the required volume was examined. This limitation was originally submitted to the NRC i on March 25,1997, in the form of a relief request. Subsequent to the NRC Request for Addition Information, dated July 23,1997, an Alternative Request (BVI-RV-AUG-1, Rev. 0) was submitted on November 24,1997. Revision 1 to the Alternative Request was necessary following a telephone conference between NRC and DLC on March 11,1998.
Revision 1 was submitted to the NRC on May 12,1998 (L-98-098).
Question F:
l In Request for Relief No.1-TYP-3-APP-I-1, revision 0, the licensee seeks relief from Appendix I, Paragraph I-2300, which requires ultrasonic inspection of bolts and studs to
, be conducted in accordance with Appendix VI.
The licensee states in their Alternative Qualification that "DLC personnel will be qualified using the PDI Performance Demonstration Initiative Program and DLC written !
practice QSP2.11 which meets the requirements of Section XI, Appendix VII (1989 Edition)." This request for reliefis specifically written for the Class 1 (Category B-G-1) and Class 2 (Category C-D) bolts and studs. Is it the utent of DLC to use the PDI
Enclosure Response to NRC Request for Additional Information Third 10-Year Interval Inservice Inspection Program Plan and Associated ReliefRequests Page 4 ,
qualification of the UT personnel for all UT applications or for bolting only?
Considering that implementation of Appendix VIII is imminent, describe DLC's plans regarding the implementation of Appendix VIII.
Response F:
Since September 1997, DLC has used only PDI qualified UT personnel (both in-house and contractors) for UT examinations ofitems governed by existing PDI procedures.
This includes the following components:
- 1. Class 1 and 2 Austenitic piping (except CCSS and Dissimilar Metal Welds)
- 2. Class 2 ferritic piping
- 3. Class 1 and Class 2 bolting (>2")
DLC intends to continue using PDI qualified UT personnel for these applications at BV-1.
Refer to Request for ReliefNo.1-TYP-3-UT-1, Revision 0 for the current DLC position on the scope of Appendix VIII implementation. This position may be revised in response to published proposed rulemaking.
Question G:
In Request for Relief No.1-TYP-3-C6.10-1, Revision 0, the licensee seeks relief from performing the surface examinations on the Recirculating Spray Pump Casing Welds RS-P-2A(2B)-C-10 through 27 and the Safety Injection (SI) Pump Casing Welds SI-P-1 A(1B)-C-1 through 20 as required by ASME XI, Item C6.10.
The licensee states that "All of the welds listed above are located below floor level in the pump sump and are therefore inaccessible. See attached drawings." It appears from the drawings submitted that Welds C-18, C-19 and C-20 on the SI pump (s), and Weld C-10 on the Recirculation pump (s) may be above floor level. However, it also appears from the drawing that other obstacles may limit the accessibility of these welds. Provide additional information concerning the accessibility of these welds.
The licensee also states that " Access to these welds requires removal of the pump casings from the sump. This evolution risks damage to the pump, in order to examine components that have a proven reliability record throughout the industry." Are these pump casings designed to be removed for normal maintenance, repair, and inspections?
Also, provide additional information concerning the risk of damage to the pump that could occur if the pump is removed.
Enclosure Response to NRC Request for AdditionalInformation l Third 10-Year Interval Inservice Inspection Program Plan and Associated Relief Requests Page 5 ,
Response G:
The four welds noted above are not located below floor level. However, these welds are inaccessible due to other obstacles, i.e., the outer pump casing extension. Request for ReliefNo.1-TYP-3-C6.10-1 shall be revised to reflect the appropriate limitation.
The pumps were designed to require no preventive maintenance. If repairs to the pumps are required, pump dismantling and re-installation instmetions are available. These instructions are quite involved, with repeated cautions to prevent bearing damage, alignment problems, tie rod thread damage, impeller and casing ring damage. Shes there has been no evidence of a generic industry problem with the casing welds on those types of pumps, the effort to gain access to these welds for the sole purpose of the required surface examinations is considered a hardship or unusual difficulty without a compensating increase in the level of quality and safety.
- i. Questien H:
In Request for Relief 7 Alternate Examination No.1-TYP-3-UT-1, Revision 0, the licensee has proposed, as an alternative to the 1989 Edition of ASME XI, to use ultrasonic l examination procedures meeting the requirements of the PDI Program Description, Revision 1, for volumetric UT examination of austenitic piping welds, ferritic piping welds, and bolting.
Identify the specific requirements of the 1989 Edition of ASME XI that will not be met if ultrasonic examination procedures meeting the requirements of the PDI Program Description, Revision 1, are used.
Response H:
The following requirements of the 1989 edition of ASME XI will not be met as published:
Paragraph IWA-2232 states " Ultrasonic Examinations shall be conducted in accordance with Appendix I."
Appendix 1, Paragraph I-2200 refers to Appendix HI, as supplemented by l
Appendix I for Vessel Welds Less than or equal to 2 inches thickness and all piping welds. Paragraph I-2300 refers to Appendix VI for ultrasonic exanunation j l of bolts and studs. I Relief Request No.1-TYP-3-APP-I-1, Revision 0 and Request for Alternative ,
Examination No.1-TYP-3-UT-1, Revision 0, both describe the scope and details of the !
proposed alternatives. Paragraph IWA-2240 provides requirements for alternative examination methods. The proposed alternative examinations have been demonstrated to be equivalent or superior to those specified in the 1989 Edition of ASME Section XI.
ao .<
l Enclosure Response to NRC Request for Additional Information Third 10-Year IntervalInservice Inspection Program Plan and Associated ReliefRequests Page 6 .
