L-98-163, Forwards Response to 980601 RAI Re Beaver Valley Unit 2 Second 10-yr ISI Program Plan & Associated Relief Requests
| ML20236W736 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/29/1998 |
| From: | Jain S DETROIT EDISON CO., DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20236W737 | List: |
| References | |
| L-98-163, TAC-MA0333, TAC-MA333, NUDOCS 9808060176 | |
| Download: ML20236W736 (41) | |
Text
/
Beaver Valley Pows- Station Shippingport, PA 15077 0004 l-SUSHIL C. JAIN (412) 393-5517 Se r Vice President L-98-163 Fax (724) 643 8069 l Nue: ear Power Division L U. S. Nuclear Regulatory Commission l
Attention: DocumentControlDesk Washington, DC 20555-0001 i
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Response to Request for Additional Information Regarding Review of the Second 10-Year Interval Inservice Inspection (ISI) Program Plan and Associated Relief Requests (TAC No. MA0333)
This submittal forwards the Duquesne Light Company response to the NRC request for additional information (RAI) dated June 1,1998, regarding the Beavel Valley Unit No. 2 (BV-2) Second Ten-Year ISI Plan. The RAI resulted from the NRC review of the December 9,1997 submittal of the BV-2 Second Ten-Year Interval ISI Plan and associated reliefrequests.
The enclosure provid:s the restatement of the NRC questions (RAI Items 1 through 9, J and K), fellowed by a response to each.
If you have any questions regarding this submittal, please contact Mr. S. Hobbs at (412) 393-5203.
Sincerely, 1
I
,A -n b & l Sushil C. Jain i I
c: Mr. D. S. Brinkman, Sr. Project Manager ,
Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, NRC Region I Administrator 3- l Mr. M. T. Anderson, INEEL Research Center 9808060176 980729 PDR DEllVERING e ADOCK 03000412 PDR q Q U A LIT Y E II E R G V
i L
ENCLOSURE Response to NRC 2equest for AdditionalInformation Second 10-Year IntervalInservice Insnection Program Plan aud Associated Relief Reauegg l
Question 1:
Tue licensee's 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 naessary to know the total number of components eligible for examination as well as the total number of components to be examined. Provide an examination summary that includes each Examination Category, the total number of components in each category, ar.d the total number of examinations to be performed in periods 1,2 and 3 for each Examination Category.
Response 1:
See attachment titled, " Beaver Valley Power Station Unit 2 ASM3 XI Percentage Reconciliation," dated 12/17/97.
Question 2:
In accordance with 10 CFR 50.55a(c)(3),10 CFP. 50.55a(d)(2), and 10 CFR 50.55a(e)(2), ASME Code cases may be used as.darnatives to Code requirements. Code cases that the NRC has approved for use are listeo in Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, with any additional conditions that the NRC may have imposed. When used, these Code cases must be implemented in their entirety. The licensee may adopt an approved Code case by notifying the NRC in writing. Published Code cases awaiting approval and subsequent listing in Regulatory Guide 1.147 may be adopted only if the licensee requests, and the NRC authorizes, their use on a case-by-case basis. The licensee has provided a list of Code cases that will be used during the Unit 2 second 10-year interval. Two of the Code cases listed, N-416-1, and N-498-1, refereuce NRC approval letters dated 12/7/94 and 1/12/95, respectively. These Code cases were approved for use during the Unit I second 10-year interval and the Unit 2 first 10-year interval. When inservice inspection programs are updated and sabmitted for a new interval, requests for relief that were approved for previous intervals, including requests for use of Code case not approved in Regulatory Guide 1.147, must be resubmitted for evaluation. Provide an appropriate request for relief to use Code Cases N-416-1 and N-498-1 for the Unit 2 second 10-year interval.
Response 2:
The noted NRC approval letters stated that each of these Code cases were " authorized j until such time as the Code Case is published in a future revision of Regulatory Guide (RG) 1.147." Based on these words, Duquesr.c Light Company (DLC) regar ded this )
authorization as the same as if the Code cases were listed in RG 1.147, and therefore, only reference to the use of these Code cases was included in the updated ten-year plan. It is DLC's understanding that no subsequent re-submittals of the original requests are required.
. Enclosure Response to NRC Request for Additional Information
' Second 10-Year Inteival Innervice Inspection Program Plan and Associated Relief Requests Page 2 Question 3:
Provide a list of all ultrasonic calibration blocks to be used during the second 10-year interval; including calibration block identi6 cation, material specifications, and sizes. Also, provide a list of all ultrasonic examination procedures that will be used in the j 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.
l Response 3: -
l See attachment titled, " Response 3." Included are calibration blocks and NDE procedures.
l
- Question 4:
IWB-1220, IWC-1220, and IWD 1220 of ASME Section XI provide rules for exemption ofcertain Class I,2 and 3 components from examination. Appendix F gives nonmandatory guidance for insoection 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 2, Program
- Plan, provide the specific exemption criteria applied to each system exempted from l volumetric and surface examination.
Response 4:
See attachment tiiled, " Response 4." 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.