Both of the above referenced documents propose the use of Appendix VIII as implemented by PDI to govern Performance Demonstration of UT Examination Systems on the specific components listed within the documents. There are no Appendix VIII requirements in the 1989 Edition of the Code. The PDI Program Description (Revision 1, Change 1, dated 12/30/96) provides a paragraph by paragraph comparison of Appendix VIII and the PDI Implementation of those requirements.
Since both proposed alternatives comply with Paragraph IWA-2240 criteria, there are no specific requirements of the 1989 Code that will not be met. The alternatives proposed (Appendix VIII as implemented by PDI) are superior to the ultrasonic techniques delineated in Appendix I of the 1989 Code.
Question I:
Request for Relief / Alternative Examination No.1-TYP-3-N-521, Revision 0, proposes an alternative schedule for reactor pressure vessel nozzle examinations. Code Case N-521, Alternative Rules for Deferral ofInspections of Nozzle-to-Vessel Welds, Inside Radius Sections, and Nozzle-to-Safe End Welds of a Pressurized Water Reactor Vessel, states that examination of RPV nozzles, IR sections, and nozzle-to-safe end welds may be deferred provided a) no inservice repairs or replacements by welding have ever been performed on any of the subject areas b) none of the subject areas contain identified flaws or relevant conditions that currently require successive inspections in accordance with IWB-2420(b), and c) the unit is not in the first interval. An additional requirement imposed by the NRC is that all subject areas be scheduled for examination such that the new sequence of examinations will not exceed 10 years between examinations. Confirm that all of the above conditions will be met.
Response I:
l Regarding the BV-1 Reactor Vessel Nozzle-to-Vessel Welds, Inside Radius Sections, and Nozzle-to-Safe End Welds, it is confirmed that: a) no inservice repairs or replacements l by welding have ever been performed on any of the subject areas, b) none of the subject areas contain identified flaws or relevant conditions that currently require successive inspections in accordance with IWB-2420(b), and c) the unit is not in the first interval.
Further, all of the noted welds were examined during the final 40-month period of the l Second Ten-Year Interval (lR11,1996), and are scheduled for t.xamination in the final !
i 40-month period of the third ten-year interval (i.e., May 2004 to September 2007). Note 1
that half of the examinations performed on these welds in the third period of the second interval were in excess of the ASME XI requirements, but were performed in preparation l
for implementation of Code Case N-521.
l l
Enclosure Response to NRC Request for Additional Information Third 10-Year Interval Inservice Inspection Program Plan and Associated Relief Requests Page 7 .
I Question J:
Verify that there are no requests for reliefin addition to those submitted. If additional requests for relief are required, the licensee should submit them for staff review.
Response J:
Currently, there are no further relief requests, beyond those submitted with the Ten-Year Plan (ITYPP-3). All Relief and Alternative Requests prepared to date for the Third Ten-Year Interval were provided with the Plan. In addition to these requests, the Program Description Section of the Plan provided a listing of approved Code Cases to be used, along with the bases for the Plan and descriptions and clarifications to assist in implementation of the Plan. As examination coverage limitations are identified during the interval, or Code requirements are identified as impractical to meet, additional requests shall be submitted in accordance with 10 CFR 50.55a.
I i
( . . ..
l I
PAGE NO. 1
. .v e i 12/17/97 BEAVER VALLEY POWER STATION UNIT 1
. ASME XI PERCENTAGE RECONCILIATION l
! EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE
. ass.. ....... .. ........... .. ....... .......... ,,,,,,,,,, ,,,,,,,,,, ,,,,,,,,, ,,,,,,,,, ,,,,,,,,,
- CATEGORY: BA B01.011 3 3 0 0 3 3 0 100.00 0.00 B01.012 4 4 0 0 4 4 0 100.00 0.00
, 801.021 3 1 0 0 1 1 0 33.33 0.00 B01.022 10 10 0 0 10 10 0 100.00 0.00 B01.030 1 2 1 0 1 2 0 pulaq 200.00 0.00 B01.040 1 1 1 0 0 1 0 4 100.00 0.00
- Subtotal **
22 21 2 0 19 21 0 0.00 A Assssh a gaf 4
e t___________
7 d.s a 9
.s -s .
-PAGE NO.' 2
'12/17/97 BEAVER VALLEY POWER STATION UNIT 1
- ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED j f EM - NUMBER OF SCHEDULED 1ST PERIOD 2WD PERIOD 3RD PER100 EXAMS IN EXAMS SCHEDULED %
NUMSER . CANDIDATES IN INTERVAL.
EXAMS, EXAMS EXAMS INTERVAL TO DATE % TO DATE
_ seasse sseessness sessenessas assissssse seassensse sesessness esssssssas sessnes== sessnesas massssses
- CATEGORY: B-8 802.011 2 2' 0 1' 1 2 0 100.00 0.00
. 'B02.012 2~ -2 0 1 1 2 0 100.00 0.00 302.040 3 1 1- 0 0 1 0 33.33 'O.00
- Subtotet **
7 5 1 2 2 5 0 0.00 46'4 4Eu 20'4 1
Lo% 4
\004 ,
6 i
l a l f
_ _ _ _ _ _ _ _ _ _ - _ . - _ . - . _ _ _ - - - . _ . - - - - . . - . - - _ _ - - - - - - - _ - - . - - - - - - - - - - _ - _ _ - - - - - - ~ - - - -
- a. .e-PAGE NO. M 12/16/97
. BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETE 0' NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS- SCHEDULED %
ITEM NUMSER CANDIDATES IN INTERVAL EXAMS' EXAMS EXAMS INTERVAL TO DATE % TO DATE eusses seassesses sessasssses sessassses assessasse asssessssa ===ssesssa sessssses ==ssesses essensses
! - ** CATEGORY: 3D 803.090' 6 6 0 0 6 6 0 100.00 0.00
- '803.100 6' 6
- . 0 0 6 6 0 100.00 0.00
- Subtotal **
- 12. 12 0 0 12 12 0 0.00 M N # 3'2.l. - fem d g ,, . d e
_e s .e:
9
. v- -so .
PAGE No. 3B _
12/18/97
. ' BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED l
~lTEM NUMBER OF SCHEDULED iST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL 10 DATE % TO DATE
..ssses sessassses sensassness asess..... ==senessse sessssessa sess...... seasss=== maassenes . ssessa.
- CATEGORY: BD 803.120 6 6 3 0 3 6 0 100.00 0.00 303.140 .6' -6 2 2 2 6 0 100.00 0.00
- Subtotal **
12 12 5 2 5 12 0 0.00 4t*/o t1 . 42?/,
I 4
. %'6 L
. \co'/,
O V "' M k WTL 6.) : 25% b, <d4Pr ed - kt nc, A., so'4 , N Yaw.sks 6 3 % .o ~.L h sn V,v J i
l l
I-8 I-1 l-4+ m-eW ,
PAGE NO. 4
.12/17/97
- SEAVER VALLEY POWER STATION UNIT 1 l- ASME XI PERCENTAGE RECONCILIATION L-EXAMS - REMAIN!'aC COMPLETED EXAMS ' COMPLETED ITEM NUMBER of SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED' %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE assses sesssssses sessassassa esssam m ans ========== ssssssssse ========== s=====ssa ========= seassass -
1
- ** CATEGORT: BE B04.012 2- 2 0- 0 2 2 0 100.00 0.00
.804.013 . 1 -1 0 0 1 1 0 100.00 0.00 804.020- 1 1 0 0 1 1 0 100.00 0.00
- Bubtotal **
4 4 0- 0 4 4 0 0.00 Jvm s */b 4
9
)
I ' ' e 4_ . _ e 's 1
l PAGE No.1 5h I '12/18/97.
r
. BEAVER VALLEY POWER STAfl0N UNIT 1 j ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM :. NUMBER OF ' SCHEDULED IST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED ;%'
I NUMBER ' CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE l
- CATEGORY: 5-F 805.010 6 6 0 0 6 6 0 100.00 0.00
' ** Subtotat **'-
'6 6 0 0 6 6 0 0.00
- h b M,61) 4 f*d vi l
l l
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- l I'
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f PACE NO. $6 12/18/97
. BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED l- ITEM NUMBER of SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS- EXAMS INTERVAL TO DATE % TO DATE ses... seasssa... . ......... .......... ses. .... .......... os...s ss. ......... .s essses asemassa.
- e CATEGORY: B F-l B05.040 6 6 0 1 5 6 0 100.00 0.00
. B05.070 6 6 ~2 4 0 6 0 100.00 0.00
- Subtotal **'
12 12 -2 5 5 12 0 0.00 4
IY4 @t*4 1
M
- w. s too%
- _ - _ _ - . - _ - - . - - _ _ _ _ . - _ _ - . . _ - - - - ~ - - .l
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PAGE NO. 6 12/17/97
- BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION' REMAINING COMPLETE 0 EXAMS COMPLETED EXAMS EXAMS SCHEDULED %
IIEM NUMBER OF SCHEDULED 1ST PERIOD 2ND PERICu 3RD PERIOD EXAMS IN EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE NUMBER CANDIDATES IN INTERVAL sessssssus essessneses saussssses sensassses sesssssssa essssssses assessses seasssses assasssas messse
- CATE00RY 0G1 1 3 0 100.00 0.00
'306.010' 3 3 1 1 3 1 3 0 100.00 0.00
+ B06.030 3- 1 1 3 0 0 3 3 0 100.00 0.00 B06.040 3 3 1 1 3 0 100.00 0.00 006.050 3 1 0 0 1 1 0 33.33 0.00 806.180 3 1 0 0 1' 1 0 33.33 0.00 806.190 3 1 0 0 1 1 0 16.67 0.00 806.210 6 1 0 0 1 1 0 16.67 0.00 804.220 6 1 0 0 1 1 0 16.67 0.00 806.230' 6 1
- Subtotet **
17 3 3 11 17 0 0.00 36 J J %. 4tcogh wW Q&L t$
O t
~
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--**" ' PAGE NO. 7 12/17/97.
SEAVER VALLEY POWER STATION UNIT 1
. ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER'0F' SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED 7, NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE s..... . . . . . s : .. s e s s a s a s s e s . . ... . . . . . == = .. ... . . .. ... ... = = s s e s s m a s . ....... assassses ........e
- CATEGORY: BG2 807.020 1 .1 0 1 0 1 0 100.00- 0.00 B07.030 .6 2 0 0 2 2 0 33.33 0.00 B07.050 9 9 4 3 2 9 .0 100.00 0.00 B07.060 3 1 1 0 0 1 0 33.33 0.00 B07.070- 28 6 1 1 4 6 0 21.43 0.00 807.080 4 4 0 4 0 4 0 100.00 0.00
- Subtotat **
51 23 6 9 8 23 0 0.00 2(pk MI6 #
I
. (86 ,
h
. PAGE NO. 8-l' 12/17/97'
. BEAVER VALLEY POWER STATION UNIT 1 l- ASME XI PERCENTAGE RECONCILIATION 1
EXAMS REMAINING COMPLETED EXAMS CCMPLETED-NUMBER OF -SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN - EXAMS SCHEDULED %-
ITEM ~
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL- To DATE % TO DATE e..... .......... ........... .......... .......... .......... .......... ......... ......... .........