Question 5:
Augmented examinations have been established by the NRC when added assurance of structural reliability is deemed necessary. Examples of documents that address augmented examins,tions are:
I (1) Branch Technical Position MEB 3-1, High Energy Fiuid Systems, Protection Against Postulated Piping Failures in Fluid Systems Outside Containment; (2) Regulatory Guide 1.150, Ultrasonic Testing ofReactor 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 second 10-year ' ISI Program Plan.
p Enclosure l Response to NRC Request for Additional Information Second 10-Year Interval Inservice Inspection Program Plan and Associated Relief Requests Page 3 Response 5:
The following augmented examinations, in excess of ASME XI requirements, are included in the BV-2 Ten-Year Plan (2TYPP-2) for ease of administration:
m High Energy Line Break Inspection Program, based on UFSAR Section 6.6; the Ten-Year Plan includes the examinations specified in this Section of the UFSAR for postulated high energy line break points.
m Regulatory Guide 1.150, Ultrasonic Testing ofReactor Vessel Welds During Preservice and Inservice Examinations; DLC will ensure compliance with this RG at the time of the RV examination. The impact ofir sending rulemaking activities and ongoing Code changes shall be included in the evaluation for compliance to this RG.
l m Reactor Coolant Pump Flywheel Examir.ations; these examinations are based on the f
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.
Question 6:
Request for ReliefNo. 2-TYP-2-B3.110-1, Revision 0. The licensee seeks relief from the requirements of Table IWB-2500-1, Category B-D, Item No. B3.110 for Welds 2RCS* PRE 21-N-10, -11, -12, -13, and -14. Table 1 in the relief request provides examination coverage percentages for these welds. Do the examination percentages listed in Table 1 represent the actual first 10-year interval examination coverages for these welds? It appears that reliefwas not requested for these exanunations during the first interval. Discuss the status of the first interval examinations and clarify the coverage estimates.
Response 6:
The examination percentages listed in Table 1 of the reliefrequest are the actual first 10-
, year interval examination coverages. The limitations for welds 2RCS* PRE 21-N-10, -11,
-12, -13, and -14 were previously identified during the first 10-year interval in Relief Request BV-2-B3.110-2, Rev 0. This request was transmitted to the NRC by DLC letter dated March 25,1997. The NRC approval was provided in the SER dated October 8, 1997.
The confusion over this issue may be due, in part, to the consolidation of all the Pressurizer nozzle welds onto one relief request. During the first 10-yeai interval, one request (BV2-B3.110-1) was submitted early in the interval for the surge nozzle weld and a subsequent request (BV2-B3.110-2) was submitted for the remaining five nozzle welds.
This was necessary since the examinations were scheduled at different times during the L interval. The second 10-year interval relief request (2-TYP-2-B3.Il0-1) includes all six
! of the Pressurizer nozzle welds and provides the examination coverage percentages obtained during the first 10-year interval.
l l
Enclosure Response to NRC Request for Additional Information Second 10-Year Interval Inservice Inspection Program Plan and Associated ReliefRequests Page 4 4 Question 7:
Request for ReliefNo. 2-TYP-2-APP-I-1, revision 0. The licensee seeks relief from l Appendix I, Paragraph I-2300, which requires that ultrasonic inspection of bolts and studs be conducted in accordance with Appendix VI.
The licensee states in " Alternative Qualification" that "DLC personnel will be qualified l 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) bolts and studs. However, it should be noted that implementation of Appendix VIII is imminent for ultrasonic examination systems. Is it the intent of DLC to use the PDI qualification for all UT applications or for bolting only? Discuss DLC's plans regarding the implementation of Appendix VIII.
l Response 7:
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-2.
l Refer to Request for ReliefNo. 2-TYP-2-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 8:
Request for Relief No. 2-TYP-2-C6.10-1, Revision 0. The licensee seeks relief from performing the surface examinations on the Recirculating Spray Pump Casing Welds as equired by ASME XI, Item C6.10.
The licensee states that " Access to these welds requires disassembly of the pump casing for those welds located in the floor sleeve; disassembly and removal from the sump for the lower casing section; removal of welded gasset plates for welds 9,10,17 and 18.
This evolution risks damage to the pump, in order to examine plant components that have a proven reliability record throughout the industry." Are these pump casings designed to be removed for normal maintenance, repair, and inspections? Provide additional information concerning the risk of damage to the pump if the casing is removed.
Enclosure Response to NRC Request for Additional Information Second 10-Year Interval Inservice Inspection Program Plan and Associated Relief Requests Page 5 It appears from the weld numbers pre C ied and the referenced drawing that the licensee is seeking relief for only a portion of r.e welds. The licensee states in the " Alternative Examination" portion of the request for relief that a complete examination is performed j on eleven other casing welds. Provide the " Weld Number" and "Examinable Amount" for the other eleven casing welds. {
{
Using the referenced drawing,10080-ISI-E-2M, it is diflicult to locate Welds 2RSS*P21 A-C-21 and C-24 (circumferential welds). However, Welds 2RSS*P21 A-L 'I and L-24 (longitudinal welds) are identified. To evaluate this request for relief, it is necessary to obtain the correct identity for the subject welds. Verify that all welds requiring relief are identified.
Response 8:
The pumps were designed to require no preventive maintenance. If repairs to the pumps are required, pump dismantling and re-installation instructions are available. These instructions are quite involved, and include special cautions for handling the pressure chamber assembly and fabrication of special tools to preclude diaphragm and piston damage. The potential exists during disassembly and re-assembly for foreign materials entry into the pump suction well causing damage during subsequent pump operation.
Multiple lifts (raising and lowering the same portion of pump) are required for pump disassembly, which increases the potential risk of bumping and springing of shafts.