- CATEGORY: B J-309.011 413 106 34 33 39 106 0 25.67 0.00 809.012 12 6 '2- '4 -0 6 -0 50.00 0.00 809.021 - 91 24 7- 8 9 24 0 26.3T 0.00 809.031 13 - 5 2 1 2 5 0 38.46 0.00 809.032 35 9. 3 3 3 9 0 25.71 0.00 309.040 581- 147 47 50 50 147 0 25.30 0.00
- Subtotet **
1145 297 95 99 '103 297 0 0.00 MU Yo No a
bYO o to0f ,
)
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PAGE No. 9~
-12/17/97
... BEAVER VALLEY POWER STAi!ON UNIT 1
,. ASME XI PERCENTArt RECONCILI ATION EXAMS- REMAINING COMPLETED EXAMS COMPLETED ITEM- NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PER100 EXAMS IN EXAMS SCHEDULED r.
NUMBER' CANDIDATES IN INTERVAL EXAMS EXAMS ., EXAMS INTERVAL TO DATE % TO DATE senses - sesessness essessneses seassessas seassesses esssssenes sessenesse essasssas assssssas seassass.
- CATEGORY: BK1
~
810.010 5 1 -0 1- 0 1 0 20.00 0.00
, B10.020 130 14 3 5 6 14 0 10.77 0.00 510.030 9 1- 1 0 0 1 0 11.11 0.00
- Subtotal **
144 16- 4 6 6 16 0 0.00 1 2W, 3@. $
(,3% <
\d t
l l
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o . . . ,
PACE NO. 10 12,'17/97 BEAVCR VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER OF SCHEDULED IST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE sesssa essssssses asssssssese aussnessas assassasse assass==ss assssssssa seassss== ssssssas assasses.
" CATEGORY: 8L1 812.010 3 1 1 0 0 1 0 33.33 0.00
- Subtotat **
3 1 1 0 0 1 0 0.00 J4 k' Y) tera O
o ..a a e .
PAGE NO. 11.
12/17/97
. SEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER OF SCHEDULED iST PERIOD 2ND PERIOD 3RD PERIDD EXAMS IN EXAMS SCHEDULED %
. NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE assess. sessassssa assassssssa ====sssssa assssssess ==sesasssa assassassa assassssa ========= ==sassses
- CATEGORY: BL2' B12.020 3 0 0 0 0 0 0 0.00**""*""""*"
- ** Subtotal "
0 0 0 0 0 """""""""
3 0 l
Js m. ,(d . 66% (' ') o^ti wb4
- v. c :. s i, ~,umaa ,
1 t
l I
1' l-1 L
l
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J w- w PAGE NO, 12
. 12/17/97 ' '
BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATE!DN EXAMS REMAINING COMPLETED EXAMS COMPLETED
' ITEM NUMBER OF SCHEDULED 1ST FERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUM8ER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE asetas essassesse =========== ====sasssa sessnesses assasssmas ===ssessas ses==sess assesses. sesssues.
- CATEGORY: BM2 B12.050 35 0 0 0 0 0 0 0.00*"""********"*
.** subtotat **
0 " * " " " " " * " *
- 35 0 0 0 0 0 T,,-
qsJ. .
w <<go as H wm vans va 6.sm,s .sM d.
9 5
e A
w - - - - . - - _ - - _ - _ - _ _ . - . . . - - - _ - - - _ . - . . . _ . - - - _ - _ . _
e . . ,
.s ~-.e l PACE NO. 13 12/17/97 BEAVER VALLEY POWER STATICN UNIT 1 ASME XI PERCENTACE RECONCIL!ATION EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER OF SCHEDULED iST PERICO 2ND PERICO 3RD PERIOD EXAMS IN EXAMS SCHEDULED %'
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE sasssa sesssssssa sesssssams ========== sassassssa assessassa =======ssa sasssssss ========= sassssssa
- CATECORY: B N-1 B13.010 1 3 1 1 1 3 0 300.00 0.00
- Subtotat **
1 3 1 1 1 3 0 0.00 M 33 53 4 1 (4 s too l
l L--______
's . ..
.a, . ro .
PAGE No. 14 12/17/97
' BEAVER VALLEY POWER STATION UNIT 1
' ASME XI PERCENTAGE RECONCILIATION l' EXAMS REMAINING COMPLETED EXAMS .COMPLETEC i ITEM NUMBER OF- SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAM 3 SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE i.
l: '** CATEGORY: BN2' B13.060- I' 1 0 0 1 1 0 100.00- 0.00
- Subtotat **
1 1 0' O 1 1 0 0.00 l .r e w vid
- j. * . , ._, 2 1 s
, ,. aer PAGE NO. 15 12/17/97 BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION EXAMS l ~
REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER OF ' SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
l- . NUMBER _ CANDIDATES IN INTERVAL EXAMS EXAMS' EXAMS INTERVAL TO DATE X TO DATE i
I
- CATEGORT: BN3 B13.070 2 2 0 0 2 2 0 100.00 0.00
- -** Subtotat **
2 0 0 2 2 0 0.00 1
%.g.,JL l i H
1 i
- 3. . j I
i l
l ',
- e . e n
.s- ~w .
PAGE NO. 16 I
12/17/97 ~
BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION
~ EXAMS- REMAINING COMPLETED EXAMS COMPLETED ITEM-.
NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN- EXAMS SCHEDULED %.