Special care must be taken to support the shafts to preclude bowing and to insure straightness of shafts. Proper clearances between pump components during reassembly are critical to avoid alignment problems and potential pump damage. Due to cleaning l
requirements of the disassembled parts, flammable solvents are used which create a l restricted and potentially dangerous work environment. Due to headroom limitations, ceiling plugs in the Safeguards Building must be removed to allow disassembly of the i I
pump, causing security, radiation control, and cleanliness complications. The three seismic supports for the pump require removal along with girders above the pump which support intermediate levels within the Safeguards Building. Crane access to this area of the Safeguards area is difficult and necessitates special loading requirements due to the extended angle of the lifl. Since there has been no evidence of generic industry problems with welds on these types of pumps, the effort to gain access to these welds and the increased potential for damage incurred, for the sole purpose of performing the surface ,
examinations is considered a hardship and unusual difliculty without a compensating l increase in the level of quality and safety.
As requested in Question 8, the following is a listing of the other eleven casing weld numbers. The examination coverage percentage for each of these welds was essentially 100% Note: Weld N-20 is located below the floor level, but the configuration of the floor and walls allows access for examination.
a
Enclosure Response to NRC Request for Additional Information Second 10-Year Interval Inservice Inspection Program Plan and Associated Relief Requests Page 6 2RSS*P21 A-C-01 2RSS*P21 A-C-05 2RSS*P21 A-C-19 2RSS*P21 A-N-02 2RSS*P21 A-L-06 2RSS*P21 A-N-20 2RSS*P21 A-C-03 2RSS*P21 A-C-07 2RSS*P21 A-L-22 2RSS*P21 A-C-04 2RSS*P21 A-L-08 Relief Request 2-TYP-2-C6.10-1, Rev. O contains two typographical errors. Welds listed as 2RSS*P21 A-C21 and -C24 are actually longitudinal welds as shown on drawing 10080-ISI-E-2M. This request for relief will be revised to show these welds as L21 and L24.
Question 9:
Request for Relief / Alternate Examination No. 2-TYP-2-UT-1, Revision 0. The licensee has proposed to use ultrasonic 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 as an alternative to the 1989 Edition of ASME XI.
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. Also, provide a copy of PDI Program Description, Revision 1 as referenced in the request for relief.
Response 9:
Relief Request No. 2-TYP-2-APP-I-1, Revision 0 and Request for Relief /Alternaive Examination No. 2-TYP-2-UT-1, Revision 0, both describe the scope and details of the proposed alternatives.Section XI,1989 Edition, Paragraph IWA-2240 provides requirements for alternative examination methods. The proposed alternative l
i examinations have been demonstrated to be equivalent or superior to those specified in )
the 1989 Edition of ASME Section XI.
Both of the above referenced documents propose the use of Appendix VIII as 1 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.
f
! Attached is a copy of the PDI Piogram Description, Revision 1, Change 1, as requested.
1 L
l Enclosure Response to NRC Request for AdditionalInformation i Second 10-Year Interval Inservice la==+ ion Program Plan and Associated ReliefRequests Page 7 l
Question J:
Reques: for Relief 7 Alternative Ev incion No. 2-TYP-2-N-521, Revision 0, proposes an alternative schedule for reactor pressure vessel nozzle examinations. Code Case N-521, Alternative Rules for Deferral ofInspections ofNozzle-te Vessel Welds, Inside 1 Radius Sections, and Nozzle 4o-Safe End Welds of a Pressurized Water Reactor Vessel,
}
states that examination ofRPV 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 acccrdance with IWB-2420(b), and c) the unit is not in the first interval. An additional re@ement imposed by the NRC is that all subject areas be scheduled for examination such that the time lapse between examinations will not exceed 10 years, except as adjusted by IWA-2430(a). Confirm that all of the above conditions will be : net.
J Response J:'
Regarding the BV-2 Reactor Vessel Nozzle-to-Vessel Welds, Inside Radius Sections, i
i and Nozzle-to-Safe End Welds, it is confirmed that: 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. Further, all of the noted welds were examined during the final 40-month period of the Srst ten-year interval (2R06,1996), and are scheduled for examination in the final 40-month period of the second ten-year interval (i.e., July 2004 to November 2007).
Note, half of the examinations performed on these welds in the third period of the first interval, were in excess of the ASME XI requirements, but were performed in preparation for implementation of Code Case N-521.
Question K:
j Verify that there are no requests for reliefin addition to those submitted. If additional l requests for relief are required, the licensee should submit them for staff review. j Regnse K:
Currently, there are no further relief requests, beyond those submitted with the Ten-Year Plan (2TYPP-2). All Relief and Alternative Requests prepared to date for the Second 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 I 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.
PAGE NO. I 12/17/97 OEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMSER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED 1 NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE
...... .......... ........... .r......... .......... .......... .......... .........
" CATEGORY: BA
! B01.011 3 3 0 0 3 3 0 100.0 0.0 l 801.012 7 7 0 0 7 7 0 100.0 0.0 B01.021 1 1 0 0 1 0 1 100.0 0.0 l 801.022 4 4 0 0 4 4 0 100.0 0.0 B01.030 1 2 0 1 1 2 0 h et**% M . 200.0 0.0
( B01.040 1 1 1 0 0 1 0 4 100,0 0,0
- subtotst **
- 17 18 2 0 16 18 0 l 0.0 l
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- AGE NO. 2 12/17/97 BEAVER VALLEY POWER STAf!ON UNIT 2 ASME XI PERCENTAGE RECONCILIAf!ON EXAMS '
REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER CF SCHEDULED IST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE 1 TO DATE I senses asesssenes sassssssssa esassasssa sessssassa sessassses assessessa sessssssa assasassa sammesssa .