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE .% TO DATE sasssa , assessssas asassessans assassassa ========== ========== smes===ssa san ====== ========= sasasssas
- CATEGORY: B0 814.010 3 3 0 0 3 3 0 100.00 0.00
- Subtotet **
-3 3 0 0 3 3 0 0.00
.t , m . */
e l.
t l
- e *,
PAGE No. 17 .e 12/17/97 ~
BEAVER VALLEY POWER STAil0N UNIT 1
. ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED s ITEM NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD- EXAMS IN EXAMS SCHEDULED %
NUMBER 0.*?OIDAfES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE
...... .......... ........... .......... .......... .......... .......... ......... ......... ......... i
- CATEGORY CA C01.010 13 5 1 2 2 5 0 38.46 0.00 C01.020 9 5 2 2 1 5 0 55.56 0.00
, C01.030 3 1 1 0 0 1 0 33.33 0.00
- Subtotat **
25 11 4 4 3 11 0 0.00 R
Yi Yo klg 1
1 v/T l w/,
l .
1 4 bAa.h k d6 466 6 of V f ssa.\ f 4 A u s per M - 40 8-2. , il h d.M.' cud
% m.ac., , bow waq ua suc<ssi .<% $., .;,_, ,g l avid oph M u en%s, i.e., p.ccAudi <<-od of ms wb.b.% M a.
% <.cb.c , c.ppl3 for w el pw p osect tod4 G.sa , kcA mc m s,es
- /o coepb4 m Gho. LA4 v.c ,,.omsd3 , cwc.4. L % Q ,
l-l Th Coh ct.u. 'is nd issua/ pp,ma % m pr 7,,g g fu,
% %*>k LO M k $ 0 0 J40 = ' h 6 4 4M s *1.sh % 44s .
aSq r
l ,-
1 l
l l.
', a I'*e' l
! . , , - wr, .
l i PAGE NO. 18 ,
12/17/97 '
BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION EXAMS ..
REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %^
l NUMSER CANDIDATES .!N INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE %- TO DATE I- sesass asesssassa sesassssssa sess.... . sessassses sessnesass semes==ssa masassans . s sess. u========
i ** CATEGORY: CB C02.021. 12 - 6 1 3 2 6 0 50.00 0.00 f
- C02.022' 6 2 0- 1 1 2 0 33.33 0.00
' C02.033 '4 6 2 2 2 6 0 150.00 0.00
- Subtotal **
22 .14 3 6 5 14 0 0.00 7
- 2. t */, 4 Ya Na q ,
No v f
lod, 9
[
- _s s b
l .-,,- .-,
PAGE No. 19f 12/17/97:
- l BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION
- j. EXAMS REMAINING COMPLETED EXAMS COMPLETED l ! TEM . NUMBER OF SCHEDULED 1ST PERIOD 2ND PER100 3RD PERIOD. EXAMS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL . EXAMS ' EXAMS EXAMS INTERVAL TO DATE X TO DATE emessa ss.... ssa seassenes== ==== .... ...s..... sass ..... .......... sessasses assmesess seassssas l
- CATEGORY: C*C -
C03.010 20- 4 2 1 1 4 0 20.00 0.00 C03.020 168 17 4 6 7 17 0 10.12 0.00 C03.030 18- 2 0 1 1 2 0 11.11 0.00
- Subtotal "
206 23 6 8 9 23 0 0.00 r
)
unr.
i (CCI6 1
1 1
i l
I l'
1 l
i l
7
-e , , -. . l w* eo .
! PAGE No. 20 12/17/97 '
-BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION EXAMS- REMAINING COMPLETED EXAMS COMPLETED ITEM NUMSER OF SCHEDULED 1ST PER!co 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE
- CATEGORY: CD C04.010= 16. 16 5 5 6 16 0 100.00 0.00
. ** subtotal ?*
16 ' 16 5 5 6 16 0 0.00 31*lo Yo bTly L
Lt% p.
t00/0 l
v
- - _______m.______m_m _m. -__ . _ _ _ - _ . - _ _ , _ _ _ _ _ _ _ _ . _ ._ ___,_____m .__..w -
_ _ _ = _ _ _ _ _ _ _ = _ _ _ _
- e, **a PACE NO. 21 12/17/97
, SEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION
-EXAMS REMA!NING COMPLETED EXAMS COMPLETED
- ITEM NUM8ER OF SCHEDULED 1ST PERIOD 2ND PERIDO 3RD PERICO EXAMS IN EXAMS SCHEDULED %
NUMBER. CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE X TO DATE assess sessassess mesesssemos assansssas assasssses assassssas === sesssa assassssa asesssssa massasssa
- CATEGORY: C-F-1 C05.011 1012 ' 78 17 46 15 78 0 7.71 0.00 C05.012 466. 52 12 21 19 52 0
- 11.16 0.00 C05.021 545 41 10 8- 23 41 0- 7.52 0.00
-C05.030 494 39 13 13 39 0 7.89 0.00 C05.041 18 2 'O 0 2 2 0 11.11 0.00
- Subtotat **
2535 212 52 88 72 212 0 0.00 A$g $Yo Yb
( -I uk ,
100'/,
l t
l:
l
_______--__.-_____-_L:-__ _ _ _ _ _ _ _ _ - _ - - - .
- e 4, .n o ,
PAGE No. 22 12/17/97
. .* BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION
- 1. .