I
- CATEGORf: 88 B02.011 2 2 0 1 1 2 0 100.0 0.0 802.012 2 2 0 1 1 2 0 100.0 0.0 802.040 3 1 1 0 0 0 1 33.3 0.0
" Subtotat **
7 5 1 2 2 5 0 0.0 2d/, 40IO M8 1 )
as o i
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PACE No. h 12/18/97 SEAVER VALLEY POWER'STAfl0N UNIT 2 ASME XI PERCENTAGE RECONCILIAfl0N 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 X TO DATE as....
sesasssses asssssesses amassseses essassames assenesses seassasssa seasssmas . ssesses essesssa.
" CATEGORY: BD 803.090 6 6 0 0 6 6 0 100.0 0.0 803.100 6 6 0 0 6 6 0 100.0 0.0
" Subtotal "
12 12 0 0 12 12 0 0,0 0 k % u-un -
Po~. 9,< J I
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l . -. . _ _ _ _ _ - - _ _ _ _ _
l PAGE NO. 3B 12/18/97 BEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIAfl0N EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM WUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED 1 ;
NUMBER CAN0! DATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE '
% TO DATE
- sassanssas sessasssens essesssnes sessassess sssssssssa essenesses samassses assenssas seassenes
- CATEGCRY: B-0 803.110 6 6 2 0 4 6 0 100.0 0.0 803.120 6 6 2 0 4 6 0 100.0 0.0 B03.140 6 6 2 2 2 6 D 100.0 0.0
" subtetat **
18 18 6 2 10 18 0 0.0 3W. ItTo 56F.
- /o % g w ar mt '. At 6d 15% , Lt % me<< bg ge4 ,, gr p,,y i
N6dv % d abd 6 4Wket/
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PACE NO. 4 12/17/97 BCAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIATION s
EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMsER OF SCHEDULED iST PER100 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANo! DATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE
- CATEGORY: 8E 804.012 1 1 0 0 1 0 1 100.0 0.0 804.013 1 1 0 0 1 0 1 100.0 0.0 J B04.020 1 1 0 0 1 0 1 100.0 0.0
" Subtotat **
3 3 0 0 3 3 0 0.0 AS$e Od$
l I
PAGE NO. %
13/10/0F BEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS ltEM COMPLETED WUMBER OF SCHEDULED iST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUM8ER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE E TO DATE maasse essassenes asssssssses seassessna esssenessa essenesess sessa. ses asssemass massses== essassses
- CATECORY: 8F B05.010 6 6 0 0 6 6 0 100.0 00
- s Suetoret **
6 6 0 0 6 6 0 0.0 k M-4LL -
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.. _ - _ - _ _ - . _ . _ _ _ _ - _ _ . . _ _ _ = . __ _ _ _ _ . _ _.
PACE N0. SB 12/18/97 SEAVER VALLEY POWER STATION UNIT 2 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
. .. . .......... sees .. ssa .......... ......... ss...... e .......... mas... .. ...... .. . .. . .a
- CATEGORY: 8F 805.040 6 6 2 0 4 6 0 100.0 0.0 805.070 6 6 2 2 2 6 0 100.0 0.0
- Subtotal "
12 12 4 2 6 12 0 0.0 3% % 5#.
A 5*. a 14 i
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l PAGE NO. 6 12/17/97
\
BEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIAf!ON EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMSER OF SCHEDULED iST PEtt00 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED 1
- NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE
\ ...... .......... ........... .......... .......... ..n...... .......... ......... ......... .........
l I
" CATEGOR1: 8G1 C06.010 3 3 1 1 1 3 0 100.0 0.0 806.030 3 3 1 1 1 3 0
' 100.0 0.0 806.040 3 3 0 0 3 3 0 100.0 0.0 806.050 3 3 1 1 1 3 0 100.0 0.0 806.180 3 1 0 0 1 0 1 33.3 0.0 806.190 3 1 0 0 1 0 1 33.3 0.0 j B06.210- 6 1 0 0 1 0 1 16.7 0.0 l 806.220 6 1 0 0 1 0 1 16.7 0.0 B06.230 6 1 0 0 1 1 0 16.7 0.0
" Subtotal "
36 17 3 3 11 17 0 0.0 i 7*** %*J <u<gt w% \uny a w hg, l ,
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PAGE No. T 02/04/98
]
BEAVER VALLEY POWER STATION UNIT 2 A$ME XI PERCENTAGE RECONCILIATION l EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER OF SCHEDULED IST PERICD 2ND PERIOD 3RD PERIOD EXAMS IN CXAMS SCHEDULED %
NUM4ER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE 1 TO DATE sessas assesssses sensassessa assessemos esessasses smassesses sessmasses essaasssa seasssses essasassa
- CATEGORY: BG2 B07.020 1 1 0 1 0 1 0 100.0 0'0 I i 807.030 6 2 2 0 0 2 0 33.3 0'O B07.050 9 9 3 2 4 9 0 100.0 0'O B07.060 3 1 0 0 0 1 1 33.3 0'0 B07.070 32 8 2 2 4 8 0 25.0 0O 807.080 4 4 1 0 3 4 0 100.0 0*0
- Subtotal **
55 25 8 5 12 25 0 0.0 327, 284 46%
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%Ya 1 1 1467e
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, ' ACE No. 8 i
. 12/17/97 l BEAVER VALLEY POWER STAf!CN UNIT 2 l ASME XI PERCENTAGE RECONCILIAf!ON EXAMS REMAINING COMPLC'ED EXAMS COMPLETED ITEM NUMBER OF SCHEDULED IST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN E 4"$ SCHEDULED %
NUMBER. CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE
...... .......... ........... .......... ..... i... .......... .......... ......... ......... .........