EXAMS- REMAIN!NG COMPLETED EXAMS COMPLETED' ITEM NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
' NUMBER CANDIDATES IN INTERVAL EXANS EXAMS EXAMS INTERVAL TO DATE % TO CATE
.esesse asessosass masassasssa as ss sssssa ======ss== ========== sasssssses ========= ========= ==seasses
- CATEGORY: CF2 C05.051 128 25 7 9 9 25 0 19.53 0.00 C05.052 19 8 2 4' 2 8 0 42.11 0.00 C05.081- 21 -6 1 2 3 6 0 28.57 0.00
- Subtotal "
'168' 39 to 15 14 39 0 0.00 Ylo Yo 0
-o O
e F
9
_ _ . - _ - _ . _ .-_____---_----a
e , e.: ,
PAGE No. 23 12/17/97
- BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS ITEM COMPLETED NUMBER CF SCHEDULED 1ST PERIOD 2ND PER!ao 3RD PERIOD EXAMS IN EXAMS SCHEDULED NUMBER CANDIDATES IN INTERVAL EXAMS %
EXAMS EXAMS INTERVAL TO DATE asssas % TO DATE esassesses sessassenes assamassas messameses assssenssa ausssssssa sessanssa ausssames massasses ,
- CATEGORY: C-G C06.010 ' 20 8 2 }
2 4 8 0
- Subtotal " 40.00 0.00
)
20 8 2 2 4 8 0 0.00 169, . 2$
- O l
w.
\c4
?
a
.o g , .se ,
)
PAGE NO. 24 12/17/97
- BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED l ITEM- . NUMBER OF . SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN- ' EXAMS SCHEDULED %
NUM8ER- CAN010ATES IN INTERVAL EXAMS' EXAMS EXAMS INTERVAL TO DATE % To DATE
...... .......u.. _'
i I
- CATEGORY: 0A '
001.010 31 19 6 8 5 19 0 61.29 0.00 001.020 227 25 7 7 11 25 0 11.01 0.00
- Subtotet **
)
258 44 13 15 16 44 0 0.00 Ylo YO U L L ,
O l ImL
. _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _a
wo PAGE NO. }j 12/17/97 BEAVER VALLEY POWER STATION UNIT 1 ASME XI PERCENTACh RECONCILIATION EXAMS REMAINING COMPLETED EXAMS' COMPLETED ITEM NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUhBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO CATE %
s===== ==sess=============================================ss================= 70 DATE
========= ========. 1
- CATEGORT: FA F01.10A 32 11 4 2 5 0 11 34.38 0.00 F01.100. 17 5 2 2 1 .5 0 29.41 0.00
.F01.10H 1 1 0 1 0 1 0 100.00 0.00
.F01.10L- .18 5 1 4 0 5 0 27.78 0.00 F01.10R' 205 54 15 22 17 54 0 26.34 0.00 F01.105 46 12 4 5 3 12 0 26.09 0.00 F01.10V 7 4 0 0- 4 4 0 57.14 0.00 701.20A , 51 - 9 2 4 3 9 0 17.65 0.00 F01.200 13 2 .0 1 1 2 0 15.38 0.00
'F01.20N 13 3 0 1 2 3 0 23.08 0.00
- F01.204 466 71' 23 18 - 30 71 0 15.24 0.00 701.20$ 81 14 6 5 3 14 0 17.28 0.00 F01.207 2 1 0 1 0 0 50.00 1 0.00 F01.20V 30 6 3 1 2 6 0 20.00 0.00 F01.30A 53 ;7 3 3 7 0 1 13.21 0.00
- F01.30H 34 7 2 1 4 7 0 20.59 0.00 F01.30L 3 1- 0 0 0 33.33 1 1 0.00
/F01.30R '496 50 16 22 12 50 0 10.08 0.00 101.30$ '41 7 1 2- 4 7 0 17.07 0.00 F01.30T 6 2 0 1 2 0 33.33 1 0.00 F01.30V 60- 7 1 2 4 7 0 11.67 0.00 F01.40E 143 84 18 16 50 84 0 58.74 0.00
- Subtotal "
1818 363 101 114 148- 363 0 0.00
$h/g Y0 59% o tod/,
l
- l
[' _ _ ..__ _ _ .- __ ___ -_-. _ _ _ ---_-_- _ ---_ _ - - . . _
l RESPONSE B -
Page 1 or 4-"
The following list of calibration blocks are scheduled for use during the third 10-year interval.
Additional blocks may be used if augmented or modified techniques are desired or mandated during the interval.
Piping Blocks identification Material Diameter / "T" (in.) Application Schedule PP-22 A376, TP 316SS 02/160 0.343 SIS PP-21 SA376, TP 316SS 03/160 0.438 SIS BV1-19 SA376, TP316SS 04/120 0.437 , PZR SPRAY LINE BV1 18 A376, TP316SS 06/160 0.766 SIS /PZR SPRAY NOZZLE / BIT TANK NOZZLE ;
BV1-17 A376,TP316 08/140 0.830 RCS LOOP BY-PASS '
PP-6 SA376, TP316 08/160 0.910 PZR SAFETY NOZZLES BV152A A376, GR304SS 10/40 0.365 RHR/QS PP-5 SA376, TP316SS 10/160 1.125 RHR BV1-51 A312/304HSS 12/40 0.419 RHR/ SIS BV1-15 A376, TP316 12/160 1.260 SIS BV1-50A A358, GR304 14/40 0.438 RHR BV1-14 SA312, TP304H 14/160 1.424 RHR/PZR SURGE & NOZZLE BV1-60 SA106, GR.B 16/80 0.844 FEEDWATER BV1-59 A155, CLASS 1 32/SPL 1.220 MAIN STEAM PP-2 SA351, GR CF8A 24/SPL 2.500 RCS LOOP PIPING BV 12-2.91-SS SA182,F316SS 18.06 2.910 RCS BRANCH CONNECTIONS C001-SS A182, F316SS 6.812 1.594 RCS BRANCH CONNECTIONS C002-SS A182, F316SS 9.188 1.990 RCS BRANCH CONNECTIONS Vessel Blocks l Identificati.on Material Diameter / "T" fin.) Application !
Schedule BV-BIT-2.12- SA516, GR 70 (CMD) N/A 2.12 bit NOZZLE-TO-HEAD WELDS CLAD-CS BV-IR 1 A508, CLASS 2 N/A VARIOUS STEAM GEN MS AND FW NOZZLE INNER RADIUS i BV-lR-2 SA216, GR WCC N/A VARIOUS PZR NOZZLE INNER RADIUS (CLAD)
BV1-55 A508, CMSS 2 N/A 3 STEAM GENERATOR l
BV124 SA508, CLASS 2 N/A 6 STEAM GENERATOR (CHANNEL (CLAD) HEAD)
th .* ,
RESPONSE B '
1 "'Page 2 of 4 I BV128 .
SA533, CLASS 2 N/A 4 PRESSURIZER l (CLAD)
BV1-29 A508, CLASS 2 N/A 15.25 & RV FLANGE iO SHELL (CLAD) 41.5 BV1-23 A508, CLASS 2 N/A 7 RV CLOSURE HEAD &
(CLAD INTERMEDIATE SHELL BV1-27 A508 CLASS 2 N/A 11 & 42 RV FLANGE & LIGAMENTS (CLAD) l DLW-HJE-001 SA533, GRADE B N/A 9 RV SHELL AND LOWER HEAD (CLAD)
RV-6 SA508, CLASS 2 N/A 18 & 36 RV FLANGE & NOZZLE TO (CLAD) SHELL Bolting Blocks identification Material Diameter / Size Application Schedule l
BS-1 SA-540, GR. B24 6* DIA. 55.75" RV STUDS LONG BS-3 SAS40, GR. B24 4.FDLA N/A RCP FLANGE BOLTS BV167 SA540, GR B23 2.875" DIA 18' LONG LOOP ISOLATION VALVE STUDS l
BV168 SAS40, GR B24 4.5 30.5" RCP FLANGE LONG The following NDE procedures are planned for use during the third 10-year interval.
Additional (or revised) procedures may be used if augmented or modified techniques are desired or mandated during the interval.
Number Rev Title Application GP-101 11 Requirements for Data Recording General procedure for recording ISI data GP-104 9 Establishment of Reference Points Provides instructions to install ISI for Data Recording' datum and reference points.
GP-105 6 Evaluation of PSI /ISI Flaw Indications Provides sequence and protocol instructions for evaluation of NDE indications LP-101 15 Solvent Removable Visible Dye provides requirements and acceptance criteria for Class 1,2 and 3 PT (surface) examinations LP-102 9 High Temperature Removable Dye Provides requirements and l
acceptance criteria for Class 1,2 l and 3 high temperature (125'-
l 350*) PT (surface) examinations f 1
- - _--_ A
j
- c, * * -
I f "'
RESPONSE B Page 3 of 4 I
l Number ,
Rev Title -
Application MT-201 13 Magnetic Particle Examination Provides requirements and i acceptance criteria for Class 1,2 l
and 3 MT (surface) examinations.
UT-301 9 Linearity for Ultrasonic Instruments Self-explanatory UT-304 8 Manual Ultrasonic Examination of Self-explanatory RCP Flywheel UT-305 8 Manual Examination of Studs and Applicable only to items less than 2" Bolting Less than 2 inches Diametcr in diameter (High Gain Technique)
UT-306 9 Manual Ultrasonic Examination of (Class 1and 2) Self-explanatory Vessel Welds Greater than 2" Thickness UT-308 11 Component Weld Profiling and Self-explanatory I Thickness Measurements Using j Straight Beam Ultrasonic Techniques l
UT-309 4 Ultrasonic Examination of RV Closure Secondary procedure to allow I Head Studs from Central Bore augmented examination from ;
nozzle bore (if required) !
UT-312 0 UT Through-Wall Flaw Depth Sizing UT TW Flaw sizing procedure in Piping Welds based on PDI Procedure PDI-UT-3, i l
Revision B UT-313 4 Manual Ultrasonic Examination of (Class 1and 2) Self-explanatory Vessel Nozzle inner Radius Sections ,
UT-315 1 Ultrasonic Thickness Measurements Used for MIC and FAC Using the ABB/AMDATA intraspect examinations 1/UX21 Ultrasonic imaging System UT-317 1 Manual Straight Beam Ultrasonic (Class 1and 2) Primary UT bolting Examination of Bolting procedure based on PDI-UT-5, Revision A UT-318 1 Ultrasonic Examination of " Set-ON" (Class 1 RCS) Self-explanatory Austenitic Branch Connection Welds UT-320 1 Ultrasonic Examination of Ferritic (Class 1and 2) Ferritic piping exams Piping Welds - based en PDI-UT-1, Rev. A UT-321 1 Ultrasonic Examination of Austenitic (Class 1and 2) Austenitic piping Piping Welds exams - based on PDI-UT-2, Rev. A UT-322 1 Ultrasonic Examination of Dissimilar (Class 1and 2) Self-explanatory -
Metal Welds IWA-2240 procedure UT-323 0 Ultrasonic Examination of Welds (Class 1) RCS Loop piping - IWA-
} Joining Cast Austenitic Piping 2240 procedure l Components
. a c_ws
-" RESPONSE B ,
Page 4 of 4 g ' Number
, Rev Tigg _ .