CATECORY: BJ B09.011 452 114 44 31 39 114 0 25.2 0.0 l B09.021 687 174 47 60 67 174 0 25.3 0.0 809.031 13 4 2 1 4 0 30.8 1
0.0 809.032 48 12 4 4 4 12 0 25.0 0.0 l 809.040 177 45 14 14 17 45 0 25.4 0.0
" Subtotal "
1377 349 111 110 126 349 0 0.0 31 5 4Y. 37 %
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U$ 4 1o0, l
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l l
i I
PACE No. 0 12/1F/07 BEAVER VALLEY POWER STAf!ON UNIT 2 ASME XI PERCENTAGE RECONCILIAf!ON EXAMS REMAINING COMPLETED EXAMS ITEM COMPLETED NUMSER OF SCHEDULED 157 PERIOD 2ND PERIOD 3RD PERICO EXAMS IN EXAMS SCHEDULED X NUMSER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE- 1 to CAtt sessas assassesse assassasses assassessa ensamasses sesssasses assassassa sessanssa seassessa sassasses ;
- CATECORY: 8K1 B10.010 5 1 1 0 0 1 0 20.0 00 B10.020 20 3 0 1 2 3 0 15.0 0$0
- Subtotal **
25 4 1 1 2 4 0 0.0 uf, td. 54 1
'h M o 1
e d
l J
l
...__..___________ _ _______J
PAGE No. 10 12/17/97 BEAVER VALLEY POWER STATION UNIT 2 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 E To DATE se.... .......... ssesses==== assa...... ....... .. asasse ess us ....... .........
- CATECORY: BL1 812.010 3 1 0 0 0 1 1 33.3 0.0
" Subt ot al **
3 1 0 0 1 1 0 0.0
% py.<J t
l l
1
J PACE 40, 11 12/17/97 SEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMSER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NLM8ER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL to DATE 1 to DATE sassas assessanss seassamassa sensessnes assessassa essssssses usammasssa seassessa seassessa seasseses
" CATECORT: BL2 812.020 3 0 0 0 0 0 0 0 . 0 "" "" * "" = * *
" Subtotal "
3 0 0 0 0 0 0 ******************
2em. 49 l
l l
l
PAGE No. 12 12/17/97 BEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIATE!0N EXAMS REMA!NING COMPLETED EXAMS COMPLETED ITEM NUM8ER OF SCHEDULED IST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED 1 NUMBER CANDIDATES IN INTERVAL EXAMS ' EXAMS EXAMS INTERVAL To DATE % TO DATE
- CATEGOR Y: BM2 812.050 37 0 0 0 0 0 0 0.0"""*"""*****
- Subtotal "
37 0 0 0 0 0 0 *"******++++++++e Pn . qA.
I t
l l
1 I
i i
)
PACE NC. 13
{
12/17/97 BEAVER VALLEY POWER STAf!ON UNIT 2 l ASME XI PERCENTAGE RECONCILIATION I
i I EXAMS REMAINING COMPLETED 095 COMPLETED ttEM NUMBER OF SCHEDULED IST PERIOD 2ND PERico 3RD PERIOD EXAMS IN EXAMS SwMEDULED % !
NUMBER CANDICATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % to DATE l essnes sassansses assassanssa =====ssous asassssssa assssssssa ==ssanassa sassasssa ========= sassassas l CATEGORY: BN1 813.010 1 3 1
== Suetotal as 1 1 3 0 300.0 0.0 )
1 3 1 1 1 3 0 o,o NY6 We %5Yg l h
O,,. Kn . I
,@1 W6 4 l4 l
, I i
1 i,
w__ - . _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ . _ _ _
PaGE n,0. 14 12/17/0?
SEAVER VALLEY POWER 57A710N UNif 2 ASME XI PERCENTAGE RECONCIL!Afl0N EXAMS REMAINING COMPLETED EXAMS ITEM COMPLETED NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUM8ER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE X to DATE
" CATEGORY: BN2 813.060 1 1 0 0 1
{
1 0 100.0 0.0 Subtota! ** l I
1 1 0 0 1 1 0 0.0
%~ 9..J i
PAGE NO. 15 BEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIATION EXAMS 1 REMAINING COMPLETED EXAMS COMPLETED ITEM i NUMSER OF SCHEDULED 1$f PERIOD 2ND PER!a0 3RD PERIOD EXAM $ IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE a
- CATEGORY: 8 N*3 B13.070 1 1 0 0 1 0 1 100.0 0.0
- Subtotal **
1 1 0 0 1 1 0 0.0 04...g-.A
}
l 4
I
, PACE No. 1G
) .- 12/1F/97 BEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIAfl0W EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM
. NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXANS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE %
To DATE
, " CATECORY: B0-
! B14.010 24 3 0 0 3 3 0 12.5 0.0
- " Subtotat **
24 3 0 0 3 3 0 0.0 L
@cs. ga al l
l 1
1 4
I
PAGE No. 18 12/17/97 BEAVER VALLEY POWER STAi!ON UNIT 2 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER OF SCHEDULED IST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANDICATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE
- CATECORY: CA C01.010 13 6 1 3 2 6 0 46.2 0.0 C01.020 7 4 1 2 4 1 0 57.1 0,0 C01.030 11 4 1 2 4 1 0 36.4 0.0
" Subtotal "
31 14 3 6 5 14 0 0.0 2% 4 31(, %f.
- w. o led.
l l
l l
l
PACE NO. 19 12/17/97 BEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTACE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMSER OF SCHEDULED 1ST PERIOD 2ND PER!ao 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE assess ausssssssa essassesses assenesssa sesseessas assasssses auss==sess sessansas as sesses assunsens
" CATECORY: CB CO2.011 16 4 0 0 4 4 0 25.0 0.0 CO2.021 14 6 2 4 0 6 0 42.9 0.0 CO2.022 6 2 2 0 0 2 0 33.3 0.0
" Subtotat "
36 12 4 4 4 12 0 0.0 N h 6 L
n% , ,
\eeis f
I 1
i l
PAGE No. 20 i 12/17/97 BEAVER VALLEY POWER STAfl0N UNIT 2 ASME XI PERCENTAGE RECONCILIATION j EXAMS REMAIN!NG COMPLETED EKAMS JTEM COMPLETED l
NUM8ER OF SCHEDULED 157 PERIOD 2ND PERIOD 340 PERIOD EXAMS !N EXAMS SCHEDULED %
l NUMBER CANDIDATES IN INTER'.'AL EXAMS EXAMS EXAMS INTERVAL TO DATE i seasse 1 TO DATE essasseses sessssssses seassenssa seassessas sessnesses seassasssa smassesse sessansas assesses.
i l ** CATECORY: CC C03.010 38 3 3 0 0 3 0 7.9 0.0 C03.020 155 16 & 6 6 16 0 10.3 0.0 C03.030 62 8 1 3 4 3 0 12.9 0.0
- Subtotst **
55 27 8 9 10 27 0 0.0 l #4 W. M l
- w. , ,
\so1e 4
I PACE No. 21 12/17/97 BEAVER VALLEY POWER STATION UNIT 2 f
A$NE XI PERCENTAGE RECONCILIATION l
EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMBER OF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMSTR CAN0! DATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO DATE
.nsses sanssssses aussssssses masasssses seassessas assssssses ...s..s . sessanssa massassau sessa,s,.
' " CATEGORY: CF1 C05.011 1365 101 31 28 42 101 0 7.4 0.0 C05.021 706 59 20 18 21 59 0 8.4 0.0 C05.030 497 42 - 7 10 25 42 0 8.5 0.0 4
- C05.041 13 2 0 1 1 2 0
'- 15.4 0.0 a subtorat a 2581 204 58 57 89 204 0 0.0 24 % 24 4 Me 5s/4 v
totf/,
1 I
i i
l PAGE No. 22 12/17/97 SEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIAf!ON EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMOER OF SCHEDULED 1ST PERlac 2NO PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUM8ER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE 1 TO DATE I
- ;ATECORY: CF2 j
C05.051 193 29 10 8 11 29 0 15.0 0.C C05.052 29 11 3 6 2 11 0 37.9 0.0 C05.081 3 1 0 0 0 1 1 33.3 0.0
- Subtotal **
, 225 41 13 14 14 41 0 0.0 N
\ u l
47.
1 9
l i
I l
l I
e 6
PACE No. 23 12/17/97 BEAVER VALLEY POWER STAf!0N UNIT 2 ASME XI PERCENTAGE RECONCILIATION EXAMS ItEMt.!NING COMLETED EXAMS COMPLETED ITEM NUM0ER CF SCHEDULED 1ST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED 1 NUM8ER CANDIDATES IN IN7ERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % fo DATE
- CATECORY: CG C06.010 96 16 4 6 6 16 0 16.7 0.0
Subtotal **
96 16 4 6 6 16 0 0.0
%% 2% 38 %
1 1
n 9 'I
\enk
PACE =0. 24 12/1F/0P SEAVER VALLEY POWER STAT!0N UNIT 2 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS COMPLETED ITEM NUMSER OF SCHEDULED IST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE % TO CATE senses ===sessess massessemos assssasses assasssses samme==ssa assenesses seassesas asasssses seasssses
" CATECoaY: DA D01.010 26 12 10 1 1 12 0 46.2 0.0 001.020 405 47 9 17 21 47 0 11.6 0.G
" Subtotal "
431 59 19 18 22 59 0 0.0 34 M We
\
b 6% ,
loot, o
PACE No. 25 12/17197 SEAVER VALLEY POWER STATION UNIT 2 ASME XI PERCENTAGE RECONCILIATION EXAMS REMAINING COMPLETED EXAMS ITEM COMPLETED NUMSER OF SCHEDULED IST PERIOD 2ND PERIOD 3RD PERIOD EXAMS IN EXAMS SCHEDULED %
NUMBER CANDIDATES IN INTERVAL EXAMS EXAMS EXAMS INTERVAL TO DATE 1 TO DATE
...... .......... ... ssessas se........ as........ .......... ...s...... .........
" CATEGORY: F-A F01.10A 24 8 3 3 2 8 0 33.3 0.0 F01.104 1 73 47 12 16 19 47 0 27.2 0.0 l F01.10$ - 72 19 5 7 7 19 0 26.4 0.0
! F01.10T 75 21 8 7 6 21 0 28.0 0.0 F01.20A 85 17 6 6 5 17 0 20.0 0.0 F01.20R 488 79 25 20 34 79 0 16.2 0.0 F01.20$ 89 17 4 5 8 17 0 19.1 0.0 F01.20T 100 19 7 5 7 19 0 19.0 0.0 F01.30A 87 13 4 5 4 13 0 14.9 0.0 F01.30H 16 2 0 1 1 2 0 12.5 0.0 F01.30R 414 48 14 14 20 48 0 11.6 0.0 F01.30$ 38 6 1 3 2 6 0 15.8 0.0 701.30T 56 8 3 1 4 8 0 14.3 0.0 F01.40E 136 61 16 16 29 61 0 44.9 0.0 i
" Subtotal "
1853 365 108 109 148 365 0 l 0.0 2 M 40%
l a o
%'4
1 I
RESPONSE 3 i Page 1 of 5 l
)
The following list of calibration blocks are scheduled for use during the second 10-year interval. Additional blocks may be used if augmented or modified techniques are desired or mandated during the interval, {
j i
Piping Blocks l Identification Matsrial Diameter / "T" (in.) Application ,
Schedule PP-22 SA376, TP 316 02/160 0.343 CHS/ SIS PP-19 SA106, GR B 03/80 0.308 MSS l PP-22 A376, TP 316 02/160 0.343 SIS I PP-21 SA376, TP 316 03/160 0.438 CHS/ SIS PP-18 SA106, GR B 04/80 0.340 MSS PP-8 SA376 TP316 04/160 0.531 RCS/PZR. SPRAY LINE PP-17 SA106, GR B 06/80 0.426 SVS PP-7 SA312,TP316 06/160 0.766 RCS/CHS/ SIS /PZR SPRAY NOZZLE PP-15 SA106, GR B 08/80 0.458 SVS PP-6 A376,TP316 08/160 0.906 RCS LOOP BY-PASS, PZR SAFETY NOZZLES PP-16 SA106, GR B 09/SPL 1.45 MSS PP-14 SA106, GR B 10/80 0.506 SVS PP-5 SA376,TP316 10/160 1.125 RHS/ SIS I PP-20 SA312,TP304 12/40 0.440 RHS/RSS/QSS PP-4 A376,TP316 12/160 1.260 RHS/ SIS PP-3 SA376, TP16 14/160 1.38 RCS/PZR SURGE & NOZZLE PP-12 SA106, GR.B 16/80 0.788 PVS PP-13 SA106, GR.B 16/100 1.30 FWS PP-10 SA106, GR B 32.5/SPL 1.37 MSS PP-11 A155,KC70,CL1 32.5/SPL 1.38 MSS BV1-55 A508, CLASS 2 N/A 3 MAIN STEAM HEADER PP-9 SA106, GR C 34 1.85 MAIN STEAM l
PP-2 SA351, GR CF8A 34/SPL 2.500 RCS LOOP PIPING BV-12X29SI SA351, GR CF8A & N/A N/A RCS BRANCH CONNECTIONS A182,TP304N (MOCK-UP) l 1
i
RESPONSE 3 Page 2 of 5 Vessel Blocks identification Material Diameter / "T" (In.) Application Schedule BV-IR-1 A508, CLASS 2 N/A VARIOUS STEAM GEN MS AND FW NOZZLE INNER RADIUS, PRESSURIZER NOZZLE INNER RADIUS SG-1 SA508, CLASS 2 N/A 5.40 STEAM GENERATOR (CHANNEL (CLAD) HEAD)
SG-2 SA533, CLASS 1 N/A 3.52 STEAM GENERATOR SHELL PR-1 SA533, CLASS 1 N/A 4 PRESSURIZER (CLAD)
PR-2 SA533, CLASS 1 N/A 2.80 PRESSURIZER NOZZLE-TO-(CLAD) HEAD WELDS RV-1 SA533, GR. B CLASS N/A 9.06 RV INTERMEDIATE SHELL 1 (CLAD)
~
RV-2 SA533, GR. B CLASS N/A 7 RV CLOSURE HEAD 1 (CLAD)
RV-3 SA533, GR. B CLASS N/A 5 LOWER HEAD 1 (CLAD)
RV-4 SA533, GRADE B N/A 10.31 RV NOZZLE BELT SHELL (CLAD)
RV-5 SA 508 CL2 / SA182, N/A 2.6 RV NOZZLE TO SAFE-END F316 WELDS RV-6 SA508, CLASS 2 N/A 18 & 36 RV FLANGE & NOZZLE TO (CLAD) SHELL BV1-16 A312.TP304 10/140 1.00 SEAL WATER INJ. FILTERS HE-1 SA240,TP304 N/A 1.00 RHS/NON-REGEN HX HE-7 SA240, TP304 N/A 0.322 VOLUME CONTROL TANK HE-9 SA240,TP304 N/A 0.375 RSS HX/RSS PUMP CASING Bolting Blocks l Identification Material Diameter / Size Application Schedule BS-1 SA-540, GR. 82/ 6* DIA. 55.75' RV STUDS LONG BS-2 A453 GR 660 3.0 DIA 20" LONG LOOP ISOLATION VALVE STUDS BS-3 SAS40, GR. B24 4.5" DIA N/A RCP FLANGE BOLTS
RESPONSE 3 Page 3 of 5 The following NDE procedures are planned for use during the second 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 Applicaton ;
GP-101 11 Requirements for Data Recording General procedure for recording ISI data GP-104 9 Establishment of Reference Points for Provides instructions to install ISI Data Recording datum and reference points.
GP-105 6 Evaluation of PSl/ISI Flaw Indications Provides sequence and protocol instructions for evaluation of j 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 acceptance criteria for high temperature (125' -350') PT (surface) examinations
, MT-201 13 Magnetic Particle Examination Provides requirements and acceptance criteria for Class 1,2 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 on'y to items less Bolting Less than 2 inches Diameter than 2'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 Thickness Measurements Using ,
Straight Beam Ultrasonic Techniques l '
UT-309 4 Ultrasonic Examination of RV Closure Sec,cndary procedure to allow Head Studs from Central Bore augmented examination from nozzle bore (if required)
UT-312 0 UT Through-Wall Flaw Depth Sizing in UT TW Flaw sizing procedure Piping Welds based on PDI Procedure PDI-
RESPONSE 3 Page 4 of 5 Number Rev Title Application UT-3, Revision B Number Rev Title Application UT-313 4 Manual Ultrasonic Examination of (Class 1and 2) Self-explanatory Vessel Nozzle Inner Radius Sections UT-314 2 Ultrasonic Examination of Unit 2 RV RV Shell-to-Flange .
Shell-to-flange Weld from the Flange l Mating Surface UT-315 1 Ultrasonic Thickness Measurements Used for MIC and FAC Using the ABB/AMDATA Intraspect examinations I/UX2i Ultrasonic Imaging System UT-317 1 Manual Straight Beam Ultrasorde (Class 1and 2) Primary UT Examination of Botting bolting procedure based on PDI-UT-5, Revision A UT-319 1 Ultrasonic Examination of " Set-In' (Class 1 RCS) Self-explanatory Austenitic Branch Connection Welds UT-320 1 Ultrasonic Examination of Ferritic (Class 1and 2) Ferritic piping Piping Welds exams - based on PDI-UT-1, Revision A UT-321 1 Ultrasonic Examination of Austenitic (Class 1and 2) Austenitic piping Piping Welds exams - based on PDI-UT-2, Revision A UT-322 1 Ultrasonic Examination of Dissimilar (Class 1and 2) Self-explanatory -
Metal Welds IWA-2240 procedure 1 UT-323 0 Ultrasonic Examination of Welds (Class 1) RCS Loop piping -
Joining Cast Austenitic Piping IWA-2240 procedure Components VT-500 8 Gene.'al Requirements for Visual Self-explanatory Examination VT-501 5 Visual Examination of Threaded (Class 1,2 and 3) Self- l Fasteners explanatory (VT-1) I 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-Supports explanatory (VT-3)
VT-504 6 Visual Examination Requirements for (Class 1,2 and 3) Self-Intemal Surfaces of Pumps, Valves explanatory and Reactor Vessel Interior /Intemals VT-507 7 Visual Examination of Rubber Self-explanatory j Expansion Joints ;
VT-509 5 Visual Examination of Welds and (Class 1,2 and 3) Self-l 1
RESPONSE 3 Page5of 5 Number Rev Title Application Components explanatory VT-510 6 Visual Examination for Boric Acid (Class 1,2 and 3) Self-explanatory Number Rev Title Application 4
VT-511 2 Attemative Pressure Test (Class 1,2 and 3) VT Requirements for Welded Repairs or requirements for Code Case N-Installation of Replacement items by 416-1 examinations Welding RT-600 4 General Requirements for Self-explanatory Radiographic examination i
RT-602 4 Radiographic Examinations Govemed RT technique and acceptance I by ASME lil,1971 Edition, W-72 criteria for " code year of record" l Addenda examinations. )
RT-603 4 Radiographic Examinations Govemed RT techniques when RTis used !
by the 1989 Edition of ASME Section to meet the volumetric XI. examination 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-by ASME Section lil,1992 Edition 1 is applied for the repair / replacement activity.
I i
l I
RESPONSE 4 Pag 31 of 2
$ 5 5 s s s M i $ M M M s s s s s s M f y 5 g g s s s s e a System $ $ $ f f f f i 5 $ $ $ $ $ $
Boron Recovery
- X Chemical and Volume Control X X X Containment Vacuum
- X Feedwater X Hydrogenated Drains X X Leakage Monitoring
- X Main Steam X Quench Spray X X X Reactor Coolant System X X Recirculation Spray X X X Residual Heat Removal X X Safety injecin,n X X X X X X Sample
- X X Service Water X Steam Vents and Drains X
~ Steam Generator Blowdown
- X X
- Entire system is exempt from specified examination requirements lWB-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 boundary, 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 t
systems which are operable from on-site emergency power; (b)(1) piping of NPS 1 and smaller, except for steam generator tubing; t
(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.
l IWC-1220, the following components (or parts of components) are axempted from the volumetric and surface examination requirements of IWC-2500.
"4C-1221 Components Within RHR, ECC, and CHR Systems (or Portions of Systems)
( ) Vessels, piping, pumps, valves and other components NPS 4 and smaller in all systems except high pressure safety injechon systems of pressurized water reactor plants.
(b) Vessels, piping, pumps, valves, and other components NPS 1% and smaller in high pressure safety injection syster ., r f 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 connections) in vessels, piping, pumps, valves, and other components of any size in high pressure safety injection systems of nessurized water reactor plants.
(e) Vr wis, piping, pumps, valves, other components, and component cor,nections of any size in statically pressurized, passive (i.e., no pumps) safety injection systems of pressurized water reactor plants.
RESPONSE 4 Paga 2 of 2 (f) Piping End other components of any siza beyond the 1:st shutiff vilva in open cnded portions of systems that do not contain water during normal plant operating conditions.
IWC-1222 Components Within Systems (or Portions of Systems) Other Than RHR, ECC, and 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.
IWD-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 exempt from the visual examination VT-3, except for PWR Auxiliary Feedwaior Systems.
LWD-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:
(a) the components are located in systems (or portions of systems) whose function is not required in 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.
i l
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- _ - - - - - -