Application UT-324 O Ultrasonic Examination of Unit 1 RV (Class 1) Self-explanatory Shell-to-Flange Weld from the Flange Surface VT-500 8 General Requirements for Visual Self-explanatory l' Examination VT-501 5 Visual Examination of Threaded (Class 1,2 and 3) Self-explanatory ~
I Fasteners (VT-1)
VT-502 5 Leakage Examination Requirements (Class 1,2 and 3) Self-explanatory (VT-2)
VT-503 - 19- Visual Examination for Component (Class 1,2 and 3) Self-explanatory Supports (VT-3) j VT-504 6 Visual Examination Requirements for (Class 1,2 and 3) Self-explanatory intomal Surfaces of Pumps, Valves and Reactor Vessel Interior /iniemals VT-507 7 Visual Examination of Rubber Self-explanatory Expansion Joints VT-509 ' 5 Visual Examination of Welds and (Class 1,2 and 3) Self-explanatory Components VT-510 - 6 Visual Examination for Boric Acid (Class 1,2 and 3) Self-explanatory VT-511 - 2 Altemative Pressure Test (Class 1,2 and 3) VT requirements Requirements for Welded Repairs or for Code Case N-416-1 Installation of Replacement items by examinations Welding RT-600 - 4 General Requirements for Self-explanatory Radiographic Examination RT-601 4 Radiographic Examinations RT technique and acceptance Govemed by ANSI B31.1.0-1967 with criteria for" code year of record" Addenda Through June,1971- examinations.
RT-603 - 4 Radiographic Examinations RT techniques when RT is used to j Govemed by the 1989 Edition of meet the volumetric examination ASME Section XI. requirements of ASME XI,1989 Edition.
RT-604 1_ Radiographic Examination of Piping RT techniques and acceptance -
Circumferential Butt Welds Govemed criteria when Code Case N-416-1 is by ASME Section Ill,1992 Edition applied for the repair / replacement activity.-
I J
_ _1 _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ . . . . _ _ _ . _ . _ _ _ _ _
e a <a o RESPONSE C Page 1 of 2
.e .e System n
e e_,an se u u n n e 3- E a e a n u n n e 3 s a B a e u
l Baron Recovery
- X
, Chemical and Volume Control X X X Containment Vacuum
- X Demineralized Water- X Feedwater X Leakage Monitoring *- X
! Main Steam X
, Quench Spray X X X Reactor Coolant System X X l Reactor Vents and Drains X X Recirculation Spray X X X Residual Heat Remova! X X River Water X Safety injection X X X X X X Sample
- X X Steam Generator Blowdown
- X X
- Entire system is exempt from specified examination requirements
(
IWB-1220, the following components (or parts of components) are exempted from the volumetric and surface examination requirements of IWB-2500:
(a) components that are connected to the reactor coolant system and part of the reactor coolant pressure bour.dary, and that are of such a size and shape so that upon postulated rupture the resulting flow of coolant from the reactor coolant system under normal plant operating conditions is within the capacity of makeup systems which are operable from on-site emergency power, (b)(1) piping of NPS 1 and smaller, except for steam generator tubing; (2) components and their connections in piping of NPS 1 and smaller; (c) reactor vessel head connections and associated piping, NPS 2 and smaller, made inaccessible by control rod drive penetrations.
(WC-1220, the following components (or parts of components) are exempted from the volumetric and surface examination requirements of IWC-2500.
IWC 1221 Components Within RHR, ECC, and CHR Systems (or Portions of Systems) l (a) Vessels, piping, pumps, valves and other components NPS 4 and smaller in all systems except high pressure safety injection systems of pressurized water reactor plants.
(b) Vessels, piping, pumps, valves, and other components NPS 1% and smaller in high pressure safety injection systems of pressurized water reactor plants. .
(c) Component connections NPS 4 and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size in all systems except high pressure safety injection systems of pressurized water reactor plants.
(d) Component connections NPS 1% and smaller (including nozzles, socket fittings, and other j
- connections) in vessels, piping, pumps, valves, and other components of any size in high pressure safety l injection systems of pressurized water reactor plants.
(e) Vessels, piping, pumps, valves, other components, and component connections of any size in statically pressurized, passive (i.e., no pumps) safety injection systems of pressurized water reactor plants.
(f) Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions.
l
[ '#**a RESPONSEC Pags 2 of 2 IWC-1222 Components Within Systems (or Portions of Systems) Other Than RHR, ECC, and i
CHR Systems (a) Vessels, piping, pumps, valves and other components NPS 4 and smaller.
(b) Component connections NPS 4 and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size.
(c) Vessels, piping, pumps, valves, other components, and component connections of any size in systems or portion of systems that operate (when the system function is required) at a pressure equal to
- or less than 275 psig and at temperature equal to or less than 200F.
( (d) Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions. -
lWD-1220 ITEMS EXEMPT FROM EXAMINATION IWD-1220.1 Integral attachments of supports and restraints to components that are NPS 4 and smaller within the system boundaries of Examination Categories D-A, D-B, and D-C of Table IWD-2500-1 shall be i exempt from the visual examination VT-3, except for PWR Auxiliary Feedwater Systems.
l IWD-1220.2 Integral attachments of supports and restraints to components exceeding NPS 4 may be exempted from the visual examination VT-3 of Table IWD-2500-1 provided:
l (a) the components are located in systems (or portions of systems) whose function is not required in l support of reactor residual heat removal, containment heat removal, and emergency core cooling; and
! (b) the components operate at a pressure of 275 psig or less and at a temperature of 200F or less.
b
_ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _