Text

Risk-Informed Inservice Inspection (RI-ISI) Program and Updated Inservice Inspection Program for Third 10-Year Interval
	ML061210105
Person / Time
Site:	Sequoyah
Issue date:	04/21/2006
From:	Pace P; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	TAC MB1566, TAC MB1567
	Download: ML061210105 (374)
	v • d • e

Tennessee Valley Authority, Post Office Box 2000, Soddy-Daisy, Tennessee 37384-2000 April 21, 2006 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentleman:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT - (SQN) RISK-INFORMED INSERVICE INSPECTION (RI-ISI) PROGRAM AND UPDATED INSERVICE INSPECTION (ISI) PROGRAM FOR THIRD 10-YEAR INTERVAL

References:

1) NRC letter to TVA dated October 23, 2001, "Sequoyah Nuclear Plant (SQN),

Units 1 and 2 - Clarification of Relief Requests Regarding Risk-Informed Inservice Inspection Program (TAC Nos. MB1566 and MB1567)"

2) NRC letter to TVA dated October 19, 2001, "Sequoyah Nuclear Plant (SQN),

Units 1 and 2 - Approval of Relief Requests Regarding Risk-Informed Inservice Inspection Program (TAC Nos.

MB1566 and MB1567)"

By the reference letters, NRC staff provided approval of relief requests submitted for SQN's second 10-year ISI interval.

Pursuant to 10 CFR 50.55a(a)(3)(i), TVA is submitting relief requests for SQN's third 10-year ISI interval.

The relief requests (one for each unit) propose using SQN's RI-ISI program as an alternative to the ASME Section XI Code for inspection of Class 1 and Class 2 piping welds during SQN's third 10-year interval.

PRntedonrecycledpaper

i IU.S. Nuclear Regulatory Commission Page 2 April 21, 2006

!;QN's RI-ISI program is a "living" program that is developed in accordance with the Westinghouse Owners Group (WOG) Topical Report, WCAP-14572, Revision 1-NP-A, WCAP-14572, Revision 1-NP-A Supplement 1; and WCAP-l 4572, Revision 1-NP-A, Supplement 2. Consistent with these topical reports, new information has been 1ncorporated in SQN's RI-ISI analysis as part of the "living" RI-ISI program. The new information includes revised consequences for all segments based on Revision 3 of the SQN Probabilistic Risk Assessment (SQN PRA model dated August 2004), and provides revised failure probabilities for a limited number of segments based on industry and plant experience and plant modifications, and updated test intervals for a limited number of segments.

The results of the revised RI-ISI analysis were reviewed by the SQN RI-ISI expert panel. A comparison with SQN's Unit 1 second 10-year RI-ISI program indicates that 16 Jlow safety significant (LSS) segments were reclassified as high safety significant (HSS) and 36 HSS segments were reclassified as LSS. For SQN Unit 2, 15 LSS segments were reclassified as HSS and 36 HSS segments were reclassified as LSS segments. The expert panel has concurred with these reclassifications and existing segment classifications.

The RI-ISI analysis indicates a slight reduction in risk and TVA considers SQN's RI-ISI program to-be risk neutral. Accordingly, the SQN RI-ISI program provides an acceptable level of quality and safety as required by 10 CFR 50.55a (a) (3) (i).

Pursuant to .10 CFR 50.55a(a) (3) (ii), TVA is submitting a second set of relief requests (one for each unit) that proposes a visual testing (VT)-2 visual examination in

].ieu of the RI-ISI program requirement (i.e., WCAP-14572) for performing a volumetric examination of branch connection welds < 2 inches nominal pipe size and socket welds that are subject to thermal fatigue or stress corrosion cracking. The basis for relief is compliance with the specified requirements would result in hardship or unusual difficulty to TVA without a compensating i ncrease in the level of quality and safety.

f U.S. Nuclear Regulatory Commission Page 3 April 21, 2006 Enclosure 1 provides the relief requests associated with S;QN's RI-ISI program. Enclosure 2 provides the relief requests associated with VT-2.

Enclosure 3 provides an information copy of SQN's updated ISI program for the third 10-Year inspection interval. The program has been updated to comply with the 2001 Edition and the 2003 Addenda of the ASME Section XI Code. Pursuant to 10 CFR 50.55a(g)(4)(ii),

ISI programs are required to be updated every 10 years to meet the requirements of the latest NRC approved Edition and Addenda of ASME Section XI which is in effect 12 months prior to the start of the next 120-month inspection interval. TVA plans to submit future requests for relief for SQN's ISI program as ISIs are performed and limitations identified during SQN's third 10- year inspection interval.

SQN Units 1 and 2 will start the third 10-year ISI interval on June 1, 2006, and implement the RI-ISI program during the Unit 2, Cycle 14 (U2C14) refueling outage that starts November 2006. Accordingly, TVA requests NRC approval of the enclosed RI-ISI program by October 2006 to support implementation of the RI-ISI program during the U2C14.refueling outage.

TVA's proposed RI-ISI program for SQN is consistent with the WCAP-15572, Supplement 2, the NRC draft Safety Evaluation Report (SER) for Supplement 2, and the Westinghouse response to the SER for Supplement 2.

If you have any questions regarding this response, please contact J. D. Smith at extension (423) 843-6672.

Sincerely, Paul L. Pace Manager, Site Licensing and Industry Affairs Enclosures cc: See Page 4

U.S. Nuclear Regulatory Commission Page 4 April 21, 2006 cc (Enclosures)

Mr. Edgar D. Hux 94 Ridgetree Lane Marietta, Georgia 30068 Mr. Douglas V. Pickett, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop 08G-9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. William T. Russell 400 Plantation Lane Stevensville, Maryland 21666

ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2 REQUESTS FOR RELIEF 1-RI-ISI-1 AND 2-RI-ISI-1 EXECUTIVE

SUMMARY

The SQN Risk-Informed Inservice Inspection. (RI-ISI) program was approved for SQN's second 10-year inspection interval by NRC letters dated October 19, 2001 and October 23, 2001. Pursuant to 10 CFR 50.55a(a)(3)(i), TVA is requesting NRC review and approval of SQN's RI-ISI program for SQN's third ISI interval. The RI-ISI program is considered by TVA to be an acceptable alternative to ASME Section XI requirements for selecting the number and locations of the elements to be examined. The ASME code of reference for the third inspection interval is the 2001 Edition, 2003 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code.

Additionally, in accordance with 10 CFR 50.55a(b)(2)(ii), the extent of examination for Examination Category B-J welds under SQN's ISI program is in accordance with the 1974 Edition, Summer 1975 Addenda of ASME Section XI.

Consistent with the Westinghouse Owners Group (WOG) RI-ISI methodology documented in WCAP-14572, Revision 1-NP-A; WCAP-14572, Revision 1-NP-A, Supplement 1; and WCAP-14572, Supplement 2, new information has been incorporated into SQN's RI-ISI analysis as part of the "living" RI-ISI program. The new information includes changes to the SQN Probabilistic Risk Assessment (PRA) model, revised failure probabilities for a limited number of segments based on industry and plant experience and plant modifications, and updated test intervals for a limited number of segments.

Two reactor coolant system segments were required to be added to the SQN Unit 1 RI-ISI program to meet the change in risk criteria on page 214 of WCAP-14572. For SQN Unit 2, one reactor coolant system segment was identified to be added to the RI-ISI program to meet the change in risk criteria. The eight reactor coolant system examinations added for defense in depth considerations for each unit remain the same as in the previously approved RI-ISI program for SQN's second inspection interval.

Comparisons between SQN's ASME Section XI ISI program, the RI-ISI program for the second inspection interval, and the RI-ISI program for the third inspection interval for each unit are presented in Tables 1 and 2. The RI-ISI analysis indicates a slight reduction in risk and TVA considers the third interval RI-ISI program to be risk neutral. Accordingly, the third interval RI-ISI program provides an acceptable level of quality and safety as required by 10 CFR 50.55a(a)(3)(i).

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UNITS: SQN Units 1 and 2 SYSTEM: Various ASME CODE CLASS: 1 and 2 ASME SECTION XI CODE EDITIONIADDENDA: 2001 Edition, 2003 Addenda of ASME Section XI and WCAP-14572, Revision 1-NP-A; WCAP-14572, Revision 1-NP-A, Supplement 1; and WCAP-14572, Supplement 2 CODE TABLE: IWB-2500-1 and IWC-2500-1 EXAMINATION CATEGORY: B-F, B-J, C-F-1, C-F-2 EXAMINATIONITEMNUMBER: B5.10, B5.40, B5.70, B9.10, B9.20, B9.30, B9.32, B9.40, C5.10, C5.20, C5.30, C5.40, C5.50, C5.60, C5.70 and C5.80 REQUIREMENTS:

ASME Section XI, 2001 Edition, 2003 Addenda ISI requirements for Code Class 1 and Class 2 piping welds.

REQUIREMENT FROM WHICH RELIEF IS REQUESTED:

Examination of piping welds in accordance with Examination Categories B-F, B-J, C-F-1 and C-F-2.

BASIS -FOR RELIEF:

Consistent with the WOG RI-ISI methodology documented in WCAP-14572, Revision 1-NP-A; WCAP-14572, Revision 1-NP-A, Supplement 1; and WCAP-14572, Supplement 2, new information has been incorporated into the RI-ISI analysis as part of the "living" RI-ISI program.

The new information includes changes to the SQN Probabilistic Risk Assessment (PRA) model, revised failure probabilities for a lim'ted number of segments based on industry and plant experience and plant modifications, and updated test intervals for a limited number of segments.

The changes described above required re-performing the risk evaluation. The revised results were reviewed by the SQN Units 1 and 2 RI-ISI expert panel and 16 low safety significant segments were reclassified as high safety significant and 36 high safety significant segments were reclassified as low safety significant1 segments for SQN Unit 1. For SQN Unit 2, 15 low safety significant segments were reclassified as high safety significant and 36 high safety significant segments were reclassified as low safety significant segments. The expert panel concurs with the reclassifications and the existing segment classifications.

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The change in risk evaluation was also re-performed to compare the original Section XI programs with the revised third inspection interval RI-ISI program for each unit. Two reactor coolant system segments were required to be added to the SQN Unit 1 RI-ISI program to meet the change in risk criteria on page 214 of WCAP-14572. The two additional examinations are visual testing (VT)-2 visual exams.

For SQN Unit 2, one reactor coolant system segment was identified to be added to the RI-ISI program to meet the change in risk criteria. The one additional examination is a VT-2 visual examination. The eight reactor coolant system examinations added for defense-in-depth considerations for each unit remain the same as in the previously approved RI-ISI program for SQN's second inspection interval. The RI-ISI analysis indicates a slight reduction in risk and TVA considers the third interval RI-ISI program to be risk neutral.

The attached Tables 1 and 2 provide more detailed information regarding the RI-ISI program for piping on each unit and the changes between intervals.

ALTERNATIVE EXAMINATIONS:

The Westinghouse Owners Group (WOG) RI-ISI methodology documented in WCAP-14572, Revision 1-NP-A; WCAP-14572, Revision 1-NP-A, Supplement 1; and WCAP-14572, Supplement 2, new information has been incorporated into the RI-ISI analysis as part of the "living" RI-ISI program and will be used for the selection and examination of piping welds for ASME Section XI Examination Categories B-F, B-J, C-F-1 and C-F-2.

JUSTIFICATION FOR GRANTING RELIEF:

SQN's RI-ISI program for the third inspection interval was prepared consistent with SQN's program for the second inspection interval..

The third interval RI-ISI program incorporates changes from WCAP-14572, Supplement 2. The RI-ISI program information has been updated and analyzed in accordance with WCAP-14572, Revision 1-NP-A; WCAP-14572, Revision 1-NP-A, Supplement 1; and WCAP-14572, Supplement 2 and the revised locations for inspection have been selected in accordance with the approved methodology. The change in risk evaluation was conducted and two segments for Unit 1, arid one segment for Unit 2, were added to the inspection program to meet the change in risk criteria in WCAP-14572. The RI-ISI analysis indicates a slight reduction in risk and TVA considers the third interval RI-ISI program to be risk neutral. Therefore, the RI-ISI program for the third inspection interval maintains plant:

safety when compared to a Section XI inspection program. In addition, eight reactor coolant system locations per unit (at the reactor vessel nozzle to safe-end pipe welds) are included in the RI-ISI program for defense-in-depth considerations.

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Accordingly and pursuant to 10 CFR 50.55a(a)(3)(i), TVA requests.

relief from the ASME Section XI Code to utilize SQN's RI-ISI program as an alternative to the ASME Section XI requirements.

IMPLEMENTATION SCHEDULE:

This request for relief is applicable to the third 10-year ISI interval for SQN Units 1 and 2.

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Table 1 SQN Unit 1 Inspection Location Selection Comparison to ASME Section XI and WCAP-14572 Rev. I-NP-A System Number of HSS Degradation Class ASME Weld CountP ASME XI 2nd Interval RI-ISI 3 rd Interval Rl-ISI a Segments (No. Mechanism(s) of HSS in Code Examination Augmented Category Methods Program / Total No.

of Segments in (Volumetric and Augmented Surface or Surface Program) Only)'

Butt Socket SES Matrix Number of SES Matrix Number of Region Exam Region Exam Locations Locations AF 4 (0/2) TF, Strip/Strat Class 2 C-F-2 0 0 2 4 BDC 6 (6/12) TF, VF, FAC Class 2 C-F-2 0 IA 12 b+ 8c IA 6e+ 6c CH' 10 (0/3) TF, VF, Class 1 B-J 66 248 71 IA, lB 10+ I1A, 1B 4+ 8b 9

Strip/Strat Class 2 C-F-1 399 165 44 2 2 ClI 0 (0/1) TF, Erosion\ Class 2 C-F-1 - - 0 0 0 Corrosion C-F-2 - - 0 - 0 - 0 CS 3 (0/0) TF, VF Class 2 C-F-I 147 26 16 2 3+1K 2 5n+lg FWc 0 (0/4) TF, VF, Class 2 C-F-2 73 0 11 IA, 1B 88 8 94 8c - 0 Strip/Strat, Erosion\

Corrosion MSC 4 (4/14) TF, VF Class 2 C-F-2 120 0 18 I 2 4 El-5

Table 1 SQN Unit i inspcction Location Sciection Comparison io ASiE Section Xi anl WCtW-1q5J/ iCV. -i4r-A System Number of HSS Degradation Class ASME Weld Count' ASME XI Interval RI-ISI Interval RI-ISI a 2nd 3rd Segments (No. Mechanism(s) Code Examination of HSS in Augmented Category Methods Program / Total No.

of Segments in (Volumetric and Augmented Surface or Surface Program) Only)'

Butt Socket SES Matrix Number of SES Matrix Number of Region Exam Region Exam Locations Locations RC 6 (1/7) TF, VF, Class I B-F 22 0 22 1A, 1B, 2 8 IA,1B 8 Strip/Strat, PWSCC B-J 164 71 73 11+91 3+ 5 + 2 RH 5 (1/1) TF, VF, Class I B-J 54 26 5 2 2 IA, 1B, 2 2 Strip/Strat, SCC Class 2 C-F-I 331 6 23 4 lg+ 4 6+ 1g Si, 31 (6/8) TF, VF, Class 1 B-J 135 229 110 IA, IB, 2 12+ 13b IA, 1B, 2 12+ 13b Strip/Strat, SCC Class 2 C-F-1 508 207 60 12+ 6 + 3g 14+4 + 2g SQ 0 (0/0) TF Class 2 C-F-1 - - 0 0 0 Class I B-F 22 0 22 8 NDE + 8 NDE +

TOTAL 0 VT2 0 VT2 B-J 419 574 259 35 NDE + 21 NDE +

. I _ . 31 VT2 28 VT2 El-6

Table 1 SQN Unit 1 Inspection Location Selection Comparison to ASME Section XI and WCAP-14572 Rev. 1-NP-A System Number of HSS Degradation Class ASME Weld Count' ASME XI 2nd Interval RI-ISI 3 rd Interval Rl-ISI a Segments (No. Mechanism(s) Cd xmnto of HSS in Code Examination Augmented Category Methods Program / Total No.

of Segments in (Volumetric and Augmented Surface or Surface Program) Only)t '

Butt Socket SES Matrix Number of SES Matrix Number of Region Exam Region Exam Locations Locations Class 2 C-F-1 1385 404 143 23 NDE + 25 NDE +

13 VT2 10 VT2 C-F-2 193 0 29 25 0 NDE + 14P NDE +

20 VT2 6 VT2 El-7

Table 2 SQN Unit 2 Inspection Location Selection Comparison to ASME Section XI and WCAP-14572 Rev. 1-NP-A System Number of HSS Degradation Class ASME Weld Count' ASME XI 2nd Interval Rl-ISI 3rd Interval Rl-ISI Segments (No. Mechanism(s) C of HSS in oHSin. Code Examination Augmented Category Methods Program / Total No.

of Segments in (Volumetric and Augmented Surface or Surface Program) Only)m Butt Socket SES Matrix Number of SES Matrix Number of Region Exam Region Exam Locations Locations AF 4 (0/2) TF, Strip/Strat Class 2 C-F-2 - 0 0 2 4 BDC 6 (6/12) TF, VF, FAC Class 2 C-F-2 - 0 IA 12 b+ 8c IA 6e+ 6c CH' 10 (0/3) TF, VF, Class I B-J 66 238 77 IA, 1B 10+ IA, IB Ib 4+ 8b Strip/Strat Class 2 C-F-I 414 153 46 2 2 CIC 0 (0/1) TF, Erosion\ Class 2 C-F-I - - 0 0 0 Corrosion C-F-2 - 0 - 0 - 0 CS 3 (0/0) TF, VF Class 2 C-F-I 144 26 17 2 3+19 2 5n+lg FWC 0(0/4) TF,VF, Class 2 C-F-2 71 0 I IA, lB 8 g 8c - 0 Strip/Strat, Erosion\

Corrosion MSC 4(4/14) TF,VF Class 2 C-F-2 122 0 1s 0 2 4 El-8

Table 2 SQN Unit 2 Inspection Location Selection Comparison to ASME Section XI and WCAP-14572 Rev. 1-NP-A System Number of HSS Degradation Class ASME Weld Count' ASME XI 2nd Interval Rl-ISI Interval RI-ISI 3 rd a Segments (No. Mechanism(s) of HSS in . Code Examination Augmented Category Methods Program t Total No.

of Segments in (Volumetric and Augmented Surface or Surface Program) Only)'

Butt Socket SES Matrix Number of SES Matrix Number of Region Exam Region Exam Locations Locations RC 6 (1/7) TF, VF, Class I B-F 22 0 22 IA, IB, 2 IA, 1B 8 Strip/Strat, PWSCC B-J 161 70 65 11+9 3+5+1 RH 5 (0/0) TF, VF, Class1 B-i 50 18 6 2 2 2 2 Strip/Strat, SCC Class 2 C-F-1 342 6 23 4T+1+4 4+ 18 SlI 28 (7/13) TF, VF, Class 1 B-J 128 170 90 IA, lB, 2 7+ 13 b IA, IB, 2 9 + 13 Strip/Strat, SCC Class 2 C-F-I 536 215 61 12+ 6 + 3g 13+ 4 + 2

+ 2 bk SQ 0 (0/0) TF Class 2 C-F-1 - - 0 0 0 Class I B-F 22 0 22 8 NDE + 8 NDE +

TOTAL 0 VT2 0 VT2 B-J 405 496 238 30 NDE + 18 NDE +

l l 31 VT2 l _ l 27 VT2 J El-9

Table 2 SQN Unit 2 Inspection Location Selection Comparison to ASME Section XI and WCAP-14572 Rev. 1-NP-A System Number of HSS Degradation Class ASME Weld Count' ASME XI Interval R-ISI 2 nd 3 rd Interval Rm-ISI a Segments (No. Mechanism(s) of HSS in o SinCode Ctgr Examination Augmented Category Methods Program / Total No.

of Segments in (Volumetric and Augmented Surface or Surface Program) Only) m Butt Socket SES Matrix Number of SES Matrix Number of Region Exam Region Exam Locations Locations Class 2 C-F-1 1436 400 147 23 NDE + 22 NDE +

15 VT2 10 VT2 C-F-2 193 0 29 24°NDE + I4P NDE +

20 VT2 6 VT2 Summary: There are several changes to the number of exams in the RI-ISI program for the 3rd ten-year inspection interval. Prior Unit I ASME Section XI selects a total of 453 non-destructive exams while the 3rd Inspection Interval RI-ISI program selects a total of 62 non-destnictive exams, which results in an 86% reduction. Prior Unit 2 ASME Section XI selects a total of 436 non-destructive exams while the 3rd Interval RI-ISI program selects a total of 56 non-destructive exams, which results in an 87% reduction.

Degradation Mechanisms: FAC - Flow-Assisted Corrosion, SCC - Stress Corrosion Cracking; Strip/Strat - Striping/Stratification; VF - Vibratory Fatigue; TF - Thermal Fatigue El-10

Systems: AF - Auxiliary Feedwater BD -Steam Generator Blowdown CH - Chemical and Volume Control Cl - Containment Isolation CS - Containment Spray FW - Feedwater MS - Main Steam RC - Reactor Coolant RH - Residual Heat Removal SI - Safety Injection SQ - Sampling and Water Quality Notes for Tables

a. System pressure test requirements and VT-2 visual examinations shall continue to be performed in all ASME Code Class 1, 2, and 3 systems.

b. VT-2 examination for entire segment. (See Requests for Relief I-RI-ISI-2 and 2-RI-ISI-2)

c. Augmented programs for erosion-corrosion (including MIC) continue.

d. VT-2 examination for entire segment.

e. VT-2 examination for entire segment; two segments have an inaccessible 2" butt weld inside a pipe penetration (total 2 butt welds). (See Requests for Relief I-RI-ISI-2 and 2-RI-ISI-2)

f. Five examination locations added for change in risk considerations.

g. VT2 examination for a portion of the segment. (See Requests for Relief I-RI-ISI-2 and 2-RI-ISI-2)

h. Eight examination locations added for defense-in-depth at the reactor vessel nozzle to safe-end pipe welds.

1. Augmented program for thermal stratification of base metal at socket weld areas continues.

j. These weld counts arc based on the original ASME Section XI program boundaries for the systems and not the RI-ISI piping classification boundaries for each system. These counts are based on plant procedure O-SI-DXI-O00-1 14.2 Revision 10 "ASME Section XI ISIINDE Program Unit 1 and Unit 2".

k. Six examination locations added for change in risk considerations.

1. VT2 examination added to meet change in risk criteria.

m. These examinations are based on the segments identified in the RI-ISI system boundaries and not the original ASME Section XI program boundaries for the systems as identified in plant procedure O-SI-DXI-000-1 14.2 Revision 10 "ASME Section XI ISIINDE Program Unit 1 and Unit 2."

n. Socket and branch connection welds on two containment spray system segments that are in open ended piping are being addressed in requests for relief l-RI-ISI-2 and 2-RI-ISI-2.

o. Includes 16 examinations in the augmented program for BD and FW.

p. Includes 6 examinations in the augmented program for BD.

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iVe ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2 REQUESTS FOR RELIEF 1- RI-ISI-2 AND 2- RI-ISI-2 EXECUTIVE

SUMMARY

The SQN Risk-Informed Inservice Inspection (RI-ISI) program was developed in accordance with the provisions of WCAP-14572, Revision 1-NP-A; WCAP-14572, Revision 1-NP-A, Supplement 1; and WCAP-14572, Supplement 2. Table 4.1-1 of WCAP-14572 requires that high safety significant piping segments which are subject to thermal fatigue or stress corrosion cracking and that have been selected for examination be volumetrically examined. The requirements contained in Table 4.1-1 have been taken directly from Code Case N-577, Risk-Informed Requirements for Class 1, 2, and 3 Piping, Method A.

WCAP-14572, Supplement 2 was followed to develop SQN's RI-ISI program for the third 10-year ISI interval. The topical report (WCAP-14572, Supplement 2) has been submitted to NRC and is currently undergoing review for approval.

Certain high safety significant segments or portions of high safety significant segments, at SQN have been identified as subject to stress corrosion cracking or thermal fatigue. These segments have been identified with a potential stress corrosion cracking or thermal fatigue damage mechanism either caused by a postulated temperature stratification or as a default mechanism for segments selected for their consequence of failure with no active or postulated mechanism occurring. Some of these segments, which are subject to stress corrosion cracking or thermal fatigue, contain branch connection welds < 2 inches nominal pipe size and/or socket welds. Performance of a volumetric examination of branch connection welds < 2 inches nominal pipe size and/or socket welds will not result in an examination that achieves meaningful results due to the size and geometric configuration of the weld joint.

Performance of surface examinations from the outside diameter would not provide additional information for inside diameter initiated flaws.

TVA has taken protective measures to mitigate outside diameter initiated or outside diameter postulated failures. These measures include programmatic control of procurement of piping and components, control of welding processes, surface cleanness

.specifications, and utilizing insulation to reduce temperature differentials.

Code Case N-577 has been revised to allow a VT-2 examination of socket. welds for all failure mechanisms. Performance of a VT-2 examination of branch connection welds < 2 inches NPS and/or socket welds is considered by TVA to be a reasonable alternative to the required volumetric examination. The required volumetric E2-1

examination would result in a hardship or unusual difficulty to TVA without a compensating increase in the level of quality and safety.

Two steam generator blowdown System segments at each unit contain one butt weld that is located inside a pipe penetration and is riot accessible for nondestructive examination (NDE). The remaining welds in the segments are socket welds. Performance of a VT-2 examination on these segments is the most reasonable alternative to the required volumetric examination. The required volumetric examination would result in a hardship or unusual difficulty to TVA without a compensating increase in the level of quality and safety.

Two containment spray System segments on each unit contain socket welded piping that cannot be isolated from the containment spray headers; therefore, the segments cannot be pressurized for a VT-2 examination. Any attempt to pressurize these segments would result in spraying down upper containment with borated water. The ASME Section XI pressure test requirements for the segments are in Section XI Table IWC-2500-1. In addition, Paragraph IWC-5222(b) of ASME Section XI states that open-ended discharge piping is excluded from the examination requirements. Any examination on socket welds for these sections of piping would result in a hardship without a compensating increase in the level of quality and safety. Butt welds selected for examination in these segments will receive a volumetric examination.

Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), it is requested that relief be granted.

UNITS: SQN Units 1 and 2 SYSTEM: Various ASME CODE CLASS: 1 and 2 ASME SECTION XI CODE EDITION/ADDENDA: 2001 Edition, 2003 Addenda of ASME Section XI and WCAP-14572, Revision 1-NP-A; WCAP-14572, Revision 1-NP-A, Supplement 1; and WCAP-14572, Supplement 2 CODE TABLE: Table 4.1-1 of WCAP-14572, Revision 1-NP-A and WCAP-14572, Supplement 2 EXAMINATION CATEGORY: R-A, Risk-Informed Piping Examinations EXAMINATION ITEM NUMBER: R1.11, High Safety Significant Piping Structural Elements Subject to Thermal Fatigue R1.16 High Safety Significant Piping Structural Elements Subject to Stress Corrosion Cracking E2-2

REQUIREMENTS: Table 4.1-1 of WCAP-14572, Examination Category F.-A, Item Number R1.11 or R1.16, requires elements in high safety significant segments which are subject to thermal fatigue or stress corrosion cracking and that have been selected for examination be volumetrically examined. This requirement is changed in WCAP-14572 Supplement 2 for socket welds of any size and branch pipe connection welds nominal pipe size (NPS) 2 inches and smaller. A VT-2 examination is required for these welds.

REQUIREMENT FROM WHICH RELIEF IS REQUESTED:

Relief is requested from performing a volumetric examination of branch connection welds < 2 inches NPS and socket welds that are subject to thermal fatigue. Relief is also requested from performing a volumetric examination for each unit on two steam generator blowdown system piping welds located inside containment penetration sleeves and for a portion of two piping segments in the containment spray system that are open ended.

BASIS FOR RELIEF:

The design joint configuration and size of branch connection welds that are < 2 inches NPS and socket welds prohibit the performance of a volumetric examination that would achieve meaningful results.

The performance of a VT-2 examination during a system-pressure test provides reasonable assurance of continued structural integrity.

The steam generator blowdown system piping segments that contain.

the inaccessible butt welds will be examined with visual examinations (VT-2). The remaining welds in the segments are socket welds. The performance of a VT-2 examination during a system pressure test provides reasonable assurance of continued structural integrity for these welds.

The containment spray system piping segments that contain socket welded piping cannot be isolated from the containment spray headers; therefore, the segments cannot be pressurized for a VT-2 examination. Any attempt to pressurize these segments would result in spraying down upper containment with borated water. The ASME.

Section XI pressure test requirements for the segments are in Section XI Table IWC-2500-1. In addition, paragraph IWC-5222(b) of ASME Section XI states that open-ended discharge piping is excluded from thae examination requirements.

ALTERNATIVE EXAMINATIONS:

Branch connection welds < 2 inches NPS and socket welds in high safety significant segments subject to thermal fatigue or stress corrosion cracking will be VT-2 examined each refueling outage during a system pressure test or a pressure test specific to a component/element. Butt welds selected for examination will be vol~umetrically examined.

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The steam generator blowdown System segments with the inaccessible butt welds will be VT-2 examined each refueling outage during a system pressure test.

Butt welds selected for examination in the containment spray system segments that are open ended will be volumetrically examined in accordance with the RI-ISI program requirements.

JUSTIFICATION FOR GRANTING RELIEF:

Table 4.1-1, Examination Category R-A, of WCAP-14572, Rev. 1-NP-A provides information for the examination of structural elements (welds or base material for failure mechanisms such as FAC) in piping segments which have been identified as high safety significant. The requirements contained in Table 4.1-1 have been taken directly from Code Case N-577, "Risk-Informed Requirements for Class 1, 2, and 3 Piping, Method A." Piping welds within a high safety significant segment are selected for examination, and examination methods are determined based on active or postulated failure mechanisms as identified in Table 4.1-1. Piping welds subject to thermal fatigue or stress corrosion cracking that are selected for examination, are required to be volumetrically examined in accordance with Item Number Rl.11 or R1.16 of Examination Category R-A. This requirement is changed in WCAP-14572, Supplement 2 for socket welds of any size and branch pipe connection welds NPS 2 inches and smaller. A VT-2 examination is required for these welds.

Certain high safety significant piping segments at SQN have been identified as being subject to thermal fatigue or stress corrosion cracking, and therefore, require volumetric examination. Some of these segments include branch connection welds which are < 2 inches NPS and/or socket welds. These segments have been identified with a potential stress corrosion cracking or thermal fatigue damage mechanism either caused by a postulated temperature stratification or as a default mechanism for segments selected for their consequence of failure with no active or postulated mechanism occurring. The requirement in WCAP-14572 to perform a volumetric examination on branch connection weld < 2 inches NPS or socket weld does not consider the size and geometric limitations imposed by these types of welds. Performance of a volumetric examination on branch connection welds < 2 inches NPS or socket welds will not result in an examination that achieves meaningful results.

Performance of surface examinations from the outside diameter would not provide additional information for inside diameter initiated flaws such as thermal stratification.

E2 -4

TVA has taken protective measures to mitigate outside diameter initiated or outside diameter postulated failures. These failures include, but are not limited to transgranular stress corrosion cracking, halogen-induced stress corrosion cracking, outside diameter initiated fatigue mechanisms, and intergranular stress corrosion cracking. Austenitic stainless steel and nickel-based alloy piping and components are purchased to ASTM/ASME requirements which ensures that no sensitized/improperly heat treated parts are bought or issued for installation. These are covered by TVA's General Engineering Specifications G-29, Part B for these materials. In addition, TVA's welding program (G-29, Part A) requirements ensure that proper measures are taken prior to welding. The purchase of filler metals and related materials (e.g., insulation, temperature indicating materials, etc.) are controlled such that limited amounts of detrimental halides are introduced to the weldments. The welding procedures utilized by TVA are controlled to prevent undue sensitization of the heat-affected zones of the weldments. Surface cleanliness is addressed in the SQN UFSAR, Section 5.2.5, and by General Engineering Specification G-29 P.S. 4.M.4.1 and related site implementing procedures (TI-29, "Determination of Surface Chloride, Fluoride and Boron Contamination on Stainless Steel Surfaces" and TI-70, "Cleanliness of Fluid Systems"). These requirements ensure that the external surface is left in a condition where detrimental halides are minimized to reduce the possibility of cracking, such as chloride stress corrosion cracking. Temperature differentials are reduced by applying insulation where applicable and the appropriate supports when necessary. This reduces the possibility of temperature fluctuations which could lead to outside diamete:-

initiated thermal fatigue. In addition, plant system operation is performed in a manor to minimize thermal stratification.

The ASME Code Committee has revised and published Code Case N-577 to allow a VT-2 examination of socket welds for all failure mechanisms. The revised code case is identified as N-577-1. Code Case N-577-1 allows the performance of the VT-2 examination of socket. welds in note 12 of Table 1. It is understood that NRC has not yet published results of a review of Code Case N-577-1. WCAP-14572, Supplement 2, Table 4.1-1, also allows the performance of the VT-2 examination of socket welds of any size and branch pipe connection welds nominal pipe size 2 inches and smaller (see note 8 of this table).

TVA currently performs a self-imposed augmented ultrasonic examination of piping base metal adjacent to selected socket welds located in piping which is not isolatable from the reactor coolant system main loop piping. These areas are selected due to potential thermal stratification. The base metal areas are ultrasonically E2 -5

A I I .

examined for cracks located circumferentially on the pipe inside diameter on a best effort basis. The socket weld is not included in these examinations. The augmented ultrasonic examinations of these areas are not affected by this request for relief.

Performance of a volumetric examination of branch connection welds

< 2 inches nominal pipe size and/or socket welds will not result: in an examination that achieves meaningful results due to the size and geometric configuration of the weld joint. The required volumetric examination would result in a hardship or unusual difficulty to TVA without a compensating increase in the level of quality and safety.

Performance of a VT-2 examination of branch connection welds < 2 inches nominal pipe size and/or socket welds in high safety significant segments, or portions of high safety significant segments, is the most reasonable alternative to the required volumetric examination.

Two steam generator blowdown system segments on each unit contain one butt weld that is located inside a pipe penetration and is not accessible for nondestructive examination. The remaining welds in the segments are socket welds. Performance of a VT-2 examination of the segments, including the inaccessible 2-inch butt welds i:,

the mcst reasonable alternative to the required volumetric examination. The required volumetric examination would result in a hardship without a compensating increase in the level of quality and safety.

Two containment spray system segments on each unit contain socket welded piping that cannot be isolated from the containment spray headers; therefore, the segments cannot be pressurized for a VT-2 examiration. Any attempt to pressurize these segments would result in spraying down upper containment with borated water. The ASME Section XI pressure test requirements for the segments are in Section XI, Table IWC-2500-1. In addition, Paragraph IWC-5222(b) of ASME Section XI states that open-ended discharge piping is excluded from the examination requirements. Accordingly, any examination on this section of piping would result in a hardship or unusual difficulty to TVA without a compensating increase in the level of quality and safety. Butt welds selected for examination in these segments will be volumetrically examined in accordance with the RI-ISI program requirements.

Accordingly, and pursuant to 10 CFR 50.55a(a)(3)(ii), TVA requests relief from SQN's RI-ISI program to perform a VT-2 visual examination in lieu of volumetric examination for branch connection welds < 2 inches nominal pipe size and/or socket welds and the inaccessible butt welds, and not performing VT-2 on open-ended pipe.

E2-6

IMPLEMENTATION SCHEDULE:

This request for relief is applicable to the third 10-year ISI interval for SQN Units 1 and 2.

E2-7

ENCLOSURE 3 SEQUOYAH NUCLEAR PLANT (SQN)

UNITS 1 AND 2 (INFORMATION COPY)

INSERVICE INSPECTION (ISI) PROGRAM FOR THIRD 10-YEAR INTERVAL1 E3-1

Sequoyah Nuclear Plant Unit I & 2 Surveillance Instruction O-SI-DXI-000-1 14.3 ASME SECTION Xl ISI/NDE PROGRAM UNIT I and UNIT 2 Revision 0000 Quality Related Level of Use: Reference Use Effectiveb Date: 06-01-2006 Responsible Organization: SCE, System Eng - Component Prepared By: Jeffery C. Goulart Approved By: Gay S. Haliburton

SON ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 1 & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 2 of 66 Current Revision Description Intent This is the initial program for the ASME Section XI third inspection interval prepared to meet the 2001 Edition thru 2003 Addenda of the ASME Section XI Code I

SON . ASME SECTION XI ISI/NDE PROGRAM O-SI-DXI-000-114.3 Unit 1 & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 3 of 66 Table of Contents

1.0 INTRODUCTION

...................................................... 6 1.1 PURPOSE ..................................................... 6 1.2 SCOPE (APPLICABILITY) ...................................................... 6 1.3 CODES OF RECORD AND CODE CASES ................................ ...................... 7 1.4 FREQUENCY INSPECTION INTERVAL AND INSPECTION PERIODS .......... ......... 11 2.0 DEVELOPMENTAL REFERENCES ..................................................... 12 2.1 SCN UNIT 1 TECHNICAL SPECIFICATIONS ..................................................... 12 2.2 SCN UNIT 2 TECHNICAL SPECIFICATIONS ..................................................... 12 2.3 SEQUOYAH NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT.............1....................................................................................................... 12 2.4 NRC DOCUMENTS ................................ 12 2.5 PLAN

T. PROCEDURE

S & INSTRUCTIONS ................................ 15 2.6 DRAWINGS ............................. 17 2.7 REFERENCE DOCUMENTS ............................. 17 2.8 CALCULATIONS ............................. 22 2.9 ABBREVIATIONS AND DEFINITIONS ............................. 23 3.0 PREREQUISITES AND PRECAUTIONS ............................. 25 3.1 PREREQUISITES ............................. 25 3.2 PRECAUTIONS ................................. 25 4.0 SPECIAL TOOLS AND EQUIPMENT...........................................................5. ........... 25 5.0 ACCEPTANCE STANDARDS .. 26 6.0 QUALIFICATIONS OF NDE PERSONNEL .................................................... 26 7.0 IMPLEMENTATION AND RESPONSIBILITIES ......... !......................... 26 7.1 NDE EXAMINATIONS .................................................... 26 7.2 COMPONENTS SUBJECT TO EXAMINATION .................................................... 27 7.3 NOTIFICATION OF INDICATION .................................................... 38 7.4 ADDITIONAL EXAMINATIONS AND SUCCESSIVE EXAMINATIONS FOR ASME CODE CLASS 1, 2 AND 3 ....................... ............................. 39 7.4.1 Additional Examinations For ASME Code Class 1, 2, And 3 ............ ............ 39 7.4.2 Successive Examinations ........................ 45 7.5 CONFIGURATION CHANGES ........................ 48

SON ASME SECTION XI ISIINDE PROGRAM 0-SI-DXI-000-114.3 Unit 1 & 2 UNIT I and UNIT 2 Rev. 0000 Page 4 of 66 Table of Contents (continued) 7.6 CALIBRATION STANDARDS ........................................................... 48 7.7 RECORDS AND REPORTS ........................................................... 48 7.8 REQUESTS FOR RELIEF (RFR) .......................... 54 7.9 CORRECTIVE ACTION PROGRAM .......... ................ 57 7.10 SCAN PLAN .57 7.11 AUGMENTED EXAMINATIONS .. 57 7.12 RISIK-INFORMED INSERVICE INSPECTION (RI-ISI) . .60 7.12.1 Introduction .60 7.12.2 Purpose .60 7.12.3 Scope .60 7.12.4 Frequency .60 7.12.5 Periodic Updates.. 61 7.12.6 Corrective Action Program .............................. 61 7.12.7 Inspection Program .61 7.12.8 Successive Inspections .61 7.12.9 Additional Examinations .62 7.12.10 Examination Coverage .62 7.13 OWNER STATEMENT .. 64 Source Notes .65

SCN ASME SECTION XI ISIINDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 6 of 66 Table of Contents (continued)

ATTACHMENT S Attachment 1 ASME Class 1 Equivalent Components Subject to Examii nation (Unit 1 and Unit 2) ASME Class 2 Equivalent Components Subject to Examii ination (Unit 1 and Unit 2) ASME Class 3 Equivalent Components Subject to Examii ination (Unit 1 and Unit 2) Examination Schedule (Unit 1)

Table A - ASME Class 1 Components

Table B - ASME Class 2 Components

Table C - ASME Class .3 Components

Table D - ASME Class 1, 2 and 3 Component Supports

Table E - ASME Class 1 and 2 RI-ISI Components Attachment 5 - Examination Schedule (Unit 2)

Table A - ASME Class 1 Components

Table B - ASME Class 2 Components

Table C - ASME Class 3 Components

Table D - ASME Class 1, 2 and 3 Component Supports

Table E - ASME Class 1 and 2 RI-ISI Components ASME Class 1 and 2 valves (Unit 1 and Unit 2) Listing of ISI Drawings (Unit 1 and Unit 2)

ASME Class 1, 2 and 3 Boundary Drawings

ASIME. Class 1, 2 and 3 Unit 1 Isometrics

ASME Class 1, 2 and 3 Unit 2 Isometrics

RI-ISI Segment Boundary Drawings Successive Examinations (Unit 1) Successive Examinations (Unit 2). 0 Augmented Examinations (Unit 1) 1 Augmented Examinations (Unit 2)

SON ASME SECTION Xi ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT I and UNIT 2 Rev. 0000 Page 6 of 66

1.0 INTRODUCTION

1.1 PURPOSE In accordance with Title 10 Code of Federal Regulations (CFR) Part 50, 50.55a(g) this program implements the Sequoyah Nuclear Plant (SON) Unit 1 Technical Specifications, Surveillance Requirement 4.4.3.2.4 and partially satisfies the requirements for both Unit 1 and Unit 2 Technical Specifications, Surveillance Requirement 4.0.5. This procedure also fulfills the requirements of SPP-9.1, Part A, "ASME Section Xl Inservice Inspection and Augmented Nondestructive Examinations" and fulfills the inservice inspection and augmented inspections portion of SPP-9.1, Part F, "Risk-Informed Inspection and Augmented Inspection and Test Program Development and Implementation". This program is organized to comply with the Inservice Inspection (ISI) nondestructive examination (NDE) requirements of the 2001 Edition, 2003 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, Division 1,Articles 1000, 2000, 3000, and 6000.

This ISI/NDE Program is an administrative Surveillance Instruction (SI) employed to obtain data via NDE of ASME Section Xl Code Class 1, 2, and 3 equivalent components to determine acceptance of components for continued service during operation and if a flaw is an isolated case or of a generic nature. It shall serve as IVA's ISI/NDE plan and schedule in accordance with the requirements of IWA-1 400 for the third ISI inspection interval.

This ISI/NDE Program reflects the limitations of the original plant design, geometry, construction, component materials, and the current technology or state-of-the-art nondestructive examination techniques. This procedure specifies the number of components to be examined, the examination methods to be used and provides schedule tables from which specific items are scheduled for examination. These irems are described and detailed in ISI scan plans.

1.2 SCOPE (APPLICABILITY)

This program outlines details for planning and implementing the third ISI/NDE inspection interval for ASME Section Xl Code Class 1, 2, and 3 equivalent components at SON in accordance with IWA- 2432, Inspection Program B and the Risk-Informed Inservice Inspection (RI-ISI) Program.

Elements of ASME Section Xi, such as Pump and Valve Testing, Snubber Inservice Examination and Testing (Refer to section 7.2D.6), Repair and Replacements, System Pressure Tests [including the associated Examination Categories, B-F3, C-H, D-B, and R-A item numbers R1.1 1 (Refer to section 7.8, requests for relief

'I-RI-ISI-2 and 2-RI-ISI-2), R1.12 and R1.15, VT-2 Visual Examinations], and Steam Generator Tube Examinations (Examination Category B-Q) are covered by other procedures.

SC!N ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT I and UNIT 2 Rev. 0000 Page 7 of 66 1.2 SCOPE (APPLICABILITY) (continued)

Refer to Attachment 7 for ASME Section Xi Code Class Boundary Drawings and the ISII Drawings identifying the components and systems to be examined. Refer to Attachment 7 for RI-ISI segment boundary drawings identifying system segments boundaries.

Personnel responsible for performance of the examinations should familiarize themselves with the requirements of this program prior to performing the Examinations. Specifics concerning performance of NDE are NOT a part of this program, but are included in Inspection Services Organization Programs Manual (Refer to Inspection and Examination Program (IEP) series).

1.3 CODES OF RECORD AND CODE CASES A. CURRENT CODE REQUIREMENTS AND CODE CASES The Code of Record for the third inspection interval of Unit 1 and Unit 2 is the 2001 Edition, 2003 Addenda of the ASME Boiler and Pressure Vessel Code, Section Xl, Division 1 in accordance with 10 CFR 50, 50.55a(g)(4).

Additionally in accordance with 10 CFR 50.55a(b)(2)(xi) the IWB-1220 of ASME Section Xl 1989 Edition shall be used for the exemption of class 1 piping.

Additionally in accordance with 10 CFR 50.55a(b)(2)(xxii) the use of the provision in IWA-2220 of the ASME Section Xl 2001 Edition 2003 Addenda that allow use of an ultrasonic examination method is prohibited.

Additionally in accordance with 10CFR 50.55a(b)(2)(xxiv) the use of Appendix VI11 and the supplements to Appendix VI11 and Appendix I Article 1-3000 of ASME Section Xl 2001 Edition will be used. In addition, paragraphs 10CFR50.55a(b)(2)(xiv, xv and xvi) are required. Refer to section 7.8 for request for relief PDI-2 and PDI-4 which will be submitted later for NRC approval prior to use.

Additionally in accordance with 10 CFR 50.55a(b)(2)(xviii)(C) when qualifying visual examination personnel for VT-3 visual examinations under paragraph IWA-2317 of the ASME Section Xl 2001 Edition 2003 Addenda the proficiency of training must be demonstrated by administering an initial qualification examination and administering subsequent re-examinations on a 3-year interval.

Additionally in accordance with 10 CFR 50.55a(b)(2)(xviii)(A) the level I arid 11 nondestructive examination personnel shall be recertified on a 3 year interval in lieu of the 5 year interval in IWA-2314(a) and IWA-2314(b) of the ASME Section Xl 2001 Edition 2003 Addenda.

SCIN ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit l & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 8 of 66 1.3 CODES OF RECORD AND CODE CASES (continued)

Additionally in accordance with 10 CFR 50.55a(b)(2)(xix) the provisions for substitution of alternative examination methods, a combination of methods, or newly developed techniques in the ASME Section Xl 1997 Addenda of IWA-2240 must be applied. The provisions in IWA-2240 of the ASME Section )l 2001 Edition 2003 Addenda are not approved for use.

Additionally in accordance with I OCFR50.55a(b)(2)(xxi) Table IWB-2500-1 examination requirements the following are required:

1. The provisions of Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Items B3.120 and B3.140 in the 1998 Edition of ASME Section Xl must be applied. A visual examination with enhanced magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table IWB-3512-1, ASME Section Xl 2001 Edition 2003 Addenda may be performed in place of an ultrasonic examination.

2. The provisions of Table IWB-2500-1, Examination Category B-G-2, Item B7.80, that are in the ASME Section Xl 1995 Edition are applicable to reused bolting.

The SQN RI-ISI Program shall be utilized as outlined in section 7.12 for the third inspection interval as an alternative inspection program. This program describes an acceptable alternative approach to the existing ASME Section Xl requirements for scope and frequency of piping weld inspections, and satisfies the criteria of 10CFR50.55a(a)(3)(i) providing an acceptable level of quality and safety.

The RI-ISI Program shall be implemented in the third inspection interval as an alternative to the requirements of Subsections IWB and IWC for inservice inspection of Class 1 and 2 piping welds. The RI-ISI Program at SQN is in accordance with WCAP-14572, Revision 1-NP-A, "Westinghouse Owners, Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report", February 1999 and WCAP-14572, revision 1-NP-A, supplement 1, "Westinghouse Structural Reliability and Risk Assessment (SRAA) Model for Piping Risk-Informed Inservice Inspection", February 1999.

WCAP-14572 provides risk-informed requirements for inservice inspection of piping. These requirements are being utilized by SQN as an alternative tc the requirements of Examination Categories B-F, B-J, C-F-1, and C-F-2 of ASME Section Xl. Refer to section 7.12 and section 7.8 for request for relief 1-RI..ISI-1 and 2-RI-ISI-1.

SON ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 1 & 2 UNIT I and UNIT 2 Rev. 0000 Page 9 of 66 1.3 CODES OF RECORD AND CODE CASES (continued)

The extent'of examination for Class 1 and 2 piping weld examinations for the third inspection interval shall be in accordance with the RI-ISI Program. The extent of examination for other categories and types of welds shall remain to be in accordance with the requirements of the ASME Section Xl Code or as provided in approved relief requests.

Regulatory Guide 1.150, Rev. 1, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations," shall be used for Reactor Vessel Weld examinations where PDI examinations are NOT required.

(Code cases used shall be implemented in their entirety unless approved by NFRC or stated in Regulatory Guide 1.147.

The following code cases were approved for use by the NRC in Regulatory Guide 1.147 revision 14. These code cases at this revision level may continue to be utilized until the end of the inspection interval. Code cases may be used provided all the provisions in each code case and conditions or limitations issued in the Regulatory Guide 1.147, if any are followed during the inspection interval.

3. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, Section Xl, Division 1. Approved for use in Regulatory Guide 1.147 revision 14. (Refer to NRC Information Notice 98-42, reference 2.4H.2). This code case was available for use starting with revision 0 of this procedure.

4. Code Case N-526, Alternative Requirements for Successive Inspections of Class 1 and 2 Vessels, Section Xl, Division 1. Approved for use in Regulatory Guide. 1.147 revision 14 and is available for use starting with revision 0 of this procedure.

5. Code Case N-586, Alternative Additional Examinations Requirements for Class 1, 2, and 3 Piping, Components, and Supports, Section Xl, Division

1. Approved for use in Regulatory Guide 1.147 revision 14 and is available for use starting with revision 0 of this procedure. The code case is acceptable for use subject to the following NRC conditions in the Regulatory Guide 1.147.

The engineering evaluations addressed under Item (a) and the additional examinations addressed under Item (b) shall be performed during this outage. If the additional examinations performed under item (b) reveal indications exceeding the applicable acceptance criteria of Section Xl, the engineering evaluations and the examinations shall be further extended to include additional evaluations and examinations at this outage.

SQN ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 1 & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 10 of 66 1.3 CODES OF RECORD AND CODE CASES (continued) 6; Code Case N-624, Successive Inspections, Section Xi, Division 1.

Approved for use in Regulatory Guide 1.147 revision 14 and is available for use starting with revision 0 of this procedure.

7. Code Case N-648-1, Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel Nozzles Section Xl, Division 1.

Approved for use in Regulatory Guide 1.147 revision 14 and is available for use starting with revision 0 of this procedure. The code case is acceptable for use subject to the following NRC conditions in the Regulatory Guide 1.147.

In place of a UT examination, licensees may perform a visual examination with enhanced magnification that has a resolution sensitivity to detect: a 1-mil width wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio. The provisions of Table IWB-2500-1, Examination Category B-D, continue to apply except that, in place of examination volumes, the surfaces to be examined are the external surfaces shown in the figures applicable to this table.

8. Code Case N-695, Qualification Requirements for Dissimilar Metal Piping Welds, Section Xl, Division 1. Approved for use in Regulatory Guide 1.147 revision 14 and is available for use starting with revision 0 of this procedure.

When a code case is authorized for use by the NRC through a request for relief and the code case is subsequently published in the Regulatory Guide 1.147 and SQN intends to continue to implement the code case, SQN is to follow all provisions in the c:ode case with limitations issued in Regulatory Guide 1.147, if any.

[3. HISTORY OF PSI AND ISI PROGRAMS For Unit 1 and Unit 2 a preservice inspection (PSI) program was NOT reqaired.

TVA performed a self-imposed PSI program in accordance with the 1974 Edition, Summer 1975 Addenda, of ASME Section XI. SI-1 14 was the Preservice Inspection (PSI) Program for SQN Units 1 and 2.

First Inspection Interval The SQN Unit 1 operating license (low power) was issued on July 1, 1981.

The first inspection interval ISI program was conducted in accordance with 1-SI-SXI-000-114.0 (July 1, 1981 through December 15, 1995). The Unit 1 first inspection interval was extended by 42 days.

SQN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit l & 2 UNIT I and UNIT 2 Rev. 0000 Page 11 of 66 1.3 CFODES OF RECORD AND CODE CASES (continued)

The SQN Unit 2 operating license (low power) was issued on June 1,1982.

The first inspection interval ISI program was conducted in accordance with 2-SI-SXI-000-114.0 (June 1, 1982 through December 15, 1995). The unit 2 first inspection interval was extended by 63 days.

Second Inspection Interval The SQN Unit I and Unit 2 second inspection interval ISI program was conducted in accordance with 0-SI-SXI-000-1 14.2 (December 16, 1995 thru May 31, 2006). The Unit 1 and Unit 2 second inspection interval was extended by 167 days.

1.4 FREQUENCY INSPECTION INTERVAL AND INSPECTION PERIODS The inservice examinations required by ASME Section Xi shall be performed during each 10-year interval of service (inspection interval). The inspection intervals represent calendar years after the unit has been placed into commercial service.

The ISI examinations required by ASME Section Xl, Division 1, IWA-2432, Inspection Program B shall be performed during this inspection interval (June 1, 2006 through May 31, 2015) for Unit 1 and Unit 2. The inspection interval may be decreased or extended by as much as one year to coincide with a plant outage in accordance with IWA-2430(d). See note below on inspection interval extension..

NOTES

1) Any decrease or extension is to take into consideration the first and second inspection interval extension in section 1.3B. If the unit is out of service continuously for six months or more, the inspection interval may be extended for an equivalent period in accordance with IWA-2430(e).

2) The total extension for both the first and second inspection intervals for Unit 1 is 209 days and for Unit 2 is 230 days. The third inspection interval is being reduced by one year to make up for the extensions in the first and second inspection interval. The total reduction for the first, second and third inspection intervals is 156 days for unit 1 and for Unit 2 is 135 days. This reduction will allow the same number of outages between the units in the third inspection interval.

rhird Inspection Interval Periods duration for Unit 1 and Unit 2

First Period Class 1,2 and 3 (6/1/2006 through 5/31/2009)

Second Period Class 1,2 and 3 (6/1/2009 through 5/31/2012)

SCN ASME SECTION Xl ISIINDE PROGRAM 0-SI-DXI-000-114.3 Unit l & 2 UNIT 1 and UNIT 2 Rev. 0000

. Page 12 of 66 1.4 FREQUENCY INSPECTION INTERVAL AND INSPECTION PERIODS (continued)

Third Period Class 1,2 and 3 (6/1/2012 through 5/31/2015)

This Si may be performed in any mode and'is applicable for all operational modes.

Except for examinations that may be deferred to the end of the inspection interval, the required examinations shall be performed in accordance with the following schedule that complies with IWB- 2412, Program B and Table IWB-2412-1; I'vVC-2412, Program B and Table IWC-2412-1; IWD-2412, Program B and Table I'vVD-2412-1; IWF-2410 and Table IWF-2410-2 inspection Program B.

The examinations deferred to the end of the inspection interval shall be completed by the end of the inspection interval.

NOTE When examinations are limited due to design, configuration, interference etc., the item should be considered for substitution where possible with another item.

2.0 DEVELOPMENTAL REFERENCES 2.1 S'QN UNIT 1 TECHNICAL SPECIFICATIONS A. SQN Unit 1 Technical Specifications Surveillance Requirement 4.4.3.2.4 and partially satisfies the requirements of Surveillance Requirements 4.0.5 2.2 %SQNUNIT 2 TECHNICAL SPECIFICATIONS A. SQN Unit 2 Technical Specifications partially satisfies the requirements of Surveillance Requirements 4.0.5 2.3 S'EQUOYAH NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT A. Sequoyah Nuclear Plant Updated Final Safety Analysis Report, 3.2, 5.2.6, 5.2.8, and 5.4.4 2.4 NRC DOCUMENTS A. 10 CFR Part 50.55a, Code of Federal Regulations, Codes and Standards B. 10 CFR Part 50.2, Code of Federal Regulations, Definitions

SQN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit l & 2 UNIT 1 and UNIT 2 Rev. 0000]

Page 13 of 66 2.4. NRC DOCUMENTS (continued)

C. Regulatory Guide 1.14, Reactor coolant Pump flywheel Integrity

[). Regulatory Guide 1.26, Quality Group Classification and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power Plants E. Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability ASME Section Xl Division 1 F. Regulatory Guide 1.150, Ultrasonic Testing of Reactor Vessel Welds during Preservice and Inservice Examinations G. IE Bulletins

1. NRC Bulletin 79-13; Cracking in Feedwater system piping

2. NRC Bulletin 88-08, Thermal Stresses on Piping Connected to Reactor Coolant Systems, and Supplement 1

3. NRC Bulletin 88-09 and Information Notice 87-44 Supplement 1, Thimble Tube Thinning in Westinghouse Reactors

4. NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity

5. NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized Water Reactors. Referenced in section 14.0 of Attachments 10 and 11.

H. Information Notices

1. Notice 87-44 supplement 1, Thimble Tube Thinning in Westinghouse Reactors

2. Notice 98-42, Implementation of 10CFR50.55a(g) Inservice Inspection Requirements I. Safety Evaluation Reports

SON ASME SECTION XI ISIINDE PROGRAM 0-SI-DXI-000-114.3 Unit 1 & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 14 of 66 2.4 NRC DOCUMENTS (continued)

1. Safety Evaluation Report, Sequoyah Nuclear Plant, Units I and 2 - Approval of Relief Requests Regarding Risk-informed Inservice Inspection Program (TAC Nos. MB1566 and MB1567) dated October 19, 2001 (L44 011031 003). Sequoyah Nuclear Plant, Units 1 and 2 - Clarification of Relief Requests Regarding Risk-informed Inservice Inspection Program (TAC Nos. MB1566 and MB1567) dated October 23, 2001. (L44 011031 002). Referenced in section 7.8 for 1-RI-ISI-1, 1-RI-ISI-2, 2-RI-ISI-1 and 2-RI-ISI-2.

2. Safety Evaluation Report, Sequoyah Nuclear Plant; Units 1 and 2 - Relief From Code Requirements for Residual Heat Removal System Heat Exchanger Inservice Inspection (TAC Nos. MA9898 and MA9900) dated February 12, 2001. (L44 010221 007). Referenced in section 7.8 for 1-ISI-15 and 2-ISI-15..

3. Safety Evaluation Report, Browns Ferry Nuclear Plant, Units 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Unit I

- American Society of Mechanical Engineers Section Xl, Inservice Inspection Program Request for Relief Nos. PDI-1 and PDI-2 (TAC Nos.

MB1260 and MB1263-1268) dated September 19, 2001. (L44 010925 002) Referenced in section 7.8.

4. Safety Evaluation Report, Browns Ferry Nuclear Plant, Units 1, 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Unit 1

- Inservice Inspection Program Relief Request PDI-4 (TAC Nos. MCE3232, MC6233, MC6234, MC6235, MC6236, and MC6237) dated August 2, 2005. (L44 050808 030) Referenced in section 7.8 J. Federal Register, Volume 70, Number 188 published September 29, 2005 K. Amendment to the Technical Specifications - Memorandum from R.W. He, nan, NRC, to J.A. Scalice, dated March 8, 2002, "Sequoyah Nuclear Plant, Units I and 2 - Issuance of Amendments Regarding the Reactor Coolant Pump Flywheel Inspection Program (TAC NOS. MB3823 and MB3824) (TS 01-13)"

L. NRC Order EA-03-009, Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head at Pressurized Water Reactors, dated February 11, 2003 and revised February 20, 2004. Referenced in section 12 of Attachments 10 and 11.

M. Amendment to the Technical Specifications - Memorandum from Robert J.

Pascarelli, NRC, to Karl W. Singer, dated July 8, 2004, "Sequoyah Nuclear Plant, Units 1 and 2 - Issuance of Amendments Regarding Extending the Inspection Interval for Reactor Coolant Pump Flywheels (TAC NOS. MC2448 and MC2449) (TS 04-02)" (L44 040721 005)

SON ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 1 & 2 UNIT I and UNIT 2 Rev. 0000

. Page 15 of 66 2.5 PLANT PROCEDURES & INSTRUCTIONS A. Technical Instructions

1. 0-TI-GXX-000-000.0, Plant Modifications and Design Change Control B3. Surveillance Instructions

1. 0-SI-OPS-000-011.0, ContainmentAccess Control During Modes 1

2. 0-SI-SXI-000-200.0, ASME Section Xl Inservice Pressure Test Schedule and Tracking

('. SQN Maintenance Instructions

1. 0-MI-MRR-068-005.0, Removal of Reactor Pressure Vessel Head and Attachments

2. 0-MI-MVV-000-008.0, Maintenance of Safety and Quality Related Valves

3. 2-MI-MXX-068-003.0, Removal and Installation of Steam Generator Primary Manway Covers

4. 0-MI-MXX-068-004.0, Removal and Replacement of Pressurizer Mariway Covers

5. MI-2.8, Removal and Replacement of RCP Main and Seal Flange Bolts

6. MI-10.2.3, Removal, Inspection and Replacement of Reactor Coolant Pump Cartridge and Number 1 Seals

7. 1-MI-MXX-068-003.0, Removal and Installation of Steam Generator Primary Manway Covers

[). SQN Special Maintenance Instruction E. Inspection and Examination Procedures

1. IEP-100, Administration of Nondestructive Examination (NDE) Procedures

2. IEP-200, Qualification and Certification Requirements for TVA Nuclear (TVAN) Nondestructive Examination (NDE) Personnel

3. IEP-203, Control of Calibration Standards

4. IEP-300, Qualification and Certification of Ultrasonic TVA Nuclear (T\VAN)

Personnel for Preservice and Inservice ASME Section Xl Examinations F. Standard Programs and Processes

SQN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 1 & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 16 of 66 2.5 PLANT PROCEDURES & INSTRUCTIONS (continued)

1. SPP-2.2, Administration of Site Technical Procedures

2. SPP-2.4, Records Management

3. SPP-3.1, Corrective Action Program

4. SPP-3.3, NRC Commitment Management

5. SPP-3.5, Regulatory Reporting Requirements

6. SPP-4.1, Procurement of Material, Labor and Services

7. SPP-5.4, Chemical Traffic Control

8. SPP-6.1, Work Order Process Initiation

9. SPP-6.4, Measuring and Test Equipment

10. SPP-6.5, Foreign Material Control

11. SPP-7.2, Outage Management

12. SPP-8. 1, Conduct of Testing

13. SPP-8.2, Surveillance Test Program

14. SPP-9.1, ASME Section XI

15. SPP-9.3, Plant Modifications and Design Change Control

16. SPP-9.7, Corrosion Control Program G. Standard Department Procedures

1. NADP-1, Conduct of Quality Assessment and Inspection

2. MMDP-11, Erection of Scaffolds/Temporary Work Platform and Ladders H. Inspection Services Organization Program Manuals - ISOPM I. Periodic Instructions

1. 0-PI-DXI-000-116.1, ASME Section XI IWE/IWL Containment Inservice Inspection Program (CISI) Unit 1 and Unit 2

SQN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT I and UNIT 2 Rev. 0000 Page 17 of 66 2.6 DRAWINGS A. ISI Drawings (See Attachment 7)

El. Risk ISI segment Boundary Drawings (See Attachment 7) 2.7 REFERENCE DOCUMENTS A. ASME Boiler and Pressure Vessel Code, Section Xi, Division 1, 1989 Edition.

B. ASME Boiler and Pressure Vessel Code, Section Xl, Division 1, 199'5 Edition.

C. ASME Boiler and Pressure Vessel Code, Section Xl, Division 1, 1998 Edition.

D. ASME Boiler and Pressure Vessel Code, Section Xl, Division 1, 2001 Edition E. ASME Boiler and Pressure Vessel Code, Section Xl, Division 1, 2001 Edition, 2003 Addenda.

F. ASME Section XI Code Cases as listed in section 1.3.

G. Design Change Notice Drawing Deviation F-07706-A (B85 911107 124). Referenced in section 5.0 of Attachments 10 and 11.

H. Incident Investigation (llj No. Il-S-92-027. Referenced in section 1.CI and 6.0 of Attachments 10 and 11.

1. TVA Calculation SQN-SQTP-001, ASME Section Xl Inservice Code Class Boundaries for Second 10 year Interval.

J. Memorandum from J. F. Murdock to J. B. Hosmer, dated June 3, 1988 (L29 880531 914). Referenced in section 5.0 of Attachments 10 and 11.

K. Memorandum from R. W. Fortenberry to S. J. Smith, dated July 21, 1988 (S57 880721 821). Referenced in section 5.0 of Attachments 10 and 11.

L. Memorandum from P. G. Trudel to S. J. Smith, dated August 19,1988 (825 880819 014). Referenced in section 6.0 of Attachments 10 and 11.

M. Memorandum from M. J. Ray to NRC, dated August 24, 1988 (L44 880824 802). Referenced in section 6.0 of Attachments 10 and 11.

N. Memorandum from L.E. Martin to P.G. Trudel, dated August 30, 198,3 (S08 880830 843). Referenced in section 6.0 of Attachments 10 and 11.

0. Memorandum from P. G. Trudel to M. J. Ray, dated September 6, 1988 (B29 880906 008). Referenced in section 6.0 of Attachments 10 and 11.

SON ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 11& 2 UNIT I and UNIT 2 Rev. 0000

. Page 18 of 66 2.7 REFERENCE DOCUMENTS (continued)

P. Memorandum from P. G. Trudel to M. J. Burzynski, dated February 27, 1989 (B25 890227 002). Referenced in section 5.0 of Attachments 10 and 1.

Q. Memorandum from P.G. Trudel to M.J. Burzynski, dated April 20, 1990 (B25 900420 008). Referenced in section 5.0 of Attachment 10.

R. Memorandum from B.J. Garry, Westinghouse, to P.G. Trudel, dated July 2, 1991 (825 910709 008). Referenced in section 5.3 of Attachment 1 S. Memorandum from J. E. Staub to G.L. Wade, dated November 29,1993 (B25 931129 001). Referenced in section 6.0 of Attachments 10 and 11.

T. Memorandum from David E. Labarge, NRC to O.D. Kingsley Jr., dated March 15,1994 (L44 940322 006). Referenced in section 3.0 of Attachments 10 and 11.

U. Memorandum from G. Bair to G. Wade dated January 23, 1996 (S57 960208 934). Referenced in section 5.0 of Attachment 10 and 11.

V. Augmented Nondestructive Examination Form, dated July 2,1996 (1339 960703 001). Referenced in section 7.0 of Attachment 11.

W. Augmented Nondestructive Examination Form, dated October 24, 1996 (B38 961024 800). Referenced in section 8.0 of Attachment 10.

X. Augmented Nondestructive Examination Form, dated March 1, 2000 (B39 000305 001). Referenced in section 9.0 of Attachment 10.

Y. Augmented Nondestructive Examination Form, dated March 5, 2000 (B39 000306 001). Referenced in section 10.0 of Attachment 10.

Z. Augmented Nondestructive Examination Form, dated March 16, 2000 (B39 000316 001). Referenced in section 8.0 of Attachment 11.

AA. Augmented Nondestructive Examination Form, dated January 10, 20)01 (B39 010111 001). Referenced in section 9.0 of Attachment 10.

BB. Augmented Nondestructive Examination Form, dated January 10, 2001 (B39 010111 002). Referenced in sections 8.0 and 9.0 of Attachment 11.

CC. Augmented Nondestructive Examination Form, dated February 28, 2001 (B39 010228 001). Referenced in section 10.0 of Attachment I0.

DD. Augmented Nondestructive Examination Form, dated February 28, 2001 (839 010228 002). Referenced in section 10.0 of Attachment l 1.

SCIN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit l & 2 UNIT I and UNIT 2 Rev. 0000 Page 19 of 66 2.7 REFERENCE DOCUMENTS (continued)

EE. WCAP-14572, Revision 1-NP-A, "Westinghouse Owners Group Application of Risk-informed Methods to Piping Inservice Inspection Topical Report," February 1999 and WCAP-1 4572, Revision 1-NP-A, Supplement 1, "Westinghouse Structural Reliability and Risk Assessment (SRRA) Model for Piping Risk-Informed Inservice inspection," February 1999. (EDMS Item IDs 991380788, 99146022.4 and 003765126)

FF. Risk Informed-ISI Weld Selection Process for Sequoyah Nuclear Pla-it Units 1 & 2, Revision 0 (B44 001220 001), Revision 1 (B44 010906 001),Revision 2 (S57 021212 800) and Revision 3 (S57 06323 801).

RI-ISI Engineering Panel Weld Substitution for Unit 2 Pipe Segment CH-033, dated November 16, 2003 (B25 03117 002).

GG. Memorandum from John Irons, Westinghouse, to Ken Mogg, dated May 8, 2000 (B44 000509 001).

HH. Memorandum from C.W. Whitehead to John Irons, Westinghouse, dated May 2, 2000 (B44 000509 001) which includes SQN Nuclear Plant Units 1 & 2 Risk Informed Inservice Inspection (RI-ISI) Program Scope, Revision 1, April 19, 2000 document.

II. Memorandum from John Irons, Westinghouse, to Ken Mogg, "Tennessee Valley Authority Watts Bar and Sequoyah Nuclear Plants, Risk-Informed ISI Project Closeout", dated November 13, 2001, (B4Z.

011127 001).

JJ. Telephone Call and Visit Report, Subject -Clarification of Nozzle Exam Area for Unit 1, dated January 26, 1994, (S57 020401 800).

Referenced in section 3.0 of Attachment 10.

KK. Problem Evaluation Report 02-004487-000. Referenced in section 12.0 of Attachment 11.

LL. Augmented Nondestructive Examination Forms, dated June 27, 2002 (B38 020627 800) and June 23, 2003 (B38 030623 802). Referenced in section 12.0 of Attachments 10 and 11.

MM. Memorandum from R. T. Purcell to NRC " Sequoyah Nuclear Plant (SQN) Units 1 and 2 - Response to NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, dated March 18, 2002" dated April 2, 2002 (S64 020402 801). Referenced in section 12.0 of Attachments 10 and 11.

NN. Augmented Nondestructive Examination Form, dated July 10, 2002 (B38 020710 802). Referenced in section 8.0 of Attachment 10 and section 11.0 of Attachment 11.

00. Memorandum from Jeff Goulart to Gary N. Buchanan dated October 16, 2001 (S57 011016 800). Referenced in section 8.0 of Attachment 10 and section 11.0 of Attachment 11.

SON ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 1 & 2 UNIT I and UNIT 2 Rev. 0000 Page 20 of 66 2.7 REFERENCE DOCUMENTS (continued)

PP. Augmented Nondestructive Examination Form, dated November 26, 2002 (S57 021126 800). Referenced in section 13.0 of Attachments 10 and 11.

QQ. Email from Debbie Jackson, NRC to G.L. Belew "Use of Annulled/Revised Code Cases" dated June 24, 1999 (L18 030114 8()0)

RR. Memorandum from Westinghouse Owners Group Risk-Informed Inservice Inspection Subgroup to R.K. Alexander, TVA, " Risk-informed In-Service Inspection (RI-ISI) Implementation Subgroup Request for Interpretation of WCAP-14572, Revision 1;-NP-A from TVA (MUHP-7223) WOG RI-ISI IN 01-01" dated December 19, 2001, (B4.4 020118 007). Referenced in section 7.12.10.

SS. Augmented Nondestructive Examination Form, dated June 23, 2003 (B38 030623 801). Referenced in section 14.0 of Attachments 10 and 11.

TT. Augmented Nondestructive Examination Form, dated May 26, 2003, (B39 030529 001). Referenced in section 15.0 of Attachments 10 and 11.

UU. Memorandum from Jeff Goulart to Gary Buchanan "RI-ISI Periodic Update Review Information for the Third Period of the second ASME Section Xl interval", dated November 14, 2002, (S57 021115 800).

Referenced in section 7.12.5 W. Letter from Nuclear Energy Institute (NEI) to NEI Administrative Points of Contact, "NRC Meeting on PWR Reactor Pressure Vessel Head Inspection Order", dated February 25, 2003. Referenced in section 12 of Attachments 10 and 11.

WW. Memorandum from Civil Engineering to Component Engineering, "SQN UI: Cancel Augmented Examination of Steam Generator Class 2 Upper Support", dated July 8, 2003, (839 030708 001). Referenced in section 10.0 of Attachment 10.

XX. Memorandum from Civil Engineering to Component Engineering, "SON U1 andU2: Cancel Augmented Examination of Reactor Coolant Pump Supports", dated July 10, 2003, (B39 030710 001). Referenced in section 9.0 of Attachment 10 and section 8.0 of Attachment 11.

YY. NRC internal letter to Cynthia D. Pederson, from Ledyard B. Marsh, dated May 27, 2003 (NRC database ADAMS Accession No. ML030310355). Referenced in section 7.4.2 and 7.4.2E.

ZZ. Memorandum from D.L. Lundy to K.M.Rajan, Westinghouse, dated October 29, 2003 (B38 031029 801) "Sequoyah Nuclear Plant Units 1 and 2 -Nuclear Steam Supply System Engineering Support Services - Contract 99NAN-251787 - Letter N10095". Referenced in section 15.0 of Attachment 10.

SON ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 21 of 66 2.7 REFERENCE DOCUMENTS (continued)

AAA. Memorandum from D.L. Lundy to K.M.Rajan, Westinghouse, dated October 29, 2003 (838 031029 802) "Sequoyah Nuclear Plant Units 1 and 2 -Nuclear Steam Supply System Engineering Support Services - Contract 99NAN-251787 - Letter N10096". Referenced in section 15.0 of Attachments 10 and 11.

BBB. Augmented Nondestructive Examination Form, dated October 31, 2003 (838 031031 800). Referenced in section 16.0 of Attachments 10 and 11.

CCC. TVAN Engineering Bulletin, "Position on Examination Limitations as Related to the Risk Informed - Inservice Inspection (RI-ISI) Programs",

dated November 14, 2003 (B45 031114 001). Referenced in section 7.12.10.

DDD. Augmented Nondestructive Examination Form, dated November 14, 2003 (B38 031114 001). Referenced in section 15.0 of Attachment I11.

EEE. Augmented Nondestructive Examination Form, dated March 18, 2004 (838 040318 808). Referenced in section 14.0 of Attachments 10 and 11.

FFF. Augmented Nondestructive Examination Form, dated March 22, 2004 (B38 040322 801). Referenced in section 5.0 of Attachments 10 and 11.

GGG. Augmented Nondestructive Examination Form, dated July 8, 2004 (B38 040708 800). Referenced in section 12.0 of Attachments 10 and 11.

HHH. Augmented Nondestructive Examination Form, dated July 19, 2004 (838 040719 800). Referenced in section 14.0 of Attachments 10 and 11.

Ill. Augmented Nondestructive Examination Form, dated August 17, 200)4 (838 040817 800). Referenced in section 12.0 of Attachments 10 and 11.

JJJ. Augmented Nondestructive Examination Form, dated December 6, 2004 (B38 041206 800). Referenced in section 8.0 of Attachment 10).

KKK. Augmented Nondestructive Examination Form, dated April 12, 2005 -

(B38 050412 800). Referenced in section 3.0 of Attachment 11.

LLL. Memorandum from Robert J. Pascarelli, NRC to Karl W. Singer, dated October 6, 2004, "Sequoyah Nuclear Plant, Unit 2 - Response to NRC Bulletin 2003-02, Leakage From Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity (TAC NO. MC0565)" (L44 041019 008). Referenced in sectionl6.0.of Attachment 11.

SCIN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit l &2 UNIT 1 and UNIT 2 Rev. 0000 Page 22 of 66 2.7 REFERENCE DOCUMENTS (continued)

MMM. Memorandum from Douglas Pickett, NRC to Karl W. Singer, dated September 20, 2005, "Sequoyah Nuclear Plant, Unit 1 - Response to NRC Bulletin 2003-02, Leakage From Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity (TAC NO. MC0564)" (L44 050928 092). Referenced in section16.0 of Attachment 10.

NNN. Augmented Nondestructive Examination Form, dated December 9, 2005 (B38 051209 800). Referenced in section 14.0 of Attachments 10.

and 11.

000. Augmented Nondestructive Examination Form, dated March 7, 2006 (S57 060307 800). Referenced in section 13.0 of Attachments 10 arid 11.

2.8 CALCULATIONS A. SQN-MEB-MDN0999-000085, "RI-ISI Piping Segment/Direct Consequence Definition."

[3. SQN-MEB-MDQ0999-990055, "TVA RI-ISI Piping Indirect Consequence Evaluation for Sequoyah Units 1 and 2."

C. SQN-MEB-MDN0999-990077, "RI-ISI PRA Consequence Evaluation."

D[. SQN-CEB-CDNO003-000013, "RI-ISI Structural Reliability and Risk Assessment (SRRA) of the Auxiliary Feedwater System."

E. SQN-CEB-CDNO015-000014, "Rl-ISI Structural Reliability and Risk Assessment (SRRA) of the Steam Generator Blowdown System."

F:. SQN-CEB-CDNO062-000023, "RI-ISI Structural Reliability and Risk Assessment (SRRA) of the Chemical and Volume Control System and Flood Mode Boration System."

(,. SQN-CEB-CDN0999-000016, "RI-ISI Structural Reliability and Risk Assessment (SRRA) of the Containment Isolation System."'

H. SQN-CEB-CDNO072-000028, "RI-ISI Structural Reliability and Risk Assessment (SRRA) of the Containment Spray System."

I. SQN-CEB-CDNO003-000012, "Rl-ISI Structural Reliability and Risk Assessment (SRRA) of the Feedwater System."

J. SQN-CEB-CDNO001 -00001 0, "RI-ISI Structural Reliability and Risk Assessment (SRRA) of the Main Steam System."

SQN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit l & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 23 of 66 2.8 CALCULATIONS (continued)

K. SQN-CEB-CDNO068-000026, "RI-ISI Structural Reliability and Risk Assessment (SRRA) of the Reactor Coolant System."

L.. SQN-CEB-CDNO074-000029, "RI-ISI Structural Reliability and Risk Assessment (SRRA) of the Residual Heat Removal System."

M. SQN-CEB-CDNO063-000024, "Rl-ISI Structural Reliability and Risk Assessment (SRRA) of the Safety Injection System."

N. SQN-CEB-CDNO043-000019, "RI-ISI Structural Reliability and Risk Assessment (SRRA) of the Water Quality and Sampling System."

0. Westinghouse Calculation Note, CN-RRA-00-45, "TVA RI-ISI Risk Ranking Evaluation for Sequoyah Units I and 2."

P. Westinghouse Calculation Note, CN-RRA-00-54, "TVA RI-ISI Perdue Model Calculation for Sequoyah Unit 1."

C2. Westinghouse Calculation Note, CN-RRA-00-55, "TVA RI-ISI Perdue Model Calculation for Sequoyah Unit 2."

R. Westinghouse Calculation Note, CN-RRA-00-56, "TVA RI-ISI Expert Panel and RI-ISI Database for SQN 1/2."

'S. Westinghouse Calculation Note, CN-RRA-00-57, "TVA RI-ISI Delta Risk Evaluation for SQN 1/2."

2.9 ABBREVIATIONS AND DEFINITIONS

ALARA - As Low As Reasonably Achievable

ASNT - American Society for Nondestructive Testing

ASME - American Society of Mechanical Engineers

CFR - Code of Federal Regulations IEP -. Inspection and Examination Procedures ISI - Inservice Inspection

. NDE - Nondestructive Examination

NRC - Nuclear Regulatory Commission RADCON - Radiological Control

SCIN -

Unit l & 2 ASME SECTION XI ISI/NDE PROGRAM UNIT 1 and UNIT 2 0-SI-DXI-000-114.3 Rev. 0000 Page 24 of 66 i

2.9 ABBREVIATIONS AND DEFINITIONS (continued)

RFR - Request for Relief

RI-ISI - Risk Informed - Inservice Inspection

RWP - Radiation Work Permit

Si - Surveillance Instruction

SPP - Standard Programs and Processes

WRYWO - Work Request/Work Order

Components - Denotes items in a nuclear power plant such as a vessel, pump, valve, or piping system.

Normal Plant Operation - The conditions of startup, hot standby, operation within the normal power range, and cooldown and shutdown of the plant.

Normal Operating Conditions - The operating conditions during reactor startup, operation at power, hot standby, and reactor cooldown to cold shutdown conditions. Test conditions are excluded.

Pressure Retaining Material - Applies to items such as vessel heads, nozzles, pipes, tubes, fitting, valve bodies, bonnets, disks, pump casings, covers, and bolting which join pressure-retaining items.

Welded Attachment 'Attachment on the outside surface of the pressure retaining component, provides component support as defined in NF-1 100, and the attachment weld joins the attachment either directly to the surface of the component or to the integrally cast or forged attachment to the component..

SON ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 25 of 66 3.0 FPREREQUISITES AND PRECAUTIONS 3.1 PREREQUISITES A. When craft support of minor or similar maintenance (examples: scaffolding, insulation removal, buffing of welds, and cleaning bolts) is required to facilitate performance of this Si, a WRAA1O may be used. This WRIVO shall be processed in accordance with SPP-6.1.

Additional WRs are required to remove fire barrier insulation foam in sleeves, piping support clamps, steam generator insulation support rings, reactor coolant pump flywheel access covers and plugs, etc.

El. Contact RADCON for radiation work permit (RWP)/ALARA preplanning requirements.

C(. Controlled copies of American Society of Mechanical Engineers (ASME)

Section XI Code Classification Drawings and ISI Drawings are issued throgh Management Services.

3.2 PRECAUTIONS A. Safety belts should be worn when working from scaffolding or ladders in accordance with MMDP-1 1.

El. Protective clothing, such as long-sleeve shirts, should be worn when working around hot pipes and equipment.

C. Care should be exercised when climbing on plant structures and piping to ensure firm footing and to prevent damaging site equipment. Walking on flex hoses and insulation shall be avoided.

[). Efforts should be made to ensure proper planning to reduce delays and radiation exposure in performance of the work.

E. Read and observe all applicable precautions as indicated in SQN Surveillance Instruction 0-SI-OPS-000-01 1.0 "Containment Access Control During Modes 1-4," and SPP-6.5 "Foreign Material Control."

F. Standard Safety Practice as outlined in the TVA Health and Safety Manual shall be followed.

4.0 SPECIAL TOOLS AND EQUIPMENT Equipment shall be specified by individual NDE Procedures.

SCQN ASME SECTION Xl ISI/NDE PROGRAM O-SI-DXI-000-114.3 Unit I & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 26 of 66 .

5.0 ACCEPTANCE STANDARDS*

All acceptance standards for ASME Code Class 1,2 and 3 equivalent components and their supports shall be in accordance with IWA-3000, IWB-3000, IWC-3000, IWD-3000 or IWF-3000 of ASME Section Xl; Table 4.1-1 of WCAP-14572 for FI-ISI piping welds; and the Inspection Services Organization Programs Manuals.

Evaluations of examinations in accordance with IWB-3132.3, IWB- 3142.4, INC-3122.3, IWC-3132.3 or IWD-3640 shall be submitted to the regulatory authority having jurisdiction at the plant site. This information shall be submitted with the Inservice Inspection Summary Report or, if deemed necessary, a separate report shall be submitted.

6.0 QUALIFICATIONS OF NDE PERSONNEL Personnel performing NDE operations shall be qualified and certified in accordance with IEP-200 and IEP-300 as applicable. Contract personnel performing NDE operations shall be qualified and certified to a written practice approved by TVA.

7.0 IMPLEMENTATION AND RESPONSIBILITIES Any revisions to this program initiated bV other groups shall be submitted to Component Engineering for approval prior to incorporating the revisions into this program.

Responsibilities shall be in accordance with SPP-9. 1, Part A.

7.1 NDE EXAMINATIONS A. NDE methods shall be in accordance with IWA-2200 of ASME Section XI and this program as scheduled in Attachment 4 for Unit 1 and Attachment 5 for Unit 2.

B. NDE shall be performed in accordance with Inspection Services Organization Programs Manuals or approved contractor/vendor procedures.

C. In accordance with IWA-2600, a reference system shall be established for all welds and areas subject to surface or volumetric examination. Each such weld and area shall be located and identified by a system of reference points in accordance with applicable NDE procedures.

SCN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 1 & 2 UNIT I and UNIT 2 Rev. 0000 Page 27 of 66 7.1 1NDE EXAMINATIONS (continued)

[). When less than the required code examination volume or area is examined, the percentage examined shall be documented on the examination data sheet.

The cause of the limitation shall be clearly specified as a part of the data sheet documentation. The examination with less than the required ASME Section Xl Code examination volume or area shall be handled as a request for relief ;n accordance with SPP-9.1, Part A.

7.2 COMPONENTS SUBJECT TO EXAMINATION A. ASME CLASS 1 EQUIVALENT COMPONENTS SUBJECT TO EXAMINATION (IWB)

1. ASME Class 1 equivalent systems (including the components contained therein, but excluding supports) subject to examination per Unit are:

Chemical and Volume Control System Reactor Coolant System Reactor Coolant System Main Loop Reactor Coolant Pumps (4)

Reactor Vessel Pressurizer Steam Generators (4)

ResiduaI Heat Removal System Safety Injection System RI-ISI program includes (Chemical and Volume Control System, Reaztor Coolant System, Reactor Coolant System Main Loop, Residual Heat Removal System, Safety Injection System, and Sampling and Water Quality System)

SCIN ASME SECTION Xl ISIINDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT 1 and UNIT 2 Rev. 0000

. .Page 28 of 66 7.2 COMPONENTS SUBJECT TO EXAMINATION (continued)

2. Components (except for piping welds) are scheduled for examination in accordance with ASME Section XI, Table IWB-2500-1. Piping welds are scheduled for examination in accordance with WCAP-14572, Table 4.1-1.

The specific components subject to examination are described in Attachment 1 and identified on drawings listed in Attachment 7, ISI Drawings List. The number of components within each system, the number selected for examination during the inspection interval and the number selected for examination by period are provided in Tables A and E of Attachment 4 for Unit 1 and in Tables A and E of Attachment 5 for Unit 2. ASME Class 1 valves are further defined in Attachment 6 for UJnit 1 and Unit 2.

3. Exemptions using the rules of IWB-1220.

a. The rules of IWB-1220 (a),(b), (c) and (d) have been used to exempt components (except for piping per 10CFR50.55a(b)(2)(xi)) from examination and establish the numbers in Table A, of Attachment 4 for Unit 1 and Table A of Attachment 5 for Unit 2. Components (except piping) exempted from examination include:

(1) 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 systems that are operable from on-site emergency power. The emergency core cooling systems are excluded from the calculation of makeup capacity.

(2) Piping of NPS 1 and smaller, except for steam generator tubing (3) Components and their connections in piping of NPS 1 and smaller NOTE In piping is defined as having a cumulative inlet and a cumulative outlet pipe cross-sectional area neither of which exceeds the normal outside diameter cross sectional area of the designated size.

(4) Reactor vessel head connections and associated piping, NPS 2 and smaller, made inaccessible by control rod drive penetrations; (5) Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe.

SCIN ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT I and UNIT 2 Rev. 0000 Page 29 of 66 7.2 COMPONENTS SUBJECT TO EXAMINATION (continued)

b. Piping welds are selected for examination in accordance with RI-ISI program in section 7.12 and no exemptions criteria is utilized.

Therefore, the exemption criteria of IWB-1220 of ASME Section Xl 1989 Edition per 10CFR50.55a(b)(2)(xi) will utilized for piping to determine examination selections for Examination Categories B-G-1, B-G-2, B-K and F-A.

(1) 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 systems that are operable from on-site emergency power. The emergency core cooling systems are excluded from the calculation of makeup capacity.

(2) Piping of NPS I and smaller, except for steam generator tubing (3) Components and their connections in piping of NPS 1 and smaller NOTE In piping is defined as having a cumulative inlet and a cumulative outlet pipe cross-sectional area neither of which exceeds the normal outside diameter cross sectional area of the designated size.

4. Examination Category B-A, B-B, B-D, B-G-1, B-G-2, B-K, B-L-1, B-M-1, B-L-2, B-M-2, B-N-1, B-N-2, B-N-3 and B-O components shall be selected for examination in accordance with 2001 Edition, 2003 Addenda of ASME Section Xl.

5. Examination Categories B-F and B-J for the third inspection interval, shall be in accordance with the RI-ISI examination requirements outlined in section 7.12 of this Program.

6. The entire length of each weld selected shall be examined, unless otherwise noted or if a physical limitation exists.

7. ASME Class 1 equivalent component supports shall be selected for examination in accordance with ASME Section Xl Subsection IWF. See section 7.2D.

SON ASME SECTION Xl ISl/NDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT 1 and UNIT 2 Rev. 0000 Paqe 30 of 66 7.2 COMPONENTS SUBJECT TO EXAMINATION (continued)

8. Welded support attachment' examination is also required whenever component support member deformation (e.g., broken, bent, or pulled out parts) is identified during operation, refueling, maintenance, examinat on, inservice inspection, or testing.

B. ASME CLASS 2 EQUIVALENT.COMPONENTS SUBJECT TO EXAMINATION (IWC)

1. ASME Class 2 equivalent systems (including the components contained --

therein, but excluding supports) subject to examination per Unit are:

Containment Spray System Containment Spray Heat Exchangers (2)

Containment Spray Pumps (2)

Feedwater System High Pressure Safety Injection System (includes Safety Injection Residual Heat Removal, Containment Spray, and Chemical Volume Control)

Centrifugal Charging Pump (CCP) Tank [Boron Injection Tank (BIT)](-I)

CVCS Centrifugal Charging Pumps (2)

Safety Injection Pumps (2)

Seal Water Filter Seal Water Heat Exchanger Seal Water Injection Filters (2)

Main Steam System Residual Heat Removal System RHR Heat Exchangers (2)

RHR Pumps (2)

Safety Injection System Steam Generators Secondary Side (4)

SCIN ASME SECTION Xl ISIYNDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT I and UNIT 2 Rev. 0000 Page 31 of 66 7.2 COMPONENTS SUBJECT TO EXAMINATION (continued)

RI-ISI program includes (Auxiliary Feedwater System, Steam Generator Blowdown System, Chemical Volume Control System, Containment Isolation System, Containment Spray System, Feedwater System, Main Steam System, Reactor Coolant System, Residual Heat Removal System, Safety Injection System, and Sampling and Water Quality System)

2. Components (except for piping welds ) are scheduled for examination in accordance with ASME Section Xi, Table IWC-2500-1. Piping welds are scheduled for examination in accordance with WCAP-1 4572, Table 4. 1-1.

The specific components subject to examination are described in Attachment 2 and identified on drawings listed in Attachment 7, ISI Drawings List. The number of components within each system, the number selected for examination during the inspection interval and the number selected for examination by period are provided in Tables B and E of Attachment 4 for Unit I and in Tables B and E of Attachment 5 Unit:2.

3. The rules of IWC-1221 and IWC-1222 have been used to exempt components (except for piping welds) from examination and establish the numbers in Table B of Attachment 4 for Unit 1, and in Table B of Attachment 5 for Unit 2.

4. Piping welds are selected for examination in accordance with RI-ISI program in section 7.12 and no exemption criteria is utilized. Therefore, the exemption criteria of IWC-1221 and IWC-1222 will be utilized for piping to determine selections for Examination Category C-C.

- 5. Examination Category C-A, C-B, C-C, C-D, and C-G components shell be selected for examination in accordance with Table IWC-2500-1.

6. Examination Category C-F-1 and C-F-2 shall be in accordance with the RI-ISI examination requirements outlined in section 7.12 of this Program.

7. ASME Class 2 equivalent component supports shall be selected for examination in accordance with ASME Section Xl Subsection IWF. See section 7.2D.

8. Welded support attachments examination is also required whenever component support member deformation (e.g., broken, bent, or pulled out parts) is identified during operation, refueling, maintenance, examination, inservice inspection, or testing.

9. Where examinations specify a percentage of the total length of weld to be examined, the areas(s) examined shall be documented in the examination report. Where a percentage of weld length is NOT referenced, the entire weld length shall be examined.

SON ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 11& 2 UNIT 1 and UNIT 2 Rev. 0000 Page 32 of 66 7.2 COMPONENTS SUBJECT TO EXAMINATION (continued)

C:. ASME CLASS 3 EQUIVALENT COMPONENTS SUBJECT TO EXAMINATION (IWD)

1. ASME Class 3 equivalent systems (including the components contained therein, but excluding supports) subject to examination per Unit are:

Auxiliary Feedwater System Turbine Driven Auxiliary-Feedwater Pump (1) Support -TDAFP (AFW)

Motor Driven Auxiliary Feedwater Pump (2) Support -MDAFP (AFW)

Component Cooling System Component Cooling Surge Tank (1) Support - CCST (CCS)

Component Cooling System Water Pumps Unit 1(3), Unit 2(2) Support

-CCSWP (CCS)

Component Cooling Heat Exchanger (2) Support - CCHX (CCS)

Gas Stripper and Boric Acid Evaporator GSBAE Evaporator Condenser (1) Support -EC (CCS)

GSBAE Distillate Cooler (1) Support - DC (CCS)

GSBAE Support Frame (1) - SF (CCS)

Nonregenerative Letdown Heat Exchanger (1) Support -NRLHX (CC';)

RHR Heat Exchanger Secondary Side (2) Supports -RHRHSXH (CCS)

Essential Raw Cooling Water System Essential Raw Cooling Water System Strainer (2) Support - ERCWS (ERCW)

Essential Raw Cooling Water System Pump Station Pump Supports (included in Unit 1 only)

Essential Raw cooling Water Screen Wash Pump Support (included in Unit 1 only)

Old ERCW Pumping Station Strainer Containment Spray Heat Exchanger (2) Support - CSH (ERCW)

SCQN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit "I& 2 UNIT I and UNIT 2 Rev. 0000 XPage 33 of 66 7.2 COMPONENTS SUBJECT TO EXAMINATION (continued)

Fuel Pool Cooling System (included in Unit 1 only)

Fuel Pool Cooling And Cleaning System - Spent Fuel Pit Pump Support (included in Unit 1 only)

Fuel Pool Cooling And Cleaning System - Spent Fuel Pit Heat Exchanger Support (included in Unit 1 only)

Air Conditioning Chilled Water System - (ACCW)

Shutdown Board Room Water Chiller Chilled Water Circulation Pump Chilled Water Air Separator

2. The specific welded support attachments subject to examination are described in Attachment 3 and identified on drawings listed in Attachment 7, ISI Drawings. The number of welded support attachments within each system, the number selected for examination during the inspection interval and the number selected for examination by period are provided in Table C of Attachment 4 for Unit 1 and in Table C of Attachment 5 for Unit 2.

3. Welded support attachment examination is also required whenever component support member deformation (e.g., broken, bent, or pulled out parts) is identified during operation, refueling, maintenance, examination, inservice inspection, or testing.

4. The rules of IWD-1220 have been used to exempt components from examination and establish the numbers in Table C of Attachment 4 for Unit 1, and in Table C of Attachment 5 for Unit 2.

5. Examination category D-A components shall be selected for examination in accordance with Table IWD-2500-1.

6. ASME Class 3 equivalent component supports shall be selected for examination in accordance with ASME Section Xl Subsection IWF. See section 7.2D.

[). COMPONENT SUPPORTS SUBJECT TO EXAMINATION (IWF)

ASME Class 1, 2, and 3 equivalent systems including the components supports subject to examination per unit:

1. ASME Class 1 equivalent supports subject to examination per Unit are:

7.2

)QN Uni!t 1 & 2 ASME SECTION Xi ISI/NDE PROGRAM UNIT I and UNIT 2 COMPONENTS SUBJECT TO EXAMINATION (continued) 0-SI-DXI-000-114.3 Rev. 0000 Page 34 of 66 I Chemical and Volume Control System Reactor Coolant System Reactor Coolant System Main Loop Reactor Coolant Pumps (4)

Reactor Vessel Pressurizer Steam Generators (4)

Residual Heat Removal System Safety Injection System

2. ASME Class 2 equivalent supports subject to examination per Unit are:

Containment Spray System Containment Spray Heat Exchangers (2)

Containment Spray Pumps (2)

Feedwater System High Pressure Safety Injection System (includes Safety Injection, Residual Heat Removal, Containment Spray, and Chemical Volume Control)

Centrifugal Charging Pump (CCP) Tank/(Boron Injection Tank (BIT)) (One)

CVCS Centrifugal Charging Pumps (2)

Safety Injection Pumps (2)

Seal Water Filter Seal Water Heat Exchanger Seal Water Injection Filters (2)

Main Steam System Residual Heat Removal System RHR Heat Exchangers (2)

SON ASME SECTION XI ISI/NDE PROGRAM O-SI-DXI-000-114.3 Unit 1 & 2 UNIT I and UNIT 2 Rev. 0000 Page 35 of 66 7.2 COMPONENTS SUBJECT TO EXAMINATION (continued)

RHR Pumps (2)

Safety Injection System Steam Generators (4)

3. ASME Class 3 equivalent supports subject to examination are:

Auxiliary Feedwater System Turbine Driven Auxiliary Feedwater Pump (1) Support -TDAFP (AFWM Motor Driven Auxiliary Feedwater Pump (2) Support -MDAFP (AFW)

Chemical and Volume Control System Component Cooling System Component Cooling Surge Tank (1) Support - CCST (CCS)

Component Cooling System Water Pumps Unit 1(3), Unit 2(2) Suppoit

-CCSWP (CCS)

Component Cooling Heat Exchanger (2) Support - CCHX (CCS)

Gas Stripper and Boric Acid Evaporator GSBAE Evaporator Condenser (1) Support -EC GSBAE Distillate Cooler (1) Support - DC (CCS)

GSBAE Support Frame (1) - SF (PCS)

Nonregenerative Letdown Heat Exchanger (1) Support -NRLHX (CCS)

RHR Heat Exchanger Secondary Side (2) Supports -RHRHSXH (CC:i)

Essential Raw Cooling Water System Essential Raw Cooling Water System Strainer (2) Support

-ERCWS (ERCW)

Essential Raw Cooling Water System Pump Station Pump Supports (included in Unit 1 only)

Essential Raw cooling Water Screen Wash Pump Support (included in Unit 1 only)

SCQN ASME SECTION XI ISIUNDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 36 of 66 7.2 COMPONENTS SUBJECT TO EXAMINATION (continued)

Old ERCW Pumping Intake Station Strainer Containment Spray Heat Exchanger (2) Support - CSH (ERCW)

Fuel Pool Cooling System (included in Unit 1 only)

Fuel Pool Cooling And Cleaning System - Spent Fuel Pit Pumps (included in Unit 1 only)

Fuel Pool Cooling And Cleaning System - Spent Fuel Pit Heat Exchanger (included in Unit 1 only)

Air Conditioning Chilled Water System - (ACCW)

Shutdown Board Room Water Chiller Chilled Water Circulation Pump Chilled Water Air Separator

4. Component supports exempt from NDE examinations are those connected to piping or other items exempted from volumetric, surface or VT-1 o. VT-3 visual examination by IWB-1220, IWC-1220, and IWD-1220, and portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe.

5. Component supports shall be examined in accordance with Table IWF-2500-1. Component supports to be examined shall be the supports of components NOT exempted in accordance with section 7.2D.4.

These component and piping supports are within the systems identified in sections 7.2D.1, 7.2D.2, and 7.2D.3. The specific supports subject tc examination are identified on ISI Drawings listed in Attachment 7 and described in Attachments 1, 2, and 3.

6. Supports depicted as snubbers on the support drawings are subject to examination up to and including the snubber pins in accordance with IWF-5300(c). The snubber is outside the examination boundary. The examination/testing of snubbers are covered by the Snubber Inservica Testing Program. Refer to section 7.8 for snubber request for relief.

7. The number of supports subject to an examination sample plan, the number selected for examination during the inspection interval and the number selected for examination by period are provided in Table D of Attachment 4 for Unit 1, and in Table D of Attachment 5 for Unit 2.

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8. Support examination boundaries shall be in accordance with IWF-1 300.

When determining equipment support boundaries, consideration is to be given to include miscellaneous steel for each equipment support.

Acceptance range for support settings shall be calculated in accordance with Inspection Services Organization Programs Manuals (Refer to Nondestructive Examination Procedure N-GP-7).

9. Component supports that have been adjusted in accordance with IWF-3000 or corrected by repair or replacement shall be preservice examined prior to return of the system to service per the applicable examinations listed in Table IWF-2500-1.

Also for systems that operate above 200 degrees F during normal operation, an additional preservice examination shall be performed on the affected component supports during or following the subsequent system heat-up and cool-down cycle unless determined unnecessary by evaluation. This examination shall be performed during operation or at the next refueling outage. Component supports requiring an additional preservice examination shall be scheduled for examination (see Attachment 8 for Unit I and Attachment 9 for Unit 2).

10. Component Support Functions Piping support function is determined by using the latest analysis drawing with change paper for piping. If the piping doesn't have an associated analysis drawing, the latest support drawing with change paper will be used to determine support function.

a. Support Function A - Supports such as a one-directional restraints.

b. Support Function B - Supports such as a multidirectional restraints.

c. Support Function C - Supports that allow thermal movement, such as variable and constant force springs.

d. Support Function D - Supports where a load is transmitted through a hydraulic fluid or mechanical components (i.e., hydraulic or mechanical snubbers).

Equipment support function is determined by type of equipment (i.e., pump, heat exchanger, vessel, filter, valve, tank, cooler). The following is a listing of equipment support functions:

El- heat exchanger multidirectional support E2- heat exchanger variable support

SQN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT 1 and UNIT 2 Rev. 0000

-- Page 38 of 66 7.2 COMPONENTS SUBJECT TO EXAMINATION (continued)

E3- pump multidirectional support E4- reactor vessel one direction support E5- pressurizer multidirectional support E6- filter/strainer multidirectional support E7- cooler/chiller/evaporator/separator multidirectional support E8- tank multidirectional support E9- valve variable support 7.3 NOTIFICATION OF INDICATION Whenever an unacceptable inservice examination indication is discovered, during tie performance of scheduled ISI examinations a notification of indication (NOI) shall be initiated in accordance with SPP-9.1, Part A. The NOI is to be used to:

A. Notify Plant Management of unacceptable indications found during the performance of scheduled ASME Section Xl inservice examinations that will require evaluation and a disposition in accordance with plant procedures.

B. Notify Component Engineering Representative of indications that exceed the acceptance criteria of Article 3000 of the ASME Section Xl Code and that the indications have been documented on an examination report form contained within the NDE procedure used for examination.

C. Provide ISO and Component Engineering Representative with a method to track examination reports that require reexamination or a documented disposition for closure.

[). *As a final product, with the disposition provided in accordance with plant procedures added to Part II of the NOI Form; to provide the Component Engineering Representative a method of determining if additional and/or successive examinations are required in accordance with the Code.

SQN ASME SECTION XI ISIINDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT I and UNIT 2 Rev. 0000 Page 39 of 66 7.4 ADDITIONAL EXAMINATIONS AND SUCCESSIVE EXAMINATIONS FOR ASME CODE CLASS 1, 2 AND 3 Additional examinations and successive examinations for ASME Code Class 1. 2 and 3 are determined in accordance with the following.

NOTE Code Case N-586 may be used as an alternative to additional examination requirements of ASME Section XI, provided the engineering evaluations addressed under Item (a) of the code case and the additional examinations addressed under Item (b) of the code case shall be performed during this outage. If the additional examinations performed under item (b) of the code case reveal indications exceeding the applicable acceptance criteria of Section XI, the engineering evaluations and the examinations shall be further extended to included additional evaluations and examinations at this outage.

7.4.1 Additional Examinations For ASME Code Class 1, 2, And 3 After an NOI has been dispositioned and returned to the Component Engineering Representative, the NOI shall be evaluated to determine if additional examinations shall be required in accordance with ASME Section Xl IWB-2430, IWC-2430, IWD-2430 or IWF-2430. If it is determined that additional examinations are required, these examinations shall be performed during the same outage as the initial examinations.

NOTE Note: Class 1 and 2 piping welds for the third inspection interval shall be in accordance with the RI-ISI additional examination requirements as outlined in section 7.12.

A. Additional Examinations for Class I Equivalent Components (IWB)

Additional examinations for Class 1 equivalent components (IWB) except component supports shall be in accordance with the requirements of IWB-2430.

NOTE Class 1 Piping Welds for the third inspection interval shall be in accordance with the F1l-ISI additional examination requirements as outlined in section 7.12.

The initial sample is the sample scheduled for examination at a particular outage for ASME Section Xl credit.

SON Unit 'I & 2 ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 UNIT I and UNIT 2 Rev. 0000 Page 40 of 66I I

7.4.1 Additional Examinations For ASME Code Class 1, 2, And 3 (continued)

1. Examinations performed in accordance with Table IWB-2500-1, except for Examination Category B-P, of the initial sample that reveal flaws or relevant conditions exceeding the acceptance standards of Table IWB-341 0-1 shall be extended to include additional examinations except for volumetric and surface examinations where IWB-3112(b) is applicable.

(Such as, flaws detected by volumetric or surface examinations that meet the nondestructive examination standards of NB-2500 and NB-5300, as documented in QA records, shall be acceptable).

2. The first additional examination sample shall include an additional number of welds, areas, or parts included in the inspection item equal to the number of welds, areas, or parts included in the inspection item that were scheduled to be performed during the present inspection period. The additional examinations shall be selected from welds, areas, or parts of similar material and service. This additional selection may require inclusion of piping systems other than the one containing the flaws or relevant conditions.

NOTES

1) Welds, areas, or parts are those described or intended in a particular inspection item of Table IWB-2500-1.

2) An inspection item, as listed in Table IWB-2500-1, may comprise a number of welds, areas, or parts of a component required to be examined in accordance with the inspection plan and schedule (IWA-2420).

3. If the first additional examinations of section 7.4.1A.2 reveal flaws or relevant conditions exceeding the acceptance standards of Table IWB-3410-1, except where IWB-3112(b) is applicable, the examinations shall be further extended to include additional examinations during the current outage. The second additional examination sample shall include the remaining number of welds, areas, or parts of similar material and service subject to the same type of flaws or relevant conditions.

4. If examinations performed in the second additional examination sample reveal indications exceeding the acceptance standards of Table IWB-341 0-1, the indications shall be evaluated for further action, if needed.

5. For the inspection period following the period in which the examinations of IWB-2430(a) or (b) were completed, the examinations shall be performed as originally scheduled in accordance with IWB-2400.

SON ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 1 & 2 UNIT I and UNIT 2 Rev. 0000

. Page 41 of 66 7.4.1 Additional Examinations For ASME Code Class 1, 2, And 3 (continued)

6. If welded attachments are examined as a result of identified component support deformation and the results of these examinations exceed the acceptance standards of Table IWB-341 0-1, additional examinations shall be performed, if determined necessary, based on an evaluation by Engineering.

B. Additional Examinations for Class 2 Equivalent Components (IWC)

Additional examinations for Class 2 equivalent components (IWC) except component supports shall be in accordance with IWC-2430.

NOTE Class 2 piping welds for the third inspection interval shall be in accordance with the RI-ISI additional examination requirements as outlined in section 7.12.

The initial sample is the sample scheduled for examination at a particular outage for ASME Section Xl credit.

1. Examinations performed in accordance with table IWC-2500-1, except for Examination category C-H, of the initial sample that reveal flaws or relevant conditions exceeding the acceptance standards of Table IWC-341 0-l shall be extended to include additional examinations except for volumetric and surface examinations where IWC-31 12(b) is applicable. (Such as, flaws detected by volumetric or surface examinations that meet the nondestructive examination standards of NC-2500 and NC-5300, as documented in QA records, shall be acceptable).

2. The first additional examination sample shall include an additional number of welds, areas, or parts included in the inspection item equal to 20% of the number of welds, areas, or parts included in the inspection item that are scheduled to be performed during the inspection interval. The additional examination sample shall be selected from welds, areas, or parts of similar material and service. This additional selection may require inclusion of piping systems other than the one containing the flaws or relevant conditions.

SON ASME SECTION Xl ISIINDE PROGRAM 0-SI-DXI-000-114.3 Unit 11& 2 UNIT 1 and UNIT 2 Rev. 0000 Page 42 of 66 7.4.1 Additional Examinations For ASME Code Class 1, 2, And 3 (continued)

NOTES

1) Welds, areas, or parts for those described or intended in a particular inspection item of Table IWC-2500-1.

2) An inspection item, as listed in Table IWC-2500-1, may comprise a number of welds, areas, or parts of a component required to be examined in accordance with the inspection plan and schedule (IWA-2420).

3. If the first additional examinations sample of section 7.4.1 B.2 reveal flaws or relevant conditions exceeding the acceptance standards of Table IWC-341 0-1, the examinations shall be further extended to include additional examinations during the current outage. The second addifional examination sample shall include the remaining number of welds, areas, or parts of similar material and service subject to the same type of flaws or relevant conditions. If no items remain in the inspection interval sample, a notification of the first additional sample results shall be provided, in accordance with section 7.4.1 E, to evaluate the indications for further action, if needed.

4. For the inspection period following the period in which the examinations of IWC-2430(a) or (b) were completed, the examinations shall be performed as originally scheduled in accordance with IWC-2400.

5. If welded attachments are examined as a result of identified component support deformation and the results of these examinations exceed the acceptance standards of Table IWC-3410-1, additional examinations shall be performed, if determined necessary, based on an evaluation by Engineering.

(. Additional Examinations for Class 3 Equivalent Components (IWD)

Additional examinations for Class 3 equivalent component supports (IWD) except component supports shall be in accordance with IWD-2430.

The initial sample is the sample scheduled for examination at a particular outage for ASME Section XI credit.

1. Examinations performed in accordance with Table IWD-2500-1, except for Examination Category D-B, of the initial sample that reveal flaws or relevant conditions exceeding the acceptance standards of Table IWD-3000 shall be extended to include additional examinations during the current outage.

SQN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 'I & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 43of 66 7.4.1 Additional Examinations For ASME Code Class 1, 2, And 3 (continued)

2. The first additional examination sample shall include an additional number of welds, areas, or parts included in the inspection item equal to 20% of the number of welds, areas, or parts included in the inspection item that are scheduled to be performed during the inspection interval. The additional examination sample shall be selected from welds, areas, or parts of similar material and service. This additional selection may require inclusion of piping systems other than the one containing the flaws or relevant conditions..

NOTES

1) Welds, areas, or parts for those described or intended in a particular inspection item of Table IWD-2500-1.

2) An inspection item, as listed in Table IWD-2500-1, may comprise a number of welds, areas, or parts of a component required to be examined in accordance with the inspection plan and schedule (IWA-2420).

3. If the first additional examinations sample of section 7.4.1 C.2 reveal flaws or relevant conditions exceeding the standards of Table IWD-3000, the examinations shall be further extended to include additional examinations during the current outage. The extent of the additional examinations shall be determined by engineering based upon an engineering evaluation of the root cause of the flaws or relevant conditions. The corrective actions shall be documented in accordance with IWA-6000.

4. For the inspection period following the period in which the examinations of IWD-2430(a) or (b) were completed, the examinations shall be performed as originally scheduled in accordance with IWD-2400.

5. If welded attachments are examined as a result of identified component support deformation and the results of these examinations exceed the acceptance standards of Table IWD-3000, additional examinations shall be performed, if determined necessary, based on an evaluation by Engineering.

[). Additional Examinations for Class 1, 2 and 3 equivalent Component Supports (IWF)

Additional examinations for component supports (IWF) shall be in accordance with IWF-2430.

The initial sample is the sample scheduled for examination at a particular outage for ASME Section Xl credit.

SCN ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 'I& 2 UNIT 1 and UNIT 2 l Rev. 0000 lPage 44 of 66 7.4.1 Additional Examinations For ASME Code Class 1, 2, And 3 (continued)

1. Examinations performed in accordance with IWF-2500 of the initial sample that reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400 and that require corrective action shall be extended to include the component supports immediately adjacent to those for which corrective action is required. The first additional examination sample shall also be extended to include additional supports within the system, equal in number and of the same type and function as those scheduled for examination during the inspection period.

2. When the first additional examination sample of section 7.4.1 D.1 reveal flaws or relevant conditions exceeding the acceptance standards of /IWF-3400 and that require corrective action, the examinations shall be further extended to include additional examination during the current outage. The second additional examination sample shall include the remaining component supports within the system of the same type and function as in section 7.4.1D.1.

3. When the second additional examination sample of section 7.4.1D.2 reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400 and that require corrective action, examinations shall be extended to include a third additional examination sample of all nonexempt supports potentially subject to the same failure modes that required corrective actions in accordance with sections 7.4.1D.1 and 7.4.1 D.2. Also, these additional examinations shall include nonexempt component supports in other systems when support failures requiring corrective actions indicate non-system related failure modes.

At the request of the Component Engineering Representative, Site Engineering shall make the determination of failure mode applicability and select a third additional sample. The request shall be in accordance with section 7.4.1 F.

4. When the third additional examination sample of section 7.4.1 D.3 reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400 and that require corrective action, examinations shall be extended to those exempt component supports that could be affected by the sama observed failure modes and could affect nonexempt components.

At the request of the Component Engineering Representative, Site Engineering shall make the determination of failure mode applicability and select the fourth additional sample which shall be made of all component supports on exempt components which could affect nonexempt components. The request shall be in accordance with section 7.4.1 F.

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E. Completion of Additional Examinations After completion of the additional examinations, identified in section 7.4.1, ASME Section Xl Code requirements for additional examinations are complete.

If the final sample examinations reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400 and that require corrective actions, the indications shall be evaluated by Site Engineering for further action, if needed, within this and /or other systems. Evaluation for further actions shall be in accordance with section 7.4.1 F.

F. Notification of Additional Sample Results, Evaluation Request and Failure Mode Applicability The notification should include a summary of the indications found, number of examinations, number of indications in each sample, type of examinations performed, examination category, item number, copies of the NOls, and any other pertinent information. The above information shall be included when requesting Site Engineering to perform evaluations for additional samples, or failure mode applicability.

7.4.2 Successive Examinations NOTE The sample expansion and additional examination requirements of IWX-2430 apply when conducting successive inspections in accordance with IWX-2420(b). The purpose of successive inspections is to ensure that assumptions made in the analyses which allow leaving a flaw in service remain valid. However, if new flaws are found while conducting the successive examinations, then those flaws must be appropriately dispositioned because (1) they may or may NOT be related to the original flaw left in service, and (2) the provisions of IWX-2430 must be followed. See reference YY.

See Attachment 8 for Unit 1 and Attachment 9 for Unit 2 for scheduled successive examinations.

A. Successive Examinations - Class 1 Equivalent Components and Class 1 RI-ISI Piping Welds (except component supports)

1. Component with areas containing flaws or relevant conditions evaluated in accordance with IWB-3132.3 or IWB 3142.4 and SPP-3.1 that qualify for continued service shall be re-examined during the next three inspection periods listed in the inspection schedules.

Alternatively, acoustic emission may be used to monitor growth of existing flaws in accordance with IWA-2234, except for RI-ISI piping welds.

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If the re-examinations reveal that the flaw or relevant conditions remain essentially unchanged for three successive inspections periods, then the component examination schedule may revert to the original schedule.

Components requiring successive examinations shall be scheduled for examination (see Attachment 8 for Unit 1 and Attachment 9 for Unit 2).

Refer to Code Case N-526 for vessel examinations volumes containing subsurface flaws.

2. When welded attachments are examined as a result of identified component support deformation and the results of these examinations exceed the acceptance standards of Table IWB-3410-1 successive examinations shall be performed when determined necessary based on an Site Engineering evaluation. This evaluation may be documented in accordance with Section 7.4.1 F.

El. Successive Examinations - Class 2 Equivalent Components

1. Class 2 Equivalent Components (except for RI-ISI piping welds and component supports)

Components with areas containing flaws or relevant conditions evaluated in accordance with IWC-3122.3 or IWC-3132.3 and SPP-3.1 that qualify for continued service shall be re-examined during the next inspection period listed in the inspection schedule.

Alternatively, acoustic emission may be used to monitor growth of existing flaws in accordance with IWA-2234.

If the re-examination reveals that the flaw or relevant conditions remain essentially unchanged, the component examination schedule may revert to the original schedule. Components requiring successive examinations shall be scheduled for examination, (see Attachment 8 for Unit I and Attachment 9 for Unit 2). Refer to Code Case N-526 for vessel examinations volumes containing subsurface flaws.

2. Class 2 Equivalent RI-ISI piping welds in the third inspection interval Piping welds with areas containing flaws or relevant conditions evaluated in accordance with IWC-3122.3 or IWC-3132.3 and SPP-3.1 that qualify for continued service shall be re-examined during the next three inspection periods listed in the inspection schedule.

If the re-examination reveals that the flaws or relevant conditions remain essentially unchanged, the successive inspection periods, the piping weld examination schedule may revert to the original schedule. Piping welds requiring successive examinations shall be scheduled for examination (see Attachment 8 for Unit 1 and Attachment 9 for Unit 2).

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3. When welded attachments are examined as a result of identified component support deformation and the results of these examinations exceed the acceptance standards of Table IWC-341 0-1 successive examinations shall be performed when determined necessary based Dn an Site Engineering evaluation. This evaluation may be documented in accordance with Section 7.4.1 F.

G,. Successive Examinations for Class 3 Equivalent components (except component supports)

1. Successive examinations for Class 3 Equivalent Components (except component supports)

Components with areas containing flaws or relevant conditions evaluated in accordance with IWD-3000 and SPP-3.1 that qualify for continued service shall be re-examined during the next inspection period listed in the inspection schedule.

If the re-examination reveals that the flaws or relevant conditions remain essentially unchanged for the next inspection period, the component examination schedule may revert to the original schedule. Components requiring successive examinations shall be scheduled for examination (see Attachment 8 for Unit 1 and Attachment 9 for Unit 2).

2. When welded attachments are examined as a result of identified component support deformation and the results of these examinations exceed the acceptance standards of IWD-3000, successive examinations shall be performed when determined necessary based on an Site Engineering evaluation. This evaluation may be documented in accordance with Section 7.4.1F.

[). Successive Examinations for Class 1, 2 and 3 Equivalent Component Supports (IWF)

NOTE See sec:ion 7.2D.9 for component supports requiring an additional preservice examination.

1. When a component support is accepted for continued service in accordance with IWF-31 12.2 or IWF-3122.2 the component support shall be re-examined during the next inspection period listed in the inspection schedule. Component supports requiring successive examinations shall be scheduled for examination (see Attachment 8 for Unit 1 and Attachment 9 for Unit 2).

SCIN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit I & 2 UNIT I and UNIT 2 Rev. 0000 Page 48 of 66 7.4.2 Successive Examinations (continued)

2. When the examinations required by section 7.4.2D.1 do not require additional corrective measures, the inspection schedule may revert to the original schedule.

E. Applicability of IWX-2430 to Successive Examinations The sample expansion and additional examination requirements of IWX-2430 apply when conducting successive inspections in accordance with

-WX-2420(b). The purpose of successive inspections is to ensure that assumptions made in the analyses which allow leaving a flaw in service remain valid. However, if new flaws are found while conducting the successive examinations, then those flaws must be appropriately dispositioned because (1) they may or may NOT be related to the original flaw left in service, and (2) the provisions of IWX-2430 must be followed. See reference YY.

7.5 CONFIGURATION CHANGES The Component Engineering Representative shall be responsible for reviewing the proposed change, revising and issuing the ISI examination drawings as necessary in accordance with SPP-9.1, Part A.

7.6 C(ALIBRATION STANDARDS Calibration standards shall be in accordance with SPP-9.1, Part A and IEP-20'3..

7.7 RECORDS AND REPORTS A. ISI Summary Report for Class 1 and 2 Components An ISI summary report for Class 1 and 2 components shall be prepared and submitted to Site Licensing and other review organizations on a schedule that permits submittal to the NRC within 90 days after turbine generator synchronization following a refueling outage. Examinations, tests, replacements, and repairs conducted since the preceding summary repor: shall be included.

Each summary report shall be formatted to contain:

1. Cover Sheet A cover sheet stating "ASME Section Xl Inservice Inspection Summary Report for Sequoyah Nuclear Plant, Unit, and Refueling Outage,".

The cover sheet shall also provide'the following information:

a. Date of document completion.

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b. Name and address of owner.

c. Name and address generating plant.

d. Name or number assigned to the nuclear power unit by TVA.

e. Commercial operation date for unit.

2. Table of Contents A Table of Contents for the report should follow the title page.

3. Form NIS-1 The Owner's Report for Inservice Inspections, Form NIS-1, as shown in Appendix II of the code shall be completed and included for preservice and inservice examinations.

r NOCTE

., .

Signing of the Form NIS-1 by TVA certifies that all non-destructive examinations have been performed as required by this procedure.

4. Introduction and Summary of the Inspection The introduction should include the following information: Plant, unit number, period, inspection interval, preservice or inservice examinations, RFO cycle, systems, components and vessels examinations were performed on, organization examinations were performed by, dates examinations were performed, ASME Section Xl ISI Code of Record. The summary should include a brief description of the overall inspection.

Included as part of the summary, ASME Class 1, 2, and 3 equivalent components whose examination results require evaluation analysis (IWB-3132.3 andlWB-3142.4 for Class 1; IWC-3122.3 and IWC-3132.3 for Class 2; and IWD-3640 for Class 3) shall be submitted to the NRC as.

required by IWB-3134, IWB -3144, IWC-3125, IWC-3134 and IWD-3340.

5. Examination Summary The examination summary shall tabulate the ASME Section Xl examinations credited for the applicable period. Items should include the following information: category, total number required for the inspection interval, total number required for the applicable period, total number credited for the applicable period, percentage complete and exclusions, exceptions or deferrals.

QCN ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3

'I & 2 UNIT I and UNIT 2 Rev. 0000 Page 50 of 66 7.7 RECORDS AND REPORTS (continued)

6. Examination Plan The Examination Plan shall give a detailed description of all areas subject to examination during the inspection. It should contain the following information: Examination Area (component), code class, Code Category and Item Number, Reference Drawing, Examination Method, code case, Examination Procedure, Examination Report Number, Calibration Block, date of examination and results of examination. This plan may be submitted as the computerized Outage Report.

7. Component Preservice Examinations The component preservice examinations list shall give a detailed description of all components subject to preservice examination due to rework, repair, or replacement. This list should contain Examination Area (component), Code Category and Item Number, Reference Drawing, Examination Method, Examination Procedure, Calibration Block, date of examination and results of examination.

8. Summary of Notification of Indications (NOls)

The summary of NOls shall give a short summary of each NOI report along with the indication discrepancy. It should also contain the final disposition including a reference to the corrective action taken.

9. Additional Sample The additional sample section, if applicable, shall indicate additional sample examinations performed as a result of a result of a failed /

component. The summary should include reference to the applicable system, the affected component, the number of components examined as a result of failed and a description of additional samples and results cf the additional sample.

10. Successive Examinations The successive examination section, if applicable, shall indicate examinations performed as a result of the requirements of ASME Section Xl. The successive examination section should reference to the applicable system, the affected components and results of the successive examination.

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.7.7 RECORDS AND REPORTS (continued)

11. Analytical Evaluation The analytical evaluation section for ASME Class 1, 2, and 3 equivalent components whose examination results require evaluation analysis, if applicable shall include a short summary of each analytical evaluation, the indication discrepancy and its location. It should contain a copy of the analytical evaluation including a reference to the Notification of Indication and the component identifier.

12. Augmented Examinations A brief summary of augmented examinations reportable to the NRC as described in section 7.11 and the augmented examination plan including the information in 7.7A.6 shall be included.

13. Requests for Relief The summary of requests for relief shall give a short summary of each relief request resulting from the inspection, that may be needed. The request for relief section shall summarize components which did NOT receive the required examination coverage. The results should indicate the applicable component, code class, code category, code item number, examination method and calculated coverage. In addition, a description should summarize the access limitations and applicable reason why coverage cannot be obtained.

14. Appendix A, Summary of Steam Generator Tubing Examinations A brief summary of the Steam Generator tubing examinations and plugging results shall be supplied in accordance SPP-9.1, Part A as supplied by Corporate Steam Generator Programs shall be included.

15. Appendix B, Report for Repair and Replacements, Form NIS-2 The Owner's Report for Repair and Replacements, Form NIS-2 as shown in Appendix II of ASME Section Xl shall be included, as supplied by the Repair and Replacement Engineer in accordance with SPP-9.1.

16. Appendix C, Pressure Test Report A brief summary of the pressure tests performed as supplied by the Pressure Test Engineer in accordance with SPP-9.1.

17. IWE Metal Containment Evaluations A summary of the flaw evaluations prepared for IWE in accordance with SPP-9.1 Part E and O-PI-DXI-000-116.1.

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E[. Site Final Report

1. A Site Final report of all examinations conducted in accordance with 0-SI-DXI-000-1 14.3 shall be prepared. The Site Final Report shall be submitted to Management Services for retention as a quality assurance record. The Site Final Report should contain, but NOT be limited to, the following information:

a. A title page stating "ASME Section Xl Inservice Inspection Site Final Report Sequoyah Nuclear Plant, Unit, and Refueling Outage."

b. Table of Contents

c. The ISI Summary Report with appendices prepared in section 7.7A

d. Summary of ISI Examinations on ASME Code Class 3 and MC Components, Non-Regulatory Augmented Examinations (self imposed), Preservice Examinations, Voluntary Examinations, Successive Examinations and Additional Samples.

e. Scan Plan and Scan Plan Revision Log (if applicable)

f. Summary of Personnel Certifications

g. Calibration and Examination Data Sheets, and Notification of Indication Log and Reports

2. All procedures and equipment shall be identified sufficiently to permit duplication of the examination at a later date. All required and pertinent information shall be recorded on the appropriate data sheets by the performing organization. When portions of the inspection work are contracted, a detailed report shall be submitted to TVA by the contractor with all pertinent and required information. TVA shall retain the origiral copies of all data taken.

3. The Site Final Report should be formatted similar to the follows:

a. Part I - Introduction and Overall Summary

b. Part II - ISI Summary Report for Class 1 and 2 Components

c. Part IlIl - Summary of ISI Examinations ASME Class 3 and MC Components, Non-regulatory Augmented Examinations (self imposed), Preservice Examinations, Voluntary Examinations, Successive Examinations and Additional Samples

d. Part IV - Unit and Cycle Scan Plan and the Scan Plan Revision Log

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e. Part V - Personnel Information such as: Contract Approvals, ISI/NDE Personnel, Summary of Certifications, Signature Log, Reading List, NDE Equipment and Materials

f. Part VI - NDE Examination Reports, and Calibration Reports, Inspection Reports and Notifications of Indication Log and Reports

4. The Site Final Report shall be reviewed and submitted in accordance with SPP-8.2, Surveillance Program, for retention as a quality assurance record -

in accordance with SPP-2.4, Records Management. Records and reports shall be in accordance with SPP-9.1, Part A.

C. Records for ASME Code Class 1, 2 and 3 (Equivalent)

[). The following records and drawings are QA Records are generated by this instruction and shall be retained in accordance with SPP-2.4:

1. Site Final Report

2. ASME Section Xl Boundary Classification Drawings

3. ASME Section Xi ISI Drawings In process records shall be controlled with SPP-2.4.

E-. Augmented Examination Reports For specific details on Augmented Examinations records, reports and reporting see Attachment 10 for Unit 1 and Attachment 11 for Unit 2.

F:. Status of Completed Examinations Status of completed examinations shall be as described in section 7.10.

SCIN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit l & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 54 of 66 7.8 REQUESTS FOR RELIEF (RFR)

Requests for relief shall be in accordance with SPP-9. 1, Part A.

The following is a listing of requests for relief:

Unit I

The following RFR numbers were used in the previous inspection interval 1-lSI-1 through 1-ISI-14. These RFR numbers are not being used at this time id the third inspection interval.

1-1SI-15, Pressure Retaining Nozzle Welds in Vessels, Nozzle Inside Radius Section, Residual Heat Removal Heat Exchangers 1A and 1B. RFR to use, the nozzle-to-vessel weld examination for the nozzle inside radius section This request for relief was approved for the second inspection interval and is going to be resubmitted for NRC approval prior to use for the third inspection interval, see reference 2.41.2.

The following RFR numbers were used in the previous inspection interval 1-ISI-16 through 1-ISI-26. These RFR numbers are not being used at this time in the third inspection interval.

1-RI-ISI-1, Risk Informed Inservice Inspection (RI-ISI) program Plan. (RFR to use the alternative RI-ISI program for ASME Section Xl Categories B-F, B-J, C-F-1 and C-F-2 piping as described in WCAP-14572, Revision 1-NP-A and Supplement 1. This request for relief was approved for the second inspection interval and is being resubmitted to NRC for approval for the third inspection interval, see reference 2.41.1.

I-RI-ISI-2, Risk informed Piping Examinations, Examination Category R-A., Item Number R1.11, High Safety Significant Piping Structural Elements

Subject:

to Thermal Fatigue. RFR to NOT perform volumetric examination on branch connection welds < 2 inches nominal pipe size (NPS) and socket welds that are subject to thermal fatigue. This request for relief was approved for the second inspection interval and is being resubmitted to NRC for approval for the third inspection interval, see reference 2.41.1.

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Unit 2

The following RFR numbers were used in the previous inspection interval :2-ISI-1 through 2-ISI-14. These RFR numbers are not being uses at this time in the third inspection interval.

2-ISI-15, Pressure Retaining Nozzle Welds in Vessels, Nozzle Inside Radius Section, Residual Heat Removal Heat Exchangers 2A and 2B. RFR to use, the nozzle-to-vessel weld examination for the nozzle inside radius section. This request for relief was approved for the second inspection interval and is being resubmitted to NRC for approval prior to use for the third inspection interval, see reference 2.41.2.

. The following RFR numbers were used in the previous inspection interval :2-ISI-16 through 2-ISI-26. These RFR numbers are not being used at this time in the third inspection interval.

2-RI-ISI-1, Risk Informed Inservice Inspection (RI-ISI) program Plan. RFR to use the alternative RI-ISI program for ASME Section Xl Categories B-F, B-J, C-F-1 and C-F-2 piping as described in WCAP-14572, Revision 1-NP-A and Supplement 1. This request for relief was approved for the second inspection interval and is being resubmitted to NRC for approval for the third inspection interval, see reference 2.41.1.

2-RI-ISI-2, Risk informed Piping Examinations, Examination Category R-A, Item Number R1.1 1, High Safety Significant Piping Structural Elements Subject to Thermal Fatigue. RFR to NOT perform volumetric examination on branch connection welds < 2 inches nominal pipe size (NPS) and socket welds that are subject to thermal fatigue. This request for relief was approved for the second inspection interval and is being resubmitted to NRC for approval for the third inspection interval, see reference 2.41.1.

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Unit I and 2

This RFR number PDI-1 was used in the previous inspection interval. This RFR number is not being used at this time in the third inspection interval.

M PDI-2, Examination Category B-D, Item Number B3.90, Pressure Retaining Nozzle-to-Vessel Welds. RFR to reduce the examination volume to one-half (1/2) inch from each side of the weld crown in lieu of the 1/2 through-wall thickness from each side of the weld required by Figures IWB-2500-7(a) and (b). This request for relief was approved for the second interval and is going to be resubmitted to NRC for approval prior to use for the third inspection interval, see reference 2.41.3.

a This RFR number PDI-3 was used in the previous inspection interval, This RFR number is not being used at this time in the third inspection interval.

PDI4, alternative to ASME Code Xl, Subarticle IWA-2232 and its referenced Section V, Article 4 requirements. RFR to use procedures, personnel, and equipment qualified to meet the requirements of ASME Section XI Appendix VilI, Supplements 4 and 6 of the 1995 Edition through the 1996 Addenda, as administered by the Electric Power Research Institute's (EPRI) Performance Demonstration Initiative (PDI) processes to conduct the vessel-to-flange weld examinations. Welds Unit 1 W06-07 and Unit 2 W06-07. This request for relief was approved for the second inspection interval and is going to be resubmitted to NRC for approval prior to use for the third inspection interval, see reference 2.41.4.

Unit I and 2 - Snubbers

Snubber request for relief is being submitted to NRC for approval for the third inspection interval.

SCIN ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit l & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 57 of 66 7.9 CORRECTIVE ACTION PROGRAM Any corrective action required as a result of ISI examinations shall be handled in accordance with SPP-3.1.

7.10 SCAN PLAN A computerized data base system will be utilized for status and Section Xl credit of completed ISI examinations and those augmented examinations which have been integrated with the ASME Section XI ISI/NDE Program. The data base is utilized to provide a scan plan. A scan plan is the primary scheduling document listing components requiring examination during a specific refueling outage. A scan plan may also be utilized to provide a listing of components to be examined for nonoutage activities. Responsibilities for preparing, maintaining, and approving the data base and scan plans shall be in accordance with SPP-9. 1, Part A.

During implementation phases (usually outage periods), it may become necessary to revise the scan plan. Scan plan revisions can be initiated by Component Engineering Representative, ISO, or by other personnel involved with the implementation of the scan plan. All changes shall be coordinated with an Component Engineering Representative and, as needed, with the appropriate plant planning and scheduling personnel for facilitating the use of supporting craft personnel. Revisions to the scan plan shall be controlled in the same manner as the original (see SPP-9. 1, Part A). However, interim working copies may be hand

\Written to allow examinations to be performed before a formal revision is issued.

The approving individuals shall initial and date revisions on the scan plan.

f MIXTF Iev % I LA When inservice examinations are performed as a result of instructions other than this program (e.g., maintenance instructions, work plans, etc.), copies of the examination cata sheet shall be submitted to Compohent Engineering by the performing organization for assignment of a report number and incorporation into the scan plan.

7.11 AUGMENTED EXAMINATIONS Augmented examinations are performed in addition to ASME Section Xl code requirements. The augmented examinations may be required by the NRC or be self-imposed by TVA. Typical sources include generic letters, IE bulletins, technical specifications, vendor recommendations, and industry experience. SPP-9. 1, Part A provides requirements for requesting augmented examinations.

Attachment 10 for Unit 1 and in Attachment 11 for Unit 2 provides a description and schedule for augmented examinations. The following is a listing of augmented examinations:

SON ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 'I & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 58 of 66 7.11 AUGMENTED EXAMINATIONS (continued)

Unit 1

Feedwater Nozzle-to-Pipe Welds and Adjacent Pipe/Fittings and Nozzle Areas/Auxiliary Feedwater

Reactor Coolant Pump Flywheel (not required for the third inspection interval)

RPV Nozzle Cladding [C.1]

Control Rod Guide Tube Flexures (not required for the third inspection interval)

Thimble Tube Guide

Examination of Piping Connected to the Reactor Coolant System Due to Thermal Stresses a Pressurizer Relief Line Repair Welds and Adjoining Areas

Safety Injection and RHR Welds and Adjoining Areas, and RI-ISI Region 3 welds

Reactor Coolant Pump Support (not required for the third inspection interval)

Steam Generator Class 2 Upper Support (not required for the third inspection interval)

Nuclear Experience Review (NER) Item SER 00-001

. Reactor Pressure Vessel Closure Head Penetrations [C.2]

. Reactor Coolant Pump Shafts

-Examination of Alloy 600 and Alloy 82/182 Potential Leak Locations in Primary Components

4. Examination of Reactor Vessel Head Vent Pipe

Reactor Pressure Vessel Lower Head Penetrations

SQN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 'I& 2 UNIT I and UNIT 2 Rev. 0000 Page 59 of 66 7.11 AUGMENTED EXAMINATIONS (continued)

Unit 2

Feedwater Nozzle-to-Pipe Welds and Adjacent Pipe/Fittings and Nozzle Areas/Auxiliary Feedwater

Reactor Coolant Pump Flywheel (not required for the third inspection interval)

RPV Nozzle Cladding [C.1]

Control Rod Guide Tube Flexures (not required for the third inspection interval)

Thimble Tube Guide

. Examination of Piping Connected to the Reactor Coolant System Due to Thermal Stresses

Centrifugal Charging Pump Injection Tank (CCPIT) (2-TNK-63-7) Weld BIT-4

Reactor Coolant Pump Support (not required for the third inspection interval)

Steam Generator Class 2 Upper Support

Nuclear Experience Review (NER) Item SER 00-001

Reactor Pressure Vessel Closure Head Penetrations [C.2]

Safety Injection and RHR Welds, and Adjoining Areas, and RI-ISI Region 3 welds

Reactor Coolant Pump Shafts

Examination of Alloy 600 and Alloy 82/182 Potential Leak Locations in Primary Components

Examination of Reactor Vessel Head Vent Pipe

Reactor Pressure Vessel Lower Head Penetrations

SCIN ASME SECTION XI ISI/NDE PROGRAM O-SI-DXI-000-114.3 Unit l & 2 UNIT I and UNIT 2 Rev. 0000 Page 60 of 66 7.12 RISK-INFORMED INSERVICE INSPECTION (RI-ISI) 7.12.1 Introduction The objective of the RI-ISI program is to provide an alternative method for selec ting and categorizing piping components into High Safety Significant (HSS) and Low Safety Significant (LSS) groups for the purpose of developing a RI-ISI program as alternative to the ASME Section XI requirements for piping. NRC approved an alternative inspection program which meets the criteria of 10CFR50.55a(a)(3)(i) to provide an acceptable level of quality and safety for the second inspection inteival.

The alternative inspection program is being resubmitted for the third inspection interval. The alternative inspection program follows WCAP-14572, Revision 1-NP-A and Supplement I for the development of a Rl-ISl program for inservice inspection Of piping.

7.12.2 FPurpose Rl-ISI program as approved in the second inspection interval in request for relief 1-RI-ISI-1 and 2-RI-ISI-1 outlines an acceptable alternative approach to the existing Section Xl requirements for the scope and frequency of piping examination of the ISI Program examination categories (B-F, B-J, C-F-1 and C-F-2) by utilizing risk informed techniques. Request for relief 1-RI-ISI-1 and 2-RI-ISI-1 are being resubmitted to NRC for approval for the third inspection interval.

10CFR50.55a(a)(3)(i) allows the use of alternatives when authorized by the Director of the Office of Nuclear Reactor Regulation, when the alternative provides an acceptable level of quality and safety. This alternative approach provides an acceptable level of quality and safety per I OCFR50.55a(a)(3)(i) by incorporating iisights from probabilistic safety assessment and traditional analysis calculations supplemented with plant operating data.

7.12.3 Scope Rl-ISI program in the second inspection interval in request for relief 1-RI-ISI-1 and 2-RI-ISI-1 outlines the details for risk-informed requirements for inservice inspection of ASME Class 1, and 2 equivalent piping. Request for relief 1-RI-ISI-1 and 2-RI-ISI-1 are being resubmitted to NRC for approval for the third inspection interval.

7.12.4 I:requency The inspection periods and inspection interval are defined in section 1.4. The piping segments and inspection strategy (i.e., frequency, number of examinations, and examination methods) are defined in Table E of Attachment 4 for Unit 1 and in Table E of Attachment 5 for Unit 2.

SCN ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit Il & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 61 of 66 7.12.5 Periodic Updates The RI-ISI program is a living program requiring feedback of new relevant information to ensure the appropriate identification of high safety significant piping locations. As a minimum, risk ranking of piping segments will be reviewed and adjusted on an ASME period basis (See section 1.4). Areas to be considered are plant design feature changes, plant procedure changes that affect system operating parameters, equipment performance changes, RI-ISI examination results, plant and industry failure information, corrective action program results, and PSA changes.

Expedited program updates should be performed to address significant PSA changes or the occurrence of significant plant events. Significant plant events may include such events as pipe ruptures, earthquakes, or severe operational transients.

History of RI-ISI program update; Initial program review to 08/01/1999 Periodic program update 08/01/1999 to 05/31/2002 (reference UU)

Interval program update for the third inspection interval 05/31/2002 to 06/01/2005 Fl-ISI program interval update for the third inspection interval has been incorporated in this procedure and requests for relief 1-RI-ISI-1, 2-RI-ISI-1, 1-RI-ISI-2 and 2-RI-131-2 are being submitted to NRC for approval for the third interval.

7.12.6 corrective Action Program Any corrective action required as the result of RI-ISI examinations shall be handled in accordance with section 7.9.

7.12.7 Inspection Program The examinations shall be completed during each ten-year inspection interval with the following exceptions.

1. If, during the inspection interval, a reevaluation using the RI-ISI process is conducted and scheduled items are no longer required to be examined, these items may be eliminated.

2. If, during the inspection interval, a reevaluation using the RI-ISI process is conducted and items are required to be added to the examination prcgram, those items shall be added.

7.12.8 Successive Inspections successive examinations shall be in accordance with section 7.4.2:'

SQN ASME SECTION XI ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit l & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 62 of 66 7.12.9 Additional Examinations Since the risk-informed inspection program will require examinations on a large rnumber of elements constructed to lesser pre-service inspection requirements, the program in all cases will determine through an engineering evaluation the root cause of any unacceptable flaw or relevant condition found during examination as described in WCAP-14572. The evaluation will include the applicable service conditions and degradation mechanisms to establish that the element(s) will still perform their intended safety function during subsequent operation. Elements NOT meeting this requirement will be repaired or replaced.

The evaluation will include whether other elements on the segment or segments are subject to the same root cause and degradation mechanism. Additional examinations will be performed on these elements up to a number equivalent to the number of elements required to be inspected on the segment or segments initially. If Unacceptable flaws or relevant conditions are again found similar to the initial problem, the remaining elements identified as susceptible will be examined. No additional examinations will be performed if there are no other additional elements identified as being susceptible to the same service related root cause conditions or degradation mechanism..

7.12.10 Examination Coverage The process outlined in Section 4.0 of WCAP-1 4572 revision 1-NP-A will be followed for RI-ISI program examinations that do NOT achieve greater than 90 percent examination coverage and if item 1 or item 2 below do NOT apply.

Apply item 1 if an inservice examination or inservice augmented examination has been performed prior to implementation of the Rl-lSI Program or item 2 if only a preservice examination has been performed prior to implementation of the RI-ISI Program.

Item 1: If examination limitations occur for locations in sub region 1A, sub-region 1B, region 2, region 3, or region 4 segments and a previously performed ASME Section Xl inservice examination or inservice augmented examination was a partial examination or an examination with >90% coverage and the partial examination continues to be a partial examination (with approximately the same % coverage) or the examination with >90% coverage becomes a partial examination only due to the implementation of the PDI in the RI-ISI process, the amount of risk addressed by the examination remains the same for that location. No evaluation or additional examination areas would be required. The partial examination coverage should be submitted as a relief request. Reference RR, CCC and SPP-9.1 Part F Appendix D.

SQN ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit l & 2 UNIT I and UNIT 2 Rev. 0000 Page 63 of 66 7.12.10 Examination Coverage (continued)

Item 2: If a previously performed ASME Section XI preservice examination or preservice augmented examination was a partial examination or an examination with >90% coverage and the partial examination continues to be a partial examination (with approximately the same % coverage) or the examination with

>90% coverage becomes a partial examination only due to the implementation of the PDb in the Ri-ISI process, the amount of risk addressed by the examination remains the same for that location if the segment containing the location is high safety significant only because of the failure consequence. No evaluation or additional examination areas would be required, if the location is in a region 2 or region 4 segment. If the location is in a sub-region 1A, sub-region 1B, or region 3 segment and has previously had only a preservice examination, consideration must be given to performing more examinations than are currently required for the RI-ISI program in accordance with Section 4 of the WCAP even if the examination coverage's are technically the same.

When considering performing more examinations for region 1A, it must be determined if all susceptible locations currently require examination or if examinations are currently required where the identified failure mechanism would first be detected. If all susceptible locations currently require examination, then performance of more examinations would NOT be required.

The partial examination coverage should be submitted as a relief request.

Reference RR, CCC and SPP-9.1 Part F Appendix D.

SQN ASME SECTION XIISI/NDE PROGRAM O-SI-DXI-000-114.3 Unit I & 2 UNIT 1 and UNIT 2 Rev. 0000 Page 64 of 66 7.13 OWNER STATEMENT Owner: Tennessee Valley Authority Address of Corporate Office: Chattanooga Office Complex 1101 Market Street Chattanooga, Tennessee 37402-2801 Name and Address of Nuclear Power Plant Sequoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37384-2000 Applicable Nuclear Power Units: Sequoyah Nuclear Plant, Unit 1 and Unit 2 Commercial Operation Dates: July 1,1981 - Unit 1 June 1, 1982 - Unit 2 First ISI Inspection Interval: July 1, 1981 thru December 15,1995 Unit 1 June 1, 1982 thru December 15,1.995 Unit 2 Second ISI Inspection Interval: December 16, 1995 Unit 1 thru May 31, 2006 December 16, 1995 Unit 2 thru May 31, 2006 Third ISI Inspection Interval Start Date: June 1, 2006 Unit 1 June 1, 2006 Unit 2

SON ASME SECTION Xi ISI/NDE PROGRAM O-SI-DXI-000-1 14.3 Unit 1 & 2 UNIT I and UNIT 2 Rev. 0000 Page 65 of 66 Source Notes (Page 1 of 2)

Implementing Requirements Statement Source Document Statement All SPP-9.1, Part A All All applicable articles ASME Boiler and Pressure All Vessel Code Section Xl 2001 Edition, 2003 Addenda All applicable articles as shown in ASME Boiler and Pressure All procedure section 1.3. Vessel Code Section Xl 2001 Edition All applicable articles as shown in ASME Boiler and Pressure procedure section 1.3. Vessel Code Section Xl 1998 Edition All applicable articles as shown in ASME Boiler and Pressure procedure section 1.3. Vessel Code Section XI 1995 All Edition through the 1997 Addenda All applicable articles as shown in ASME Boiler and Pressure procedure section 1.3. Vessel Code Section Xl 1995 All Edition All applicable articles as shown in ASME Boiler and Pressure All procedure section 1.3. Vessel Code Section Xl 1989 Edition All applicable articles ASME Boiler and Pressure All Vessel Code Section V All applicable chapters FSAR - SQN All Surveillance requirements 4.0.5 Technical Specifications Unit 1 All and 4.4.3.2.4 Surveillance requirements 4.0.5 Technical Specifications Unit 2 All

SCN ASME SECTION Xl ISI/NDE PROGRAM 0-SI-DXI-000-114.3 Unit 'Il& 2 UNIT I and UNIT 2 Rev. 0000 Page 66 of 66 Source Notes (Page 2 of 2)

Implementing Requirements Statement Source Document Statement 10CFR50 55a Code of Federal Regulations All 10CFR50 As applicable U.S.N.R.C. Regulatory Guides All 1.14, 1.26,1.147, and 1.150 All Code Cases N-460, N-521, N-524, N-526, N-586, N-624, N-648-1, and N-695 Augmented Examination Reactor Memorandum C.1 Pressure Vessel Nozzles from R.A. Fenech to NRC, dated February 22, 1994 Referenced in section 7.11 and (S64 940218 801) Attachments 10 Memorandum from D.E. Labarge, and 10 NRC to O.D. Kingsley, Jr., dated March 15, 1994 (L44 940322 006) (NCO 930202 003, and NCO 930202 004)

Reactor Pressure Vessel Head Memorandum from R.T. Purcell to C.2 Penetrations NRC Dated April 2, 2002 Referenced in (S64 020402 801) section 7.11 and Attachments 10 and 11

SQN ASME Class 1 Equivalent Components O-SI-DXI-000-114.3 ATTM Unit I & 2 . Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 1 of 18 ATTACHMENT I - ASME Class 1 Equivalent Components Subject to Examination (Unit 1 and Unit 2)

SCIN ASME Class I Equivalent Components 0-SI-DXI-000-114.3 ATT1 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and Unit 2) Page 2 of 18 The ASME Code Class 1 (equivalent) components to be examined during the inspection interval are outlined below. The entire length of each weld described shall be examined for the third 10-year ISI interval unless otherwise noted. When a portion of a weld length is to be examined during an inspection period, the areas Examined each inspection period shall be documented on the examination data sheets.

Table A, Table D (Component Supports), and Table E (RI-ISI elements/segments) of Attachment 4 for Unit 1 and Attachment 5 for Unit 2 shall be used for items selected for examination. These tables provide the examination schedule for the interval and additional information such as reference ISI drawings numbers and ASME Section Xl, Table IWB-2500-1, and RI-ISI examination categories.

NOTE Additional material specifications for piping and equipment is stated on the ISI drawings 1.0 REACTOR VESSEL 1.1 Reactor Vessel Seam Welds (B-A)

A. Circumferential Shell Welds (Item Number B13.11)

There are four circumferential shell welds on the Reactor Vessel. Three cf the circumferential shell welds are located behind the thermal shield. The entire length of each of these four welds shall be ultrasonically examined during the third inspection period using remote inspection devices from the vessel inside diameter with the core internals removed.

El. Longitudinal Shell Welds (Item Number B1.12)

There are no longitudinal shell welds associated with the reactor vessel.

C(. Closure Head Circumferential Weld (Item Number B13.21)

The entire length of the closure head cap weld shall be manually ultrasonically examined from the head outside diameter. The entire length of the weld shall be ultrasonically examined during the third inspection period.

D. Lower-Head Circumferential Weld (Item Number B1.21)

The entire length of the lower head circumferential weld shall be ultrasonically examined during the third inspection period using remote inspection devices from the vessel inside diameter with the core internals removed.

E. Closure Head Meridional Weld (Item Number B1.22)

SQN ASME Class I Equivalent Components 0-SI-DXI-000-1 14.3 AT1T Unit 'I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 3 of 18 1.1 Fteactor Vessel Seam Welds (B-A) (continued)

The closure head does not include any meridional welds.

F. Lower-Head Meridional Welds (Item Number B1.22)

There are six meridional welds located in the lower head. The entire length of each of these welds shall be ultrasonically examined during the third inspection period using remote inspection devices from the vessel inside diameter with the core internals removed.

GI. Shell-to-Flange Weld (Item Number B13.30)

The vessel shell-to-flange weld is 39 inches for Unit 1 and 41.9 inches for Unit 2 below the flange face. The entire length of the vessel shell-to-flange weld will be ultrasonically examined during the third inspection period using remote inspection devices from the vessel inside diameter with the core internals removed. Refer to request for relief PDI-4 which will be submitted for NRC approval prior to use.

H. Closure Head-to-Flange Weld (Item Number B1.40)

The entire length of the closure head-to-flange weld shall be surface examined and ultrasonically examined from the head outside diameter during the third inspection period.

I. Repair Welds (Item Numbers B13.50 and B13.51)

There are no base metal repair welds in the beliline region of the Unit 1 or Unit 2 reactor vessel.

1.2 Reactor Vessel Nozzle-to-Vessel Welds (B-D) (Item Number 133.90)

-rhere are four inlet nozzles and four outlet nozzles. The eight nozzle-to-vessel welds shall be ultrasonically examined from the nozzle bore and from the vessel inside wall. These examinations will be performed during the third inspection period when the core barrel has been removed. Following the submittal and approval by 14RC of request for relief PDI-2, the examination volume may be reduced to 1/2 inch from each side of the weld crown, in lieu of the 1/2 through-wall thickness from each side of the weld required by figure IWB-2500-7(a) and (b).

SQN ASME Class 1 Equivalent Components 0-SI-DXI-000-114.3 ATT' Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and Unit 2) Page 4 of 18 1.3 Reactor Vessel Nozzle Inside Radius Section (B-D) (Item Number E13.1 00)

The eight nozzle inside radius sections shall be examined in accordance with visual examination method VT-1 per Code Case N-648-1 and conditions in Regulatory Guide 1.147 at the same time as the examination of the nozzle-to-vessel welds curing the third inspection period when the core barrel has been removed.

1.4 Reactor Vessel Partial Penetration Welds The vessel includes 4 Upper Head Injection (UHI) nozzles (capped in Unit 1 and Unit 2 Cycle 4 UHI removal), I vent pipe nozzle, 78 control rod drive nozzles, and 58 instrumentation nozzles with partial penetration welds. These partial penetration welds are not required to be examined by ASME Section Xl 2001 Edition, 200$

Addenda.

1.5 Reactor Vessel Nozzle-to-Safe End Welds (B-F)(ltem Number B35.1 0)

NOTE This examination is to include the pipe to safe end weld.

Each nozzle safe end weld is a stainless steel type 304 weld build up (buttering).

The inlet and outlet nozzle-to-safe end welds are included in Examination category R-A Risk Informed Piping Examination (R-A). Refer to section 9.0 of this attachment. these welds shall be ultrasonically examined from the inside diameter using remote inspection devices. The ultrasonic examination, when required, shall be performed at the same time as the examination of the nozzle-to-vessel welds conducted from the nozzle bore during the third inspection period when the core barrel has been removed. See Section 1.2 1.6 Reactor Vessel Pressure Retaining Bolting Larger Than Two Inches In Diameter (B-G-1) (Item Numbers B6.10, B6.20, 136.40, B6.50)

During each refueling outage all closure studs, nuts, and washers are removed.

The closure studs shall be ultrasonically or magnetic particle examined when removed. The threads in flange shall be ultrasonically examined. The closure nuts and closure washers shall be examined in accordance with visual examination method VT-1.

The bolting may be examined either (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed.

SQN ASME Class 1 Equivalent Components 0-SI-DXI-000-114.3 ATT 7 Unit I & 2 Subject to Examination Effective Date: 06-01-2D06 (Unit I and Unit 2) Page 5 of 18 1.6 Reactor Vessel Pressure Retaining Bolting Larger Than Two Inches In Diameter (B-G-1) (Item Numbers B6.10, B6.20, E06.40, B6.50) (continued)

These examinations will be performed during the third period.

Provisions for this examination are in accordance with 0-MI-MRR-068-005.0 and the applicable NDE procedure.

1.7 Reactor Vessel Pressure Retaining Bolting Two Inches And Smaller In Diameter (B-G-2) (Item Number B7.10)

There is no pressure retaining bolting two inches or smaller in diameter.

1.8 Reactor Vessel Control Rod Drive Housing Pressure Retaining Bolting Two Inches And Smaller In Diameter (B-G-2) (Item Number 7.80 ) and 10CFR50.55a(b)(2)(xxi)(B)

There is no pressure retaining bolting two inches or smaller in diameter.

1.9 Reactor Vessel Interior (B-N-1)(ltem Number B13.10)

The vessel interior shall be examined in accordance with visual examination method N/T-3. This examination shall include the space above and below the reactor core that is made accessible for examination by removal of components during normal refueling outages. This examination shall be performed each inspection period.

1.10 Reactor Vessel Interior Attachments Within BeItline Region (B-N-2)(Item Number B13.50)

There are no interior attachments within the Reactor Vessel beltline region.

1.11 Reactor Vessel Interior Attachments Beyond Beltline Region IB-N-2)(ltem Number B13.60)

There are 6 interior attachments (core support pads) beyond the beltline region all 6 core support pads shall be examined in accordance with visual examination method VT-3. This examination may be deferred to the third inspection period.

1.12 Reactor Vessel Removable Core Support Structures (B-N-3)(ltem Number B13.70)

The accessible attachment welds and accessible surfaces of the core support structure shall be examined in accordance with visual examination method VT-3.

This examination may be deferred to the third inspection period. The core support structure shall be removed from the reactor vessel for examination.

SCN ASME Class 1 Equivalent Components 0-SI-DXI-000-114.3 ATTI Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 6 of 18 1.13 Reactor Vessel Control Rod Drive Housings (B-O)(ltem Number E14.10)

There are 78 control rod drive housings penetrating the closure head. Each housing includes a pressure retaining dissimilar metal butt weld.

There are 17 peripheral control rod drive housings. Two (10 percent) of the peripheral housing butt welds shall be ultrasonically examined during the inspection interval.

II: is impractical due to radiation exposure, access, and time on the head to examine these welds in different periods as done in the first inspection interval. Since the examinations may be deferred the welds shall be examined in the third inspection period.

2.0 PRESSURIZER 2.1 Pressurizer Circumferential Shell-to-Head Welds (B-B)(ltem Number B2.11)

There are two circumferential shell-to-head welds to be ultrasonically examined during the inspection interval.

2.2 Pressurizer Longitudinal Shell-to-Head Welds (B-B)(Item Number E32.12)

There is one longitudinal weld intersecting each circumferential shell-to-head weld.

One foot of the longitudinal weld per head shall be ultrasonically examined during the inspection interval.

The one foot of weld examined during each examination shall include the length of weld as measured from the point of intersection of the longitudinal weld with the circumferential head-to-shell weld.

2.3 Pressurizer Head Circumferential and Meridional Welds (B-B)(ltem Numbers B2.21 and B2.22)

There are no pressurizer circumferential or meridional head welds.

SQN ASME Class I Equivalent Components O-SI-DXI-000-114.3 ATTI1 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 7 of 18 2.4 Pressurizer Nozzle-to-Vessel Welds and Nozzle Inside Radius Section (B-D)(ltem Numbers B3.1I0 and B3.120) and I OCFR50.55a(b)(2)(xxi)(A)

NOTE Per 10CF:R50.55a(b)(2)(xxi)(A) item number B3.120 in the 1998 Edition must be applied when us ng the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (b)(2) of the 10CFR50.55a. A visual examination with enhanced magnification that has a resolution sensitivity to detect a 1-mill width wire or crack, utilizing the allowable flaw length criteria in Table IWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (b)(2)of 10CFR50.55a, may be performed in place of an ultrasonic examination.

The pressurizer includes three 6-inch safety valve nozzles, one 6-inch relief valve nozzle, one 4-inch spray nozzle, and one 14-inch surge nozzle. All of the nozzle-to-vessel welds, shall be ultrasonically examined during the inspection interval. The nozzle inside radius sections on each nozzle shall be ultrasonically or visually examined. Examinations shall be distributed among the inspection periods.

2.5 Pressurizer Heater Penetration Welds There are 78 heater penetration welds located in the pressurizer lower head. These welds are not required to be examined by ASME Section Xl 2001 Edition, 2003 Addenda.

2.6 Pressurizer Nozzle-to-Safe End Welds (B-F)(ltem Number B5.40)

Each of the six nozzles identified in Section 2.4 includes a welded forging safe end.

TIhese pressurizer nozzle to safe end welds are included in the Risk Informed Piping Wlelds Examination Category (R-A). Refer to Section 9.0 of this Attachment.

2.7 .Pressurizer Pressure Retaining Bolting Larger Than Two Inches In Diameter (B-G-1)(ltem Number B6.60)

There is no pressure retaining bolting larger than 2 inches in diameter.

2.8 Pressurizer Pressure Retaining Bolting Two Inches And Smaller In Diameter (B-G-2)(ltem Number B7.20).

The pressurizer manway bolts shall be examined in accordance with visual examination method VT-1 during the inspection interval only when the connection is.

disassembled or the bolting is removed.

SCIN ASME Class I Equivalent Components 0-SI-DXI-000-114.3 ATT' 7 Unit 'I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 8 of 18 2.8 Fressurizer Pressure Retaining Bolting Two Inches And Smaller In Diameter (B-G-2)(Item Number B7.20) (continued)

Removal of the manway cover is performed in accordance with 0-MI-MXX-068-004.0 end provides for examination of bolting.

The pressurizer manway includes 16 bolts at 1.88 inches in diameter.

3.0 STEAM GENERATORS (4)

NOTE All four steam generators on Unit 1 were replaced during Unit 1 Cycle 12 refueling outage in the third period of the second inspection interval.

3.1 Steam Generator Primary Side Head Circumferential And Meridional Welds (B-B)(ltem Numbers B2.31 and B2.32)

There are no steam generator primary side circumferential or meridional head welds.

3.2 Steam Generator Primary Tubesheet-to-Head Weld (B-B)(ltem Number B2.40)

Each steam generator includes a tubesheet-to-head weld. The entire length of one tubesheet-to-head weld shall be ultrasonically examined during inspection interval.

3.3 Steam Generator Primary Nozzle Inside Radius Section (B-D)(ltem Number B.140)

NOTE Per 10CFR50.55a(b)(2)(xxi)(A) item number B3.140 in the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (b)(2) of the 10CFR50.55a. A visual examination with enhanced magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utiliZing the allowable flaw length criteria in Table IWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (b)(2)of 10CFR50.55a, may be performed in place of an ultrasonic examination.

SQN ASME Class I Equivalent Components 0-SI-DXI-000-114.3 AT1T Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit l and Unit 2) Page 9 of 18 3.3 Steam Generator Primary Nozzle Inside Radius Section (B-D)(ltem Number B.140) (continued)

The steam generator primary nozzles are an integral part of the vessel. Each steam generator consists of two integrally cast/forged nozzles. The Unit 1 replacement steam generators have forged nozzles. The primary nozzle inside radius section of all nozzles shall be ultrasonically or visually examined during the inspection interval.

Examinations shall be distributed among the inspection periods.

3.4 Steam Generator Primary Nozzle-to-Safe End Welds (B-F)(ltem Number B5.70)

Each Unit 2 steam generator includes two nozzles with buttered safe ends, and each Unit I steam generator includes two nozzles with separate safe end welds due to replacement steam generators.

These steam generator nozzle to safe end welds are included in the Risk Informed Piping Welds Examination Category (R-A). Refer to Section 9.0 of this Attachment.

3.5 Steam Generator Primary Pressure Retaining Bolting Larger Than Two Inches In Diameter (B-G-1 )(Item Number B6.90)

There is no pressure retaining bolting larger than two inches in diameter.

3.6 Steam Generator Primary Pressure Retaining Bolting Two Inches And Smaller In Diameter (B-G-2)(ltem Number B7.30)

Each steam generator includes two manways. Each manway includes 16 bolts at 1.88 inches in diameter. The bolting of two manways (all bolts, studs, and nuts) from one steam generator shall be visually examined in accordance with visual examination method VT-1 during the inspection interval when the connection is disassembled or the bolting is removed.

Removal of bolting is performed in accordance with 1-MI-MXX-068-003.0 and 2-MI-IMXX-068-003.0 and provides for examination of bolting.

4.0 -PIPING All ASME Code Class 1 (equivalent) piping systems to be examined are fabricated of stainless steel. The reactor coolant main loop piping straight lengths are centrifugal cast and the elbows are static cast. The reactor vessel auxiliary head adapters include a pressure retaining dissimilar metal weld in each and are include in the reactor coolant system. Specific material specifications for each piping system are included on the weld drawings.

SQN ASME Class 1 Equivalent Components 0-SI-DXI-000-114.3 AT'71 Unit I & 2 Subject to Examination Effective Date: 06-01-2D06 (Unit I and Unit 2) Page 10 of 18 4.0 PIPING (continued)

The following ASME Code Class I (equivalent) piping systems are subject to examination:

Chemical and Volume Control (CVC)

Reactor Coolant Main Loop (RX)

Reactor Coolant System (RC)

Residual Heat Removal (RHR)

Safety Injection (SI)

Ftl-ISI program includes the Chemical and Volume Control System, Reactor Coolant system Main Loop, Reactor Coolant System, Residual Heat Removal System, Safety Injection System, and Sampling and Water Quality System.

NOTE For third inspection interval, Class 1 Piping Welds (B-J) shall be in accordance with the RI-ISI examination requirements. See section 9.0 of this Attachment.

4.1 Piping Pressure Retaining Bolting Larger Than 2 Inches In Diameter (B-G-1)(Item Number B6.160)

There is no piping pressure retaining bolting larger than 2 inches in diameter.

4.2 Piping Pressure Retaining Bolting 2 Inches and Smaller in Diameter (B-G-2)(ltem number B7.5)

The following systems contain bolted piping flange connections. The examination of flange bolting in piping systems may be limited to one bolted connection among a group of bolted connection that are similar in design, size, function, and service.

Examination is required only when a flange connection is disassembled.

Examination of a bolted connection is required only once during the inspection interval in accordance with visual examination method VT-1.

A. Reactor Coolant System Piping Bolting The Reactor Coolant System piping includes bolted flange connections.

13. Chemical and Volume Control System Piping Bolting

SCN ASME Class I Equivalent Components 0-SI-DXI-000-114.3 ATTT Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and Unit 2) Page 11 of 18 4.2 Piping Pressure Retaining Bolting 2 Inches and Smaller in Diameter (B-G-2)(ltem number B7.5) (continued)

The Chemical and Volume Control System (seal water injection) piping includes bolted flange connections.

G. RHR System Piping Bolting The RHR System piping does not include any bolted connections.

[). Safety Injection System Piping Bolting The Safety Injection System piping includes bolted flange connections.

4.3 Pressure retaining welds in Piping (B-J)

NOTE For the third inspection interval, Class 1 Piping Welds (B-J) shall be in accordance with the RI-ISI examination requirements. Refer to section 9.0 of this Attachment.

5.0 REACTOR COOLANT PUMPS (4) - RCP 5.1 IRCP Pressure Retaining Bolting Larger Than Two Inches In Diameter (B-G-1)(Item Numbers B6.180, B6.190 and B6.200)

The main flange on all four Unit 1 pumps and on three Unit 2 pumps (#1, 2 and 3) includes 24 bolts of 4-1/2 inches in diameter and 30-1/2 inches in length.

The main flange on Unit 2 pump # 4 includes 24 studs of 4-1/2 inches in diameter and 30.6 inches in length, and 24 hydraulic nuts. The bolts on Unit 2 pump #4 were replaced during the U2C1 3 refueling outage per DCN E21858.

All of the bolts, or studs and nuts, from one pump shall be examined during the inspection interval if the (B-L-2) pump interior surface examination is performed.

The main flange bolts shall be ultrasonically or magnetic particle examined or the studs shall be ultrasonically or magnetic particle examined and the hydraulic nits shall be visually examined (VT-1) from one pump once during the inspection interval if the connection is disassembled at any time during the inspection interval.

The flange surface (one inch annular surfaces) surrounding each stud shall be visually examined (VT-1) from one pump once during the inspection interval if the connection is disassembled at any time during the inspection interval.

SCN ASME Class 1 Equivalent Components O-SI-DXI-000-114.3 ATT 7 Unit 'I& 2 Subject to Examination Effective Date: 06-01-2D06 (Unit I and Unit 2) Page 12 of 18 5.1 FRCP Pressure Retaining Bolting Larger Than Two Inches In Diameter (B-G-1)(Item Numbers B6.180, B6.190 and B6.200)

(continued)

F'rovisions for this examination are included-in MI-2.8 5.2 FtCP Pressure Retaining Bolting 2 Inches and Smaller in Diameter (B-G-2)(ltem Number B7.60)

Each RCP includes two sets of pressure retaining bolting 2 inches and smaller in ciameter. The bolting sets include the number 1 seal housing and cartridge seal assembly bolting. The Number 1 seal housing assembly bolting includes 12 HIEX head cap screws at 2 inches in diameter. The cartridge seal assembly bolting includes 8 socket head cap screws at 1.5 inches in diameter. The number 1 seal assembly bolting and cartridge seal assembly bolting from one pump shall be visually examined in accordance with visual examination method VT-1. All of the bolting from one pump shall be visually examined during the inspection interval, if the (B-L-2) pump interior surface examination is performed.

Removal of bolting is performed in accordance with MI-10.2.3 and provides for examination of bolting.

5.3 FtCP Casing Welds (B-L-1)(ltem Number B12.10)

The Unit 2 RCPs pumps do NOT have casing welds.

Each Unit 1 RCP casing includes a 2-piece welded type 304SST casting (reference memo B25910709 008).

The RCP casing weld from one Unit 1 pump shall be examined in accordance with visual examination method VT-1. The examination may be deferred to the end of the interval.

5.4 RCP Casing (B-L-2)(ltem Number B12.20) 11a pump is disassembled for maintenance, repair or volumetric examination during the inspection interval, the internal pressure boundary surfaces shall be visually Examined in accordance with visual examination method VT-3. The examination is limited to one pump.

Examination of the internal pressure boundary shall include the internal pressure retaining surfaces made accessible for examination by disassembly. If a partial examination is performed and a subsequent disassembly of the pump allows a more extensive examination, an examination shall be performed during the subsequent disassembly. A complete examination is required only once during the interval.

SON ASME Class I Equivalent Components O-SI-DXI-000-114.3 ATT 7 Unit I & 2 Subject to Examination Effective Date: 06-01-21306 (Unit 1 and Unit 2) Page 13 of 18 6.0 VALVES A tabulation of valves is contained in Attachment 6 for Unit 1 and Unit 2.

6.1 Valve Pressure Retaining Bolting Larger Than 2 Inches in Diameter (B-G-1)(ltem Numbers B6.210, 86.220 and B6.230)

There are no valves with pressure retaining bolting larger than 2 inches in diameter.

6.2 Valve Pressure Retaining Bolting 2 Inches and Smaller in Diameter (B-G-2)(ltem Number 87.70)

All of the bolts or studs and nuts in each connection of one valve within each group of valves shall be visually examined during the inspection interval in accordance with visual examination method VT-1, if the (Examination Category EB-M-2) valve interior surface examination is performed.

Valve disassembly is performed in accordance with 0-MI-MW-000-008.0 and provides for examination of bolting.

The following systems contain valves exceeding 4 inches NPS with bolted bonnet connections:

Reactor Coolant System Valve Bolting Residual Heat Removal System Valve Bolting Safety Injection System Valve Bolting 6.3 Valve Body Welds (B-M-1)(Item Numbers 812.30 and B12.40)

There are no valves with body welds.

6.4 V'alve Bodies (B-M-2)(ltem Number B12.50)

IFa valve exceeding 4-inch NPS is disassembled for maintenance, repair or volumetric examination during the inspection interval, the internal pressure boundary surface of the valve body shall be visually examined in accordance with visual examination method VT-3. Examinations are limited to one valve within each group of valves that are of the same constructional design (i.e., globe, gate, or check valve), manufacturing method, and that are performing similar functions in the system.

SCQN ASME Class I Equivalent Components O-SI-DXI-000-114.3 ATT1 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and Unit 2) Page 14 of 18 6.4 Valve Bodies (B-M-2)(ltem Number B12.50) (continued)

Examination of the internal pressure boundary shall include the internal pressure retaining surfaces made accessible for examination by disassembly. If a partial examination is performed and a subsequent disassembly of the valve allows a more extensive examination, an examination shall be performed during the subsequent disassembly. A complete examination is required only once during the interval.

The following systems contain valves exceeding 4-inches NPS:

Reactor Coolant System Residual Heat Removal System safety Injection System A tabulation of valves by groupings is presented in Attachment 6 for Unit 1 and Unit 2. Disassembly of valves is performed in accordance with 0-MI-MW-000.008.0 and provides for examination of valve internal pressure boundary surfaces.

-Listingsof valve examinations are identified on the Valve Interior Examination Drawing (See Attachment 7 for drawing number.).

7.0 WELDED SUPPORT ATTACHMENT NOTE Examination is required whenever component support member deformation, e.g., broken, bent, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.

7.1 Reactor Vessel Welded Support Attachments (B-K)(Item Number 1310.10)

There are no welded vessel supports.

7.2 Pressurizer Welded Support Attachments (B-K)(Item Number 1310.10)

A. Pressurizer Support Skirt Welded Support Attachment (Item Number BlO10)

The entire length of the pressurizer support skirt-to-vessel weld shall be surface examined from one side during the inspection interval.

B. Pressurizer Seismic Lugs (Item Number B1O.10)

SON ASME Class 1 Equivalent Components 0-SI-DXI-000-114.3 ATT1 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 15 of 18 7.2 Pressurizer Welded Support Attachments (B-K)(ltem Number E310.10) (continued)

There are four (4) welded seismic lugs on the pressurizer. All four (4) lugs shall be surface examined during the inspection interval.

7.3 Steam Generator Primary Welded Support Attachments (B-K)(Qtem Number B10.10)

There are no welded support attachments on the steam generator primary side main support. The four main support pads are secured to the steam generator support system by high strength bolts.

7.4 Piping Welded Support Attachments (B-K)(ltem Number B10.20)

Welded support attachments include the support attachments of piping required to be examined by Examination Category B-J. Included are those supports which have attachment welds to piping pressure retaining boundary. The entire length of each support attachment weld selected for examination shall be surface examined.

The examinations performed during the inspection interval should include 10 percent of the welded attachments. As a minimum 10 percent of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined. The examinations shall be distributed during the inspection interval.

Thefollowing systems include welded support attachments:

Chemical and Volume Control System Reactor Coolant System Residual Heat Removal System Safety Injection System 7.5 *RCP Welded Support Attachments (B-K)(Item Number BI 0.40)

There are no welded support attachments associated with the Unit 1 RCP.

There are three Unit 2 reactor coolant pumps, serial numbers 566 (RCP-1 cas ng),

704 (RCP-3 casing), and 709 (RCP-4 casing), with welded support attachments.

RCP-2 casing does not have any welded support attachments. Each pump has I:hree welded pump feet. The welded pump feet from one RCP shall be surface examined during the inspection interval. The examination shall cover 100 percent of the required area of each support attachment:

SQN ASME Class I Equivalent Components 0-SI-DXI-000-1 14.3 ATTi-Unit 'I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit land Unit 2) Page 16 of 18 7.6 Valves Welded Support Attachments (B-K)(ltem Number BI0.40)

There are no welded valve support attachments.

8.0 COMPONENT SUPPORTS 8.1 Reactor Vessel Component Support (F-A)(ltem Number F1.40)

The Reactor Vessel is supported by one reactor vessel support at alternative nozzles (outlet). The component support shall be examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the nozzles up to and including the attachment to the supporting structure.

8.2 Pressurizer Component Supports (F-A)(ltem Number F1.40)

A. Pressurizer Support Skirt The Pressurizer support skirt shall be examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the Pressurizer support skirt up to and including the attachment to the supporting structure.

EB. Pressurizer Seismic Lugs The Pressurizer seismic lugs support shall be examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the Pressurizer seismic lugs support up to and including the attachment to the supporting structure.

8.3 Steam Generator Component Supports (F-A)(ltem Number F1.40)

There is one component support associated with each Steam Generator.

The component support from one-Steam Generator shall be examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the Steam generator support up to and including the attachment to the supporting structure.

SCIN ASME Class 1 Equivalent Components 0-SI-DXI-000-114.3 ATT1 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and Unit 2) Page 17 of 18 8.4 Piping Component Supports (F-A)(ltem Number F1.10 Twenty-five percent of the class I piping component supports on piping not Exempted from volumetric, surface, or VT-1 or VT-3 visual examination by IWB-1220 shall be visually examined during the inspection interval in accordance with visual examination method VT-3. In addition, portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe are also exempt from examination requirements of IWF-2000. This examination includes integrally welded and non-integrally welded component supports.

Component supports extend from the piping up to and including the attachment to the supporting structure.

The settings of variable and spring-type hangers shall be verified in accordance with the applicable NDE procedure with the acceptance criteria identified in the ScaI Plan (see PRISIM data base) or the applicable work instruction.

The following systems include component supports:

Chemical and Volume Control System Piping.Component Supports Reactor Coolant System Piping Component Supports Reactor Coolant System Main Loop Piping Component Supports Residual Heat Removal System Piping Component Supports Safety Injection System Piping Component Supports 8.5 FRCP Component Supports (F-A)(Item Number F1.40)

There is one component support associated with each RCP. The component support from one RCP shall be visually examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the RCP up to and including the attachment to the supporting structure.

8.6 Valve Component Supports (F-A)(ltem number F1.40)

There are no valves with component supports.

9.0 EXAMINATION CATEGORY R-A RISK INFORMED PIPING

[EXAMINATIONS (R-A)

Refer to Table E of Attachment 4 for Unit 1 and Table E of Attachment 5 for Unit 2 for examination schedule under the RI-ISI program.

SQN ASME Class I Equivalent Components 0-SI-DXI-000-114'3 ATT1 Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and Unit 2) Page 18 of 18 9.0 EXAMINATION CATEGORY R-A RISK INFORMED PIPING EXAMINATIONS (R-A) (continued)

FRI-ISI program includes the Chemical and Volume Control System, Reactor Ccolant System, Reactor Coolant System Main Loop, Residual Heat Removal System, safety Injection System, and Sampling and Water Quality System.

ASME Code Class 1 high safety significant piping structural elements subject to thermal fatigue selected for examination shall be ultrasonically examined.

ASME Code Class 1 high safety significant piping segments subject to thermal fatigue containing branch connections welds 2 inches NPS and less and/or socket wields shall be visually (VT-2) examined. (A request for relief is being submitted to NRC for the third interval RFR 1-RI-ISI-2 and 2-RI-ISI-2)

A.SME Code Class 1 high safety significant piping structural elements subject to high cycle mechanical fatigue shall be visually (VT-2) examined.

ASME Code Class 1 high safety significant piping structural elements subject to corrosive, erosive, or cavitation wastage selected for examination shall be ultrasonically (for internal wastage) or surface (for external wastage) examined.

ASME Code Class 1 high safety significant piping structural elements subject to crevice corrosion cracking selected for examination shall be ultrasonically examined.

ASME Code Class I high safety significant piping structural elements subject to primary water stress corrosion cracking (PWSCC) shall be visually (VT-2) examined.

ASME Code Class 1 high safety significant piping structural elements subject to intergranular stress corrosion cracking (IGSCC) selected for examination shall be ultrasonically examined.

ASME Code Class 1 high safety significant piping structural elements subject to microbiologically influence corrosion (MIC) selected for examination shall be visually (VT-3) examined on internal surface or ultrasonically examined.

ASME Code Class 1 high safety significant piping structural elements subject to flow accelerated corrosion (FAC) selected for examination shall be in accordance with the owner FAC program, SPP-9.7.

SQN ASME Class 2 Equivalent Components O-SI-DXI-000-114.3 ATT2 Unit 1 & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 1 of 20 ATTACHMENT 2 - ASME Class 2 Equivalent Components Subject to Examination (Unit I and Unit 2)

SON ASME Class 2 Equivalent Components O-SI-DXI-000-114.3 ArT2 Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 2 of 20 The ASME Code Class 2 (equivalent) components to be examined during the inspection interval are outlined below.

The entire length of each weld described shall be examined for the third 10-year ISI interval unless otherwise noted. When a portion of a weld length is to be examined during an inspection period, the areas examined each inspection period shall tie documented on the examination data sheets.

IMaterial specifications for piping and equipment is stated on the ISI drawings.

Table B, Table D (Component Supports) and Table E (RI-ISI elements/segments) of Attachment 4 for Unit 1 and Attachment 5 for Unit 2 shall be used for items selected for examination. These tables provide the examination schedule for the interval and additional information such as reference ISI drawing numbers and ASME Section Xl Table-IWC-2500-1 and RI-ISI examination categories.

1.0 S3TEAM GENERATORS (4)

NOTE All four steam generators on Unit 1 were replaced during Unit 1 Cycle 12 refueling outage in the th rd period of the second interval.

1.1 Steam Generator Secondary Side Circumferential Shell Welds (C-A)(Item Number C1.10)

A. Steam Generator Secondary Side Circumferential Shell Welds (Unit 2 only)

There are three circumferential shell welds at gross structural discontinuities on each unit 2 steam generator. The entire length of these three shell welds from one steam generator shall be ultrasonically examined during the inspection interval.

13. Steam Generator Secondary Side circumferential Shell Welds (Unit 1 only)

There are no circumferential shell welds at gross structural discontinuities on the replacement steam generators.

1.2 Steam Generator Secondary Side Circumferential Head Welds (C-A)(Qtem Number C1.20)

[Each steam generator includes a circumferential head-to-shell weld. The entire length of one head-to-shell weld from one Steam Generator shall be ultrasonically examined during the inspection interval.

SON ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATT2 Unit 1 & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and Unit 2) Page 3 of 20 1.3 steam Generator Secondary Side Tubesheet-to-Shell Weld (C-A)(ltem Number C1.30)

Each steam generator includes a tubesheet-to-shell weld. The entire length of one lubesheet-to-shell weld from one Steam Generator shall be ultrasonically examined during the inspection interval.

1.4 Steam Generator Secondary Side Nozzle-to-Vessel Welds (C-B)(ltem Number C2.21)

A. Steam Generator Secondary Side Nozzle-to-Vessel Welds (Unit 2 only)

Each unit 2 steam generator is greater than 1/2 inch nominal thickness and includes one feedwater nozzle and one main steam nozzle. A total of two nozzle-to-vessel welds from one Steam Generator shall be ultrasonically and magnetic particle examined during the inspection interval.

13. Steam Generator Secondary Side Nozzle-to-Vessel Welds (Unit 1 only)

Each unit 1 steam generator is greater than 1/2 inch nominal thickness and includes one feedwater nozzle-to-vessel weld. The main steam nozzle is NOT welded (forged with the head). One feedwater nozzle-to-vessel weld from one steam generator shall be ultrasonically and magnetic particle examined during the inspection interval.

1.5 s3team Generator Secondary Side. Nozzle Inside Radius Section (C-B)(ltem Number C2.22)

The nozzle inside radius sections on each nozzle from one Steam Generator shall be ultrasonically examined during the inspection interval.

A. Steam Generator Secondary Side Nozzle Inside Radius Section (C-B)(ltem Number C2.22) Unit 2 only]

Each unit 2 steam generator includes one feedwater nozzle inside radius section and one main steam nozzle inside radius section. A total of two nozzle inside radius sections from one steam generator shall be ultrasonically examined during the inspection interval.

13. Steam Generator Secondary Side Nozzle Inside Radius Section (C-B)(ltem Number C2.22)(Unit 1 only)

Each unit 1 steam generator includes one feedwater nozzle inside radius section. The main steam nozzle is forged with the head and does not have an inside radius section, due to the design for the flow limiters. A total of one feedwater nozzle inside radius section from one steam generator shall be ultrasonically examined during the inspection interval.

SON ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATr2 Unit I & 2 Subject to Examination Effective Date: 06-01--2006 (Unit 1 and Unit 2) Page 4 of 20 1.6 Steam Generator Secondary Side Pressure Retaining Bolting Exceeding 2 Inches in Diameter (C-D)(ltem Number C4.10)

There is no steam generator secondary side bolting exceeding 2 inches in diameter.

2.0 RESIDUAL HEAT REMOVAL HEAT EXCHANGERS (2) - RHRHX 2.1 RHRHX Shell Circumferential Weld (C-A)(ltem Number C1.10)

There is one circumferential shell weld located at a gross structural discontinuity on each RHRHX. The entire length of one circumferential shell weld from one RHRHX shall be ultrasonically examined during the inspection interval.

2.2 IRHRHX Head Circumferential Weld (C-A)(ltem Number C1.20) 1There is one circumferential head-to-shell weld per RHRHX. The entire length of one head-to-shell weld from one RHRHX shall be ultrasonically examined during the inspection interval.

2.3 RHRHX Tubesheet to Shell Weld (C-A)(ltem Number C1.30)

There are no RHRHX tubesheet-to-shell welds.

2.4 RHRHX Nozzle-to-Vessel Welds (without reinforcing plate)

(C-B)(ltem Number C2.21)

The channel cylinder section of each RHRHX is over 1/2 inch nominal thickness and includes one inlet nozzle (14-inches NPS) and one outlet nozzle (14-inches NPS).

A total of two nozzle-to-vessel welds from the one RHRHX shall be ultrasonically and liquid penetrant examined during the inspection interval.

2.5 FZHRHX Nozzle Inside Radius Section (C-B)(ltem Number C2.22)

A total of two nozzle inside radius sections from one RHRHX shall be ultrasonically examined during the inspection interval when the nozzle-to-vessel welds are being examined. See request for relief 1-ISI-1 5 and 2-lSI-15 which will be submitted later for NRC approval.

2.6 RHRHX Pressure Retaining Bolting Exceeding 2 Inches in Diameter (C-D)(ltem Number C4.10)

There is no RHRHX bolting exceeding 2 inches in diameter.

SCIN ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATTY2 Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 5 of 20 3.0 C:ONTAINMENT SPRAY HEAT EXCHANGERS (2) - CSHX (UNIT 1) 3.1 CSHX IA (Unit 1)

A. CSHX IA Shell Circumferential Weld (C-A)(Item Number C1.10)

There is one circumferential shell weld (flange-to-shell) on the CSHX. The entire length of this shell weld shall be ultrasonically examined during the inspection interval.

E,. CSHX IA Head Circumferential Weld (C-A)(ltem Number C1.20)

There are no CSHX circumferential head-to-shell welds C:. CSHX IA Tubesheet-to-Shell Weld (C-A)(ltem Number C1.30)

There is one tubesheet-to-shell weld on the CSHX. The entire length of this tubesheet-to-shell weld shall be ultrasonically examined during the inspeclion interval.

D. CSHX IA Nozzle-to-Vessel Welds (without reinforcing plate) (C-B)(ltem Number C2.21).

The channel cylinder section of the CSHX is over 1/2 inch nominal thickness and includes one inlet nozzle (12-inches NPS) and one outlet nozzle (12-inches NPS). The two nozzle-to-vessel welds shall be ultrasonically and magnetic particle examined during the inspection interval.

E. CSHX IA Nozzle-to-Vessel Inside Radius Section (C-B)(ltem Number C2..22)

There are no CSHX nozzles greater than 12 inches NPS.

F. CSHX IA Pressure Retaining Bolting Exceeding 2 Inches in Diameter (C-D)(ltem Number C4.10)

There is no CSHX bolting exceeding 2 inches in diameter.

3.2 CSHX 1B (Unit 1)

The containment spray heat exchanger 1B was replaced in Ul C9 of the second interval.

A. CSHX lB Shell Circumferential Weld (C-A)(ltem Number Cl.10)

There are two circumferential shell welds (one flange-to-shell and one flange-to-head) on the CSHX. The entire length of.these shell welds shall be ultrasonically examined during the inspection interval.

SIN ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATT2 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 6 of 20 3.2 CSHX 1B (Unit 1) (continued)

B. CSHX 1B Head Circumferential Weld (C-A)(ltem Number C1.20)

There are no CSHX circumferential head-to-shell welds

('. CSHX 1B Tubesheet-to-Shell Weld (C-A)(ltem Number C1.30)

There is one tubesheet-to-shell weld on the CSHX. The entire length of the tubesheet-to-shell weld shall be ultrasonically examined during the inspec:ion interval.

[). CSHX 1B Nozzle-to-Vessel Welds (without reinforcing plate) (C-B)(Item Number C2.21)

The channel cylinder section of each CSHX is over 1/2 inch nominal thickness and includes one inlet nozzle (12-inches NPS) and one outlet nozzle (12-inches NPS). The nozzles are set on the shell and are 3/8 inch nominal thickness.

The two nozzle-to-vessel welds shall be ultrasonically and liquid penetrant examined during the inspection interval.

E. CSHX 1B Nozzle-to-Vessel Inside Radius Section (C-B)(ltem Number C2.22)

There are no CSHX nozzles greater than 12 inches NPS.

F. CSHX 1B Pressure Retaining Bolting Exceeding 2 Inches in Diameter (C-D)(ltem Number C4.10)

There is no CSHX bolting exceeding 2 inches in diameter.

3.3 COSHX 2A and 2B (Unit 2)

A. CSHX 2A and 2B Shell Circumferential Weld (C-A)(ltem Number C1.10)

There is one circumferential shell weld (flange-to-shell) on each CSHX. The entire length of this shell weld from one CSHX shall be ultrasonically examined during the inspection interval.

13. CSHX 2A and 2B Head Circumferential Weld (C-A)(ltem Number C1.20)

There are no CSHX circumferential head-to-shell welds IJ. CSHX 2A and 2B Tubesheet-to-Shell Weld (C-A)(ltem Number C1.30)

There is one tubesheet-to-shell weld on each CSHX. The entire length of one tubesheet-to-shell weld from one CSHX shall be ultrasonically examined during the inspection interval.

SCIN ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATIY2 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 7 of 20 3.3 CSHX 2A and 2B (Unit 2) (continued)

[). CSHX 2A and 2B Nozzle-to-Vessel Welds (without reinforcing plate) (C-B)(ltem Number C2.21)

The channel cylinder section of each CSHX is over 1/2 inch nominal thickness and includes one inlet nozzle (12-inches NPS) and one outlet nozzle (12-inches NPS). A total of two nozzle-to-vessel welds from one CSHX shall be ultrasonically and magnetic particle examined during the inspection interval.

E. CSHX 2A and 2B Nozzle-to-Vessel Inside Radius Section (C-B)(ltem Number C2.22)

There are no CSHX nozzles greater than 12 inches NPS.

F.. CSHX 2A and 2B Pressure Retaining Bolting Exceeding 2 Inches in Diameter (C-D)(ltem Number C4.10)

There is no CSHX bolting exceeding 2 inches in diameter.

4.0 SEAL WATER HEAT EXCHANGER (1) (SWHX) 4.1 ';WHX Shell Circumferential Weld (C-A)(ltem Number C1.10)

There is one circumferential shell weld located at a gross structural discontinuity on tie SWHX. The SWHX nominal wall thickness is less than 0.20 inches. The entire length of this shell weld from the SWHX shall be surface examined during the inspection interval.

4.2 S;WHX Head Circumferential Weld (C-A)(ltem Number C1.20)

There is one circumferential head-to-shell weld on the SWHX. The SWHX nominal wall thickness is less than 0.20 inches. The entire length of one head-to-shell 'weld from the SWHX shall be surface examined during the inspection interval.

4.3 S;WHX Tubesheet to Shell Weld (C-A)(ltem Number C1.30)

There are no SWHX tubesheet-to-shell welds.

4.4 SWHX Nozzle-to-Vessel Welds (C-B)(ltem Number C2.11)

The SWHX nominal wall thickness is less than 0.20 inches.

There are no SWHX nozzles greater than 4 inches NPS.

SON ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATr2 Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 8 of 20 4.5 'iWHX Pressure Retaining Bolting Exceeding 2 Inches in Diameter (C-D)(ltem Number C4.10)

There is no SWHX bolting exceeding 2 inches in diameter.

5.0 SEAL WATER FILTER(1)- SWF 5.1 SWF Shell Circumferential Weld (C-A)(ltem Number C1.10)

There is one circumferential shell weld located at a gross structural discontinuil:y on the SWF. The SWF nominal wall thickness is less than 0.20 inches. The entire length of this shell weld shall be surface examined during the inspection interval.

5.2 SWF Head Circumferential Weld (C-A)(ltem Number C1.20)

There is one circumferential head-to-shell weld on the SWF. The SWF nominal wall thickness is less than 0.20 inches. The entire length of this head-to- shell weld from the SWF shall be surface examined during the inspection interval.

5.3 SWF Tubesheet to Shell Weld (C-A)(ltem Number C1.30)

There are no SWF tubesheet-to-shell welds.

5.4 SWF Nozzle-to-Vessel Welds (C-B)(ltem Number C2.1 1)

The SWF nominal wall thickness is less than 0.20 inches.

There are no SWF nozzles greater than 4 inches NPS.

5.5 SWF Pressure Retaining Bolting Exceeding 2 Inches in Diameter (C-D)(ltem Number C4.10)

There is no SWF bolting exceeding 2 inches in diameter.

6.0 SEAL WATER INJECTION FILTER (2) - SWIF 6.1 SWIF Circumferential Weld (C-A)(ltem Number C1.10)

There is one circumferential shell weld located at a gross structural discontinuity on Each SWIF; The SWIF nominal wall thickness is 0.875 inches. The entire length of this shell weld from one SWIF shall be ultrasonically examined during the inspection interval.

SCIN ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATIY2 Unit 'l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and'Unit 2) Page 9 of 20 6.2 S;WIF Head Circumferential Weld (C-A)(ltem Number C1.20)

There is one circumferential head-to-shell weld on each SWIF. The SWIF nominal wall thickness is greater than 0.20 inches. The entire length of this head-to-shell weld from one SWIF shall be ultrasonically examined during the inspection interval.

6.3 S;WIF Tubesheet to Shell Weld (C-A)(Item Number C1.30)

There are no SWIF tubesheet-to-shell welds.

6.4 SWIF Nozzle-to-Vessel Welds (without reinforcing plate)

(C-B)(ltem Number C2.21)

There are no SWIF nozzles greater than 4 inches NPS.

6.5 S'WIF Nozzle-to-Vessel inside Radius Section (C-B)(Item Number G2.22)

There are no SWIF nozzles greater than 12 inches NPS.

6.6 SWIF Pressure Retaining Bolting Exceeding 2 Inches in Diameter (C-D)(ltem Number C4.10)

There is no SWIF bolting exceeding 2 inches in diameter.

7.0 CENTRIFUGAL CHARGING PUMP (CCP) TANK (BORON INJECTION TANK (BIT)) (1)

, . I NOTE The CCP tank was formerly identified as the BIT tank. This change occurred in Unit I Cycle 4 and Unit 2 Cycle 4 refueling outages. As a transition, both IDs are being retained for tractability.

7.1 CCP Tank (BIT) Circumferential Shell Welds (C-A)(Item Number

(,1.1 0) 7here are no CCP tank circumferential shell welds.

7.2 CCP Tank (BIT) Circumferential Head Welds (C-A)(ltem Number C1.20)

There are two circumferential head-to-shell welds located at structural discontinuities on the CCP Tank. CCP Tank nominal wall thickness is greater than 0.20 inch.

These welds shall be ultrasonically examined during the inspection interval.

SCN ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATiF2 Unit 1 & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 10 of 20 7.3 ACCP Tank (BIT) Nozzle-to-Head Welds (without reinforcing plate)

(C-B)(ltem Number C2.21)

The CCP Tank is over 1/2 inch nominal thickness and includes two nozzles. One nozzle is located on each head with a 6-inch NPS. A total of two nozzle-to-vessel welds shall be ultrasonically and surface examined during the inspection interval.

7.4 CCP Tank (BIT) Nozzle-to-Head inside Radius Section (C-B)(Item Number C2.22)

There are no CCP Tank nozzles greater than 12 inches NPS.

7.5 GCP Tank (BIT) Pressure Retaining Bolting Exceeding Two Inches in Diameter (C-D)(ltem Number C4.10)

There are 16 manway cover studs at 2-1/2 inches in diameter. All 16 studs shall be ultrasonically examined during the inspection interval. The studs may be examined either in place under load or upon disassembly of the connection.

8.0 PIPING Material specifications for each piping system are stated on the weld isometrics.

The following Class 2 piping systems are subject to examination:

High Pressure Safety Injection (includes parts of CVC, CS, RHR and SI)

Residual Heat Removal (RHR) safety Injection (SI)

Main Steam (MS)

Feedwater (FW)

Containment Spray (CS)

Auxiliary Feedwater RI-ISI program includes the Auxiliary Feedwater System, Steam Generator Ellowdown System, Chemical Volume Control System, Containment Isolation system, Containment Spray System, Feedwater System, Main Steam System, Reactor Coolant System, Residual Heat Removal System, Safety Injection System, and Sampling and Water Quality System.

SON ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATi-r2 Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page II of 20 8.1 -Piping Pressure-Retaining Bolting Greater Than 2 Inches In Diameter (C-D)(ltern Number C4.20)

There is no Class 2 Pressure-Retaining Bolting larger than two inches in diameter.

8.2 Pressuring Retaining Welds in Piping (C-F-1 and C-F-2)

NOTE For the third inspection interval, Class 2 Piping Welds (C-F-1 and C-F-2) shall be in accordance with the RI-ISI examination requirements. Refer to Section 13.0 of this Attachment.

9.0 PUMPS 9.1 RHR Pumps (2) - RHRP A. RHRP Pressure Retaining Bolting Greater Than 2 Inches in Diameter (C-D)(Item Number C4.30)

There is no pressure retaining bolting greater than 2 inches in diameter or, the RHRP.

The stuffing box extension to pump casing connection bolting is not greatE r than two inches in diameter.

The connection includes 24 studs at 1-1/4 inches in diameter with nuts and washers.

[3. RHRP Casing Welds (C-G)(Item Number C6.10)

The RHRP does not include any casing welds. The casing is a one piece forging.

9.2 CVCS Centrifugal Charging Pumps (2) - CCP A. CCP Pressure Retaining Bolting Greater Than 2 Inches In Diameter (C-D)(ltem Number C4.30)

There is no pressure retaining bolting greater than 2 inches in diameter on the CCP.

SQN ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 AT1I2 Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 12 of 20 9.2 C:VCS Centrifugal Charging Pumps (2) - CCP (continued)

El. CCP Casing Welds (C-G)(ltem Number C6.10)

The CCP does NOT include any casing welds. The casing is a one piece forging.

9.3 Safety Injection Pumps (2) - SIP A. SIP Pressure Retaining Bolting Greater Than 2 Inches in Diameter (C-D)(Jtem Number C4.30)

There is no pressure retaining bolting greater than 2 inches in diameter on the SIP.

B. SIP Casing Welds (C-G)(ltem Number C6.10)

The SIP does NOT include any casing welds. The casing is a one piece forging.

9.4 Containment Spray Pumps (2) - CSP A. CSP Pressure Retaining Bolting Greater Than 2 Inches In Diameter (C-D)(Item Number C4.30)

There is no pressure retaining bolting greater than 2 inches in diameter on the CSP.

[3. CSP Casing Welds (C-G)(Item Number C6.10)

The CSP does NOT include any casing welds. The casing is a one piece forging.

10.0 VALVES Systems including ASME Code Class 2 valves subject to examination are identified in Section 8.0. A tabulation of valves is presented in Attachment 6 for Unit 1 and lJnit 2.

10.1 Valve Pressure-Retaining Bolting Greater Than 2 Inches in Diameter (C-D)(Item Number C4.40)

There is no Class 2 pressure-retaining bolting greater than 2 inches in diameter.

SQN ASME Class 2 Equivalent Components O-Sl-DXI-000-114.3 ATI-2 Unit*l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and Unit 2) Page 13 of 20 10.2 V/alve Body Welds (C-G)(Item Number C6.20)

There are no Class 2 valves with body welds.

11.0 WELDED SUPPORT ATTACHMENTS (C-C)

NOTE Examination is required whenever component support member deformation, e.g., broken, bent, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.

11.1 steam Generator Secondary Side Welded Support Attachments (C-C)(ltem Number C3.10)

There are no vessel welded support attachments.

11.2 FZHRHX Welded Support Attachments (C-C)(ltem Number C3.10)

There are two welded support attachments on each RHRHX. A total of two support pad-to-vessel welds from one RHRHX shall be liquid penetrant examined during the inspection interval.

11.3 (CSHX Welded Support Attachments (C-C)

A. CSHX 1A Welded Support Attachments Unit 1 (C-C)(ltem Number C3.10)

There are four welded support attachments on the Unit 1 CSHX. The four welded support attachments shall be magnetic particle examined during the inspection interval.

EB. CSHX 1B Welded Support Attachments Unit 1(C-C)(ltem Number C3.10)

The Unit 1 containment spray heat exchange I B was replaced in U1 C9 of the second interval.

There are four welded support attachments on the Unit 1 CSHX. The four welded support attachments shall be liquid penetrant examined during the inspection interval.

,. CSHX 2A and 2B Welded Support Attachments Unit 2 (C-C)(ltem Number C3.1 0)

SCQN ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 AT1-2 Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 14 of 20 11.3 (CSHX Welded Support Attachments (C-C) (continued)

There are four welded support attachments on each Unit 2 CSHX. A total of four welded support attachments from one CSHX shall be magnetic particle examined during the inspection interval.

11.4 ';WHX Welded Support Attachments (C-C)(Item Number C3.10)

There are two welded support attachments on the SWHX. A total of two welded support attachments from the SWHX shall be liquid penetrant examined during the inspection interval.

11.5 SWF Welded Support Attachments (C-C)(Item Number C3.10)

There are four welded support attachments on the SWF. A total of four weldec support attachments from the SWF shall be liquid penetrant examined during the inspection interval.

11.6 SWIF Welded Support Attachments (C-C)(ltem Number C3.10)

There are three welded support attachments on each SWIF. A total of three welded support attachments from one SWIF shall be liquid penetrant examined during the inspection interval.

11.7 CCP Tank (BIT) Welded Supports (C-C)(ltem Number C3.10)

There are four. welded support attachment pads welded to the shell. A total of four welded support attachments from the CCP Tank shall be surface examined during tie inspection interval.

11.8 Piping Welded Support Attachments (C-C)(ltem Number C3.10)

Welded support attachments include the support attachments of piping required to be examined by Examination Category C-F-1 and C-F-2. Included are those supports which have attachment welds to piping pressure retaining boundary. The E.entire length of each welded support attachment weld selected for examination shall be surface examined during the inspection interval.

The examinations performed during the inspection interval should include 10 percent of the welded support attachments. As a minimum 10 percent of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined. The examinations shall be distributed during the inspection interval.

The following piping systems include welded support attachments:

Chemical Volume Control

SQN ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATT2 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 15 of 20 11.8 Piping Welded Support Attachments (C-C)(ltem Number C3.10)

(continued)

Containment Spray Feedwater High Pressure Safety Injection (which includes Chemical Volume Control, Containment Spray, Residual Heat Removal, and Safety Injection Systems)

The High Pressure Safety Injection welded support attachments selected for examination are included in the Chemical Volume Control, Containment Spray, Residual Heat Removal, or Safety Injection Systems.

Main Steam Residual Heat Removal Safety Injection Auxiliary Feedwater 11.9 C.CP Welded SuppDrt Attachments (C-C)(ltem Number C3.30)

There are four welded support attachments on each CCP. A total of four welded support attachments from one CCP shall be liquid penetrant examined during the inspection interval.

11.10 (CSP Welded Support Attachments (C-C)(ltem Number C3.30)

There are no welded support attachments associated with the CSP.

11.11 FZHRP Welded Supports Attachments (C-C)(ltem Number C3.30)

There are no welded support attachments associated with the RHRP.

11.12 SIP Welded Support Attachments (C-C)(ltem Number C3.30)

There are no welded support attachments associated with the SIP.

11.13 Valves Welded Support Attachments (C-C)(ltem Number C3.40)

There are no welded valve support attachments.

12.0 COMPONENT SUPPORTS (F-A)

SQN ASME Class 2 Equivalent Components O-SI-DXI-000-114.3 AT-Ir2 Unit 1 & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and Unit 2) Page 16 of 20 12.1 steam Generator Secondary Side Component Supports (F-A)(ltem Number F1.40)

There is one component support on each steam generator. The component support from one steam generator shall be visually examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from steam generator up to and including the attachment to the supporting structure.

12.2 RHRHX Component Supports (F-A)(Item Number FI.40)

There is one component support on each RHRHX. The component support from one heat exchanger shall be visually examined during the inspection interval ir, accordance with visual examination method VT-3. The component support extends from the heat exchanger up to and including the attachment to the supporting Structure.

12.3 GSHX Component Supports (F-A)(ltem Number FI.40)

A. CSHX 1A Component Supports Unit 1 (F-A)(ltem Number F1.40)

There is one component support on the CSHX. The component support shall be examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the heat exchanger up to and including the attachment to the supporting structure.

13. CSHX 1 B Component Supports Unit 1 (F-A)(ltem Number F1.40)

The containment spray heat exchange 1B was replaced in Ul C9 in the second interval.

There is one component support on the CSHX. The component support from shall be examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the heat exchanger up to and including the attachment to the supporting structure.

,. CSHX 2A and 2B Component Supports Unit 2 (F-A)(ltem Number F1.40)

There is one component support.on each CSHX. The component suppor. from one heat exchanger shall be examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the heat exchanger up to and including the attachment to the supporting structure.

SCN ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 AT12 Unit 'I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 17 of 20 12.4 S'WHX Component Supports (F-A)(Item Number F1.40)

There is one component support on the SWHX. The component support from 1he heat exchanger shall be examined during the inspection interval in accordance with

,visual examination method VT-3. The component support extends from the heat Exchanger up to and including the attachment to the supporting structure.

12.5 S;WF Component Supports (F-A)(ltem Number F1.40)

There is one component support on the SWF. The component support from the SWF shall be examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the SWF up to and including the attachment to the supporting structure.

12.6 SWIF Component Supports (F-A)(ltem Number F1.40)

There is one component support on each SWIF. The component support from one

'iWIF shall be visually examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the SWIF up to and including the attachment to the supporting structure.

12.7 CCP Tank (BIT) Component Supports (F-A)(Item Number F1.40)

There is one component support associated with the CCP tank. The component support shall be examined VT-3 during the inspection interval. The component support extends from the CCP Tank up to and including the attachment to the support structure.

12.8 Piping Component Supports (F-A)(ltem Number F1.20)

Fifteen percent of the class 2 piping component supports on piping not exempt from volumetric, surface, or VT-1 or VT-3 visual examination by IWC-1 220 shall be examined during the inspection interval in accordance with visual examination method VT-3. In addition, portions of supports that are in accessible by being encased in concrete, buried underground, or encapsulated by guard pipe are also exempt from the examination requirements of IWF-2000. This examination includes integrally welded and non-integrally welded component supports. Component supports extend from the piping up to and including the attachment to the supporting structure.

The setting of variable and spring-type hangers shall be verified in accordance with the applicable NDE procedure with the acceptance criteria shown in the Scan Plan (see PRISIM data base) or the applicable work instruction.

The following piping systems include component supports:

Chemical Volume Control

SON ASME Class 2 Equivalent Components O-SI-DXI-000-114.3 ATT2 Unit 1 & 2 Subject to Examination Effective Date: 06-01-21306 (Unit I and Unit 2) Page 18 of 20 12.8 Piping Component Supports (F-A)(ltem Number F1.20)

(continued)

Containment Spray Feedwater High Pressure Safety Injection (which includes Chemical Volume Control, Containment Spray, Residual Heat Removal, and Safety Injection Systems) component supports selected for examination are included in the Chemical Volume C:ontrol, Containment Spray, Residual Heat Removal, or Safety Injection Systems.

Main Steam Residual Heat Removal safety Injection Auxiliary Feedwater 12.9 FtHRP Component Supports (F-A)(ltem Number F1.40)

Each RHRP includes one component support bolted to the pump feet which are integrally forged with the pump. The component support from one pump shall be visually examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the RHRP up to and including the attachment to the supporting structure.

12.10 CCP Component Supports (F-A)(ltem Number F1.40)

Each CCP includes one component support bolted to the pump feet which are integrally welded to the pump. The component support from one pump shall be visually examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the CCP up to and including the attachment to the supporting structure.

12.11 SIP Component Supports (F-A)(ltem Number F1.40)

Each SIP includes one component support bolted to the pump feet which are integrally forged with the pump. The component support from one pump shall be visually examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the SIP up to and including the attachment to the supporting structure.

SON ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATT2 Unit 1 & 2 subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 19 of 20 12.12 C:SP Component Supports (F-A)(ltem Number F1.40)

Each CSP includes one component support bolted to the pump feet which are integrally forged with the pump. The component support from one pump shall be visually examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the CSP up t: and including the attachment to the supporting structure.

12.13 V'alve Component Supports (F-A)(Item Number F1.40)

There are two valves with one support each in the Residual Heat Removal system.

The component support from one valve shall be examined during the inspection interval in accordance with visual examination method VT-3. The component support extends from the valve up to and including the attachment to the supporting structure.

The settings of variable and spring-type hangers shall be verified in accordance with the applicable NDE procedure with the acceptance criteria shown in the Scan Plan (see PRISIM database) or the applicable work instruction.

13.0 EXAMINATION CATEGORY R-A RISK INFORMED PIPING EXAMINATIONS (R-A) -THIRD INTERVAL Refer to Table E of Attachment 4 for Unit 1 and Table E of Attachment 5 for Unit 2 for examination schedule for examination under the RI-ISI program.

FRI-ISI program includes the Auxiliary Feedwater System, Steam Generator Ellowdown System, Chemical Volume Control System, Containment Isolation

System, Containment Spray System, Feedwater System, Main Steam System, Reactor Coolant System, Residual Heat Removal System, Safety Injection System, and Sampling and Water Quality System.

ASME Code Class 2 high safety significant piping structural elements subject to thermal fatigue selected for examination shall be ultrasonically examined.

ASME Code Class 2 high safety significant piping segments subject to thermal fatigue containing branch connections welds 2 inches NPS and less and/or socket welds shall be visually (VT-2) examined. (Refer to RFR 1-RI-ISI-2 and 2-RI-ISI-2)

ASME Code Class 2 high safety significant piping structural elements subject to high cycle mechanical fatigue shall be visually (VT-2) examined.

ASME Code Class 2 high safety significant piping structural elements subject to corrosive, erosive, or cavitation wastage selected for examination shall be ultrasonically (for internal wastage) or surface (for external wastage) examined.

SQN ASME Class 2 Equivalent Components 0-SI-DXI-000-114.3 ATT2 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit I and Unit 2) Page 20 of 20 13.0 EXAMINATION CATEGORY R-A RISK INFORMED PIPING EXAMINATIONS (R-A) -THIRD INTERVAL (continued)

ASME Code Class 2 high safety significant piping structural elements subject to crevice corrosion cracking selected for examination shall be ultrasonically examined.

ASME Code Class 2 high safety significant piping structural elements subject to primary water stress corrosion cracking (PWSCC) shall be visually (VT-2) examined.

ASME Code Class 2 high safety significant piping structural elements subject to intergranular stress corrosion cracking (IGSCC) selected for examination shall be ultrasonically examined.

ASME Code Class 2 high safety significant piping structural elements subject to microbiologically influence corrosion (MIC) selected for examination shall be visually (VT-3) examined on internal surface or ultrasonically examined.

ASME Code Class 2 high safety significant piping structural elements subject to flow accelerated corrosion (FAC) selected for examination shall be in accordance with the owner FAC program, SPP-9.7.

SQN ASME Class 3 Equivalent Components O-SI-DXI-000-114.3 ATT3 Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 1 of 10 ATTACHMENT 3 - ASME Class 3 Equivalent Components Subject to Examination (Unit 1 and Unit 2)

SON ASME Class 3 Equivalent Components 0-SI-DXI-000-114.3 ATY13 Unit 1 & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 2 of 10 1-he ASME Code Class 3 (equivalent) components to be examined during the inspection interval are outlined below..

iTable C for integrally welded support attachments and Table D for component supports of Attachment 4 for Unit 1 and Attachment 5 for Unit 2 shall be used for items selected for examination which provide examination schedule for the interval and additional information such as reference ISI drawings numbers, and ASME section Xl Examination Categories.

1.0 WELDED SUPPORT ATTACHMENTS NOTE Examination is required whenever component support member deformation, e.g., broken, bent, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.

11.1 Piping Welded Support Attachments (D-A)(ltem Number D1.20)

The entire length of each piping welded support attachments shall be VT-1 examined.

The examination performed during the inspection interval shall include 10 percent of the welded attachments. The examinations shall be distributed during the inspection interval.

The following piping system contains welded support attachments:

Air Conditioning Chilled Water Auxiliary Feedwater Component Cooling Essential Raw Cooling Water F-uel Pool Cooling (Unit 1 only)

The Chemical and Volume Control System piping has no ASME Code Class 3 (equivalent) components welded support attachments required to be examined.

Rules of IWD-1220(c) have been used to exempt the components.

SCN ASME Class 3 Equivalent Components 0-SI-DXI-000-114.3 ATI'3 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 3 of 10 1.2 Equipment Welded Support Attachments (D-A)(ltem Number

[)1.10)

The equipment welded support attachments shall be VT-1 examined.

1.3 Containment Spray Heat Exchanger Secondary Side(2) - Welded Support Attachments - CSH (ERCW)

A. CSHX lA Welded Support Attachments Unit 1 (D-A)(Item Number Dl.10)

There are four welded support attachments on the Unit 1 CSHK Four welded support attachments from the CSH shall be examined during the inspection interval.

El. CSHX 1B Welded Support Attachments Unit 1 (D-A)(ltem Number D1.10)

The containment spray heat exchange 1B was replaced in U1 C9 of the second interval.

There are four welded support attachments on the Unit 1 CSH. Four welded support attachments from the CSH shall be examined during the inspection interval.

C. CSHX 2A and 2B Welded Support Attachments Unit 2 (D-A)(Item Number D1.10)

There are four welded support attachments on each Unit 2 CSH. Four welded support attachments from one CSH shall be examined during the inspection interval.

1.4 Nonregenerative Letdown Heat Exchanger (1) - Welded Support Attachments - NRLHX (CCS) (D-A)(ltem Number D1.10)'

There is one welded support attachment on the NRLHX. The welded support attachment on the NRLHX shall be examined during the inspection interval.

1.5 Gas Stripper and Boric Acid Evaporator (1) - Welded Support Attachments - GSBAE (CCS) (D-A)(Item Number D1.10)

A. GSBAE Evaporator Condenser (1) - Welded Support Attachments - EC (D-A)(ltem Number D1.10)

There are no welded support attachments on the EC.

El. GSBAE Distillate Cooler (1) - Welded Support Attachments - DC (CCS) (D-A)(ltem Number D1.10)

There are no welded support attachments on the DC

SCN ASME Class 3 Equivalent Components 0-SI-DXI-000-114.3 ATT3 Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 4 of 10 1.5 C;as Stripper and Boric Acid Evaporator (1) - Welded Support Attachments - GSBAE (CCS) (D-A)(Item Number D1.10)

('continued)

C. GSBAE Support Frame (1) Welded Support Attachment SF (CCS) (D-A)(Iiem Number D1.1O)

There are no welded support attachments on the SF.

1.6 Component Cooling Surge Tank (1) - Welded Support Attachments - CCST (CCS) (D-A)(ltem Number D1.10)

There is one welded support attachment on the CCST. The welded support attachment on the CCST shall be examined during the inspection interval.

1.7 Essential Raw Cooling Water System Strainer (2) - Welded Support Attachments- ERCWS (ERCW) (D-A)(ltem Number

[)1.10)

There are 16 welded support attachments on strainer A2A-A and 17 welded support attachments on strainer B2B-B. All welded support attachments on one ERCWAS shall be examined during the inspection interval.

1.8 Air Conditioning Chilled Water System Shutdown Board Room Water Chiller (1) - Welded Support Attachments- SDBRWC (D-A)(ltem Number D1.10)

There are 2 welded support attachments on the SDBRWC. The welded attachments on the SDBRWC shall be examined during the inspection interval.

1.9 Air conditioning Chilled water System Chilled Water Air Separator (1)- Welded Support Attachments- CWAS (D-A)(ltem Number D1.10)

There are 4 welded support attachments on the CWAS. The welded attachments on tihe CWAS shall be examined during the inspection interval.

1.10 Component Cooling Heat Exchanger (2) - Welded Support Attachment CCHX (CCS) (D-A)(ltem Number D1.10)

There are no welded support attachments on the CCHX.

SCIN ASME Class 3 Equivalent Components 0-SI-DXI-000-114.3 AT'3 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 5 of 10 1.11 Fuel Pool Cooling And Cleaning System - Spent Fuel Pit Heat Exchanger (2) - Welded Support Attachments- SFPHX (FPC)

Unit 1 only (D-A)(Item Number D1.10)

These welded attachments are included in Unit 1. There are two welded support attachments on each SFPHX. Two welded attachments on one SFPHX shall bie examined during the inspection interval.

1.12 RHR Heat Exchanger Secondary Side (2) -Welded Support Attachments- RHRHSXH (CCS) (D-A)(ltem Number D1.10)

There are two welded support attachments on each RHRHSHX. Two welded attachments on one RHRHSHX shall be examined during the inspection interval.

1.13 EERCW Old Intake Pumping Station Strainer (2) - Welded Support Attachments- ERCW-STR) (D-A)(ltem Number D1.10)

There are two welded support attachments on each ERCW-STR. Two welded attachments from one ERCW-STR shall be examined during the inspection interval.

1.14 Turbine Driven Auxiliary Feedwater Pump (1) - Welded Support Attachment TDAFP (AFW) (D-A)(ltem Number D1.30)

There are no welded support attachments on the TDAFP.

1.15 Motor Driven Auxiliary Feedwater Pump (2) - Welded Support Attachment MDAFP (AFW) (D-A)(ltem Number D1.30)

There are no welded support attachments on the MDAFP.

1.16 Component Cooling System Water Pumps (3) - Welded Support Attachment CCSWP (CCS) (D-A)(ltem Number D1.30)

There are no welded support attachments on the CCSWP.

1.17 Essential Raw Cooling Water System Pump Station Pump (8) -

Welded Support Attachments ERCWP (ERCW) Unit 1 only (D-A)(ltem Number D1.30)

These welded support attachments are included in Unit 1. There is one welded support attachment on each ERCWP. One welded support attachment on one EiRCWP shall be examined during the inspection interval.

SON ASME Class 3 Equivalent Components 0-SI-DXI-000-114.3 ATr3 Unit I & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 6 of 10 1.18 F-uel Pool Cooling And Cleaning System - Spent Fuel Pit Pumps

13) - Welded Support Attachment SFPP (FPC) Unit 1 only (D-iA)(Item Number D1.30)

There are no welded support attachments on the SFPP.

1.19 Air Conditioning Chilled Water System Chill Water Circulation Pump (1) - Welded Support Attachments- CWCP (D-A)(ltem Number D1.30)

There are no welded support attachments on the CWCP.

1.20 ERCW Screen Wash Pump Support (4) supports - Welded Support Attachments- ERCWSWPH (ERCW) Unit 1 only (D-Ak)(ltem Number D1.30)

There are no welded support attachments on the ERCWSWPH.

2.0 1I1PING COMPONENT SUPPORTS (F-A)(ITEM NUMBER F1.30)

Ten percent of the class 3 piping component supports associated with Examination Category D-A piping shall be visually examined during each inspection interval in accordance with visual examination methods VT-3 (Note: Piping supports to be examined shall be the supports of piping NOT exempted under IWD-1220). This examination includes integrally welded and non-integrally welded component supports. Component supports extend from the piping up to and including the attachment to the supporting structure.

The setting of variable and spring-type hangers shall be verified in accordance with the applicable NDE procedure with the acceptance criteria shown in the Scan Plan (see PRISIM database) or the applicable work instruction.

The following piping system contains component supports:

Air Conditioning Chilled Water Auxiliary Feedwater.

Component Cooling Essential Raw Cooling Water F:uel Pool Cooling (Unit 1 only)

The Chemical and Volume Control System piping has no ASME Code Class 3 (equivalent) components supports required to be examined. Rules of IWD-1220(c) have been used to exempt the components.

SON ASME Class 3 Equivalent Components 0-SI-DXI-000-114.3 ATT3 Unit 1 & 2 Subject to Examination Effective Date: 06-01--2006 (Unit I and Unit 2) Page 7 of 10 3.0 EQUIPMENT COMPONENT SUPPORTS (F-A)(ITEM NUMBER 1-11.40)

The equipment component supports shall be VT-3 examined.

3.1 Containment Spray Heat Exchanger Secondary Side 1:2)-Component Support - CSH (ERCW) (F-A)(ltem Number F1.40)

A. CSHX 1A Component Support Unit 1 (F-A)(ltem Number F1.40)

There is one component support on the Unit 1 CSH. The component support shall be examined during the inspection interval.

13. CSHX 1B Component Support Unit 1 (F-A)(ltem Number F1.40)

The containment spray heat exchanger 1B was replaced in Ul C9 of the second interval.

There is one component support on the Unit I CSH. The component support shall be examined during the inspection interval.

C. CSHX 2A and 2B Component Support Unit 2 (F-A)(ftem Number F1.40)

There is one component support on each Unit 2 CSH. The component support from one CSH shall be examined during the inspection interval.

3.2 Nonregenerative Letdown Heat Exchanger (1)-Component Support - NRLHX (CCS) (F-A)(Item Number F1.40)

There is one component support on the NRLHX. The component support on the 1NRLHX shall be examined during the inspection interval.

SON ASME Class 3 Equivalent Components O-SI-DXI-000-114.3 ATI13 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 8 of 10 3.3 Gas Stripper and Boric Acid Evaporator (1) - GSBAE (CCS) (F-A)(ltem Number F1.40)

A. GSBAE Evaporator Condenser (1)-Component Support - EC (F-A)(ltem Number F1l.40)

There is one component support on the EC. The component support on the EC shall be examined during the inspection interval.

El. GSBAE Distillate Cooler (1)-Component Support - DC (F-A)(ltem Number F1.40)

There is one component support on the'DC. The component support on the DC shall be examined during the inspection interval.

C. GSBAE Support Frame (1) - SF (F-A)(ltem Number F1.40)

There is one component support on the SF. The component support on the SF shall be examined during the inspection interval.

3.4 Component Cooling Surge Tank (1)-Component Support - CCST (CCS) (F-A)(ltem Number F1.40)

There is one component support on the CCST. The component support on the C#CST shall be examined during the inspection interval.

3.5 Turbine Driven Auxiliary Feedwater Pump (1)-Component support - TDAFP (AFW) (F-A)(ltem Number F1.40)

There is one component support on the TDAFP. The component support on the 1DAFP shall be examined during the inspection interval.

3.6 Motor Driven Auxiliary Feedwater Pumps (2)-Component Support - MDAFP (AFW) (F-A)(ltem Number F1.40)

There is one component support on each MDAFP. The component support on one MDAFP shall be examined during the inspection interval.

3.7 Component Cooling System Water Pumps (3)-Component Support - CCSWP (CCS) (F-A)(ltem Number F1.40)

There is one component support on each CCSWP. One component support on one CCSWP shall be examined during the inspection interval.

SON ASME Class 3 Equivalent Components 0-SI-DXI-000-114.3 ArT3 Unit 1 & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 9 of 10 3.8 Component Cooling Heat Exchanger (2)-Component Support - CCHX (CCS) (F-A)(ltem Number F1.40)

There is one component support on each CCHX. One component support on one CCHX shall be examined during the inspection interval.

3.9 Essential Raw Cooling Water System Strainer (2)-Component support - ERCWS (ERCW) (F-A)(ltem Number F1.40)

There is one component support on each ERCWS. One component support from one ERCWS shall be examined during the inspection interval.

3.10 Essential Raw Cooling Water System Pump Station Pump(8)-Component Supports ERCWP (ERCW) Unit 1 only (F-A)(ltem Number F1.40)

These supports are included in Unit 1. There is one component support on each ERCWP. One component support on one ERCWP shall be examined during the inspection interval.

3.11 Fuel Pool Cooling And Cleaning System - Spent Fuel Pit Pumps (3)-Component Supports SFPP (FPC) Unit I only (F-A)(ltem Number F1.40)

These supports are included in Unit 1. There is one component support on each SFPP. One component support on one SFPP shall be examined during the inspection interval.

3.12 Air Conditioning Chilled Water System SHUT DOWN Board Room Water Chiller (1)-Component Supports SDBRWC (F-A)(ltem Number F1.40)

There is one component support on the SDBRCW. The component support on the c;DBRWC shall be examined during the inspection interval.

3.13 Air Conditioning Chilled Water System Chill Water Circulation Flump (1)-Component Support CWCP (F-A)(ltem Number F1.40)

There is one component support on the CWCP. The component support on the GWCP shall be examined during the inspection interval.

3.14 Air conditioning Chilled Water System Chill Water Air Separator (1)-Component Support - CWAS (F-A)(ltem Number F1.40)

There is one component support on the CWAS. The component support on the GWAS shall be examined during the inspection interval.

S IN ASME Class 3 Equivalent Components 0-SI-DXI-000-114.3 ATT3 Unit l & 2 Subject to Examination Effective Date: 06-01-2006 (Unit 1 and Unit 2) Page 10 of 10 3.15 Fuel Pool Cooling And Cleaning System - Spent Fuel Pit Heat Exchanger (2)-Component Supports - SFPHX (FPC) Unit 1 only (F-A)(ltem Number F1.40)

These supports are included in Unit 1. There are two component supports on each SFPHX. Two component supports on one SFPHX shall be examined during the inspection interval.

3.16 RHR Heat Exchanger Secondary Side (2)-Component Support - RHRHSXH (CCS) (F-A)(ltem Number F1.40)

There is one component support on each RHRHSXH. The component support on one RHRHSXH shall be examined during the inspection interval.

3.17 ERCW Screen Wash Pump Support (4)-Component supports - ERCWSWPH (ERCW) Unit I only (F-A)(ltem Number F:1.40)

These component supports are included in Unit 1. There is one component support on each ERCWSWPH. One component support on one ERCWSWPH shall be examined during the inspection interval.

3.18 ERCW Old ERCW Intake Pumping Station Strainer (2)-Component Support ERCW-STR (F-A)(ltem Number F1.40)

There is one component support on each ERCW-STR. One component suppcrt on one ERCW-STR shall be examined during the inspection interval.

3.19 Vralve Component Supports (F-A)(ltem Number F1.40)

There are no valves with component supports.

SQN Exarnination Schedule (Unit 1) 0-SI-DXI-000-1 14.3 ATT4 Unilt 1 Effective Date: 06-01-2006 Page 1 of 66 ATTACHMENT 4 - Examination Schedule (Unit 1)

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 2of66 TABLE A SQN UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI CAT. METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND INTHE INTERVAL INTERVJAL PERIOD PERIOD THIRD PERIOD B-A Pressure Retaining Welds In Reactor Vessel B-A B1.10 Reactor Vessel Shell Volumetric Welds B-A B1.1l1 Reactor Vessel Shell UT 4 100% 4 Deferral 0 0 4 ISI-0504-C Welds Circumferential Permissible B-A Bi.12 Reactor Vessel Shell Volumetric None 100% N/A Deferral N/A N/A N/A N/A Welds Longitudinal Permissible B-A B13.20 Reactor Vessel Head Volumetric Welds B-A B1.21 Reactor Vessel Head UT 2 100% of accessible 2 Deferral 0 0 2 ISI-0504C Welds (closure and length Permissible lower) .

B-A B13.22 Reactor Vessel Head UT 6 100%h of accessible 6 Deferral 0 0 6 ISI-0504-C Welds Meridional length Permissible welds B-A Bi.30 Reactor Vessel UT 1 100% 1 Deferral 0 0 1 ISI-0504-C Shell-to-Flange Weld Permissible . -

B-A B1.40 Reactor Vessel MT& UT 1 100% 1 Deferral 0 . 0 1 ISI-0504-C

_ Head-to-Flange Weld _ (Closure) . Permissible .

B-A B1.50 Reactor Vessel Beltline Volumetric Repair Areas > 10%

._ Wall B-A B1.51 Reactor Vessel Repair Volumetric None All N/A Deferral N/A N/A N/A N/A

_ Welds Beltline Region Permissible B-B Pressure Retaining Welds in Vessels Other than Reactor Vessel!

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 3 of 66 TABLE A SQN UNIT I - CLASS 1 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO 151 CAT. METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND IN THE INTERVAL INTERVAL PERIOD PERIOD THIRD PERIOD B-B B2.10 Pressurizer Volumetric Shell-to-Head Welds B-B B2.11 Pressurizer UT 2 Both 2 Deferral NOT 0 1 1 ISI-0394-C Circumferential Permissible Shell-to-Head Welds B-B B2.12 Pressurizer UT 2/1 FOOT 1 foot of 2 1 foot Deferral NOT 0 1 foot of weld 1 foot of weld ISI-0394-C Shell to Head (one each intersecting Permissible intersecting intersecting Intersecting longitudinal longitudinal weld circumferential circumferentia Longitudinal Welds weld weld selected I weld intersecting two for selected for circumferential examination examination welds)

B-B B2.20 Pressurizer Head Welds Volumetric B-B B2.21 Pressurizer Head Welds Volumetric None One weld per head N/A Deferral NOT N/A N/A N/A N/A

_ Circumferential Permissible B-B B2.22 Pressurizer Head Welds Volumetric None One weld per head N/A Deferral NOT N/A N/A N/A N/A Meridional Permissible I B-B B2.30 Steam Generator Volumetric Primary Side Head Welds I B-B B2.31 Steam Generator Volumetric None One weld per head N/A Deferral NOT N/A N/A N/A N/A Primary Side Head Permissible Welds Circumferential see note 1 B-B B2.32 Steam Generator Volumetric None One weld per head N/A Deferral NOT N/A N/A N/A N/A Primary Side Head Permissible Welds Meridional see note 1

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006

.Page 4 of 66 TABLE A SON UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL CAT. NUMBER TO NUMBER TO NUMBER TO ISI METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER INTHE TO END OF THE FIRST THE SECOND INTHE INTERVAL INTERVAL PERIOD PERIOD THIRD

.PEROD B-B B2.40 Steam Generator UT 4 Steam One weld I Deferral NOT 1 0 0 ISI-0399-C Tubesheet-to-Head Generator/ 1 Permissible Weld weld each see note 1 B-B B2.50 Heat Exchangers Volumetric (Primary Side), Head Welds B-B B2.51 Heat Exchangers Volumetric N/A One weld per head N/A Deferral NOT N/A N/A N/A N/A (Primary Side), Head Permissible Welds, Circumferential

_

B-B 82.52 Heat Exchangers - Volumetric N/A One weld per head N/A Deferral NOT N/A N/A N/A N/A (Primary Side), Head Permissible Welds, Meridional B-B 82.60 Heat Exchangers Volumetric N/A One weld per N/A Deferral NOT N/A N/A N/A N/A (Primary Side) -Shell, group Permissible Tubesheet -to-Head Welds B-B 82.70 Heat Exchangers Volumetric N/A One foot of one N/A Deferral NOT N/A N/A N/A N/A (Primary Side) -Shell, weld per group, at Permissible Longitudinal Welds each end of shell B-B B2.80 Heat Exchangers Volumetric N/A One weld per N/A Deferral NOT N/A N/A N/A N/A (Primary Side) -Shell group at each end Permissible Tubesheet-to-Shell Welds _

B-D Full Penetration Welds of Nozzles In Vessels _

B-D 83.90 Reactor Vessel UT 8 100% 8 Deferral 0 0 8 ISI-0504-C Nozzle-to-Vessel Welds I Permissible . see Note:2

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 5 of 66 TABLE A SQN UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBERTO NUMBER TO NUMBER TO ISI CAT. METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND IN THE INTERVAL INTERVAL PERIOD PERIOD THIRD

- PERIOD B-D 3.100 Reactor Vessel Nozzle VT-1 8 100% 8 Deferral 0 0 8 ISI-0504-C Inside Radius Section Code Case Permissible N-648-1 see Note 3 B-D 63.110 Pressurizer UT 6 100% 6 Deferral NOT Nozzle-to-Vessel Welds 2 2 2 ISI-0394-C Permissible BD B3.120 Pressurizer Nozzle UT 6 100% 6 Deferral NOT 2 2 2 ISI-0394-C Inside Radius Section Permissible see 10CFR50.5 Sa(b)(2)(xxi)

(A)

B-D 63.130 Steam Generator Volumetric None 100% N/A Deferral NOT N/A N/A N/A N/A Primary Side Permissible Nozzle-to-Vessel Welds see note 1 B6D 63.140 Steam Generator UT 8 100% 8 Deferral NOT 2 2 4 ISI-0399-C Primary Side Nozzle Permissible Inside Radius Section 10CsFeRe0.5 see note 1 5a(b)(2)(xxi)

(A)

B60 3.150 Heat Exchanger Volumetric N/A 100% N/A Deferral NOT N/A N/A N/A N/A Primary Side Permissible

_ Nozzle-to-Vessel Welds B-D 63.160 Heat Exchanger Volumetric N/A 100% N/A Deferral NOT N/A N/A N/A N/A Primary Side Nozzle Permissible

. Inside Radius Section

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006

.Page 6 of 66 TABLE A SQN UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI CAT. METHOD COMPONENTS DURING BE OF BE l BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN l EXAMINED IN EXAMINED NUMBER

. NUMBER INTHE TO END OF THE'FIRST l THE SECOND INTHE

- INTERVAL INTERVAL PERIOD PERIOD THIRD l PERIOD B-F ALL Pressure Retaining N/A Dissimilar Metal Welds see note 4 B-G-1 Pressure Retaining Bolting, Greater Than 2" in Diameter B-G-1 66.10 Reactor Vessel Closure Visual VT-1 54 100% 54 Deferral 0 0 54 ISI-0504-C Head Nuts > Z in Permissible diameter B-G-1 B6.20 Reactor Vessel Closure UT or MT 54 100% 54 Deferral 0 0 54 ISI-0504-C Studs > 2" diameter when Permissible removed B-G-1 66.40 Reactor Vessel Threads UT 54 100% 54 Deferral 0 0 54 ISI-0504-C in Flange I Permissible B-G-1 86.50 Reactor Vessel Closure VT-1 54 100% 54 Deferral 0 0 54 ISI-0504-C Washers, Bushings Permissible Note: Reactor Vessel does NOT have bushings only washers B-G-1 B6.60 Pressurizer Bolts and Volumetric None 100% N/A Deferral N/A N/A N/A N/A Studs >Z diameter . Permissible . .

B-G-1 B6.70 Pressurizer Flange Visual N/A 100% N/A Deferral N/A N/A N/A N/A Surfaces When Permissible Connection Disassembled B-G-1 86.80 Pressurizer Nuts, Visual N/A 100% N/A Deferral N/A N/A N/A N/A Bushings, and Washers . Permissible B-G-1 86.90 Steam Generator Bolts Volumetric None 100% N/A Deferral N/A N/A N/A N/A and Studs . Permissible

,4"i~nmcalr I_ _ . I _ _ I I .1 _ _ _ 1 _ _ _ L _ _ _ _ 1 _ _ _ _ _ _ 1 I

_ _ _ _ _ _ _ _ _ _ I

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006

_ Page 7 of 66

- TABLE A SQN UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI CAT. METHOD COMPONENTS DURING BE OF BE BE - BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINEDIN EXAMINEDIN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND INTHE INTERVAL INTERVAL PERIOD PERIOD THIRD

- -- -CR r i..fI,.J -O B-G-1 86.100 Steam Generator Visual N/A 100% N/A Deferral N/A N/A N/A N/A Flange Surfaces When Permissible Connection Disassembled ___.

B-G-1 B6.110 Steam Generator Nuts, Visual N/A 100% N/A Deferral N/A N/A N/A N/A

_ Bushings, and Washers _ _ Permissible B-G-1 B6.120 Heat Exchanger Bolts Volumetric N/A 100% N/A Deferral N/A N/A N/A N/A and Studs ___ Permissible _

B-G-1 B6.130 Heat Exchanger Flange Visual N/A -100% N/A Deferral N/A N/A N/A N/A Surfaces When Permissible

. Connection Disassembled B-G-1 B6.140 Heat Exchanger Nuts, Visual N/A 100% N/A Deferral N/A N/A N/A N/A Bushings, and Washers Permissible B-G-1 B6.150 Piping Bolts and Studs Volumetric None 100% N/A Deferral N/A N/A N/A N/A

> Z' diameter Permissible .

B-G-1 B6.160 Piping Flange Surfaces Visual N/A 100% N/A Deferral N/A N/A N/A N/A When Connection Permissible Disassembled B-G-1 B6.170 Piping Nuts, Bushings, Visual N/A 100% N/A Deferral N/A N/A N/A N/A and Washers Permissible B-G-1 B6.180 Reactor Coolant Pump UT 4 Pumps/ 24 One pump if One pump/ 24 Deferral only if only if B-L-2 only if ISI-0325-C Bolts & Studs bolts per pump selected for bolts Permissible Category B-L-2 examination is Category B-L-

> Z' diameter examination under examination is performed 2 examination

. . Category B-L-2 performed is performed B-G-1 B6.190 Reactor Coolant Pump VT-1 4 Pumps One pump if One pump Deferral only if only if only if ISl-0325-C Flange Surface, when selected for Permissible Category B-L-2 Category B-L-2 Category B-L-connection is see Note: 5 examination under examination is examination is 2 examination disassembled Category B-L-2 performed performed is performed

. see Note:_5__ J I I I I I I I

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 8 of 66 TABLE A SON UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM CAT.

ITEM NO. DESCRIPTION EXAM METHOD 1 NUMBER OF COMPONENTS IN ITEM NUMBER TO BE EXAMINED DURING INTERVAL NUMBER TO

.BE EXAMINED IN THE INTERVAL DEFERRAL OF INSPECTION TO END OF NUMBER TO BE EXAMINED IN THE FIRST NUMBER TO BE EXAMINED IN THE SECOND NUMBER TO BE EXAMINED IN THE ISI DRAWING NUMBER INTERVAL PERIOD PERIOD THIRD B-G-1 B6.200 Reactor Coolant Pump Visual None One pump if N/A Deferral N/A N/A N/A N/A Nuts, Bushings, and selected for Permissible Washers examination under

. _____ Category B-L-2 . _

B-G-1 B6.210 Valve Bolts & Studs Volumetric None Valves if selected N/A Deferral N/A N/A N/A N/A

> 2" diameter for examination Permissible under Category B-M-2 B-G-1 B6.220 Valve Flange Surface, Visual None N/A Deferral N/A N/A N/A NiA when connection is Valves if selected Permissible disassembled disassmbledfor examination under Category B-M-2 B-G-1 B6.230 Valve Nuts, Bushings, Visual None Valves if selected N/A Deferral N/A N/A N/A N/A and Washers for examination Permissible under Category B-G-2 Pressure Retaining Bolting, 2" and Less in Diameter B-G-2 B7.10 Reactor Vessel Bolts, Visual None 100% N/A Deferral NOT N/A N/A N/A N/A Studs, and Nuts Permissible

< 2" diameter B-G-2 B7.20 Pressurizer Bolts, VT-1 One Manway / 100% One Manway/ Deferral NOT 0 One Manway 0 ISI-0394-C Studs, and Nuts . 16 Bolts 16 Bolts when Permissible when

<= Z' diameter disassembled disassembled

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 9 of 66 TABLE A SQN UNIT I - CLASS 1 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI CAT. METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND IN THE INTERVAL INTERVAL PERIOD PERIOD THIRD B-G-2 B7.30 Steam Generator Bolts, VT-1 4 Generators / One Steam One Deferral NOT One Manway 0 One Manway 151-0399-C Studs, and Nuts 2 Manways / Generator selected Generator / Permissible when when

. 2c diameter 16 Bolts each for exam under 2 Manways / disassembled Z'dameerCategory disassembled B-B 16 Bolts each see note 1 when

._ disassembled B-G-2 B7.40 Heat Exchanger Bolts, Visual N/A 100% N/A Deferral NOT N/A N/A N/A N/A Studs, and Nuts Permissible Z diameter.

B-G-2 B7.50 Piping Bolts, Studs, and Visual Nuts

.= 2" diameter B7.50 CVC VT-1 one group/ 4 One bolted 1 connection Deferral NOT only when only when only when CHM-2338-C bolted connection in when Permissible disassembled disassembled disassembled connections system similar in disassembled design, size, function and service B7.50 RCS VT-1 one group/ 5 One bolted I connection Deferral NOT only when only when only when ISI-0369-C bolted connection in when Permissible disassembled disassembled disassembled connections system similar in disassembled design, size, function and service B7.50 RHR VT-1 None One bolted N/A Deferral NOT N/A N/A N/A CHM-2336-C connection in Permissible system similar in design, size, function and service .

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 10 of 66 TABLE A SQN UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO IS1 CAT. .METHOD COMPONENTS DURING BE OF BE BE BE DRAWING

. IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND IN THE

. INTERVAL INTERVAL PERIOD PERIOD THIRD B7.50 SIS VT-1 one group/ 4 One bolted I connection Deferral NOT only when only when only when CHM-2333-C bolted connection in when Permissible disassembled disassembled disassembled connections system similar in disassembled design, size,

__ ._ _ function and service B-G-2 B7.60 Pumps Bolts, Studs, VT-1 4 Pumps/ 2 One pump if One pump/ Deferral NOT only if only if only if ISI-0325-C and Nuts Sets! one set 12 selected for 2 Sets Permissible Category B-L-2 Category B-L-2 Category B-L-bolts, the other examination under examination is examination is 2 examination ctdiameter set 8 bolts Category b-L-2 only if performed performed is performed 2 examination is performed B-G-2 B7.70 Valves Bolts, Studs, Visual and Nuts c z diameter B7.70 CVC VT-1 None One valve if N/A Deferral NOT N/A N/A N/A CHM-2338-C selected for Permissible examination under Category B-M-2 B7.70 RCS VT-1 One Group One valve if One Group Deferral NOT Only if Only if Only if ISI-0369-C 3 Valves selected for one valve per Permissible Category Category Category examination under group B-M-2 B-M-2 B-M-2 Category B-M-2 examination is examination is examination done done is done B7.70 RHR VT-1 Three Groups/ One valve if Three Deferral NOT Only if Only if Only CHM-2336-C 6 Valves selected for Groups/ one Permissible Category Category Category examination under valve per B-M-2 B-M-2 B-M-2 Category B-M-2 group examination is examination is examination done done is done

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 11 of 66 TABLE A SQN UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM CAT.

I ITEM NO. DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NUMBER TO BE EXAMINED DURING INTERVAL NUMBER TO DEFERRAL BE IN THE INTERVAL OF EXAMINED INSPECTION TO END OF NUMBERTO BE NUMBERTO NUMBERTO BE EXAMINED IN EXAMINED IN EXAMINED THE FIRST THE SECOND BE IN THE S

15 DRAWING NUMBER INTERVAL PERIOD PERIOD THIRD

- - - -- E-OD B7.70 SIS VT-1 Two Groups/ One valve if Two Groups/ Deferral NOT Only if Only if Only if CHM-2333-C 14 Valves selected for one valve per Permissible Category Category Category examination under group B-M-2 B-M-2 B-M-2 Category B-M-2 examination is examination is examination done done is done B-G-2 B7.80 CRD Housing Bolts, Visual None Bolts, studs, and N/A Deferral NOT N/A N/A N/A N/A Studs, and Nuts nuts in CRD Permissible housing when see reused 10CFR50.55a(b)(2)(xxi)

(B)

B-J ALL Pressure Retaining N/A N/A N/A N/A N/A N/A N/A N/A Welds in Piping see note 4 B-K Welded Attachments for Class 1 Vessels, Piping, Pumps, and Valves B-K B10.10 Pressure Vessels Surface or Welded Attachments Volumetric B10.10 Reactor Vessel Surface None 100% of required N/A Deferral NOT N/A N/A N/A N/A areas of Permissible each welded attachment on one vessel and whenever component support member deformation is

. identified

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 12 of 66 TABLE A SQN UNIT 1 - CLASS 1 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBERTO CAT. METHOD NUMBERTO NUMBER TO 151 COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER INTHE TO END OF THE FIRST THE SECOND IN THE INTERVAL INTERVAL PERIOD PERIOD THIRD

- -e PERIOD B10.10 Pressurizer Support MT Pressurizer/ 1 100% of required Pressurizer/ Deferral NOT 0 Pressurizer/ i 0 ISI-0394-C Skirt support skirt areas of 1 support skirt Permissible support skirt each welded attachment on one vessel and whenever component support member deformation is

. ._

_ _ _.__.identified .

B10.10 Pressurizer Seismic MT Pressurizer 4 100% of required Pressurizer Deferral NOT 0 Pressurizer/ 4 0 ISI-0394-C Lugs seismic lugs areas of 4 seismic lugs Permissible seismic lugs each welded attachment on one vessel and whenever component support member deformation is identified B10.10 Steam Generator Surface None 100% of required N/A Deferral NOT N/A N/A N/A N/A areas of Permissible each welded attachment on one vessel and whenever component support member deformation is identified B-K B10.20 Piping Welded Surface Attachments .

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-1 14.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 13 of 66 TABLE A SQN UNIT 1 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL.

CAT. NUMBER TO NUMBER TO NUMBER TO ISI METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND IN THE INTERVAL INTERVAL PERIOD PERIOD THIRD PERIOD

- 10.20 CVC PT 10 100% of required 1 Deferral NOT 0 0 1 CHM-2433-areas of Permissible C each welded CHM-2434-attachment on 10% C of the welded attachments and whenever component support member deformation is identified see note 6 B10.20 RCS PT .7 100% of required 1 Deferral NOT 1 0 0 ISI-0370-C areas of Permissible each welded attachment on 10%

of the welded attachments and whenever component support member deformation is identified see note 6

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 14 of 66 TABLE A SQN UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI CAT. METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER

. NUMBER IN THE TO END OF THE FIRST THESECOND IN THE

. INTERVAL INTERVAL PERIOD PERIOD THIRD 7

PER D 810.20 RCS MAIN PT None 100% of required N/A Deferral NOT N/A N/A N/A ISI-0303-C areas of Permissible each welded attachment on 10%

of the welded attachments and whenever component support member deformation is identified see note 6 B10.20 RHR PT 3 100% of required 1 Deferral NOT 1 0 0 CHM-2435-areas of . .Permissible

. C each welded attachment on 10%

. . of the welded

. ~attachments and..

whenever.

component support member.

. deformation is

. . . identified..

see note 6.

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-1 14.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 15 of 66 TABLE A SQN UNIT 1 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBERTO 151 CAT. METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND IN THE

. INTERVAL INTERVAL PERIOD PERIOD THIRD

- - 1 PERIOD B10.20 Sis PT 14 100% of required 2 Deferral NOT 0 0 2 CHM-2436-areas of Permissible C each welded attachment on 10%

of the welded attachments and whenever component support member deformation is identified see note 6 B-K B10.30 Pump Welded Surface None 100% of required N/A Deferral NOT N/A N/A N/A N/A Attachments areas of Permissible each welded attachment on 10%

of the welded attachments associated with the component supports selected for examination and whenever component support member deformation is identified see note 6

SQN Examination Schedule (Unit 1) O-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 16 of 66 TABLE A SQN UNIT 1 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO CAT. ISI METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND IN THE INTERVAL INTERVAL PERIOD PERIOD THIRD B-K B10.40 Valve Welded Surface None 100% of required N/A Deferral NOT N/A N/A N/A N/A Attachments areas of Permissible each welded attachment on 10%

of the welded attachments associated with the component supports selected for examination and whenever component support member deformation is identified see note 6 B-L-1 Pressure Retaining Welds in Pump Casings B-L-1 B12.10 Pump Casing Welds VT-1 4 Pumps/ One (Note Unit 1 only) 1 Deferral 0 0 1 ISI-0325-C weld per pump One weld Permissible Pevrifsuramla examination of the external surfaces of the weld on one pump

_ _ _ __ _ _ _ __ __ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ ____ _ _ __ ___ __ __ ____ c a sing . _ _ _ _ _ _

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-1 14.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 17 of 66 TABLE A SQN UNIT 1 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI CAT. METHOD COMPONENTS DURING BE I OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND IN THE INTERVAL INTERVAL PERIOD PERIOD THIRD PERIOD B-L-2 Pump Casings _ _ _

B-L-2 B12.20 Pump Casing VT-3 4 Pumps At least one pump One Pump Not Applicable Only if Only if Only if ISI-0325-C Internal Surfaces in each group of disassembled disassembled disassembled pumps when disassembled B-M-1 Pressure Retaining Welds in Valve Bodies .

B-M-1 B12.30 Valves (less than NPS Surface None At least one valve N/A Deferral N/A N/A N/A N/A 4") Body Welds in each group of Permissible valves B-M-1 B12.40 Valves (NPS 4! or Volumetric None At least one valve N/A Deferral N/A N/A N/A N/A greater) Body Welds in each group of Permissible valves B-M-2 Valve bodies _

____=

B-M-2 B12.50 Valves (greater than Visual NPS 4") Body Internal Surfaces B12.50 RCS VT-3 One Group At least one valve One Group/ Not Applicable Only if Only if Only if Attachment 6 in each group of one valve per disassembled disassembled disassembled valves when group disassembled B12.50 RHR VT-3 Three Groups At least one valve Three Not Applicable Only if Only if Only if Attachment 6 in each group of Groups/ one disassembled disassembled disassembled valves when valve per

_ disassembled group B12.50 SIS VT-3 Two Groups At least one valve Two Groups / Not Applicable Only if Only if Only if Attachment 6 in each group of one valve per disassembled disassembled disassembled valves when group disassembled

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 18 of 66 TABLE A SQN UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI CAT. METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THE SECOND IN THE INTERVAL INTERVAL PERIOD PERIOD THIRD B-N-1 Interior of Reactor Vessel B-N-1 B13.10 Reactor Vessel Interior VT-3 1 Each Inspection 1 Deferral NOT 1 1 1 ISI-0504-C Accessible areas Period Permissible B-N-2 Welded Core Support Structure and Interior Attachments to Reactor Vessels B-N-2 B13.50 Reactor Vessel Interior Visual None Accessible welds N/A Deferral N/A N/A N/A N/A Attachments Within Permissible Beitline Region . . -

8-N-2 B13.60 Reactor Vessel Interior VT-3 6 Accessible welds 6 Deferral 0 0 6 ISI-0504-C Attachments Beyond Permissible Beitline Region B-N-3 Removal Core Support Structures B-N-3 B13.70 Reactor Vessel Core VT-3 1 Accessible surfaces I Deferral 0 0 1 ISI-0504-C

_ Support Structure Permissible _

SQN Examination Schedule (Unit 1) O-SI-DXI-OO0-114.3 ATT4 Unit 1 Effective Date: 06.01-2006 Page 19 of 66 TABLE A SQN UNIT I - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI CAT. METHOD COMPONENTS DURING BE OF BE BE BE DRAWING IN ITEM INTERVAL EXAMINED INSPECTION EXAMINED IN EXAMINED IN EXAMINED NUMBER NUMBER IN THE TO END OF THE FIRST THESECOND IN THE INTERVAL INTERVAL PERIOD PERIOD THIRD l PER!OD B-.0 Pressure Retaining Welds in Control Rod Housing -

B-0 B14.10 Reactor Vessel Welds UT or 78 CRD 10% of Peripheral 2 Deferral 0 0 2 ISI-0504-C in CRD Housings Surface Housings/ 17 Housings during Permissible being Peripheral last period UT is big Housings performed B-P B15.10 Pressure Retaining VT-2 This is being Components performed under another program B-Q0 B16.10 Steam Generator Volumetric N/A Tubing in Straight Tube

. _ Design B-Q0 B16.20 Steam Generator Volumetric This is being Tubing in U-Tube performed Design under another

._. _ _program .

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 20 of 66 NOTES

1) All four steam generators were replaced during UlCl2of the second interval.

2) Following submittal and approval of request for relief PDI-2 the following may be used. Table A, Examination Category B-D, item number B3.90, reactor vessel nozzle-to-vessel welds, the examination volume may be reduced to 1/2 inch from each side of the weld crown, in lieu of the 1/2 through-wall thickness from each side of the weld required by figures IWB-2500-7(a) and (b).

3) Code case N-648-1 is being used for examination of the reactor vessel nozzle inside radius section, Examination Category B-D, item number B3.1 00, to perform a VT-1 examination with the conditions in Regulatory Guide 1.147.

4) An alternative Risk-Informed Inservice Inspection Program is being implemented in the third inspection interval for categories B-F and B-J. Examinations for credit under the RI-ISI program Table E.

5) Table A, Examination Category B-G-1, item number B6.190, this includes the one inch annular surface of flange surrounding each stud, only when the connection is disassembled.

6) As a minimum 10 percent of the welded attachments associated with the component supports selected for examination under IWF-2510 shall be examined.

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 21 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO IS- DRAWING CAT. METHOD. COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SE D THIRD PERIOD PERIOD PERIOD C-A Pressure Retaining Welds in Pressure Vessels C-A C1.10 Pressure Retaining Volumetric Shell Circumferential or Surface I Welds .

C1.10 Steam Generator UT None All in one or N/A Each Inspection N/A N/A N/A ISI-0399-C distributed among Interval see note 1 see Note 4 vessels at structural

___ ._ discontinuity C1.10 Residual Heat Removal UT 2 RHRHXI All in one or 1 Each Inspection 0 0 ISI-0290-C Heat Exchanger 1 weld per distributed among Interval RHRHX vessels at structural discontinuity C1.10 Containment Spray UT 1 CSHX/ All in one or 1 Each Inspection 0 1 0 ISI-0462-C Heat Exchanger 1A . 1 weld distributed among Interval vessels, at structural

._________ _ _discontinuity C1.10 Containment Spray UT 1 CSHX/ All in one or 2 Each Inspection 0 0 2 ISI-0462-C Heat Exchanger 1B 2 welds distributed among Interval vessels at structural

._ _ ._ _ _discontinuity ..

C1.10 Seal Water Heat PT. 1 SWHX/ All in one or 1 Each Inspection 0 0 1 ISI-0460-C Exchanger 1 weld distributed among Interval vessel wall . vessels at thickness structural less nan discontinuity I I l 10.20 inches I _II_ I ll. lI ll

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006

.Page 22 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY CAT. NUMBER TO NUMBER TO NUMBER TO ISI DRAWING METHOD COMPONENTS EXAMINED TO BE OF BE BE . BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE IN THE IN THE INTHE INTERVAL FIRST SECOND THIRD PER!OD PER!00 PER!OD C1.110 Seal Water Filter PT1 SWF/ All in one or I Each Inspection .0 . . I l15-0458-C 1 weld distributed among Interval vessel wail vessels at thicknessstructural discontinuity 0.20 inches.

C1.10 Seal Water Injection UT .2 SWIF/ All in one or 1 Each Inspection 0 0 1 ISI-0456-C Filter 1 weld per distributed among Interval SWIF vessels at structural discontinuity C1.10 Centrifugal Charging Volumetric None All in one or N/A Each Inspection N/A N/A N/A N/A Pump Tank . distributed among Interval vessels at structural

._ discontinuity C-A C1.20 Pressure Retaining Volumetric Head Circumferential or Surface Welds C1.20 Steam Generator UT 4 Steam Head-to-Shell 1 Each Inspection 1 0 0 ISI-0399-C Generators/ Welds, in one Interval see note 1 1 weld per vessel

.Steam

._ Generator Cl .20 Residual Heat Removal UT 2 RHRHX/ 1 Head-to-Shell 1 Each Inspection 0 1 0 ISI-0290-C Heat Exchanger weld per Welds, in one Interval RHRHX vessel . . .

C1.20 Containment Spray UT None Head-to-Shell N/A Each Inspection N/A N/A N/A ISI-0462-C Heat Exchanger IA Welds, in oneInterval vessel__ _ _ _ _ ___ _ _ _ _ _

Heat Exchanger 1B l l Welds, in one Interval l I I I vessel l l l I I I I

SQN Examination Schedule (Unit 1) O-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 23 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY CAT. NUMBER TO NUMBER TO NUMBER TO ISI DRAWING METHOD COMPONENTS EXAMINED TO BE OF BE BE BE IN ITEM NUMBER DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE IN THE IN THE INTHE

_ INTERVAL FIRST SECOND THIRD PERIOD PFRIOD PERIOD C1.20 Seal Water Heat PT 1 SWHXJ Head-to-Shell 1 Each Inspection 0 0 1 ISI-0460-C Exchanger vessel wall I weld Welds, in one Interval thickness vessel less than 0.20 inches C1.20 Seal Water Filter PT 1 SWFI Head-to-Shell 1 Each Inspection 0 1. 0 ISI-0458-C 1 weld Welds, in one Interval vessel wall vessel thickness less than 0.20 inches C1.20 Seal Water Injection UT 2 SWIF /1 weld Head-to-Shell 1 Each Inspection 0 0 1 ISI-0456-C Filter per SWIF Welds, in one Interval vessel .

C1.20 Centrifugal Charging UT 1 CCP Tank/ Head-to-Shell 2 Each Inspection I 0 1 ISI-0069-C Pump Tank 2 welds Welds, in one Interval vessel . .

C-A C1.30 Tubesheet-to-Shell Volumetric

. Weld or Surface C1.30 Steam Generator UT 4 Steam Tubesheet-to-Shell I Each Inspection I 0 0 ISI-0399-C Generators/ 1 Welds, in one Interval see note 1 weld per Steam vessel Generator C1.30 Residual Heat Removal Volumetric None Tubesheet-to-Shell N/A Each Inspection N/A N/A N/A ISI-0290-C Heat Exchanger Welds, in one Interval vessel C1.30 Containment Spray UT 1 CSHX/ Tubesheet-to-Shell 1 Each Inspection 0 .0 ISI-0462-C Heat Exchanger 1A 1 weld Welds, in one Interval vessel l C1.30 Containment Spray UT 1 cSHX/ Tubesheet-to-Shell 1 . Each Inspection 0 Heat Exchanger 1 iSi-0462-C 1 weld Welds, in one Interval l l l _ _ l _ X_ _ _ _ _ _ _ . l_ l -vessel l

_ _ _ l l l l l l

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 24 of 66 TABLE B SQN UNIT 1 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO CAT. NUMBER TO NUMBER TO ISI DRAWING METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED. EXAMINED EXAMINED NUMBER INTERVAL IN THE INTHE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PFRIOD PFRIODl C1.30 Seal Water Heat Surface None Tubesheet-to-Shell N/A Each Inspection N/A N/A N/A ISI-0460-C Exchanger Welds, in one Interval

. ________ ._ _ _vessel C1.30 Seal Water Filter Surface None Tubesheet-to-Shell N/A Each Inspection N/A N/A N/A ISI-0458-C Welds, in one Interval

.___

____ _ _ vessel C1.30 Seal Water linjection Volumetric None Tubesheet-to-Shell N/A Each Inspection N/A N/A N/A ISI-0456-C Filter Welds, in one Interval vessel C-B Pressure Retaining Nozzle Welds in Vessels ._.

C-B C2.10 Nozzles in vessels <=

1/Z' nominal thickness C-B C2.11 Nozzle-to-Shell Surface (or Head) Weld in Vessels < 1/2" thick, and nozzles greater than 4 inches NPS C2.11 Seal Water Heat PT None All nozzles at N/A Each Inspection N/A N/A N/A ISI-0460-C Exchanger terminal ends of Interval piping runs in one vessel .

C2.11 Seal Water Filter PT None All nozzles at N/A Each Inspection N/A N/A N/A ISI-0458-C terminal ends of Interval piping runs in one vessel C2.11 Seal Water Injection PT None All nozzles at N/A Each Inspection N/A N/A N/A ISI-0456-C Filter terminal ends of Interval piping runs in one

. _vessei

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 25 of 66 TABLE B SQN UNIT 1 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD

-. .. R PER!OD PERIOD C-B C2.20 .Nozzles without.

reinforcing plate in vessels >1/Z' nominal thickness .

C-B C2.21 Nozzles without Surface and Reinforcing Plate in Volumetric Vessels > 1/2" thick C2.21 Steam Generator MT & UT 4 Steam All nozzles at (1 FW) Each Inspection 1 (FW) 0 0 ISI-0399-C Generators/ terminal ends of Interval see notes 1 and 2 1 FW nozzle piping runs in one each vessel see Note 2 C2.21 Residual Heat Removal PT & UT 2 RHRHX/ All nozzles at 2 Each Inspection 1 1 0 ISI-0290-C Heat Exchanger 2 nozzles each terminal ends of Interval piping runs in one vessel C2.21 Containment Spray MT & UT 1 CSHX/ All nozzles at 2 Each Inspection 0 0 2 ISI-0462-C Heat Exchanger 1A 2 nozzles each terminal ends of Interval piping runs in one vessel C2.21 Containment Spray PT & UT 1 CSHXJ All nozzles at 2 Each Inspection 0 0 2 ISI-0462-C Heat Exchanger 1B 2 nozzles each terminal ends of Interval piping runs in one vessel _______ _.____

C2,21 Centrifugal Charging MT& UT 1 CCP / All nozzles at 2 Each Inspection 0 1 1 ISI-0069-C Pump Tank terminal ends of Interval 2 nozzles piping runs in one

._ vessel C-B C2.22 Nozzle Inside Radius Volumetric

Seeiiuri I. II Note: only for nozzles _ l l l l _ _ _

_____ _____ greater than 1Z' NPS l l l l l l _l

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 26 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE INTHE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD C2.22 Steam Generator UT. 4 Steam All nozzles at 1 Each Inspection 1 (FW) 0 0 ISI-0399-C Generators/ terminal ends of Interval see notes 1 and 2 1 FW nozzle piping runs in one each vessel see Note 2 C2.22 Residual Heat Removal UT 2 RHRHX/ All nozzles at 2 Each Inspection 1 1 0 ISI-0290-C Heat Exchanger 2 nozzles each terminal ends of Interval piping runs in one examine with examine with vessel the RHRHX the RHRHX nozzle exam nozzle exam C2.21 C2.21 C2,22 Containment Spray UT None All nozzles at N/A Each Inspection N/A N/A N/A ISI-0462-C Heat Exchanger 1A terminal ends of Interval piping runs in one

.____ __ _ vessel . . _

C2.22 Containment Spray UT None All nozzles at N/A Each Inspection Heat Exchanger 1B N/A N/A N/A ISI-0462-C terminal ends of Interval piping runs in one vessel C2.22 Centrifugal Charging UT None All nozzles at N/A Each Inspection N/A N/A N/A ISI-0069-C Pump Tank terminal ends of Interval piping runs in one vessel C-B C2.30 Nozzles with reinforcing plate in vessels > 1/2" nominal thickness .

C-B C2.31 Nozzles with Surface None All nozzles at N/A Each Inspection N/A N/A N/A N/A Reinforcing Plate in terminal ends of Interval Vessels > 1/2" thick. piping runs in one Reinforcing Plate Welds vessel to Vessel & Nn771 _

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 27 of 66 TABLE B.

SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD C-B C2.32 Nozzle-to-Shell (or Volumetric None All nozzles at N/A Each Inspection N/A N/A N/A N/A head) Weld when inside terminal ends of Interval of Vessel is accessible piping runs in one

_____ _____vessel C-B C2.33 Nozzle-to-Shell (or Visual None All nozzles at N/A Each Inspection N/A N/A N/A N/A head) Weld when inside terminal ends of Period of Vessel is piping runs in one inaccessible vessel C-C Welded Attachments for Class 2 Vessels, Piping, Pumps, and Valves .

C-C C3.10 Pressure Vessel Surface

._____ Welded Attachments . .

C3.10 Steam Generator Surface None 100% of required N/A Each Identified N/A N/A N/A N/A areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is

._ . ._ identified C3.1 0 Residual Heat Removal PT 2 RHRHX /2 100% of required One RHRHX Each Identified 0 One RHRHX 0 ISI-0290-C Heat Exchanger lA's each areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is

__ _ _identified

.

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 28 of 66 TABLE B SQN UNIT 1 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISt DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL INTHE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD E PER!OD PER!OD PER!OD C3.10 Containment Spray MT 1 CSHX/4 A's 100% of required CSHX 1A Each Identified 0 Heat Exchanger 1A 0 CSHX 1A ISI-0462-C areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is identified ._.

C3.10 Contatnment Spray PT H CSHX/4 e A's 100% of required CSHXea Each Identified 0 CSHX B ISI-0462-C Heat Exchanger I2 I areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is identified C3.1 0 Seal Water Heat PT Heat exchanger 100% of required Heat EachlIdentified 0 Heat 0 ISI-0460-C Exchanger /2 IA's areas of exchanger Occurrence and exchanger each welded Each Inspection

.attachment on one Interval

. . vessel and

. whenever component support member deformation is

. identified

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01 -2006 Page 29 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM . NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD C3.10 Seal Water Filter PT Filter 14 IA's 100% of required Filter Each Identified 0 Filter 0 ISI-0458-C areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is

__ ____

_ _ _ __ identified C3.1 0 Seal Water Injection PT 2 SWIF/ 3 IA's 100% of required One SWIF Each Identified 0 0 One SWIF ISI-0456-C Filter each areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is

.___ _ .__ _identified C3.10 Centrifugal Charging MT Tank/ 4 lA's 100% of required Tank Each Identified 0 0 Tank ISI-0069-C Pump Tank areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is

__.identified

__ . .

SQN Examination Schedule (Unit 1) O-SI-DXI-000-1 14.3 ATT4 Unit I Effective Date: 06-01-2006 Paqe 30 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER'TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD

_PERIOD PERIOD PERIOD C-C C3.20 Piping Welded Surface P Attachments __.____

C3.20 AFW MT 18 100% of required 2 Each Identified 0 1 1 ISI-0113-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member deformation is identified C3.20 Cs PT 12 100% of required 2 Each Identified 0 1 1 ISI-0448-C areas of Occurrence and CHM-2440-C each welded Each Inspection

.attachment on 10%M Interval of the welded see note 5

. attachments and

. whenever component support member.

deformation is

. identified see note 5_.

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 31 of 66 TABLE B SQN UNIT 1 - CLASS 2 SCHEDULE PLANNING DOCUMENT

- . - -

EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL INTHE IN THE IN THE INTHE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD C3.20 CVC PT 63 100% of required 7 Each Identified 2 2 3 ISI-0448-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member deformation Is identified see note 5 C3.20 FW MT 8 100% of required 1 Each Identified 0 1 0 CHM-2439-C areas of Occurrence and

. each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever

. component support member deformation is identified see note 5

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-1 14.3 ATT4 Unit I Effective Date: 06-01-2006 Page 32 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL INTHE IN THE INTHE IN THE INTERVAL . FIRST SECOND THIRD

. PERIOD PER'O PERIOD C3.20 Ms MT 11 100% of required 2 Each Identified 0 1 1 CHM-2438-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member deformation is identified see note 5 C3.20 RHR PT 31 100% of required 4 Each Identified 1 1 2 ISI-0448-C areas of Occurrence and CHM-2435-C each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member deformation is identified

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 33 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD

._._ ._PERIOD P PERIOD PERIOD C3.20 SIS PT 67 100% of required 7 Each Identified 2 2 3 ISI-0448-C areas of Occurrence and CHM-2436-C each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member deformation is identified see note 5 C-C C3.30 Pump Welded Surface Attachments . ._.

C3.30 Centrifugal Charging PT 2 CCPI 100% of required One pump Each Identified One pump 0 0 ISI-0466-C Pump 4 IA's on each areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the component supports selected for examination and whenever component support member deformation is identified see note 5

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 34 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO CAT. NUMBER TO 1S DRAWING METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE IN THE INTHE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD C3.30 Containment Spray Surface None 100% of required N/A Each Identified N/A NIA NMA N/A Pump areas of Occurrence and each welded EachInspection attachment on IO% .Interval

. of the welded

. attachments

. associated with the component supports selected for examination.

and whenever component support member deformation is identified see note 5 C3.30 Residual Heat Removal Surface None 100% of required N/A Each Identified NIA N/A N/A N/A Pump areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the component supports selected for examination and whenever component support member deformation is identified l _

see note 5

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 35 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL INTHE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PCR-,-.D PERIOD C3.30 Safety Injection Pump Surface None 100% of required N/A Each Identified N/A N/A N/A N/A areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the component supports selected for examination and whenever component support member deformation is identified see note 5 C-C C3.40 Valve Welded Surface None 100% of required N/A Each Identified N/A N/A N/A N/A Attachments areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the component supports selected for examination and whenever component support member deformation is identified

. ._ _ 1 1

_ _ note5

_ _ _ 1see l l l l l . l

SQN Examination Schedule (Unit 1) O-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 36 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE BE BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL IN THE INTHE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD C-D Pressure Retaining Bolting Greater Than 2 Inches in Diameter _

C-D C4.10 Pressure Vessels Bolts Volumetric

& Studs > 2" diameter C4.10 Steam Generator Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A

. . component Interval _

0C4.10 Residual Heat Removal Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A Heat Exchanger _ component Interval _

C4.10 Containmcnt Spray Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A Heat Exchanger 1A component Interval C4.10 Containment Spray Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A Heat Exchanger 1B component Interval C4.10 Seal Water Heat Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A Exchanger component Interval C4.10 Seal Water Filter Volumetric None 100% of one N/A Each Inspection N/A N/A N/A

.

N/A component Interval C4.10 Seal Water Injection Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A Filter component Interval C4.10 Centrifugal Charging UT 1 CCP/ 16 bolts 100% of one I Each Inspection I 0 0 ISI-0069-C

. Pump Tank

component (16 bolts) Interval (16 bolts)

C-D C4.20 Piping Bolts & Studs Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A

> 2" diameter component in each Interval

._ group C-D 04.30 Pumps Bolts & Studs Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A

> 2" diameter component . Interval 0-0 04.40 Valves Bolts & Studs Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A

> Z' diameter component Interval .

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 37 of 66 TABLE B SQN UNIT I - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER FREQUENCY NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED TO BE OF BE B3E BE NUMBER IN ITEM DURING EXAMINED EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL INTHE IN THE INTHE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD C-F-1 ALL Pressure Retaining N/A NIA N/A N/A NIA NIA N/A N/A N/A Welds in Austenitic Stainless Steel or see note 3 High Alloy Piping C-F-2 ALL Pressure Retaining N/A N/A N/A N/A N/A N/A N/A N/A N/A Welds in Carbon or Low Alloy Steel Piping see note 3 C-G Pressure Retaining Welds in Pumps and Valves C-G C6.1 0 Pump Casing Welds Surface None 100% of welds in N/A Each Inspection N/A N/A N/A N/A components in Interval piping runs examined under

._ . Category C-F C-G C6.20 Valve Body Welds Surface None 100% of welds in N/A Each Inspection N/A N/A N/A N/A components in Interval piping runs examined under

._ _ _Category C-F .

C-H C7.1 0 Pressure Retaining VT-2 This is being Components performed under another program . .

SQN Examination Schedule (Unit 1) l 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 38 of 66 NOTES

1) All four steam generators were replaced during UC12 of the second interval

2) The main steam nozzles are forged with the head and do NOT have an inside radius section on the new steam generators.

3) An alternative Risk-Informed Inservice Inspection Program is being implemented in the third inspection interval. for categories C-F-1 and C-F-2 The examinations are credit under the RI-ISI program Table E.

4) The new steam generators do NOT have shell circumferential welds subject to examination.

5) As a minimum 10 percent of the welded attachments associated with the component supports selected for examination under IWF-251 0 shall be examined.

SQN Examination Schedule (Unit 1) O-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 39 of 66 TABLE C SQN UNIT I - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D-A Welded Attachments for Class 3 Vessels, Piping, Pumps, and Valves D-A D1.10 Pressure Vessel Visual Welded Attachments D1.10 Containment Spray VT-1 I CSHX All, 100% of CSHX1A Each Identified 0 0 CSHX IA ISI-0462-C Heat Exchanger 1A 4 IA's required areas of Occurrence and each welded Each Inspection attachment and Interval whenever component support member deformation is identified .

D1.10 Containment Spray VT-I 1 CSHX / All, 100% of CSHX I B Each Identified 0 0 CSHX 1 B ISI-0462-C Heat Exchanger 1B 4 IA's required areas of Occurrence and each welded Each Inspection attachment and Interval whenever component support member deformation is identified D1.1 0 Nonregenerative VT-1 Heat All, 100% of Heat Each Identified 0 Heat 0 ISI-021 6-A Letdown Heat Exchanger/ required areas of Exchanger Occurrence and Exchanger Exchanger 1 IA each welded Each Inspection attachment and Interval whenever rnmnnnpnt ,tinnnrt member. l deformation is identified _ l

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 40 of 66 TABLE C SQN UNIT I - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBERTO NUMBER NUMBER 15I CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.10 Gas Stripper and Boric Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Acid Evaporator areas of Occurrence and Condenser each welded Each Inspection attachment and Interval whenever component support member deformation is

_ __ identified _

D1.10 Gas Stripper and Boric Visual None All, 100% of N/A Each Identified N/A N/A N/A N/A Acid Evaporator required areas of Occurrence and Distillate Cooler each welded EachInspection attachment and Interval whenever component support member deformation is

._ identified D1.10 Gas Stripper and Boric Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Acid Evaporator areas of Occurrence and Support Frame each welded Each Inspection attachment and Interval whenever component support member deformation is identified D1.10 Component Cooling VT-1 Tank/ All, 100% of Tank Each Identified 0 Tank 0 ISI-0227-B Surge Tank 1 IA required areas of Occurrence and each welded Each Inspection attachment and Interval whenever component support member deformation is l_______ __X_ l__ _ l___ identified l l l l l l _ _

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 41 of 66 TABLE C SQN UNIT I - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE TOBE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL INTHE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.10 Essential Raw Cooling VT-1 2 ERCWS/ One Strainer, 100% One strainer Each Identified One strainer 0 0 ISI-0285-C Water System Strainer 17 IA's on A of required areas of Occurrence and and each welded Each Inspection 17 IA's on B attachment and Interval whenever component support member deformation is identified D1.10 Air Conditioning /Chilled VT-1 Chiller / All, 100% of Chiller Each Identified Chiller .0 0 ISI-0454-C Water System 2 IA's required areas of Occurrence and Shut Down Board Room each welded Each Inspection Water Chiller attachment and Interval whenever component support member deformation is

_ _ _identified .

D1.10 Air Conditioning/ Chilled VT-1 Separator / All, 100% of Separator Each Identified Separator 0 0 ISI-0478-C Water System Chill 4 lA's required areas of Occurrence and Water Air Separator each welded Each Inspection attachment and Interval whenever component support member deformation is

._ identified

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006

.Page 42 of 66 TABLE C SQN UNIT I - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.10 Component Cooling VT-1 None One Heat N/A Each Identified N/A NI NIA ISI-0284-B Heat Exchanger Exchanger, 100% Occurrence and of required areas of Each Inspection each welded Interval attachment and whenever component support member deformation is identified _

D1.10 Fuel Pool Cooling and VT-1 2 FPCCHX/ One Heat One heat Each Identified 0 0 One heat ISI-0287-C Cleaning System Spent 2 IA's each Exchanger, 100% exchanger Occurrence and exchanger Fuel Pit Heat of required areas of Each Inspection Exchanger each welded Interval attachment and whenever component support member deformation is identified D1.10 RHR Heat Exchanger VT-1 2 RHRHSHX / One Heat One heat Each Identified 0 0 One heat ISI-0290-C Secondary Side 2 IA's each Exchanger, 100% exchanger Occurrence and exchanger of required areas of Each Inspection each welded Interval attachment and whenever component support member deformation is identified

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 43 of 66 TABLE C SQN UNIT I - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE TO BE TO BE DRAWING IN ITEM . DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL INTHE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.10 ERCW Old ERCW VT-1 2ERCW-STR/ One Strainer, 100% One strainer Each Identified 0 One strainer 0 ISI-0480-C Intake Pumping Station 2 IA's each of required areas of Occurrence and Strainer each welded Each Inspection attachment and Interval whenever component support member deformation is identified D-A D1.20 Piping Welded Visual Attachments D1.20 AFW VT-1 14 100% of required 2 Each Identified 1 0 1 ISI-0113-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

. _ identified

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006

_Page 44 of 66 TABLE C SQN UNIT I - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER* NUMBER [Si CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL INTHE INTHE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D13.20 CC VT-i 74 100% of required 8 Each Identified 2 3 3 ISI-0126-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified D1.20 ERCW VT-1 90 100% of required .9 Each Identified 3 3 3 ISI-0123-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

._ identified

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 45 of 66 TABLE C SQN UNIT I - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER NUMBER [St CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD

__ __ PERIOD PERIOD PERIOD D1.20 FPCS VT-I 4 100% of required 1 Each Identified 0 0 1 ISI-0127-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified ._

D1.20 ACCW VT-1 None 100% of required N/A Each Identified N/A N/A N/A ISI-0450-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified D-A D1.30 Pump Welded Visual Attachments .

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 46 of 66 TABLE C SQN UNIT I - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD

. PERIOD PERIOD PERIOD 01.30 Turbine Driven Auxiliary Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Feedwater Pump areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified D1.30 Motor Driven Auxiliary Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Feedwater Pump areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt

. component supports and whenever component support member deformation is

._ identified

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 47 of 66 TABLE C SQN UNIT 1 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL . FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.30 Component Cooling Visual None 100% of required N/A Each Identified N/A N/A N/A N/A System Water Pumps areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

._ _ ._ identified .

D1.30 Essential Raw Cooling Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Water System Pump areas of Occurrence and Station Pump each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified .

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 48 of 66 TABLE C SQN UNIT I - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF %TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER NUMBER [Si CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE INTHE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.30 Fuel Pool Cooling and Visual None l 00% of required N/A Each Identified NM

/A NIA NA ISI10288-B Cleaning System Spent areas of Occurrence and Fuel Pit Pumps each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified D1.30 Air Conditioning/Chilled Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Water System Chill areas of Occurrence and Water Circulation Pump each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

._ _ _identified .

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 49 of 66 TABLE C SQN UNIT I - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER NUMBER ISt CAT. METHOD COMPONENTS EXAMINED . BE EXAMINATION BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.30 ERCW Screen Wash Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Pump Support areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified l D-A D1.40 Valve Welded Visual None 100% of required N/A Each Identified N/A N/A NIA N/A Attachments areas of Occurrence and each welded Each inspection attachment on 10% interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified . . -

D-B D2.10 Pressure Retaining VT-2 This is being Components performed under another program I l l

SQN Examination Schedule (Unit 1) O-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 50 of 66 NOTES

1) No notes

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 51 of 66 TABLE D SQN UNIT I - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CA.METHOD COMPONENTS EXAMINED BE . EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL INTHE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F-A F1.10A Class I Piping Visual One-directional Restraints FunctionA .A.

F1.10A CVC VT-3 26 25% 7 Each inspection 2 3 2 CHM-2433-C interval CHM-2434-C F1.10A RCS VT-3 12 25% 3 Each inspection I 1 1 ISI-0370-C

___ __ interval F1.10A RCS MAIN VT-3 None 25% N/A Each inspection N/A N/A N/A ISI-0303-C interval _ _

F1.10A RHR VT-3 8 25% 2 Each inspection 1 1 0 CHM-2435-C

._ _ interval F1.10A SIS VT-3 22 25% 6 Each inspection 1 2 3 CHM-2436-C

. _ . interval F-A F1.10B Class 1 Piping Visual Multidirectional Restraints

-_ Function B F1.1OB CVC VT-3 87 25% 22 Each inspection 7 7 8 CHM-2433-C

. , interval CHM-2434-C F1.10B RCS VT-3 6 25% 2 Each inspection 1 1 0 ISI-0370-C interval F1.10B RCS MAIN VT-3 0 25% 0 Each inspection 0 0 0 ISI-0303-C

_interval F1.10B RHR VT-3 4 25% 1 Each inspection 0 0 I_

1 CHM-2435-C

. interval I F1.10B 515 VT-3 46 25% 12 Each inspection 4 5 3 CHM-2436-C l l l l interval I_-_

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 52 of 66 TABLE D SQN UNIT I - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT -

EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER IsI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE

.INTERVAL FIRST SECOND THIRD

-

PERIOD PERIOD PERIOD F-A F1.10C Class I Piping Visual Variable Supports (Springs and Constant Force)

Function C F1.10C CVC VT-3 2 25% 1 Each inspection 0 1 0 CHM-2433-C interval CHM-2434-C F1.10C RCS VT-3 16 25% 4 Each inspection 1 1 2 ISI-0370-C interval F1.10C RCS MAIN VT-3 1 25% 1 Each inspection 0 0 1 ISI-0303-C interval ISI-0369-C F1.10C RHR VT-3 None 25% N/A Each inspection N/A N/A N/A CHM-2435-C interval F1.10C SIS VT-3 3 25% 1 Each inspection 0 1 0 CHM-2436-C interval F-A F1.1OD Class 1 Piping Visual Variable Supports (Snubbers)

.___ Function D .

F1.1OD CVC VT-3 8 25% 2 Each inspection 1 1 0 CHM-2433-C interval CHM-2434-C F1.101 RCS VT-3 18 25% 5 Each inspection 2 2 1 ISI-0370-C

._ interval F1.10D RCS MAIN VT-3 None 25% N/A Each inspection N/A N/A N/A ISI-0303-C interval ISI-0369-C F1.10D RHR VT-3 2 25% 1 Each inspection 0 0 1 CHM-2435-C interval F1.10D SIS VT-3 3 25% 1 Each inspection 0 1 0 CHM-2436-C interval .

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 53 of 66 TABLE D SQN UNIT I - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL INTHE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F-A F1.20A Class 2 Piping Visual One-directional Restraints Function A Fl.20A AFW VT-3 39 15% 6 Each inspection 2 2 2 ISI-0113-C interval.

F1.20A CS VT-3 23 15% 4 Each inspection I 1 2 ISI 0448-C interval CHM-2440-C F1.20A CVC VT-3 78 15% 12 Each inspection 4 4 4 ISI-0448-C l__ _ _interval _ -

F1.20A FW VT-3 17 15% 3 Each inspection I 1 1 CHM-2439-C

__ ]_ _ interval F1.20A MS VT-3 8 15% 2 Each inspection 0 1 1 CHM-2438-C interval _

F1.20A RHR VT-3 54 15% 9 Each inspection 3 2 4 ISI-0448-C interval CHM-2435-C F1.20A SIS VT-3 67 15% 11 Each inspection 3 4 4 ISI-0448-C interval CHM-2436-C F-A F1.20B Class 2 Piping Visual Multidirectional Restraints Function B F1.208 AFW VT-3 17 15% 3 Each inspection 1 1 1 ISI-0113-C interval F1.20B CS VT-3 25 15% 4 Each inspection 1 1 2 ISI-0448-C interval CHM-2440-C F1.20B CVC VT-3 42 15% 7 Each inspection 2 2 3 ISI-0448-C l_ interval F1.20B FW VT-3 1 15% 1 Each inspection 0 1 0 CHM-2439-C F_.20B MS VT-3 15% 2 Each inspection 1 1 0 l 1 1CHM-2438.Cl l M # I 1 I 2 I interval l l l l _l

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 54 of 66 TABLE D SQN UNIT 1 - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD

. _ .... .

PERIOD PERIOD PERIOD

-

F1 20B RHR VT-3 28 15% 5 Each inspection 1 2 2 ISI-0448-C interval HM-2435-C C_

F1.20B SIS VT.3 147 15% 23 Each inspection 7 8 8 ISI-0448-C interval CHM-2436-C F-A F1.20C Class 2 Piping Visual Variable Supports (Springs and Constant Force)

Function C F1.20C AFW VT-3 16 15% 3 Each inspection 1 1

. _

1 ISI-0113-C

.

interval F1.20C CS VT-3 8 15% 2 Each inspection 1 1 0 ISI-0448-C

__interval CHM-2440-C Fl.20C CVC VT-3 10 15% 2 Each inspection 0 1 1 ISI-0448-C interval F1.20C FW VT-3 8 15% 2 Each inspection 0 1 1 CHM-2439-C

__ interval F1.20C MS VT-3 16 15% 3 Each inspection 1 1 1 CHM-2438-C interval F1.20C RHR VT-3 18 15% 3 Each inspection 1 1 1 ISI-0448-C interval CHM-2435-C F1.20C SIS VT-3 11 15% 2 Each inspection 1 1 0 ISI-0448-C

_ interval CHM-2436-C F-A F1.20D Class 2 Piping Visual Variable Supports (Snubbers)

__ Function D F1.20D AFW VT-3 10 15% Z Each inspection 0 1 1 ISI-0113-C.

I-_interval Fi.2uD Is_ vr-s - _ _ I 1S-Oo I5 I 'ac,, i Io/A a A 1,11A

,IA N'^ cIQ.nAAZflC S

ll l interval CHM-2440-C

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-1 14.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 55 of 66 TABLE D SQN UNIT I - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE INTHE INTHE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F1.20D CVC VT-3 9 15% 2 Each inspection 1 1 0 ISI-0448-C

_interval F1.20D FW VT-3 5 15% 1 Each inspection 1 0 0 CHM-2439-C interval F1.20D MS VT-3 18 15% 3 Each inspection 1 1 1 CHM-2438-C interval F1.20D RHR VT-3 14 15% 3 Each inspection 1 1 1 ISI-0448-C interval CHM-2435-C F1.201 SIS VT-3 5 15% 1 Each inspection 0 0 1 ISI-0448-C

. interval CHM-2436-C F-A F1.30A Class 3 Piping Visual One-directional Restraints Function A F1.30A ACCW VT-3 None 10% N/A Each inspection N/A N/A N/A N/A interval _ _

F1.30A AFW VT-3 22 10% 3 Each inspection 1 1 1 ISI-0113-C interval F1.30A CC VT-3 132 10% 14 Each inspection 4 5 5 ISI-0126-C interval F1.30A CVC VT-3 None 10% N/A Each inspection N/A N/A N/A ISI-0448-C

._ interval F1.30A ERCW VT-3 143 10% 15 Each inspection 5 5 5 ISI-0123-C

._ interval F1.30A FPCS VT-3 34 10% 4 Each inspection 1 1 2 ISI-0127-C interval F-A F1.30B Class 3 Piping Visual Multidirectional Restraints F1.30B ACCW J C

VT-3 j 14 14 J 10%

1interval 2 Each inspection 0 1 1 ISI-0450-C

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 56 of 66 TABLE D SQN UNIT I - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM CAT.

ITEM NO. DESCRIPTION 1

.

EXAM METHOD NUMBER OF COMPONENTS IN ITEM TO BE EXAMINED DURING NUMBER TO BE EXAMINED FREQUENCY OF EXAMINATION NUMBER TO BE EXAMINED NUMBER TO BE NUMBER TO BE ISI DRAWING EXAMINED EXAMINED NUMBER l NUMBER INTERVAL IN THE IN THE IN THE IN THE l INTERVAL FIRST SECOND THIRD

- - PERIOD PERIOD PERIOD F1.30B AFW VT-3 18 10% 2 Each inspection 1 0 1 ISI-0113.C

. - interval I F1.30B CC VT-3 121 10% 13 Each inspection 4 4

_ISI-0126-C 5

. interval F1.30B CVC VT-3 None 10% N/A Each inspection N/A N/A N/A ISI-0448-C interval F1.30B ERCW VT.3 210 10% 21 Each inspection 7 7 7 ISI-0123-C I interval F1.30B FPCS VT-3 8 10% I Each inspection 0 1 0 ISI-0127-C interval _

F-A F1.30C Class 3 Piping Visual Variable Supports (Springs and Constant Force)

Function C FI.30C ACCW VT-3 None 10% N/A Each inspection N/A N/A N/A N/A

___ _interval .

F1.30C AFW VT-3 13 10% 2 Each inspection 1 0 1 ISI-0113-C

._ ___ interval _

F1.30C CC VT-3 21 10% 3 Each inspection 1 1 1 ISI-0126-C interval F1.30C CVC VT-3 None 10% N/A Each inspection N/A N/A N/A N/A interval F1.30C ERCW VT-3 7 10% 1 Each inspection 0 1 0 ISI-0123-C

_ ~interval .

F1.30C FPCS VT-3 4 10% 1 Each inspection 1 0 0 ISI-0127-C

._ . interval

SQN Examination Schedule (Unit 1) O-SI-DXI-000-1 14.3 ATT4 Unit I Effective Date: 06-01-2006 Page 57 of 66 TABLE D SQN UNIT I - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE. INTHE IN THE IN THE INTERVAL FIRST- SECOND THIRD PERIOD PERIOD PERIOD F-A F1.30D Class 3 Piping Visual Variable Supports (Snubbers)

Function D F1.30D ACCW VT-3 None 10% N/A Each inspection N/A N/A N/A N/A

._ . interval F1.30D AFW VT-3 3 10% 1 Each inspection 0 1 0 ISI-0113-C interval F1.30D CC VT-3 10 10% 1 Each inspection 1 0 0 ISI-0126-C interval F1.30D CVC VT-3 None 10% N/A Each inspection N/A

._

N/A N/A N/A interval F1.30D ERCW VT-3 7 10% 1 Each inspection 0 0 1 ISI-0123-C interval F1.30D FPCS VT-3 1 10% 1 Each inspection 0 1 0 ISI-0127-C interval F-A F1.40 see Class 1, 2, or 3 Visual 100% of the Each inspection Note: 1 Supports Other Than components or if interval Piping Supports multiple components only one of the multiple

._ . components Class I Equipment F1.40E4 Class 1 VT-3 ReactorVessel All Reactor Each inspection 0 0 Reactor ISI-0504-C Reactor Vessel / 1 support. Vessel interval Vessel F1.40E5 Class I VT-3 Pressurizer / All Pressurizer / Each inspection 0 Pressurizer/ I0 SI-0394-C Pressurizer 2 supports 2 supports interval 2 supports I F1.40E1 Class 1 - VT-3 4 Steam One Steam One Steam Each inspection 0 0 One Steam ISI-0399-C Steam Generator Generators / Generator Generator interval Generator 1Iqinnnrt neh.

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006

.Page 58 of 66 TABLE D SQN UNIT I - CLASS 1,2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO, DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER IS!

CAT. . METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING I IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED

. NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE

. INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F1.40E3 Class 1 VT-3 4 Reactor One Pump One Reactor Each inspection One Reactor __ _ ISI-0325-C Reactor Coolant Pump Coolant Pumps Coolant Pump interval Coolant

. / Pump a 1support each F1 .40E9 Class 2 VT-3 None 100% of the valves N/A Each inspection N0A N/A NCA Valves or if multiple valves interval

. only one of the

. _ multiple valves .

Class 2 Equipment _ _ _ __

F1 .40E2 Class 2 VT-3 4 Steam One steam One Steam Each inspection One Steam 0 0 ISI-0399-C Steam GenerHerators Generator Generator interval Generator

.I 1support each F1.40E6 Class 2 VT-3 2 RHRHX/ One Heat One Heat Each inspection 0 One Heat 0 ISI-0290-C Residual Heat Removal 1 support on Exchanger Exchanger interval Exchanger Heat Exchanger each..

F1.40E6 Class 2 VT-3 2CSHX O All CSHX IA Each inspection 0 0 CSHX IA ISI-0462-C Containment Spray 1 support interval Heat Exchanger _A . _ _

FI .40E1 Class 2 VT-3 I CSHX /All CSHX 1B Each inspection 0 0 CSHX 1 B ISI 0462-C Containment Spray .1 support interval:

Heat Exchanger IB.

F1 .40E1 Class 2 V-17-3 Seal Water All .Seal Water Each inspection 0 Seal Water 0 ISI-0460-C Seat Water Heat Heat Heat interval Heat Exchanger Exchanger / Exchanger Exchanger

. ~1 support_ .

F1 .40E6 Class 2 VT-3 Seal Water AlSeal Water Each inspection 0 Seal Water 0ISI-0458-C

.Seal Water Filter Filter / Filter interval Filter I support.

F1.40E6 Class 2 VT-3 2 SWIF / One filter One SWIF Each inspection .0 O One SWIF ISI-0456-C

.Seal Water Injection 1 support each interval

} l ~~Filter ..

SQN Examination Schedule (Unit 1) O-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 59 of 66 TABLE D SQN UNIT I - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI-CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL INTHE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD Fl .40E8 Class 2 VT-3 Centrifugal All Centrifugal Each inspection 0 0 Centrifugal ISI-0069-C Centrifugal Charging Charging Pump Charging interval Pump Tank Charging Tank/ Pump Tank Pump Tank 1 support F1.40E3 Class 2 VT-3 2 RHRP One Pump One RHRP Each inspection 0 One RHRP 0 ISI-0353-C Residual Heat Removal 1 support each interval Pump F1 .40E3 Class 2 VT-3 2 CCP / One Pump One CCP Each inspection One CCP 0 0 ISI-0466-C Centrifugal Charging 1 support each interval Pump F1.40E3 Class 2 VT-3 2SIP/ One Pump One SIP Each inspection 0 One SIP 0 ISI-0470-C Safety Injection Pump 1 support each interval Ft.40E3 Class 2 VT-3 2 CSP/ One Pump One CSP Each inspection 0 0 One CSP 151-0464-C Containment Spray 1 support each interval Pump _._. . .__

F-A F1.40E9 Class 2 Visual Valves _

F1.40E9 Class 2 VT-3 1 Valve with 100% of the valves 1 Each inspection 0 1 0 ISI-0113-C Valves one support in or if multiple valves interval the AFW only one of multiple AFW system valves F1 .40E9 Class 2 VT-3 2 Valves with 100% of the valves 1 Each inspection 0 0 1 CHM-2435-C Valves one support or if multiple valves interval each inthe only one of multiple RHR RHR system valves Class 3 Equipment _

F1.40E1 Class 3 VT-3 1 CSHX All CSHX 1A Each inspection 0 0 CSHX 1A ISI-0462-C Containment Spray 1 support interval Heat Exchanger 1A . I

_F..AQE, C idbb 3 -' VI1-3 iI-- -'nXr; In-All t S a v4--

~ 1IIIX10VU4

.k n.

I rVc A Inseto -.

,.,~v~g a.,

C*H 1I IgnAC).

I~-4 Containment Spray suppo 1 interval l .

. Heat Exchanger lI 1l l l l I I l I

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 60 of 66 TABLE D SQN UNIT 1 - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION CAT. I l

EXAM METHOD NUMBER OF COMPONENTS IN ITEM TO BE EXAMINED NUMBER TO BE FREQUENCY OF EXAMINATION NUMBER TO BE NUMBER TO BE NUMBER TO BE ISI DRAWING DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD I

PERIOD PERIOD PERIOD F1.40E1 Class 3 VT-3 Heat All Heat Each inspection 0 Heat 0 ISI-0216-A Nonregenerative Exchanger / Exchanger interval Exchanger Letdown Heat 1 support Exchanger .

F1.40E7 Class 3 VT-3 Condenser / All Condenser Each inspection 0 0 Condenser ISI-0226-C Gas Stripper and Boric 1 support interval Acid Evaporator Condenser FI .40E7 Class 3 VT-3 Cooler I All Cooler Each inspection 0 0 Cooler ISI-0226-C Gas Stripper and Boric 1 support interval Acid Evaporator Distillate Cooler F1 .40E7 Class 3 VT-3 Frame I All Frame Each inspection 0 . 0 Frame ISI-0226-C Gas Stripper and Boric 1support interval Acid Evaporator

_ Support Frame _ _

F1 .40E8 Class 3 VT-3 Tank / All Tank Each inspection 0 Tank 0 ISI-0227-B Component Cooling 1 support interval Surge Tank .

F1 .40E3 Class 3 VT-3 Pump / All Pump Each inspection 0 0 Pump ISI-0474-C Turbine Driven Auxiliary 1 support interval Feedwater Pump F1.40E3 Class 3 VT-3 2 MDAFWP/ One pump One Each inspection 0 0 One ISI-0476-C Motor Driven Auxiliary 1 support each MDAFWP interval MDAFWP

._ Feedwater Pump F1.40E3 Class 3 VT-3 3CCSWP/ One pump One CCSWP Each inspection 0 One CCSWP 0 ISI-0281-C CCS Water Pumps 1 support each interval F1.40E1 Class 3 VT-3 4 CCHX / One heat One CCHX Each inspection 0 One CCHX a ISI-0284-B CCS Heat Exchanger I support each exchanger interval F1.40E6 Class 3 VT-3 2 ERCWS / One Strainer One ERCWS Each inspection One 0 0 ISI-0285-C I ERCW Strainer l 1 support eachI I . _ I intervai I ERCWS I _ I I

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 61 of 66 TABLE D SQN UNIT I - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER 1SI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD

_ . --

F1.40E3 Class 3 VT-3 8 ERCW One Pump One Pump Each inspection 0 0 OnePump ISI-0286-B ERCW Pump Station Pumps / interval

. Pump 1 support each F1.40E3 Class 3 VT-3 3 FPCC Pumps One Pump One Pump Each inspection 0 One Pump 0 ISI-0288-B FPCC Spent Fuel Pit / interval Pumps 1 support each F1.40E7 Class 3 VT-3 Chiller / All Chiller Each inspection Chiller 0 0 ISI-0454-C ACCW Shut Down 1 support interval Board Room Water Chiller F1.40E3 Class 3 VT-3 Pump All Pump Each inspection Pump 0 0 ISI-0472-C ACCW Chill Water I support interval Circulation Pump . .

F1.40E7 Class 3 VT-3 Separator / All Separator Each inspection Separator 0 0 ISI-0478-C ACCW Chill Water Air 1 support interval

_ Separator I F1.40E1 Class 3 VT-3 2FPCCHX/ One heat Heat Each inspection Heat 0 0 ISI-0287-C FPCC Spent Fuel Pit 1 support each exchanger Exchanger interval Exchanger Heat Exchanger I .

F1.40E1 Class 3 VT-3 2 RHRHSX/ . One heat One RHRHSX Each inspection 0 0 One ISI-0290-C RHR Heat Exchanger I support each exchanger interval RHRHSX Secondary Side F1.40E3 Class 3 VT-3 4 ERCWSW One Pump One Pump Each inspection 0 One Pump 0 ISI-0296-C ERCW Screen Wash Pumps / interval Pump Support 1support each _

F1.40E6 Class 3 VT-3 2 ERCW-STR / One strainer One Each inspection 0 One 0 ISI-0480-C ERCW Intake Pumping . 1 support each ERCW-STR interval ERCW-STR Station Strainer _

F1.40E9 Class 3 VT-3 None 100% of the valves N/A Each inspection NMA N/A N/A Valves or if multiple valves interval only one of tme multiplevalves . _I . lI_

SQN Examination Schedule-(Unit 1) O-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 62 of 66 NOTES

1) TableD, item number F1.40, ReferToO-SI-DXI-000-114.3, Section 7.2.D.10 fordescription of equipment support functions.

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit I Effective Date: 06-01-2006 Page 63 of 66 TABLE E SQN UNIT I - ASME CLASS I AND 2 RI-ISI SCHEDULE PLANNING DOCUMENT ITEM DESCRIPTION EXAM NUMBER OF ELEMENTIS/EGMENTS IN TO BE DEFERRAL OF NUMBER NUMBER NUMBER ISI DRAWING EXAM NO. METHOD ITEM NUMBER EXAMINED INSPECTION TO TO BE TO BE TO BE NUMBER CAT. DURING END OF EXAMINED EXAMINED EXAMINED INTERVAL INTERVAL IN THE IN THE INTHE

. . FIRST SECOND THIRD

- _ __PERIOD PERIOD PERIOD I D R-A R1.10 High safety significant Piping structural Elements R-A RI.11 Elements subject to Volumetric 62- ELEMENTS 62 Not Permissible 20 21 21 CHM-2333-C Thermal Fatigue (UT).

see Note: 1 CHM-2335-C see note 1 AFWF-001, AFWF-006 CHM-2336-C AFWS-013, AFWS-015 CSF-058, CSF-099A CHM-2338-C CSS-013, CSS-087, CSS-109 CHM-2339-C CVCF-020, CVCF-161 CHM-2340-C CVCS-038 CHM-2422-C MSS-04, MSS-09, MSS-16, MSS-23 ISI-0369-C RC-01-SE, RC-08-SE, RC-09-SE ISI-0394C RC-16-SE, RC-17-SE, RC-24-SE RC-25-SE, RC-32-SE ISI-0430-C RC-33, RC-33-S2, RC-35 ISI-0434-C RHRF-018, RHRF-020, RHRF-022, ISI-0482-C RHRF-093, RHRF-106, RHRF-107 ISI-0504C RHRS-127, RHRS-166, RHRS-203

. Sl-1 643A SI-i643AISI-051 0-C SIF-029, SIF-031; SIF-047; SIF-194A SIF-196, SIF-197; SIF-198, SIF-199 SIS-045, SIS-075, SIS-079A SIS-080, SIS-099, S-i 88 SIS-240, SIS-244, SIS-279 SIS-291, SIS-317, SIS-320 SIW-1 063C, SWIWi 968A SWW-2040A, SWIW-2098AX SWNY-21 58A _

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 l Unit 1 Effective Date: 06-01-2006 Page 64 of 66 TABLE E SQN UNIT I - ASME CLASS I AND 2 RI-ISI SCHEDULE PLANNING DOCUMENT ITEM DESCRIPTION EXAM NUMBER OF ELEMENTSISEGMENTS IN TO BE DEFERRAL OF NUMBER EXAM NO. METHOD ITEM NUMBER EXAMINED INSPECTIONTO NUMBER NUMBER ISI DRAWING TO BE TO BE TO BE NUMBER CAT. DURING END OF EXAMINED EXAMINED EXAMINED INTERVAL INTERVAL IN THE IN THE IN THE FIRST SECOND THIRD PERIOD PERIOD PERIOD

_ I R-A R1.1 1 Elements subject to VT-2 SEGMENTS All each Not Permissible All each All each All each see TVA Thermal Fatigue see Notes: BD-009, BD-012, BD-017 refueling refueling refueling refueling Calculation see note 1 2 and 3 BD-020, BD-021, BD-024 outage outage outage outage SQN-MEB-MDN CH-030, CH-031 see Notes: 0999-000085 CH-032, CH-033 CH-034 1, 2, 3 and 5 CH-035, CH-036, CH-037 CS-012 RC-036, RC-050, RC-052, RC-053 RC-054, RC-060, RC-061 RH-003 Sl-055B, SI-056B, SI-057A, SI-058A Sl-059,. SI-069, Sl-070, Sl-071 SI-072, Sl-073, Sl-074, SI-075 SI-076, SI-077B, SI-078 Sl-079B, SI-081B, SI-089 SI-090 R-A R1.12 Elements subject to high Visual, VT-2 SEGMENTS Cycle mechanical see Note: 3 BD-009, BD-012 fatigue CH-003B, CH-004B, CH-030, CH-031 see note I CH-032, CH-033, CH-034, CH-035 CH-036, CH-037 RC-036, SI-057A SI-058A, SI-069, SI-070, SI-071 SI-072, SI-073, SI-074, SI-075 SI-076, Sl-079B, Sl-081B

SQN Examination Schedule (Unit 1) 0-SI-DXI-000114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 65 of 66 TABLE E SQN UNIT I - ASME CLASS I AND 2 RI-ISI SCHEDULE PLANNING DOCUMENT ITEM DESCRIPTION EXAM NUMBER OF ELEMENTS/SEGMENTS IN TO BE DEFERRAL OF NUMBER NUMBER NUMBER ISI DRAWING CXAT. NO. METHOD ITEM NUMBER EXAMINED INSPECTION TO TO BE TO BE TO BE NUMBER CAT. DURING END OF EXAMINED EXAMINED EXAMINED INTERVAL INTERVAL IN THE IN THE IN THE

. FIRST SECOND THIRD

__

PERIOD PERIOD PERIOD

_ - m_ .

R-A R1.13 Elements Subject to Volumetric There are no elements/segments subject to N/A N/A N/A N/A N/A Corrosive, Erosive, or (for internal Corrosive, Erosive, or Cavitation Wastage Cavitation Wastage Wastage) or surface (for see note 1 external

_Wastage)_

R-A R1.14 Elements Subject to Volumetric There are no elements/segments subject to N/A N/A N/A N/A N/A Crevice Corrosion Crevice Corrosion Cracking Cracking see note 1 R-A R1.15 Elements subject to Visual, VT-2 There are no elements/segments subject to N/A N/A N/A N/A N/A Primary Water Stress Primary Water Stress Corrosion Cracking Corrosion Cracking (PWSCC)

(PWSCC) see note 1 R-A R1.16 Elements subject to Volumetric ELEMENTS 7 Not Permissible 2 2 3 CHM-2333-C Intergranular Stress (UT) see Note-: 1 CHM-2336-C Corrosion Cracking RHRF-018, RHRF-022, RHRF-107, ISI-0434-C (IGSCC) SIF-029, SIF-031, SIF-196, SIF-198 see note 1 R-A R1.16 Elements subject to VT-2 SEGMENT All each Not Permissible All each All each All each sntegrauoatStessrefueling refueling refueling refueling Corrosion Cracking se oe:S1-081 B outage otg uae (IGSCC) otg 2 and 3 outage oue oue see note I see Notes:

1, 2 and 3

SQN Examination Schedule (Unit 1) 0-SI-DXI-000-114.3 ATT4 Unit 1 Effective Date: 06-01-2006 Page 66 of 66 TABLE E SQN UNIT I - ASME CLASS I AND 2 RI-ISI SCHEDULE PLANNING DOCUMENT ITEM DESCRIPTION EXAM NUMBER OF ELEMENTS/SEGMENTS IN TO BE DEFERRAL OF EXAM NO. METHOD ITEM NUMBER NUMBER NUMBER NUMBER 151DRAWING EXAMINED INSPECTION TO TO BE TO BE TO BE NUMBER CAT. . DURING END OF EXAMINED EXAMINED EXAMINED INTERVAL INTERVAL IN THE IN THE IN THE

. FIRST SECOND

- THIRD PERIOD PERIOD PERIOD R-A R1.17 Elements subject to Visual, VTr3 There are no elements/segments subject to N/A NIA N/A N/A N/A Microbiologically internal Microbiologically Influenced Corrosion Influenced Corrosion surfaces or (MIC)

(MIC) volumetric see note 1 R-A R1.18 Elements subject to UT SEGMENTS As N/A As As As see TVA Flow Accelerated thickness (see Note: 4) scheduled scheduled scheduled in scheduled Calculation Corrosion (FAC) Nt 4 BD-009, BD-012 in the FAC in the FAC the FAC in the FAC SON-MEB-MDN see note 1 see ote: 60-017, BD-020 program program program program 0999-000085 80-021, BD-024 see Note: 4 NOTES

1) An alternative Risk-Informed Inservice Inspection Program is being implemented in the third inspection interval. Examinations for credit under the RI-ISI program Table E. (see request for relief 1-RI-ISI-1)

2) VT-2 examinations to be performed on the segments as allowed by request for relief 1-RI-ISI-2

3) These VT-2 examinations are performed under the pressure test program REFER TO procedures O-SI-SXI-000-200.0.

4) These examinations are performed under the FAC program procedure SPP-9.7.

5) A VT-2 examination of only the socket welds and associated branch connection welds is required for segments CS-012, RH-003, Sl-059 and SI-078.

SQN Examination Schedule (Unit 2) O-SI-DXI-000-114.3 Att.,' ]

Unit: 2 Effective Date: 06-01-2006 Page 1 of 66 ATTACHMENT 5 - Examination Schedule (Unit 2)

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 2 of 66 TABLE A SQN UNIT 2- CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION . EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO DRAWING EFR CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND

. _ PERIODl B-A Pressure Retaining Welds In Reactor Vessel B-A B13.10 Reactor Vessel Volumetric Shell Welds .

B-A B1. 11 Reactor Vessel UT 4 100% 4 Deferral 0 0 4 ISI-0298-C Shell Welds Permissible Circumferential .

B-A B1.12 Reactor Vessel Volumetric None 100% N/A Deferral N/A N/A NMA N/A Shell Welds Permissible Longitudinal . -

B-A B1.20 Reactor Vessel Volumetric Head Welds .

B-A 81.21 Reactor Vessel UT 2 100% of accessible 2 Deferral 0 0 2 ISI-0298-C Head Welds (closure and length Permissible ISI-0301-C lower)

B-A B1.22 Reactor Vessel UT 6 100% of accessible 6 Deferral 0 0 6 1SI-0298-C Head Welds Meridional length Permissible

_ _ welds we d __ _ _ _ _ _ _ _ _ _ ___ __ _ _ _ _ _ _ _ _ _ _ __ ___ _ ____ _

B-A B1.30 Reactor Vessel UT 1 100% 1 Deferral 0 0 1 ISI-0298-C Shell-to-Flange Weld Permissible B-A B1.40 Reactor Vessel MT & UT 1 100% 1 Deferral 0 0 1 ISI-0301-C

. Head-to-Flange Weld (Closure) Permissible B-A B1.50 Reactor Vessel Volumetric Beltline Repair Areas > 10% Wall . _ . _

B-A B1.51 Reactor Vessel Volumetric None All N/A Deferral N/A N/A N/A N/A Repair Welds Permissible Beltline Region

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 3 of 66 TABLE A SON UNIT 2 - CLASS 1 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO CAT. NUMBER TO NUMBER TO ISI DRAWING METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER INTHE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND PERIOD B-B Pressure Retaining Welds In Vessels Other than Reactor Vessels _ _l B-B 82.10 Pressurizer Volumetric Shell-to-Head Welds . . .

B-B B2.11 Pressurizer UT 2 Both 2 Deferral Not 0 1 1 ISI-0396-C Circumferential Permissible Shell-to-Head Welds . . .

B-B B2.12 Pressurizer UT 2 / 1 foot 1 foot of 21 1 foot Deferral Not 0 1 foot of weld 1 foot of weld ISI-0396-C Shell to Head (one each intersecting Permissible intersecting intersecting Intersecting longitudinal longitudinal weld circumferential circumferential Longitudinal Welds weld weld selected weld selected for intersecting two for examination circumferential examination

________ welds) _ ._.__

B-B B2.20 Pressurizer Volumetric Head Welds . .

B-B B2.21 Pressurizer Volumetric None One weld per head N/A Deferral Not N/A N/A N/A N/A Head Welds . Permissible Circumferential __._.___l____

B-B B2.22 Pressurizer Volumetric None One weld per head N/A Deferral Not N/A N/A N/A N/A Head Welds Meridional . Permissible B-B B2.30 Steam Generator Volumetric 83 Primary Side H._Head Welds B-B B2.31 Steam Generator Volumetric None One weld per head N/A Deferral Not N/A N/A N/A N/A Primary Side Permissible Head Welds

._______ _ _Circumferential _._.__ _.

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 4 of 66

- TABLE A SQN UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND

_ - PERIOD

__ __

B-B B2.32 Steam Generator Volumetric None One weld per head N/A Deferral Not N/A N/A N/A N/A Primary Side Permissible Head Welds Meridional . . -_._.

B-B 82.40 Steam Generator UT 4 Steam One weld 1 Deferral Not 1 0 0 ISI-0401-C Tubesheet-to-Head Generators/ Permissible Weld 1 weld each B-B B2.50 Heat Exchangers Volumetric (Primary Side), Head Welds B-B 12.51 Heat Exchangers Volumetric N/A One weld per head N/A Deferral Not N/A N/A N/A N/A (Primary Side), Head Permissible Welds, Circumferential B-B 82.52 Heat Exchangers Volumetric N/A One weld per head N/A Deferral Not N/A N/A N/A N/A

. (Primary Side), Head Permissible Welds, Meridional B-B 82.60 Heat Exchangers Volumetric N/A One weld per group N/A Deferral Not N/A N/A N/A N/A (Primary Side) -Shell, Permissible Tube sheet -to-Head Welds B-B B2.70 Heat Exchangers Volumetric N/A One foot of one N/A Deferral Not N/A N/A N/A N/A (Primary Side) -Shell, weld per group, at Permissible

_ Longitudinal Welds each end of shell B-B 82.80 Heat Exchangers Volumetric N/A One weld per N/A Deferral Not NIA N/A N/A N/A (Primary Side) -Shell group at each end Permissible Tube sheet-to-Shell Welds B-D Full Penetration Welds of Nozzles in Vessels B-D 83.90 Reactor Vessel UT 8 100% B Deferral 0 0 8 ISI-0298-C I

J C-W3-VCS S INAZZ Acld Pprmkiihlp see note: 1 sl 7_C

. .. I.

_ _________.__ ISI-0392-C

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 5 of 66 TABLE A SQN UNIT 2- CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD

. NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND PERIOD B-D0 B3.100 Reactor Vessel VT-1 8 100% 8 Deferral 00 8 ISI-0008.C Nozzle Inside Radius Code Case .. Permissible

.Section N-648-1 ISI-0297-C

.ISI-0298-C see note 2 IS6-0392-C B-D0 3.110 Pressurizer UT 6 100% 6 Deferral Not 2 2 2 ISI-0396-C

.. Nozzle-to-Vessel Welds Permissible B-D 83.120 Pressurizer UT 6 100% 6 Deferral Not 2 2 2 ISI-0396-C Nozzle Inside Radius Permissible Section see 10CFR50.55a (b)(2)(xxi)(A)

B-0 B3.130 Steam Generator Volumetric None 100% N/A Deferral Not N/A N/A N/A N/A Primary Side Permissible Nozzle-to-Vessel Welds B-D 83.140 Steam Generator UT 8 100% 8 Deferral Not 2 2 4 ISI-0401-C Primary Side Permissible Nozzle Inside Radius see Section 10CFR50.55a (b)(2)(xxi)(A)

B-D 83.150 Heat Exchanger Volumetric N/A 100% N/A Deferral Not N/A N/A N/A N/A Primary. Side Permissible Nozzle-to-Vessel Welds . . .

B-0 83.160 Heat Exchanger Volumetric N/A 100% N/A Deferral Not N/A N/A N/A N/A Primary Side Nozzle Permissible Inside Radius Section I .

SQN Examination Schedule-(Unit 2) O-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 6 of 66 TABLE A SQN UNIT 2- CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO l NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND

.____ .__ PERIOD ____

B-F ALL Pressure Retaining N/A Dissimilar Metal Welds see note 3 B-G-1 Pressure Retaining Bolting, Greater Than 2" in Diameter .

B-G-1 B6.10 Reactor Vessel Visual VT-1 54 100% 54 Deferral 0 0 54 ISI-0304-C Closure Head Nuts > 2" Permissible in diameter B-G-1 B6.20 Reactor Vessel 54 100% 54 Deferral 0 0 54 ISI-0304-C Closure Studs> 2" UTor MT Permissible diameterwhen diameterremoved B-G-1 B6.40 Reactor Vessel UT 54 100% 54 Deferral 0 0 54 ISI-0304-C

_ __ _ __ _ _ _ Threads in Flange __ _ _ _ _ _ Permissible _ _ _ _ _ _

B-G-1 86.50 Reactor Vessel VT-i 54 100% 54 Deferral 0 0 54 ISI-0304-C Closure Washers, Permissible Bushings Note: Reactor Vessel does Not have bushings only washers ._..

B-G-1 B6.60 Pressurizer Volumetric None 100% N/A Deferral N/A N/A N/A N/A Bolts and Studs Z' Permissible diameter B-G-1 B6.70 Pressurizer Visual N/A 100% N/A Deferral NIA N/A N/A N/A Flange Surfaces Permissible When Connection Disassembled B-G-1 B6.80 Pressurizer Visual N/A *100% N/A Deferral N/A N/A N/A N/A Nuts, Bushings, and Permissible Wdsi1efu _ - . .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 7 of 66 TABLE A SQN UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO IS DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD

.. NUMBER IN THE TO END OF PERIOD IN THE PERIOD I INTERVAL INTERVAL SECOND PERIOD B-G-1 B6.90 Steam Generator Volumetric None 100% N/A Deferral N/A N/A N/A N/A Bolts and Studs Permissible

>Z' diameter B-G-1 B6 100 Steam Generator Visual N/A 100% N/A Deferral N/A N/A N/A N/A Flange Surfaces Permissible When Connection

._ Disassembled B-G-1 B6.110 Steam Generator Visual N/A 100% N/A Deferral N/A N/A N/A N/A Nuts, Bushings, and Permissible Washers B-G-1 06.120 Heat Exchanger Volumctric N/A 100% N/A Deferral N/A N/A N/A N/A Bolts and Studs Permissible ___

B-G-1 B6.130 Heat Exchanger Visual N/A 100% N/A Deferral N/A N/A N/A N/A Flange Surfaces Permissible When Connection Disassembled B-G-1 B6.140 Heat Exchanger Visual N/A 100% N/A Deferral N/A N/A N/A N/A Nuts, Bushings, and . Permissible Washers .. _.

B-G-1 B6.150 Piping Volumetric None 100% N/A Deferral N/A N/A N/A N/A Bolts and Studs Permissible

> Z' diameter .

B-G-1 B6.160 Piping Visual N/A 100% N/A Deferral N/A N/A N/A N/A Flange Surfaces Permissible When Connection Disassembled B-G-1 B6.170 Piping Visual N/A 100% N/A Deferral N/A N/A N/A N/A Nuts, Bushings, and Permissible Washers .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-1 14.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 8 of 66 -

TABLE A SQN UNIT 2 - CLASS 1 SCHEDULE PLANNING DOCUMENT

- - - - __ m _ , - p EXAM -_.

ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO CAT. ISI DRAWING METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION INTHE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND PERIOD B-G-1 B6.180 Reactor Coolant Pump UT 4 Pumps/ One pump if One pump/ Deferral only if Category only if only if Category ISl-0307-C Bolts & Studs 24 bolts/studs selected for 24 bolts/studs Permissible B-L-2 Category B-L- B-L-2

> Z' diameter per pump examination under see note: 4 examination is 2 examination examination is see note: 4 Category performed is performed performed

._ B-L-2 B-G-1 B6.190 Reactor Coolant Pump VT-1 4 Pumps One pump if One pump Deferral only if Category only if only if Category ISI-0307-C Flange Surface when see note: 5 selected for Permissible B-L-2 . Category B-L- B-L-2 connection is examination under examination is 2 examination examination is disassembled Category performed is performed performed see note: 5 B.L-2 B-G-1 86.200 Reactor Coolant Pump VT-i 1 pump One pump if 1 Deferral When When When ISI-0307-C Nuts, Bushings, and (RCP#4) selected for Permissible disassembled disassembled disassembled Washers examination under see note: 5 Category see note 5 B-L-2 B-G-1 B6.210 Valve Volumetric None Valves if selected N/A Deferral N/A N/A N/A N/A Bolts & Studs > Z' for examination Permissible diameter under Category B-M-2 __

B-G-1 B6.220 Valve Visual None Valves if selected N/A Deferral N/A N/A N/A N/A Flange Surface when for examination Permissible connection is under Category disassembled B-M-2 .

B-G-1 B6.230 Valve Visual None Valves if selected N/A Deferral N/A N/A N/A N/A Nuts, Bushings, and for examination Permissible Washers under Category

. . _B-M-2 B-G-2 Pressure Retaining Bolting, 2" and Less in Diameter B-G-2 B7.10 Reactor Vessel u Visual None 100% N/A Deferral Not N/A N/A N/A N/A

. Bolts, Studs, and Nuts l . Permissible l l

. _ _ _ I _diam

_2" eter l l l l _ l _ l l l

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 9 of 66 TABLE A SQN UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD

.INTERVAL INTERVAL SECOND PERIOD B-G-2 B7.20 Pressurizer VT-1 One Manway / 100% One Manway/ Deferral Not 0 One Manway 0 151-0396-C Bolts, Studs, and Nuts 16 Bolts 16 Bolts when Permissible

<= Z' diameter disassembled Wden B-G-2 B7.30 Steam Generator VT-1 4 Generators / One Steam One Deferral Not One Manway 0 One Manway ISI-0401-C Bolts, Studs, and Nuts 2 Manways/ Generator selected Generator / Permissible .

<= 2" diameter 16 Bolts each for exam under 2 Manways / When When Category B-B 1Boteahdisassembled disassembled When disassembled B-G-2 B7.40 Heat Exchanger Visual NIA 100%° N/A Deferral Not N/A N/A N/A N/A Bolts, Studs, and Nuts Permissible

<= 2" diameter

.

B-G-2 B7.50 Piping Visual Bolts, Studs, and Nuts

<= Z' diameter .

B7.50 CVC VT-1 one group/ 4 one bolted I connecton Deferral Not only when only when only when MSG-0008-C bolted connectionin coen Permissible disassembled disassembled disassembled connections system similar in disassembled design, size, function and service . _ _ .

B7.50 RCS VT-1 one group/ 5 one bolted t Deferral Not only when only when only when ISI-001 3-C bolted connectionin 1 connecon Permissible disassembled disassembled disassembled connections system similar in when design, size, function and service . .

B7.50 RHR VT-1 None one bolted N/A Deferral Not N/A N/A N/A ISI-0003-C connection in Permissible system similar in

. _ . design, size, l_function and service l

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-1 14.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 10 of 66 TABLE A SQN UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF' PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND

. iPERIOD. -

B7.50 SIS VT-1 one group/ 4 one bolted Deferral Not only when only when only when IS[-0002-C bolted connection in 1 connection Permissible disassembled disassembled disassembled connections system similar in dihsembn design, size, disassembled function and service B-G-2 87.60 Pumps VT-1 4 Pumps/ One pump if One pump/ Deferral Not only if Category only if only if Category ISI-0307-C Bolts, Studs, and Nuts 2 Sets/ one set selected for 2 Sets Permissible B-L-2 Category B-L- B-L-2 c= Z' diameter 12 bolts, the examination under examination is 2 examination examination is other set 8 bolts Category B-L-2 only if performed is performed performed category B-L-2 examination is performed B-G-2 B7.70 Valves Visual Bolts, Studs, and Nuts

<= 2" diameter B7.70 CVC VT-i None One valve if N/A Deferral Not N/A N/A N/A MSG-0008-C selected for Permissible examination under Category

______ .__ ._ _B-M-2 _______

B7.70 RCS VT-1 One Group One valve if One Group / Deferral Not Only if Category Only if Only if Category ISI-001 3-C 3 Valves selected for one valve per Permissible B-M-2 Category B-M-2 examination under group examination is B-M-2 examination is Category done examination is done B-M-2 done 87.70 RHR VT-I Three Groups/ One valve if Three Deferral Not Only if Category Only if Only if Category ISI-0003-C 6 Valves selected for Groups/ Permissible B-M-2 Category B-M-2 examination under one valve per examination is B-M-2 examination is Category group done examination is done

- _ . B-M-2 done

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-1 14.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 11 of 66 TABLE A SON UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND PERIOD B7.70 SIS VT-1 Two Groups/ One valve if Two Groups/ Deferral Not Only if Category Only if Only if Category ISI-0002-C 14 Valves selected for one valve per Permissible B-M-2 Category B-M-2 examination under group examination is B-M-2 examination is Category done examination is done

_ . B-M-2 done B-G-2 B7.80 CRD Visual None Bolts, studs, and N/A Deferral Not N/A N/A N/A N/A Housing nuts in CRD Permissible Bolts, Studs, and Nuts housing when reused see 10CFR50.55a(b)(2)(xxi)

(B)

B-J ALL Pressure Retaining N/A N/A N/A N/A N/A N/A N/A N/A Welds in Piping see note 3 B-K Welded Attachments for Class 1 Vessels, Piping, Pumps, and Valves B-K B10.10 Pressure Vessels Surface or Welded Attachments Volumetric

l SQN Examination Schedule (Unit 2) 0-SI-DXI-000-1 14.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 12 of 66 TABLE A SQN UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND PERIOD

=B1010 Reactor Vessel Surface None 100% of required N/A Deferral Not N/A N/A N/A N/A areas of Permissible each welded attachment on one vessel and whenever component support member deformation is

.___.____ _ _______ _ identified ____

B10.10 Pressurizer MT Pressurizer/ 100% of required Pressurizer/ Deferral Not 0 Pressurizer/ 0 ISI-0396-C Support Skirt 1 support skirt areas of 1 support skirt Permissible 1 support skirt each welded attachment on one vessel and whenever component support member deformation is identified B10.10 Pressurizer MT Pressurizer/ 100% of required Pressurizer/ Deferral Not 0 Pressurizer/ 0 ISI-0396-C Seismic Lugs 4 seismic lugs areas of 4 seismic lugs Permissible 4 seismic lugs each welded attachment on one vessel and whenever component support member deformation is identified _

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 13 of 66 TABLE A SQN UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND PERIOD B10.10 Steam Generator Surface None 100% of required N/A Deferral Not N/A N/A N/A N/A areas of Permissible each welded attachment on one vessel and whenever component support member deformation is

._ identified B-K B10.20 Piping Welded Surface Attachments B10.20 CVC PT 10 100% of required 1 Deferral Not 0 0 1 MSG-0012-C areas of . Permissible MSG-0015-C each welded attachment on 10%

of the welded attachments and whenever component support member deformation is identified see note 6

SQN Examination Schedule (Unit 2) O-SI-DXI-000-114.3 Att.5.

Unit 2 Effective Date: 06-01-2006 Page 14 of 66 TABLE A SQN UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT.

EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD INTHE PERIOD INTERVAL INTERVAL SECOND PERIOD B10.20 RCS 6 100% of required 1 Deferral Not 1 0 . MSG-0013-C areas of Permissible each welded attachment on 10%

of the welded attachments and whenever component support member deformation Is identified see note 6 B10.20 RCS MAIN PT None 100% of required N/A Deferral Not N/A N/A N/A ISI-0302-C areas of Permissible ISI-0321-C each welded attachment on 10%

of the welded attachments and whenever component support member deformation is identified see note 6

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 15 of 66 TABLE A SQN UNIT 2 - CLASS 1 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD. COMPONENTS DURING . BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND

. _ PERIOD 810.20 RHR PT 3 100% of required 1 Deferral Not 0 1 0 MSG-0010-C areas of Permissible

.each welded

. . .attachment on 10%

of the welded attachments and

. whenever component support

. member

. ~deformation is.

identified see note 6 B10.20 SIS PT 13 100% of required 2 Deferral Not 0 0 2 MSG-0009-C areas of Permissible each welded attachment on 10%

of the welded attachments and whenever component support I member deformation is identified see note 6

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 16 of 66 TABLE A SQN UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO CAT. NUMBER TO NUMBER TO ISI DRAWING METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND PERIOD B-K B10.30 Pump Welded PT 3 Reactor 100% of required One pump Deferral Not One pump 0 0 ISI-0326-C Attachments Coolant Pump areas of Permissible with each welded 3 lA's on attachment on 10%

each pump of the welded (Pumps 1, 3 attachments and 4) associated with the component supports selected for examination and whenever component support member deformation is identified see note 6 B-K B10.40 Valve Welded Surface None 100% of required N/A Deferral Not N/A N/A N/A N/A Attachments areas of Permissible each welded attachment on 10%

of the welded attachments associated with the component supports selected for examination and whenever component support member deformation is identified seenote ,

_F . .

SQN Examination Schedule (Unit 2) 0-SI-DXIO000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 17 of 66 TABLE A SQN UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT

-

EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND

-

I Pressure Retaining Welds in Pump

-PERIOD Casings . l _ _

B-L-1 B12.10 Pump Casing Welds Visual None (Note Unit 1 only) N/A Deferral NIA N/A N/A N/A Permissible B-L-2 Pump Casings B-L-2 B12.20 Pump Casing VT-3 4 Pumps At least one pump One Pump Not Applicable Only if Only if Only if ISI-0307-C Internal Surfaces in each group of disassembled disassembled disassembled pumps when disassembled B-M1 Pressure Retaining Welds in Valve Bodies _

B-M-1 B12.30 Valves Surface None At least one valve in N/A Deferral N/A N/A N/A N/A (less than NPS 4") each group of Permissible

. Body Welds valves B-M-1 B12.40 Valves Volumetric None At least one valve in N/A Deferral N/A N/A N/A NiA (NPS 4" or greater) each group of Permissible Body Welds valves B.M-2 Valve bodies ___ ___ _

B-M-2 B12.50 Valves Visual (greater than NPS 4 )

Body Internal Surfaces B12.50 RCS VT-3 One Group At least one valve in One Group I Not Applicable Only if Only if Only if Attachment 6 each group of one valve per disassembled disassembled disassembled valves when group disassembled B12.50 RHR VT-3 Three Groups At least one valve in Three Not Applicable Only if Only if Only if Attachment 6 each group of Groups / one disassembled disassembled disassembled valves when valve per

. disassembled group

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 18 of 66 TABLE A SON UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL NUMBER TO CAT. NUMBER TO NUMBER TO ISI DRAWING METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD INTERVAL INTERVAL SECOND PERIOD 812.50 SIS VT-3 Two Groups At least one valve in Two Groups/ Not Applicable Only if Only if Only if Attachment 6 each group of one valve per disassembled disassembled disassembled valves when group disassembled B-N-I Interior of Reactor Vessel _

B-N-1i B13.10 Reactor Vessel VT-3 1 Each Inspection 1 Deferral Not 1 1 1 ISI-0298-C Interior Accessible Period Permissible areas ._.

B-N-2 Welded Core Support Structure and Interior Attachments to Reactor

._ Vessels B-N-2 B13.50 Reactor Vessel Visual None Accessible welds N/A Deferral N/A N/A N/A N/A Interior Permissible Attachments Within

._ Beltline Region B-N-2 B13.60 Reactor Vessel VT-3 6 Accessible welds 6 Deferral 0 . 0 6 ISI-0298-C Interior Permissible Attachments Beyond Beltline Region B-N-3 Removal Core Support Structures B-N-3 B13.70 ReactorVessel VT-3 1 Accessible surfaces 1 Deferral 0 0 1 ISI-0298-C Core Support Structure _ Permissible .

B-0 Pressure Retaining Welds in Control Rod

__ __ _ __ __ _ _ _ _ _H o u sing _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

B-0 B14.10 Reactor Vessel UT or surface 78CRD 10% of Peripheral 2 Deferral 0 0 2 ISI-0097-C Welds in CRD Housings Housings/ 17 Housings during Permissible I

l UT is being l Performed p

Perioheral Housings last Deriod

.

ISI-0300-C

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 19 of 66 TABLE A SQN UNIT 2 - CLASS I SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE EXAMINED NUMBER TO DEFERRAL CAT. NUMBER TO NUMBER TO NUMBER TO ISI DRAWING METHOD COMPONENTS DURING BE OF BE EXAMINED BE BE EXAMINED

. . NUMBER IN ITEM INTERVAL EXAMINED INSPECTION IN THE FIRST EXAMINED IN THE THIRD NUMBER IN THE TO END OF PERIOD IN THE PERIOD

. INTERVAL INTERVAL SECOND PERIOD B-P B15,10 Pressure Retaining VT-2 This is being Components performed under another

__program B-Q B16.10 Steam Generator Volumetric NIA Tubing in straight Tube Design B-Q B16.20 Steam Generator Volumetric This isbeing Tubing in U-Tube performed Design under another

._ _ _program .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 20 of 66 NOTES

1) Following submittal and approval of request for relief PDI-2 the following may be used. Table A, Examination Category B-D, item number B3.90, reactor vessel nozzle-to-vessel welds, the examination volume may be reduced to 1/2 inch from each side of the weld crown, in lieu of the 1/2 through-wall thickness from each side of the weld required by figures IWB-2500-7(a) and (b).

2) Code case N-648-1 is being used for examination of the reactorvessel nozzle inside radius section, Examination Category B-D, item number B3.1 00, to perform a VT-1 examination with the conditions in Regulatory Guide 1.147.

3) An alternative Risk-informed Inservice Inspection Program Table E is being implemented in the third inspection interval for categories B-F and B-J Examinations for credit under the RI-ISI program Table E.

4) During U2C13 of the second interval reactor coolant pump number 4 main flange bolts were replaced with studs and hydraulic nuts per DCN E21858.

5) Table A, examination category B-G-1, item number B6.190 includes the one inch annular surface of flange surrounding each stud, only when the connection is disassembled.

6) A minimum 10 percent of the welded attachments associated with the component supports selected for examination under IWF-251 0 shall be examined.

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 21 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO CAT. NUMBER TO NUMBER ISI METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C-A Pressure Retaining Welds in Pressure Vessels .

C-A C1.10 Pressure Retaining Volumetric Shell Circumferential or Surface

._ Welds .

C1.10 Steam Generator UT 4 Steam All in one or 3 Each Inspection 2 0 151-0401-C Generators/ distributed among Interval Note: This 3 welds per the vessels at includes the Steam structural upper Generator discontinuity shell-to-transitio n cone girth

._

weld.

C1.10 Residual Heat Removal UT 2 RHRHX/ All in one or I Each Inspection 0 1 0 ISI-0289-C Heat Exchanger 1 weld per distributed among Interval RHRHX the vessels at structural discontinuity .

C1.10 Containment Spray UT 2 CSHX/ All in one or 1 Each Inspection 0 . 0 1 ISI-0463-C Heat Exchanger 1 weld per distributed among Interval CSHX the vessels at structural discontinuity C1.10 Seal Water PT 1 SWHXJ All in one or 1 Each Inspection 0 0 1 ISI-0461-C Heat Exchanger 1 weld distributed among Interval vessel wall the vessels at thickness structural less than discontinuity 0.20 inches

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-1 14.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 22 of 66 TABLE B bIN UNI I 2 - CLASS Z SCHEUULE PLANNINU UDOUMEN I EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER CAT. METHOD ISI COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED INTHE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C1.10 Seal Water PT 1 SWF/ All in one or I Each Inspection 0 1 0 IS-0459-C Filter I weld distributed among Interval vessel wall the vessels at thickness structural less than discontinuity 0.20 inches C1.10 Seal Water Injection UT 2 SWIF/ All in one or 1 Each Inspection 0 0 1 ISI-0457-C Filter 1 weld per distributed among Interval SWIF the vessels at structural

____________ discontinuity C1.10 Centrifugal Charging Volumetric None All in one or N/A Each Inspection N/A N/A N/A N/A Pump Tank distributed among Interval the vessels at structural discontinuity ._.

C-A C1.20 Pressure Retaining Volumetric Head Circumferential or Surface

._ Welds C1.20 Steam Generator UT 4 Steam Head-to-Shell 1 Each Inspection 1 0 0 ISI-0401-C Generators/ Welds, in one Interval 1 weld per vessel Steam Generator C1.20 Residual Heat Removal UT 2 RHRHX/ 1 Head-to-Shell 1 Each Inspection 0 1 0 ISI-0289-C Heat Exchanger weld per Welds, inone Interval RHRHX vessel C1.20 Containment Spray UT None Head-to-Shell N/A Each Inspection N/A N/A N/A ISI-0463-C Heat Exchanger Welds, in one Interval vessel .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 23 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER CAT. METHOD ISI COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C1.20 Seal Water PT 1 SWHXI Head-to-Shell Each Inspection 0 0 1 I51-0461-C Heat Exchanger vesse1 wall I weld Welds, in one Interval thickness less than 0.20 inches C1. 20 Seal Water PT 1 SWF/ Head-to-Shell Each Inspection 0 1 0 SI 0459-C Filter vessel wall 1 weld Welds, in one Interval thickness less than 0.20 inches C1.20 Seal Water Injection UT 2 SWIFI 1 weld Head-to-Shell 1 Each Inspection

. 0 0 1 ISI-0457-C Filter per SWIF Welds, in one Interval vessel C1.20 Centrifugal Charging UT 1 CCP Tank' Head-to-Shell 2 Each Inspection 0 0 1 ISI-0074-C Pump Tank 2 welds Welds, in one Interval vessel C-A C1.30 Tubesheet-to-Shell Volumetric Weld or Surface C1.30 Steam Generator UT 4 Steam Tubesheet-to-Shell 1 Each Inspection 1 0 0 ISI-0401-C Generators/ 1 Welds, in one Interval weld per Steam vessel Generator C1.30 Residual Heat Removal Volumetric None Tubesheet-to-Shell N/A Each Inspection N/A N/A N/A ISI-0289-C Heat Exchanger Welds, in one Interval

_- _ vessel C1.30 Containment Spray UT 2CSHX/ Tubesheet-to-Shell Each Inspection 0 0 1 ISI-0463-C Heat Exchanger I weld per Welds, in one Interval,

_ _ CSHX vessel C1.30 Seal Water Surface None Tubesheet-to-Shell . N/A Each Inspection N/A N/A N/A 151-0461-C

. Heat Exchanger Welds, inone l Interval l I I I l l .vessel .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006

. Page 24 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER CAT. ISI METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C1.30 Seal Water Surface None Tubesheet-to-Shell N/A Each Inspection N/A N/A N/A ISI-0459-C Filter Welds, in one Interval vessel C1.30 Seal Water Injection Volumetric None Tubesheet-to-Shell N/A Each Inspection N/A N/A N/A ISI-0457-C Filter Welds, in one Interval

._ vessel C-B Pressure Retaining Nozzle Welds in Vessels C-B C2.10 Nozzles in vessels

<= 1/Z' nominal thickness C-B C2.11 Nozzle-to-Shell Surface (or Head) Weld in Vessels <- 1/Z' thick, and Nozzles Greater than 4" NPS C2.11 Seal Water PT None All nozzles at N/A Each Inspection N/A N/A N/A ISI-0461-C Heat Exchanger terminal ends of Interval piping runs in one vessel C2.11 Seal Water PT None All nozzles at N/A Each Inspection N/A N/A N/A ISI-0459-C Filter terminal ends of Interval piping runs in one vessel C2.11 Seal Water Injection PT None All nozzles at N/A Each Inspection N/A N/A N/A ISI-0457-C Filter terminal ends of Interval piping runs in one vessel C-B C2.20 Nozzles without reinforcing plate in ves teiscki2 noensis__

l thickness . II

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 25 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER CAT. METHOD ISI COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED INTHE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C-B C2.21 Nozzles without Surface and Reinforcing Plate in Volumetric

._ Vessels > 112" thick C2.21 Steam Generator MT & UT 4 Steam All nozzles at 2 Each Inspection 1 (FW) 1 (MS) 0 ISI-0401-C Generators/ terminal ends of (1 FW and Interval 1 FW nozzle piping runs in one 1 MS) and vessel 1 MS nozzle each C2.21 Residual Heat Removal PT & UT 2 RHRHXI All nozzles at 2 Each Inspection 1 1 0 ISI-0289-C Heat Exchanger 2 nozzles each terminal ends of Interval piping runs in one vessel C2.21 Containment Spray MT & UT 2 CSHXJ All nozzles at 2 Each Inspection 0 0 2 ISI-0463-C Heat Exchanger 2 nozzles each terminal ends of Interval piping runs in one vessel C2.21 Centrifugal Charging MT & UT 1 CCP/ All nozzles at 2 Each Inspection 0 1 1 ISI-0074-C.

Pump Tank terminal ends of Interval 2 nozzles piping runs in one vessel C-B C2.22 Nozzle Inside Radius Volumetric Section Note: only for nozzles

greater than 1Z' NPS C2.22 Steam Generator UT 4 Steam All nozzles at 2 Each Inspection 1(FW) 1 (MS) 0 ISI-0401-C Generators/ terminal ends of Interval 1 FW nozzle piping runs in one (1 FW and and 1 MS vessel 1 MS) nozzle each

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 26 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C2.22 Residual Heat Removal UT 2 RHRHX/ All nozzles at 2 Each Inspection 1 1 0 ISI-0289-C Heat Exchanger 2 nozzles each. terminal ends of Interval piping runs in one examine with examine with piigeussinon the RHR nozzle the RHR exam C2.21 nozzle exam C2.21 C2.22 Containment Spray UT None All nozzles at N/A Each Inspection N/A N/A N/A ISI-0463-C Heat Exchanger terminal ends of Interval piping runs in one vessel ________.

C2.22 Centrifugal Charging UT None All nozzles at N/A Each Inspection N/A N/A N/A ISI-0074-C Pump Tank terminal ends of Interval piping runs in one vessel C-B C2.30 Nozzles with reinforcing plate in vessels > 1/2".

nominal thickness . .

C-B C2.31 Nozzles with Surface None All nozzles at N/A Each Inspection N/A N/A N/A N/A Reinforcing Plate in terminal ends of Interval Vessels> 1/Z' thick piping runs in one Reinforcing Plate Welds vessel to Vessel & Nozzle .

C-B C2.32 Nozzle-to-Shell (or Volumetric None All nozzles at N/A Each Inspection N/A N/A N/A N/A head) Weld when inside terminal ends of Interval of Vessel is accessible piping runs in one vessel ._l____

C-B C2.33 Nozzle-to-Shell (or Visual None All nozzles at N/A Each Inspection N/A N/A N/A N/A head) Weld when inside terminal ends of Period of Vessel is piping runs in one inaccessible vessel . . .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 27 of 66 TABLE B.

SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER CAT. METHOD ISI COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD. IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C-C Welded Attachmnents for.

. Class 2 Vessels, Piping, Pumps, and

. Valves C-C C3.10 Pressure Vessel Surface Welded Attachments C3.10 Steam Generator Surface None 100% of required N/A Each Identified NIA NIA NIA N/A areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is

._ ._ _identified C3.10 Residual Heat Removal PT 2 RHRHX/ 100% of required One RHRHX Each Identified 0 One RHRHX 0 ISI-0289-C Heat Exchanger 2 IA's each areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is

._ ._ ._ _identified ._ . .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 28 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBERTO FREQUENCYOF CAT. NUMBER TO NUMBERTO NUMBER iSI METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD INTHE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C3.10 Containment Spray MT 2 CSHX/ 100% of required One CSHX Each Identified 0 0 One CSHX ISI-0463-C Heat Exchanger 4 IA's each areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is

._ identified C3.10 Seal Water PT Heat exchanger 100% of required Heat Each Identified 0 Heat 0 ISI-0461-C.

Heat Exchanger 12 IA's areas of exchanger Occurrence and exchanger each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is identified C3.10 Seal Water PT Filterl 100% of required Filter Each Identified 0 Filter 0 ISI-0459-C Filter 4 IA's areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is identified .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 l Unit 2 Effective Date: 06-01-2006 Page 29 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C3.10 Seal Water Injection PT 2 SWIF/ 100% of required One SWIF Each Identified 0 0 one SWIF ISI-0457-C Filter 3 IA's each areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is identified C3.10 Centrifugal Charging MT Tank/ .100% of required Tank Each Identified 0 0 Tank ISI-0074-C Pump Tank 4 IA's areas of Occurrence and each welded Each Inspection attachment on one Interval vessel and whenever component support member deformation is identified ._.

C-C C3.20 Piping Welded Surface Attachments

SQN Examination Schedule (Unit 2) O-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 30 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER 1SI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL INTHE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C3.20 AFW MT 16 100% of required 2 Each Identified 1 1 0 ISI-0146-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member deformation is identified see note 2 C3.20 CS PT 16 100% of required 2 Each Identified 0 1 1 ISI-0449-C areas of Occurrence and MSG-001 1-C each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member

. deformation is

.identified see note 2

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 31 of 66 TABLE B SQN UNIT 2- CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER CAT. ISI METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL INTHE PERIOD IN THE INTHE INTERVAL SECOND THIRD PERIOD PERIOD C3.20 CVC PT 63 100% of required 7 Each Identified 2 2 3 ISI-0449-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member deformation is identified see note 2 C3.20 FVJ MT 5 100% of required 1 Each Identified 0 1 0 MSG-0016-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member deformation is identified see note 2

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 32 of 66 TABLE B S5EN UNIT Z - CLASS Z SCHE-IDULE PLANNINU UULUMEN I EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER CAT. ISI METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL INTHE PERIOD IN THE INTHE INTERVAL SECOND THIRD PERIOD PERIOD C3.20 MS MT 9 100% of required 1 Each Identified 0 1 0 MSG-0017-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member deformation is identified see note 2 C3.20 RHR PT 31 100% of required 4 Each Identified 1 1 2 ISI-0449-C areas of Occurrence and MSG-0010-C each welded Each Inspection attachment on 10% Interval of the welded attachments and whenever component support member deformation is identified see note 2

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 33 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO CAT. NUMBER TO NUMBER ISI METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL. INTHE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C3.20 SIS PT 69 100% of required 7 Each Identified 2 2 3 ISI-0449-C areas of each Occurrence and MSG-0009-C welded attachment Each Inspection on 10% of the Interval welded attachments and whenever component support member deformation is identified see note 2 C-C C3.30 Pump Welded Surface Attachments C3.30 Centrifugal Charging PT 2 CCP / 100% of required One pump Each Identified One pump 0 0 ISI-0467-C Pump 4 IA's on each areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the component supports selected for examination and whenever component support member deformation is identified see note 2

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Pagie 34 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO CAT. NUMBER TO NUMBER ISI METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C3.30 Containment Spray Surface None 100% of required N/A Each Identified N/A N/A N/A N/A Pump areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded .

attachments associated with the component supports selected for examination and whenever component support member deformation is identified see note 2 C3.30 Residual Heat Removal Surface None 100% of required N/A Each Identified N/A N/A N/A N/A Pump areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the component supports selected for examination and whenever component support member deformation is identified see note 2

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 35 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER CAT. METHOD COMPONENTS ISI EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL . IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C3.30 Safety Injection Pump Surface None 100% of required N/A Each Identified N/A N/A N/A N/A areas of Occurrence and each welded Each Inspection fattachment on 10% Interval

. of the welded attachments

. . . associated with the

. . component

. supports selected

.for examination and whenever component support member deformation is identified see note 2 C-C C3.40 Valve Welded Surface None 100% of required N/A Each Identified N/A N/A N/A N/A Attachments areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the component supports selected for examination and whenever component support member deformation is identified see note 2 Il _ _ il_ _ _ 1l _ _ _ 1._ _ _.. *I I _

_ _ _ _ _ _ .__ _ _ _ I _ _

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 36 of 66 TABLE B SQN UNIT 2- CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C-D Pressure Retaining Bolting Greater Than 2 Inches in Diameter .

C-D C4.10 Pressure Vessels Volumetric Bolts & Studs > Z' diameter C4.10 Steam Generator Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A component Interval C4.10 Residual Heat Removal Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A Heat Exchanger component Interval C4.10 Containment Spray Volumetric None 100% of one N/A Each Inspection NIA N/A N/A NIA Heat Exchanger component Interval C4.10 Seal Water Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A Heat Exchanger component Interval C4.10 Seal Water Volumetric None 100% of one N/A Each Inspection N/A NIA NiA N/A Filter component Interval C4.10 Seal Water Injection Volumetric None 100% of one N/A Each Inspection N/A N/A N/A N/A Filter component Interval C4.10 Centrifugal Charging UT 1 CCP/ 16 bolts 100% of one 1 Each Inspection 1 0 0 ISI-0074-C Pump Tank component (16 bolts) Interval (16 bolts)

C-D C4.20 Piping Volumetric None 100% of one NIA Each Inspection N/A NIA N/A N/A Bolts & Studs > 2" component in each Interval diameter group C-D C4.30 Pumps Volumetric None 100% of one N/A Each Inspection N/A N/A N/A NIA Bolts & Studs > Z' component Interval diameter _

C-D C4.40 Valves Volumetric None 100% of one N/A Each Inspection NIA N/A N/A N/A Bolts & Studs > Z component Interval diameter . . -

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 37 of 66 TABLE B SQN UNIT 2 - CLASS 2 SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY OF NUMBER TO NUMBER TO NUMBER ISI CAT. METHOD COMPONENTS EXAMINED BE EXAMINATION BE EXAMINED BE TO BE DRAWING IN ITEM DURING EXAMINED IN THE FIRST EXAMINED EXAMINED NUMBER NUMBER INTERVAL IN THE PERIOD IN THE IN THE INTERVAL SECOND THIRD PERIOD PERIOD C-F-1 ALL Pressure Retaining N/A N/A N/A N/A N/A N/A N/A N/A Welds in Austenitic Stainless Steel or see Note 1 High Alloy Piping ._.

C-F.2 ALL Pressure Retaining N/A ALL N/A N/A N/A N/A N/A N/A Welds in Carbon or Low Alloy Steel see note 1

. _ Piping C-G Pressure Retaining Welds in Pumps and Valves C-G C6.10 Pump Casing Welds Surface None 100% of welds in N/A Each Inspection N/A N/A N/A N/A components in Interval piping runs examined under C-F. ._.

C-G C6.20 Valve Body Welds Surface None 100% of welds in N/A Each Inspection N/A N/A N/A N/A components in Interval piping runs examined under C-F. . .- _: _

C-H C7.1 0 Pressure Retaining VT-2 This is being Components performed under another

._ _ _program _

SQN Examination Schedule (Unit 2) O-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 38 of 66 NOTES

1) An alternative Risk-Informed Inservice Inspection Program Table E is being implemented in the third inspection interval for categories C-F-1 and C-F-2.

The examinations for credit under the RI-ISI program Table E.

2) As a minimum 10 percent of the welded attachments associated with the components supports selected for examination under IWF-251 0 shall be examination.

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 39 of 66 TABLE C SQN UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF CAT.

NUMBER NUMBER NUMBER ISI NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND -THIRD PERIOD PERIOD PERIOD D-A Welded Attachments for Class 3 Vessels, Piping, Pumps, and Valves D-A D1.10 Pressure Vessel Visual Welded Attachments D1.10 Containment Spray VT-1 2 CSHX/ One Heat One heat Each Identified 0 0 One heat ISI-0463-C Heat Exchanger 4 lA's each Exchanger, 100%. exchanger Occurrence and exchanger of required areas of Each Inspection each welded Interval attachment and whenever component support member deformation is identified D1.10 Nonregenerative VT-1 Heat All, 100% of Heat Each Identified 0 Heat 0 ISI-0257-A Letdown Heat Exchanger/ required areas of Exchanger Occurrence and Exchanger Exchanger 1 IA each welded Each Inspection attachment and Interval whenever component support member deformation is identified . .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 40 of 66 TABLE C SQN UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF %TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CAT. NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER

.NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.10 Gas Stripper and Boric Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Acid Evaporator areas of Occurrence and Condenser each welded Each Inspection attachment and Interval whenever component support member deformation is identified D1.10 Gas Stripper and Boric Visual None All, 100% of N/A Each Identified N/A N/A N/A N/A Acid Evaporator required areas of Occurrence and Distillate Cooler each w:elded Each Inspection attachment and Interval whenever component support member deformation is identified D1.10 Gas Stripper and Boric Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Acid Evaporator areas of Occurrence and Support Frame each welded Each Inspection attachment and Interval whenever component support member deformation is

._ identified D1.10 Component Cooling VT-1 Tank/ All, 100% of Tank Each Identified 0 Tank 0 ISI-0227-B Surge Tank I IA required areas of Occurrence and each welded Each Inspection attachment and Interval whenever component support member.l l deformation is

__ ._

_identified .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-1 14.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 41 of 66 TABLE C SQN UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CAT. NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD 01.10 Essential Raw Cooling VT-i 2 ERCWSI One Strainer, 100% One strainer Each Identified One strainer 0 0 15X-0268-C Water System Strainer 16 IA s on A of required areas of Occurrence and and each welded Each Inspection 17 IA's on B attachment and Interval whenever component support member deformation is

._ identified D1.10 Air Conditioning I VT-1 Chiller / Ail, 100% of Chiller Each Identified Chiller 0 0 ISI-0455-C Chilled Water System 2 lA's required areas of Occurrence and Shut Down Board each welded Each Inspection Room Water Chiller attachment and Interval whenever component support member deformation is

. _identified .

D1.10 Air Conditioning I VT-1 Separator All, 100% of Separator Each Identified Separator 0 0 ISI-0479-C Chilled Water System 4 IA's required areas of Occurrence and Chill Water Air each welded Each Inspection Separator attachment and Interval whenever component support member deformation is

._ identified

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 42 of 66 TABLE C SQN UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISt CAT. NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL THE INTHE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.10 Component Cooling VT-I None One Heat N/A Each Identified N/A N/A N/A ISI-0261-B Heat Exchanger Exchanger, 100% Occurrence and of required areas of Each Inspection each welded Interval attachment and whenever component support member deformation is identified D1.10 Fuel Pool Cooling and VT-i Unit 1only 100% of required N/A Each Identified N/A N/A N/A N/A Cleaning System Spent areas of Occurrence and Fuel Pit Heat each welded Each Inspection Exchanger attachment and Interval whenever component support member deformation is

_ _identified D1.10 RHR Heat Exchanger VT-1 2 RHRHSHX/ One Heat One heat Each Identified 0 0 One heat ISI-0291-C Secondary Side 2 IA's each Exchanger, 100% exchanger Occurrence and exchanger of required areas of Each Inspection each welded Interval attachment and whenever component support member deformation is identified

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 43 of 66 TABLE C SQN UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER CAT. NUMBER NUMBER ISI NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL THE IN THE INTHE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.10 ERCW Old ERCW VT-i 2 ERCW-STR / One Strainer, 100% One strainer Each Identified 0 One strainer Intake Pumping Station 0 ISI-0481-C 2 IA's each of required areas of Occurrence and Strainer each welded Each Inspection attachment and Interval whenever component support..

member

. . deformation is identified D-A D1.20 Piping Visual

._ _ Welded Attachments .

D1.20 AFW VT-1 14 100% of required 2 Each identified 1 0 1 ISI-0146-C areas of Occurrence and each welded Each Inspection attachmenton 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

. _ identified

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 44 of 66 TABLE C SQN UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CAT. NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL THE IN THE INTHE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.20 CC VT-1 42 100% of required 5 Each Identified 1 1 3 ISI-0154-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexemrpt component supports and whenever component support member deformation is

._ . identified D1.20 ERCW VT-1 63 100% of required 7 Each Identified 2 2 3 ISI-0158-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified .

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 . Effective Date: 06-01-2006 Page 45 of 66 TABLE C SQN UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER iSI CAT. NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.20 FPCS VT-1 Unit 1 only 100% of required N/A Each Identified N/A N/A N/A N/A areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

.___ ___ _identified ._. _.

D1.20 ACCW VT-1 None 100% of required N/A Each Identified N/A N/A N/A ISI-0451-C areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

_ ._ identified D-A D1.30 Pump Welded Visual

___ __ Attachments

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 46 of 66 TABLE C SQN UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF CAT. NUMBER NUMBER NUMBER ISI NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL THE IN THE INTHE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.30 Turbine Driven Auxiliary Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Feedwater Pump areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified _ ___

D1.30 Motor Driven Auxiliary Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Feedwater Pump areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

__ identified

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 47 of 66 TABLE C SQN UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CAT. NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.30 Component Cooling Visual None 100% of required N/A Each Identified N/A N/A N/A N/A System Water Pumps areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

.__ _ identified .

D1.30 Essential Raw Cooling Visual Unit 1 only 100% of required N/A Each Identified N/A N/A N/A N/A Water System Pump areas of Occurrence and Station Pump each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

._ . identified

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 48 of 66 TABLE C SQN UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF % TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CAT. NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.30 Fuel Pool Cooling and Visual Unit 1 only 100% of required N/A Each Identified N/A N/A N/A N/A Cleaning System Spent areas of Occurrence and Fuel Pit Pumps each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is

.___ _ _identified . .

D1.30 Air Conditioning / Visual None 100% of required N/A Each Identified N/A N/A N/A N/A Chilled Water System areas of Occurrence and Chill Water Circulation each welded Each Inspection Pump attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified . _

SQN Examination Schedule (Unit 2) O-SI-DXI-000-1 14.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 49 of 66 TABLE C SON UNIT 2 - CLASS 3 SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF %TO BE NUMBER TO FREQUENCY OF NUMBER NUMBER NUMBER ISI CAT. NO. METHOD COMPONENTS EXAMINED BE EXAMINATION TO BE TO BE TO BE DRAWING IN ITEM DURING EXAMINED IN EXAMINED EXAMINED EXAMINED NUMBER NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD D1.30 ERCW Screen Wash Visual Unit 1 only 100% of required N/A Each Identified N/A N/A N/A N/A Pump Support areas of Occurrence and each welded Each Inspection attachment on 10% Interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified D-A Valve Welded Visual None I100% of required N/A Each Identified N/A N/A N/A N/A Attachments areas of Occurrence and each welded Each inspection attachment on 10% interval of the welded attachments associated with the nonexempt component supports and whenever component support member deformation is identified .

D-B 02.10 Pressure Retaining VT-2 This is being Components performed under another l I I program I

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 50 of 66 NOTES

1) No Notes.

/

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 51 of 66 TABLE D SQN UNIT 2 - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE BE NUMBER IN ITEM DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F-A F1.10A Class I Piping Visual One-directional Restraints FunctionA _

F 1.10A CVC VT-3 30 25% 8 Each inspection 2 2 4 MSG-0012 C interval MSG-0015-C F1.10A RCS VT-3 9 25% 3 Each inspection 0 1 2 MSG-0013-C

.I. interval F 1.1OA RCS MAIN VT-3 None 25% N/A Each inspection N/A N/A N/A ISI-0302-C interval ISI-0321-C F1.1OA RHR VT-3 8 25% 2 Each inspection 1 1 0 MSG-0010-C

._ interval F1.10A SIS VT-3 19 25% 5 Each inspection 1 2 2 MSG-0009-C interval F-A F1.10B Class 1 Piping Visual Multidirectional Restraints Function B F1.10B CVC VT-3 89 25% 23 Each inspection 8 7 8 MSG-0012-C

. interval MSG-0015-C F1.10B RCS VT-3 6 25% 2 Each inspection 1 0 1 MSG-0013-C interval F1.10B RCS MAIN VT-3 4 25% 1 Each inspection 1 0 0 ISI-0302-C interval ISI-0321-C F1.10B RHR VT-3 4 25% 1 Each inspection 0 0 1 MSG-0010-C

__ __ __ interval _

F1.10B SIS VT-3 54 25% 14 Each inspection 4 5 5 MSG-0009-C

_ inteal

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 52 of 66 TABLE D SQN UNIT 2- CLASS 1, 2,AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE BE NUMBER IN ITEM DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F-A F1.10C Class 1 Piping Visual Variable Supports (Springs and Constant Force)

Function C F1.10C CVC VT-3 .2 25% 1 Each inspection 0 1 0 MSG-0012-C

. interval MSG-0015-C F1.10C RCS VT-3 13 25% 4 Each inspection 1 1 2 MSG-0013-C interval F1.10C RCS MAIN VT-3 1 25% 1 Each inspection 0 0 1 ISI-0302-C

. . . interval ISI-0321-C F1.10C RHR VT-3 None 25% N/A Each inspection N/A N/A N/A MSG-0010-C

._ _ . interval F1.10C SIS VT-3 4 25% 1 Each inspection 0 1 0 MSG-0009-C I _____ __ interval F-A F1.10D Class 1 Piping Visual Variable Supports (Snubbers)

Function D F1.101) CVC VT-3 8 25% 2 Each inspection 1 1 0 MSG-0012-C interval MSG-0015-C F1.10D RCS VT-3 15 25%. 4 Each inspection 1 1 2 MSG-0013-C interval F1.1OD RCS MAIN VT-3 None 25% N/A Each inspection N/A N/A N/A ISI-0302-C

. .. interval ISI-0321-C F1.10D RHR VT-3 1 25% 1 Each inspection 0 0 1 MSG-0010-C

__ _ _ interval F1.10D SIS VT-3 9 25% 3 Each inspection 1 1 1 MSG-0009-C

._ interval

0-SI-DXI-000-1 14.3 Att.5 Effective Date: 06-01-2006 Page 53 of 66 TABLE D SQN UNIT 2 - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE BE NUMBER IN ITEM DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE IN THE IN THE INTHE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F.A F1.20A Class 2 Piping Visual One-directional Restraints

._ Function A F1.20A AFW VT-3 32 15% 5 Each inspection 1 2 2 ISI-0146-C interval F1.20A CS VT-3 23 15% 4 Each inspection 1 1 2 ISI-0449-C interval MSG-0011-C F1.20A CVC VT-3 77 15% 12 Each inspection 3 5 4 ISI-0449-C interval F1.20A FW VT-3 14 15% 3 Each inspection 1 1 1 MSG-0016-C

.__interval ._ .

F1.20A MS VT-3 8 15% 2 Each inspection 0 1 1 MSG-0017-C interval F1.20A RHR VT-3 57 15% 9 Each inspection 3 3 3 ISI-0449-C interval MSG-001 0-C F1.20A SIS VT-3 74 15% 12 Each inspection 3 3 6 ISI-0449-C interval MSG-0009-C F-A F1.20B Class 2 Piping Visual Multidirectional Restraints Function B F1.20B AFW VT-3 25 15% 4 Each inspection 1 1 2 ISI-0146-C

.____ _ _interval _. .

Fl.20B CS VT-3 25 15% 4 Each inspection 1 1 2 ISI-0449-C interval MSG-001 1-C Fl.20B CVC VT-3 44 15% 7 Each inspection 2 2 3 ISI-0449-C interval _

Fl.20B FW VT-3 3 15% 1 Each inspection 0 1 0 MSG-0016-C interval l l F1.20B l MS I VT-3 J lb% Eacn inspection interval lllll i i

,

rvivl.SG-0w;7-C

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 54 of 66 TABLE D SQN UNIT 2- CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE BE NUMBER IN ITEM DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F1.20B RHR VT-3 29 15% 5 Each inspection 1 2 2 ISI-0449-C

_ _ _ interval MSG-0010-C F1. 208 SIS VT-3 151 15% 23 Each inspection 7 8 8 SI-0449-C interval MSG-0009-C F-A F1.20C Class 2 Piping Visual Variable Supports (Springs and Constant Force)

Function C __________

F1.20C AFW VT-3 13 15% 2 Each inspection 1 0 1 ISI-0146-C interval F1.20C CS VT-3 8 15% 2 Each inspection 1 1 0 ISI-0449-C

___ _ interval MSG-001 1-C F1.20C CVC VT-3 11 15% 2 Each inspection 0 1 1 ISI-0449-C interval F1.20C FW VT-3 8 15% 2 Each inspection 0 1 1 MSG-0016-C

_ __ interval F1.20C MS VT-3 16 15% 3 Each inspection 1 1 MSG-0017-C interval F1.20C RHR VT-3 19 15% 3 Each inspection 1 1 1 ISI-0449-C interval MSG-0010-C F1.20C SIS VT-3 12 15% 2 Each inspection 1 1 0 ISI-0449-C interval MSG.0009-C F-A F1.20D Class 2 Piping Visual Variable Supports (Snubbers)

Function D F1.20D AFW VT-3 a 15% 2 Each inspection 0 1 1 ISI-0146-C

_ interval F1.20D CS VT-3 None 15% N/A Each inspection N/A N/A N/A ISI-0449-C I I I __ I interval I MSG-0011C

SQN Examination Schedule (Unit 2) O-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 55 of 66 TABLE D SQN UNIT 2 - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE BE NUMBER IN ITEM DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD

=_- m - PERIOD

-

PERIOD

- PERIOD F1.20D CVC VT-3 10 15% 2 Each inspection 1 1 0 ISI-0449-C interval F1.20D FW VT-3 5 15% 1 Each inspection 1 0 0 MSG-0016-C

._ _ _ interval .

F1.20D MS VT-3 14 15% 3 Each inspection 1 1 1 MSG-0017-C interval F1.20D RHR VT-3 7 15% 2 Each inspection 1 1 0 ISI-0449-C interval MSG-0010-C F1 .20D SIS VT-3 13 15% 2 Each inspection 0 1 1 ISI-0449-C interval MSG-0009-C F-A F1.30A Class 3 Piping Visual One-directional Restraints Function A F1.30A ACCW VT-3 None 10% NIA Each inspection N/A N/A N/A ISI-0451-C interval F1.30A AFW VT-3 20 10% 2 Each inspection 1 0 1 ISI-0146-C interval F1.30A CC VT-3 93 10% 10 Each inspection 3 3 4 ISI-0154-C interval F1.30A CVC VT-3 None 10% N/A Each inspection N/A N/A N/A 151-0449-C interval F1.30A ERCW VT-3 133 10% 14 Each inspection 4 5 5 ISI-0158-C

__ interval F1.30A FPCS VT-3 Unit 1 only 10% N/A Each inspection NIA NIA NIA N/A interval F-A F1.30B Class 3 Piping Visual Multidirectional Restraints Function B . . .

F j ACC; 'v j- 12 il2451-C 10% 2 0n 1 1

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-1 14.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 56 of 66 TABLE D SQN UNIT 2 - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE BE NUMBER IN ITEM DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE INTHE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD Fl.308 AFW VT-3 18 10% 2 Each inspection 1 0 1 ISI-0146-C interval Fl.308 CC VT-3 96 10% 10 Each inspection 3

_ _ 3 4 ISI-0154-C interval F1.30B CVC VT-3 None 10% N/A Each inspection N/A N/A N/A ISI-0449-C I interval F1.30B ERCW VT-3 161 10% 17 Each inspection 5 6 6 ISI-0158-C interval Fl.30B FPCS VT-3 Unit I only 10% N/A Each inspection N/A

. N/A N/A N/A

_ interval F-A F1.30C Class 3 Piping Visual Variable Supports (Springs and Constant Force)

Function C F1.30C ACCW VT-3 None 10% N/A Each inspection N/A. N/A N/A ISI-0451-C

. _ interval F1.30C AFW VT-3 17 10% 2 Each inspection 0 1 1 ISI-0146-C interval F1.30C CC VT-3 13 10% 2 Each inspection 1 1 0 ISI-0154-C I interval F1.30C CVC VT-3 None 10% N/A Each inspection N/A N/A N/A ISI-0449-C interval F1.30C ERCW VT-3 4 10% 1 Each inspection 0 1 0 ISI-0158-C interval F1.30C FPCS VT-3 Unit 1only 10% N/A Each inspection N/A. N/A N/A N/A interval F-A F1.30D Class 3 Piping Visual Variable Supports-(Snubbers)

Fuinrtfnn .

I F1.30D ACCW VT-3 I None 10% N/A Each inspection N/A N/A N/A ISI-0451-C II I interval I

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-1 14.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 57. of 66 TABLE 0 SQN UNIT 2 - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE BE NUMBER IN ITEM DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD Fl 300) AFW VT-3 3 10% I Each inspection 0 10 ISI-0146-C interval F1.30D . cc VT-3 I1I 10% .2 Each inspection

_ ___ __ ___ _ __ _ _

I 0 1 ISI 0154-C

_ _ _ _ _ _ _ _ __ _ __ __ __ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _in te rv al _ _ _ _ _ _ _ _ _ _ _ _

Fl 300) CVC VT-3 None 10% NIA Each inspection N/A' N/A N/A ISI 0449-C

____ ___ ____ __ _ ___

____ ____________ _____

____ ____ _Iin terv al _ _ _ _ _ _ _

Fl 300) ERCW VT-3 4 10% I Each inspection 0 0 1 ISI 0158 C

____________ __ __ ____ ____ ___ _ ___ ____ ____ ___in terval _ _ _ _ _ _ _

Fl 300) FPCS VT-3 Unit 1 only 10% N/A Each inspection .N/A N/A N/A N/A interval F-A FI.40 Class 1, 2, or 3 Visual 100% of the Each inspection see Supports Other Than components or it interval Note: I Piping Supports multiple components only one of the multiple

__________ ~components _ _ _ _ _ _

Class 1 Equipment __ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _

F1.40E4 Class 1 VT-3 Reactor Vessel All Reactor Each inspection 0 0 Reactor ISI-0298-C

_____ Reactor Vessel / I support Vessel interval Vessel F1.40E5 Class I VT-3 Pressurizer / All Pressurizer I Each inspection 0 Pressurizer I 0 1S1-0396-C

_____ Pressurizer 2 supports 2 supports interval 2 supports F1.40E1 Class 1 VT-3 4 Steam One Steam One Steam Each inspection 0 0 One Steam ISI-0401-C Steam Generator Generators / Generator Generator interval Generator

_ _ ____

_ _ _ _ _____

_ ____ ____ ____ ____ _ __ ____ ___ 1 su p p ort e a ch _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

F1.40E3 Class I VT-3 4 Reactor One Pump One Reactor Each inspection One Reactor 0 0 1S1-0326-C Reactor Coolant Pump Coolant Pumps Coolant Pump interval Coolant

/ Pump

_________ ___________ ~~1support each _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Fi.4E Class 1 *VT-3 100% of the valves N/A Each inspection

.None N/A N/A N/A nrif mlitfini. unlyaq intervalI

_ _ __ _ _ __ __ _ __ __ _ _ __ __ ____ __ __ ___ __ __ _ ____ _ _ ___ _ m ultiple valv es ______I _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 58 of 66 TABLE D SQN UNIT 2 - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE IN ITEM BE NUMBER DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE INTHE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD Class 2 Equipment l___l_._. I Fl.40E2 Class 2 VT-3 4 Steam One steam One Steam Each inspection One Steam 0 0 ISI-0401-C Steam Generator Generators Generator Generator interval Generator 1 support each F1.40E1 Class 2 VT-3 2 RHRHX/ One Heat One Heat Each inspection 0 One Heat 0 ISI-0289-C Residual Heat Removal 1 support on Exchanger Exchanger interval Exchanger Heat Exchanger each F1.40E1 Class 2 VT-3 2 CSHX / One Heat One Heat Each inspection 0 0 One Heat ISI-0463-C Containment Spray 1 support on Exchanger Exchanger interval Exchanger Heat Exchanger _ each F11.40E1 Class 2 VT-3 Seal Water All Seal Water Each inspection 0 Seal Water 0 ISI-0461-C Seal Water Heat Heat interval Heat Heat Exchanger Exchanger / Exchanger Exchanger 1support .

F1 .40E6 Class 2 VT-3 Seal Water All Seal Water Each inspection 0 Seal Water 0 ISI-0459-C Seal Water Filter / Filter interval Filter Filter 1support F1.40E6 Class 2 VT-3 2 SWIF / One filter One SWIF Each inspection 0 0 One SWIF ISI-0457-C Seal Water 1 support each interval Injection Filter F1.40E8 Class 2 VT-3 Centrifugal All Centrifugal Each inspection 0 0 Centrifugal ISI-0074-C Centrifugal Charging Charging Pump Charging interval Charging Pump Tank Tank / Pump Tank Pump Tank

___ _1 support _

F1.40E3 Class 2 VT-3 2 RHRP I One Pump One RHRP Each inspection 0 One RHRP 0 ISI-0352-C Residual Heat Removal 1 support each interval Pump F1.40E3 Class 2 VT-3 2 CCP / One Pump One CCP Each inspection One CCP 0

~ 0 ISI-0467-C

, .. f~ill IllUgal . Wlldlill gi-ngt ak .. __ _ _ . __ ____ ___intprv 1 Pumpll.

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 59 of 66 TABLE D SQN UNIT 2- CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT

-_ - - -w

_---_

EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE BE NUMBER IN ITEM DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE IN THE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F1.40E3 Class 2 VT-3 2SIPI One Pump One SIP Each inspection 0 One SIP 0 151-0471-C Safety Injection 1 support each interval Pump _

F1.40E3 Class 2 VT-3 2 CSP/ One Pump One CSP Each inspection 0 0 OneCSP ISI-0465-C Containment Spray 1 support each interval Pump

.

F-A F1.40E9 Class 2 Visual

._ Valves F1.40E9 Class 2 VT-3 1 Valve with 100% of the valves 1 Each inspection 0 1 0 ISI-0146-C Valves one support in or if multiple valves interval the AFW only one of the AFW_ system multiple valves F1 .40E9 Class 2 VT-3 2 Valves with 100% of the valves 1 Each inspection 0 0 1 MSG-0010-Q Valves one support or if multiple valves interval each inthe only one of the RHR *RHR system multiple valves Class 3 Equipment

_

F1.40E1 Class 3 VT-3 2 CSHX / One Heat One CSHX Each inspection 0 0 One CSHX ISI-0463-C Containment Spray 1support each Exchanger interval Heat Exchanger I F1.40E1. Class 3 VT-3 Heat Exchanger All Heat Each inspection 0 Heat 0 ISI-0257-A Nonregenerative /Exchanger interval Exchanger Letdown Heat .1 support Exchanger F1.40E7 Class 3 VT-3 Condenser / All Condenser Each inspection 0 0 Condenser ISI-0226-C Gas Stripper and Boric 1support interval Acid Evaporator

_ Condenser F1 .40E7 Class 3 VT-3 Cooler / All Cooler Each inspection 0 0 G'Of,;- - Em.,"pf Cooler ISI-0226-C interval Acid'Evapor;ator Distillate Cooler

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 60 of 66 TABLE D SQN UNIT 2 - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE BE NUMBER IN ITEM DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE INTHE IN THE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F1.40E7 Class 3 VT-3 Frame All Frame Each inspection 0 0 Frame ISI-0226-C Gas Stripper and Boric 1 support interval Acid Evaporator Support Frame F1.40E8 Class 3 VT-3 Tank / All Tank Each inspection 0 Tank 0 ISI-0227-B Component Cooling 1 support interval Surge Tank F1.40E3 Class 3 VT-3 Pump / All Pump Each inspection 0 0 Pump ISI-0475-C Turbine Driven Auxiliary I support interval Feedwater Pump F1.40E3 Class 3 VT-3 2 MDAFWP/ One pump One Each inspection 0 0 One ISI-0477-C Motor Driven 1 support each MDAFWP interval MDAFWP Auxiliary Feedwater Pump . _

F1.40E3 Class 3 VT-3 2 CCSWP / One pump One CCSWP Each inspection 0 One CCSWP 0 ISI-0260-C CCS Water Pumps 1 support each interval F1.40E1 Class 3 VT-3 2 CCHX One heat One CCHX Each inspection 0 One CCHX 0 ISI-0261-B CCS Heat Exchanger 1 support each exchanger interval F1.40E6 Class 3 VT-3 2 ERCWS / One Strainer One ERCWS Each inspection One 0 0 ISI-0268-C ERCW Strainer 1 support each interval ERCWS F1.40E3 Class 3 VT-3 Unit 1only One Pump N/A Each inspection N/A N/A N/A N/A ERCW Pump Station interval Pump _ __L F1.40E3 Class 3 VT-3 Unit I only One Pump N/A Each inspection N/A N/A N/A N/A FPCC Spent Fuel Pit interval Pumps . .

F1.40E7 Class 3 VT-3 Chiller / All Chiller Each inspection Chiller 0 0. ISI-0455-C ACCW Shut Down 1 support interval Board Room Water

. iChiller _

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 61 of 66 TABLE D SQN UNIT 2 - CLASS 1, 2, AND 3 SUPPORTS SCHEDULE PLANNING DOCUMENT EXAM ITEM NO. DESCRIPTION EXAM NUMBER OF TO BE NUMBER TO FREQUENCY NUMBER NUMBER TO NUMBER TO ISI DRAWING CAT. METHOD COMPONENTS EXAMINED BE OF TO BE BE BE NUMBER IN ITEM DURING EXAMINED IN EXAMINATION EXAMINED EXAMINED EXAMINED NUMBER INTERVAL THE IN THE INTHE IN THE INTERVAL FIRST SECOND THIRD PERIOD PERIOD PERIOD F1 40E3 Class 3 VT-3 Pump / All Pump Each inspection Pump 0 0 ISf-0473-C ACCW Chill Water 1 support interval Circulation Pump . _

F1 .40E7 Class 3 VT-3 Separator / All Separator Each inspection Separator 0 0 ISI-0479-C ACCW Chill Water Air 1 support interval Separator F1 .40E1 Class 3 VT-3 Unit 1 only One heat N/A Each inspection N/A N/A N/A N/A FPCC Spent Fuel Pit exchanger interval Heat Exchanger

.

F1.40E1 Class 3 VT-3 2 RHRHSX/ One heat One RHRHSX Each inspection 0 0 One RHRHSX ISI-0291-C RHR Heat Exchanger I support each exchanger interval Secondary Side . .

F1.40E3 Class 3 VT-3 Unit 1 only One Pump N/A Each inspection N/A N/A N/A N/A ERCW Screen Wash interval Pump Support F1.40E6 Class 3 VT-3 2 ERCW-STR / One strainer One Each inspection 0. One 0 IS1-0481-C ERCW Intake Pumping I support each ERCW-STR interval ERCW-STR Station Strainer F1.40E9 Class 3 VT-3 None 100% of the valves N/A Each inspection N/A N/A N/A Valves or if multiple valves interval only one of the multiple valves

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 62 of 66 NOTES

1) Table D, item number F1.40, REFER TO O-SI-DXI-000-114.3 Section 7.2.D.10 for description of equipment support functions.

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 63 of 66 TABLE E

-SQN UNI I Z - ASMEt LASS 1 AND Z KI-1I bLCHtLUL PLJANNING DOCUMlN I EXAM ITEM DESCRIPTION EXAM NUMBER OF ELEMENTS/SEGMENTS NUMBER TO DEFERRAL NUMBER NUMBER NUMBER TO IS DRAWING CAT. NO. METHOD IN ITEM NUMBER BE OF TO BE TO BE BE EXAMINED NUMBER EXAMINED INSPECTION EXAMINED EXAMINED IN THE THIRD DURING TO END OF IN THE INTHE PERIOD INTERVAL INTERVAL FIRST SECOND PERIOD PERIOD R-A Rl.10 High Safety Significant Piping Structural Elements _

R-A R1.1 1 Elements Subject to Volumetric 56 ELEMENTS 56 Not 18 19 19 CHM-2403-C Thermal Fatigue (UT) see note: 1 Permissible ISI-0002-C see note 1 AFWF-001, AFWF-007 ISI-0003-C AFWS-016, AFWS-018 ISI-0008-C CSF-058, CSF-063, CSF-099A ISI-0009-C CSS-013, CSS-109 ISI-0013-C CVCF-020, CVCF-161 . S-0015-C CVCS-038, CVC-1169 ISI-0298-C CVCW-1236A, CVCW-1057A ISI-0431-C CVCW-1091A ISI-0435-C MSS-004, MSS-009, MSS-016, MSS-023 RC-01 -SE, RC-08-SE, RC-09-SE ISI-0511-C RC-16-SE, RC-17-SE, RC-24-SE MSG-0008-C RC-25-SE, RC-32-SE RC-33, RC-33-S1, RC-35 RHRF-020, RHRF-093 RHRF-103, RHRF-105 RHRS-127, RHRS-166 Sl-1870, SIF-038, SIF-047, SIF-131 SIF-170, SIF-194B, SIF-198D, SIF-199 SIS-075, S5S-083A, S5S-084 SIS-097, SIS-199, SIS-240, SIS-244 SIS-279, SIS-291, SIS-317 SIW-1014C

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 64 of 66 TABLE E SQN UNIT 2 - ASME CLASS 1 AND 2 RI-ISI SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF ELEMENTSISEGMENTS NUMBER TO DEFERRAL NUMBER NUMBER NUMBER TO ISI DRAWING CAT. NO. METHOD IN ITEM NUMBER BE OF TO BE TO BE BE EXAMINED NUMBER EXAMINED INSPECTION EXAMINED EXAMINED IN THE THIRD DURING TO END OF INTHE IN THE PERIOD INTERVAL INTERVAL FIRST SECOND PERIOD PERIOD R-A R1.1 i Elements Subject to VT-2 SEGMENTSAll Not All each All each All each see TVA

.Thermal Fatigue each refueling Permissible refueling refueling refueling Calculation see note 1 sD-009, BD-012, BD-017 outage outage outage outage SQN-MEB-MD BD-020,80-021, BD-024 see notes:

CS-012 1, 2,3, and 5 CH-030, CH-031, CH-032, CH-033 CH-034, CH-035, CH-036, CH-037 RC-036, RC-050, RC-052 RC-053, RC-054, RC-060 RH-003 Sl-055B, Sl-056B, SC-057A, SC-05aA SI-059769,I-0l70,S1-071, SI-072 SI-073, SI-074, SI-075, SI-076 SI-077B, SI-078, Sl-079B, SI-081 B

.. .Sl-089, Sl-090 R-A R1.12 Elements Subject to Visual, VT-2 SEGMENTS AlNot All each All each All each see TVA High Cycle Mechanical see note: 3 each refueling Permissible refueling refueling refueling Calculation FatigueB-0,B-1 outage outage outage outage SN09-000085 see note I CH-003B, CH-004B, CH-030 see notes: I CH-031, CH-032, CH-033, CH-034 and 3

. CH-035, CH-036, CH-037 RC-036

. . Sl-057A, Sl-058A, S1-069, Sl-070

. ~Sl4071, Sl-072, Sl-073, Sl-074..

S1-075, Sl-076, Sl-079B, Sl-081 B

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-114.3 Att.5 Unit 2 Effective Date: 06-01-2006 Page 65 of 66 TABLE E orwhi MI' -ARACU 9P AC Q 4 Akin,) DLICt Qrlucflhi I Di APMM01irfl. nflVIMP1RKMT owAI' Unix4 I v - i.oIVIL.'s g .~ o w gI4L Lm I<~J SDlo I IbnLIJ.JL rozI4II4*. LIv~~JviIvc It EXAM ITEM DESCRIPTION EXAM NUMBER OF ELEMENTSISEGMENTS NUMBER TO DEFERRAL NUMBER NUMBER NUMBER TO ISI DRAWING CAT. NO. METHOD IN ITEM NUMBER BE OF TO BE TO BE BE EXAMINED NUMBER EXAMINED INSPECTION EXAMINED EXAMINED INTHE THIRD DURING TO END OF IN THE IN THE PERIOD INTERVAL INTERVAL FIRST SECOND CrPERIOD PERIOD ta R-A RI.13 Elements Subject to Volumetric There are no elements/segments subject N/A N/A N/A NIA N/A Corrosive, Erosive, or (for internal Corrosive,eoErosive, or Cavitation Cavitation Wastage Wastage) or Wastage.

surface (for C see notel external Wastage)

R-A R1.14 Elements Subject to Volumetric There are no elements/segments subject N/A N/A N/A N/A N/A Crevice Corrosion to Crevice Corrosion Cracking

. ~Cracking..

see note I R-A R1.15 Elements Subject to Visual, VT-2 There are no elements/segments subject N/A N/A N/A NIA . N/A Primary Water Stress to Primary Water Stress Corrosion Corrosion Cracking Cracking (PWSCC)

(PWSCC) see note 1 R-A R1.16 Elements Subject to Volumetric 4ELEMENTS 4 'N/A 1 1 2 IS[-0002-C.

Intergranular Stress ISI-0003-C Corrosion Cracking RHRF-105 (IGSCC) SIF-038, SIF-131, SIF-170 see note 1 R-A R1.16 Elements Subject to Visual, VT-2 SEGMENTS All Not All each All each All each Intergranular Stress see notes: 2 SI-081 B each refueling Permissible refueling refueling refueling Corrosion Cracking and 3 outage outage outage outage (IGSCC) see notes: 1, 2 see note 1 and 3

SQN Examination Schedule (Unit 2) 0-SI-DXI-000-1 14.3 Att.5 Unit 2 Effective Date: 06-01-2006 Paqe 66 of 66 TABLE E SQN UNIT 2- ASME CLASS 1 AND 2 RI-ISI SCHEDULE PLANNING DOCUMENT EXAM ITEM DESCRIPTION EXAM NUMBER OF ELEMENTS/SEGMENTS NUMBER TO DEFERRAL NUMBER NUMBER NUMBER TO ISI DRAWING CAT. NO. METHOD IN ITEM NUMBER BE OF TO BE TO BE BE EXAMINED NUMBER EXAMINED INSPECTION EXAMINED EXAMINED IN THE THIRD DURING TO END OF IN THE IN THE PERIOD INTERVAL INTERVAL FIRST SECOND PERIOD PERIOD R-A R1.17 Elements Subject to Visual, VT-3 There are no elements/segments subject N/A N/A N/A N/A N/A Microbiologically internal to Microbiologically Influenced Corrosion Influenced Corrosion surfaces or (MIC)

(MIC) volumetric see note 1 R-A R1.18 Elements Subject to UT SEGMENTS As scheduled N/A As As As scheduled in see TVA Flow Accelerated thickness in the FAC scheduled in scheduled in the FAC Calculation Corrosion (FAC) see note: 4 8D0 D02 D07program the FAC the FAC program SON-MEB MD Corrsio BDA12 see note: 4 program program N0999-000085 see note 1 BD-020, BD-021, BD-024 NOTES

1) An alternative Risk-informed Inservice Inspection Program is being implemented for the third interval for categories B-F, B-J, C-F-1 and C-F-2. (see request for relief 2-RI-ISI-1)

2) VT-2 examinations to be performed on the segments as allowed by request for relief 2-RI-ISI-2

3) These VT-2 examinations are performed under the pressure test program REFER TO procedures O-SI-SXI-000-200.0.

4) These examinations are performed under the FAC program procedure SPP-9.7.

5) A VT-2 examination of only the socket welds and associated branch connection welds is required for segments CS-01 2, RH-003 SI-059 and SI-078.

SQN ASME CLASS 1 AND 2 VALVES O-SI-DXI-000-114.3 ATT'S Unit 1 & 2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006 Page 1 of 11 ATTACHMENT 6 - ASME Class I and 2 Valves (Unit I and Unit 2)

SQN ASME CLASS I AND 2 VALVES O-SI-DXI-000-114.3 ATT6 Unit I & 2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006 Page 2 of 11 UNIT SYSTEM CLASS VALVE ISI DRAWING MIS DRAWING SIZE TYPE GROUP VALVE VALVE VALVE INTEGRAL UNIT I UNIT 2 BOLTING BOLTING BODY ATTACHMENT 1& 2

<= 2" > 2" WELDS CVC 62-560 CHM-2338-C SHI MSG-0008-C SH1 2 CKV N/A NONE NONE NONE NONE 1& 2 CVC 62-561 CHM-2338-C SH2 MSG-0008-C SH2 2 CKV N/A NONE NONE NONE NONE 1& 2 CVC 1 62-562 CHM-2338-C SH4 MSG-0008-C SH5 2 CKV N/A NONE NONE NONE NONE 1& 2 CVC 62-563 CHM-2338-C SH3 MSG-0008-C SH3 2 CKV N/A NONE NONE NONE NONE 1& 2 CVC 1 62-564 CHM-2338-C SHI MSG-0008-C SH1 2 GATE N/A NONE NONE NONE NONE 1& 2 CVC 1 62-565 CHM-2338-C SH2 MSG-0008-C SH2 2 GATE N/A NONE NONE NONE NONE 1&2 CVC 1 62-566 CHM-2338-C SH4 MSG-0008-C SH5 2 GATE N/A NONE NONE NONE NONE 1& 2 CVC 1 62-567 CHM-2338-C SH3 MSG-0008-C SH3 2 GATE N/A NONE NONE NONE NONE 1& 2 CVC 1 62-576 CHM-2338-C SHl MSG-0008-C SH1 2 CKV N/A NONE NONE NONE NONE 1& 2 CVC 1 62-577 CHM-2338-C SH2 MSG-0008-C SH2 2 CKV N/A NONE NONE NONE NONE I &2 CVC 1 62-578 CHM-2338-C SH3 MSG-0008-C SH4 2 CKV N/A NONE NONE NONE NONE 1& 2 CVC 1 62-579 CHM-2338-C SH4 MSG-0008-C SH5 2 CKV N/A NONE NONE NONE NONE 1& 2 CVC 1 62-659 CHM-2335-C SHI ISI-0009-C SH2 3 CKV N/A YES NONE NONE NONE see note 1 1& 2 CVC 1 62-660 CHM-2335-C SHl ISI-0009-C SH2 3 CKV N/A YES NONE NONE NONE see note 1 1& 2 CVC 1 62-661 CHM-2335-C SH1 ISI-0009-C SH2 2 CKV N/A NONE NONE NONE NONE 1&2 CVC 1 62-716 CHM-2335-C SH1 ISI-0009-C SH2 3 CKV N/A YES NONE NONE NONE see note 1 1& 2 CVC 1 62-717 CHM-2335-C SHI ISI-0009-C SH2 3 CKV N/A YES -NONE NONE NONE see note 1 1& 2 CVC 1 68-580 CHM-2335-C SH2 ISI-0009-C SHI 3 GATE N/A NONE NONE NONE NONE 1& 2 CVC 1 FCV-62-69 CHM-2335-C SH2 ISI-0009-C SH1 3 GATE N/A YES NONE NONE NONE see note 1 1&2 CVC 1 FCV-62-70 CHM-2335-C SH2 ISI-0009-C SH1 3 GATE N/A YES NONE NONE NONE

__ _~

_ _ _ _ _ __ _ _ _ _I_ _ _ _ _ _ _ _ , ... _ _ _ .__

_ _ _ _ _ 4__ _ _ _ _ I ___ _ ____ _

SQN ASME CLASS 1 AND 2 VALVES O-SI-DXI-000-114.3 ATT6 Unit 1 & 2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006 Page 3 of 11 UNIT SYSTEM CLASS VALVE ISI DRAWING ISI DRAWING SIZE TYPE GROUP VALVE VALVE VALVE INTEGRAL UNIT I UNIT 2 BOLTING

_ _ . BOLTING BODY ATTACHMENT 1& 2 CVC

. _ < 2" >2" WELDS 1 FCV-62-84. CHM-2335-C SH2 ISI-0009-C SH2 2 GATE N/A YES NONE NONE NONE see note 1 1&2 RCS 1 68-549 ISI-0369-C SH1 ISI-0013-C SH2 2 GATE N/A NONE NONE NONE 1& 2 RCS 1 NONE 68-550 ISI-0369-C SHl ISI-001 3-C SH2 2 GATE N/A NONE NONE NONE NONE 1& 2 RCS 1 68-553 ISI-0369-C SHI ISI-0013-C SH2 2 GATE N/A NONE NONE NONE NONE 1& 2 RCS 1 68-554 ISI-0369-C SHI ISI-0013-C SH2 2 GATE N/A NONE NONE NONE NONE 1& 2 RCS 1 68-557 ISI-0369-C SHI ISI-001 3-C SH4 2 GATE N/A NONE NONE NONE NONE 1& 2 RCS 1 68-558 ISI-0369-C SH3 ISI-0013-C SH4 2 GATE N/A NONE NONE NONE 1& 2 RCS NONE 1 68-563 ISI-0369-C SH3 ISI-0013-C SH3 6 RELIEF 4 YES NONE NONE NONE 1&2 RCS 1 68-564 ISI-0369-C SH3 ISI-0013-C SH3 6 RELIEF 4 YES NONE NONE NONE 1& 2 RCS 1 68-565 ISI-0369-C SH3 ISI-0013-C SH3 6 RELIEF 4 YES NONE NONE NONE 1&2 RCS 1 68-581 ISI-0369-C SHI ISI-0013-C SH4 2 GATE N/A NONE NONE NONE 1 &2 RCS 1 68-582 NONE IS1-0369-C SHI ISI-001 3-C SH4 2 GATE N/A NONE 1& 2 NONE NONE NONE RCS 1 FCV-68-332 131-0369-C SH3 ISI-0013-C SH3 3 GATE N/A YES NONE NONE NONE see note I 1& 2 RCS 1 FCV-68-333 ISI-0369-C SH3 ISi-0013-C SH3 3 GATE N/A YES NONE NONE NONE see note 1 1& 2 RCS 1 PCV-68-334 ISI-0369-C SH3 ISI-001 3-C SH3 3 GLOBE - NA NONE -NONE NONE NONE 1&2 RCS 1 PCV-68-340A ISI-0369-C SH3 ISI-001 3-C SH3 3 GLOBE N/A NONE NONE NONE NONE 1& 2 RCS 1 PCV-68-340B ISI-0369-C SH2 ISI-0013-C SHI 4 BALL N/A YES NONE NONE NONE see note 1 1&2 RCS 1 PCV-68-340D ISI-0369-C SH2 ISI-0013-C SH1 4 BALL N/A YES NONE NONE NONE see note 1 1& 2 RHR 1 63-643 CHM-2336-C SH6 ISI-0003-C SH6 8 CKV 5 YES NONE NONE NONE 1 &2 RHR 1 63-640 CHM-2336-C SH6 ISI-0003-C SH5 8 CKV 5 YES NONE NONE NONE 1& 2 RHR 1 63-641 CHM-2336-C SH6 ISI-0003-C SH5 6 CKV 6 YES NONE NONE NONE 1& 2 RHR 1 63-543 CHM-2336-C SH6 ISI-0003-C SH8 2 CKV N/A NONE NONE NONE NONE 1 &2 RHR I CHM-213-C.SHR ISI-0003-C4 S2NEOE 1&2 RHR 1 63-644 j CHM-2336-C SH6 ISI-0003-C SH 6 CKV 6 YES NONE NON NONE 1& 2 RHR 1 FCV-74-1 CHM-2336-C SH1 ISI-0003-C SH7 14 GATE 1 YES l NONE NONEl NONE

SQN ASME CLASS 1 AND 2 VALVES 0-SI-DXI-000-114.3 ATT6 Unit I & 2 (UNIT 1 AND UNIT 2) Effective Date:. 06-01-2006 Page 4 of 11 UNIT SYSTEM CLASS VALVE ISI DRAWING ISI DRAWING SIZE TYPE GROUP VALVE VALVE VALVE INTEGRAL UNIT I UNIT 2 BOLTING BOLTING BODY ATTACHMENT

. . 2" > 2" WELDS 1& 2 RHR 1 FCV-74-2 CHM-2336-C SHI ISi-0003-C SH7 14 GATE 1 YES NONE' NONE NONE 1& 2 SIS 1 63-547 CHM-2333-C SH7 ISI-0002-C SH12 2 CKV N/A NONE NONE NONE NONE 1& 2 SIS 1 63-549 CHM-2333-C SH7 ISI-0002-C SH12 2 CKV N/A NONE NONE NONE NONE 1&2 SIS 1 63-551 CHM-2333-C SH9 151-0002-C SH5 2 CKV NIA NONE NONE 1& 2 SIS 1 NONE . NONE 63-553 CHM-2333-C SH10 ISI-0002-C SH6 2 CKV N/A NONE NONE NONE NONE 1&2 S1S 1 63-555 CHM-2333-C SH10 ISI-0002-C SH6 2 CKV N/A NONE NONE 1& 2 NONE NONE SIS 1 63-557 CHM-2333-C SH9 ISI-0002-C SH4 2 CKV N/A NONE NONE NONE NONE 1& 2 SIS 1 63-558 CHM-2333-C SH7 ISI-0002-C SH7 6 CKV 3 YES NONE NONE NONE 1& 2 SIS 1 63-559 CHM-2333-C SH7 ISI-0002-C SH7 6 CKV 3 _YES NONE NONE 1& 2 SIS 1 NONE 63-560 CHM-2333-C SH9 ISI-0002-C SH5 10 CKV 2 YES NONE NONE NONE 1& 2 SIS 1 63-561 CHM-2333-C SH9O ISI-0002-C SH6 10. CKV 2 YES NONE NONE 1& 2 SIS 1 NONE 63-562 CHM-2333-C SH1O ISI-0002-C SH6 10 CKV 2 YES NONE NONE NONE 1& 2 SIS 1 63-563 CHM-2333-C SH9 ISI-0002-C SH4 10 CKV 2 YES NONE NONE 1& 2 SIS 1 NONE 63-581 CHM-2333-C SH _ISI-0002-C SH7 3 CKV N/A YES NONE NONE NONE see note 1 1& 2 SIS 1 63-582 CHM-2333-C SH1 ISI-0002-C SH8 11/2 GATE N/A NONE NONE NONE NONE 1&2 SIS . 1 63-583 HM-2333-C SH2 ISI-0002-C SH9 1 1/2 GATE N/A NONE NONE NONE 1 &2 NONE SIS 1 63-584 CHM-2333-C SH2 ISI-0002-C SH10 1 1/2 GATE N/A NONE NONE NONE NONE 1& 2 SIS 1 63-585 CHM-2333-C SH2 ISI-0002-C SH 1 1 1/2 GATE N/A NONE NONE NONE NONE 1&2 SIS 1 63-586 CHM-2333-C SH2 151-0002-C SH8 1 1/2 GKV N/A NONE NONE NONE NONE 1&.2 SIS 1 63-587 CHM-2333-C SH2 1SI-0002-C 519 11/2 KV N/A NONE NONE NONE 1& 2 SIS NONE 1 63-588 CHM-2333-C SH2 ISI-0002-C SH10 11/2 GKV N/A NONE NONE NONE NONE 1& 2 SIS 1 63-589 CHM-2333-C SH1 ISI-0002-C SH8l 11/2 CKV N/A NONE NONE NONE NONE 1& 2 SiS I 63-622 CHM-2333-C SH9 ISI-0002-C SH5 10 CKV 2 YES NONE NONE NONE 1& 2 SIS 1 63-623 CHM-2333-C SH10 ISI-0002-C SH6 10 CKV 2 YES NONE NONE NONE 1& 2 SIS 1 63-624 CHM-2333-C SHIO ISI-0002-C SH6 10 CKV 2 YES NONE NONE NONE 1&2 SIS 1 63-625 CHM-2333-C0H9 151-0002-C SH4 10 CKV 2 YES NONE NONE NONE 1& 2 SIS 1 63-632 CHM-2333-C SH10 ISI-0002-C SH6 6 CKV 3 YES NONE NONE NONE 1& 2 SIS 1 63-633 CHM-2333-C SH9 151-0002-C SH5 6 CKV 3 YES NONE NONE NONE 1& 2 SIS 1 63-634 CHM-2333-C SH10 ISI-0002-C SH6 6 CKV 3 YES NONE NONE NONE 1 S 1 63-33 CHM-23C SHu ISI- 002)C SHA 6 CV 3/-I YES I -- I 1&2 CS 2 72-503 CHM-2422-C SH3 ISI-0007-C SH4 8 I GATE lN/A N/A l NONE 1&2 CS 2 l NONE NONE 72-504 CHM-2422-C SH4 ISI-0007-C SH4 j8 j-GATE lN/A l N/A lNONE lNONE l NONE j

SQN ASME CLASS I AND 2 VALVES O-SI-DXI-000-114.3 ATT6 Unit I & 2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006

. . Page 5 of 11 UNIT SYSTEM CLASS VALVE ISI DRAWING ISI DRAWING SIZE TYPE GROUP VALVE VALVE VALVE INTEGRAL UNIT I UNIT 2 BOLTING BOLTING BODY ATTACHMENT

_ _ _ <= 2" > 2" WELDS 1& 2 Cs 2 72-506 CHM-2422-C SH1 ISI-0007-C SHI1 12 CKV N/A N/A NONE NONE NONE 1&2 CS 2 72-507 CHM-2422-C SH2 ISI-0007-C SH2 12 CKV N/A N/A NONE NONE NONE 1S 2 CS 2 72-528 CHM-2422-C SH3 ISI-0007-C SH3 12 CKV N/A N/A NONE NONE NONE 1&2 CS 2 72-529. CHM-2422-C SH5 ISI-0007-C SH5 12 CKV N/A N/A NONE NONE NONE

& _2 Cs 2 72-533 CHM-2422-C SH3 ISI-0007-C SH3 12 GATE N/A N/A NONE NONE NONE 1& 2 CS 2 72-534 CHM-2422-C SH5 ISI-0007-C SH3 12 GATE N/A N/A NONE NONE NONE 1& 2 CS 2 FCV-72-2 CHM-2422-CSSH4 ISI-0007-C SH4 12 GATE N/A N/A NONE NONE NONE 1&2 CS 2 FCV-72-21 CHM-2422-C SH2 ISI-0007-C SH2 12 GATE N/A N/A NONE NONE NONE 1&2 CS 2 FCV-72-22 CHM-2422-C SHI ISI-0007-C SH2 12 GATE N/A N/A NONE NONE NONE 1&2 CS 2 FCV-72-39 CHM-2422-CSH4 ISI-0007-C SH4 12 GATE N/A N/A NONE NONE NONE 1& 2 CS 2 FCV-72-20 CHM-2422-C SH4 ISI-0007-C SH2 12 GATE N/A N/A NONE NONE NONE 1& 2 CS 2 FCV-72-23 CHM-2422-C SHI 151-0007-C SH2 12 GATE N/A N/A NONE NONE NONE 1&2 CS/HPSI 2 62-938 ISI-0430-C SH36 ISI-0431-C SH36 2 DIAPHRAM N/A N/A NONE NONE NONE 1& 2 CS/HPSI 2 72-501 ISI-0430-C SH36 ISI-0431-C SH36 2 GLOBE N/A N/A NONE NONE NONE 1&2 CVC/HPSI 2 62.500 iSI-0430-C SH15 ISI-0431-C SH15 4 GATE N/A NIA NONE NONE NONE 1& 2 CVC/HPSI 2 62-508 ISI-0430-C SH14 ISI-0431-C SH14 4 BONNET N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-519 ISI-0430-C SH32 ISI-0431-C SH32 3 CKV N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-520 ISI-0430-C SH32 ISI-0431-C SH32 3 GLOBE N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-523 ISI-0430-C SH18 ISI-0431 -C SH188 2 CKV N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-524 ISI-0430-C SH18 ISI-0431-C SH18 2 CKV N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-525 ISI-0430-C SH17 ISI-0431-C SH17 4 CKV NIA N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-526 _Sl-0430-C SH17 ISI-0431-C SH17 3 GLOBE N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-527 ISI-0430-C SH17 ISI-0431-C SH17 4 GATE N/A N/A NONE NONE NONE 1&2 CVC/HPSI 2 62-530 ISI-0430-C SH18 ISI-0431 -C SH18 2 CKV N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-531 131-0430-C SH18 11-0431-C SH18 2 CKV N/A N/A NONE NONE NONE 1&.2 CVC/HPSI 2 62-532 ISI-0430-C ISI-0431-C SH17 4 0KV .H7 N/A N/A NONE NONE NONE 1 &2 CVC/HPSI 2 62-533 ISI-0430-C SH17 ISI-0431-C SH17 4 GATE N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-534 131-0430-C SH17 ISI-0431-C SH17 3 GLOBE N/A N/A NONE NONE NONE 1 &2 CVC/HPSI 2 62-535 ISI-0430-C SH17 ISI-0431-C SH17 3 GATE N/A N/A NONE NONE NONE 1 &2 CVC/HPSI 2 62-536 ISI-0430-C SH32 ISI-0431-C SH32 3 GATE N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-537 ISI-0430-C SH33 ISI-0431-C SH33 3 GATE N/A N/A NONE NONE NONE

&2 CVC/HPSI 2 62-538 ISI-0430-C SH33 ISi-0431-C SH33 3 GLOBE N/A N/A 1& 2 CVC/HPSI NONE NONE NONE-2 1 62-538 1ISI-0430-C SH33 I ISI-0431-C SH33 3 I GLOBE N/A j N/ NONE NONE NONE 1 & CVC/HPSI 2 j 2 J 62-539 l ISI-0430-C SH33 IS15-0431 -C SH33 3 GATE l N/A J N/A I NONE lNONE l__NONE___

SQN ASME CLASS 1 AND 2 VALVES 0-SI-DXI-000-114.3 ATT6 Unit I & 2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006 Page 6 of 11 UNIT SYSTEM CLASS VALVE ISI DRAWING ISI DRAWING SIZE TYPE GROUP VALVE VALVE VALVE INTEGRAL UNIT I UNIT 2 BOLTING BOLTING BODY ATTACHMENT 1& 2 CVC/HPSI

. <= 2' >22" WELDS 2 62-546 ISI-0430-C SH29 ISI-0431-C SH29 3 GLOBE N/A N/A NONE NONE NONE 1&2 CVC/HPSI 2 62-547 ISI-0430-C SH30 ISI-0431-C SH30 2 GATE N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-548 ISI-0430-C SH30 ISI-0431-C SH30 2 GATE N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-549 ISI-0430-C SH30 ISI-0431-C SH30 2 GATE N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-550 ISI-0430-C SH30 ISI-0431-C SH30 2 GATE N/A N/A NONE NONE NONE 1&2 CVC/HPSI 2 62-642 ISI-0430-C SH24 ISI-0431-C SH24 4 BONNET N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-643 ISI-0430-C SH25 ISI-0431-C SH25 4 BONNET N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-644 ISI-0430-C SH25 ISI-0431-C SH25 4 BONNET N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-647 ISI-0430-C SH25 ISI-0431-C SH25 4 BONNET N/A N/A NONE NONE . NONE 1& 2 CVC/HPSI 2 62-648 ISI-0430-C SH25 ISI-0431-C SH25 4 BONNET N/A N/A NONE, . NONE NONE 1& 2 CVC/HPSI 2 62-649 ISI-0430-C SH25 ISI-0431-C SH25 2 . RELIEF N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-650 ISI-0430-C SH25 ISI-0431-C SH25 4 BONNET. N/A N/A NONE NONE NONE 1& 2 CVC/HPSI . 2 62-652 ISI-0430-C SH25 ISI-0431-C SH25 4 BONNET N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-653 ISI-0430-C SH26 ISI-0431-C SH26. 4 BONNET N/A . N/A . NONE NONE NONE 1& 2 CVC/HPSI 2 62-697 ISI-0430-C SH26 ISI-0431-C SH26 4 CKV N/A N/A NONE NONE NONE 1 &2 CVC/HPSI 2 62-752 ISI-0430-C SH14 ISI-0431-C SH14 2 CKV N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-753 ISI-0430-C SH14 ISI-0431-C SH14 4 DIAPHRAM N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-755 ISI-0430-C SH15 ISI-0431-C SH15 4 DIAPHRAM N/A N/A NONE NONE NONE 1 &2 CVCIHPSI 2 62-930 ISI-0430-C SH15 ISI-0431-C SH15 3 CKV N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 62-931 ISI-0430-C SH15 ISI-0431-C SH15 2 CKV N/A N/A NONE NONE NONE 1 &2 CVC/HPSI 2 FCV-62-61 ISI-0430-C SH24 ISI-0431-C SH24 4 GATE N/A N/A NONE NONE NONE 1&2 CVC.HPSI 2 FCV-62-63 ISI-0430-C SH24 ISI-0431-C SH24 4 GATE N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 FCV-62-89 ISI-0430-C SH33 ISI-0431-C SH33 3 GLOBE N/A N/A NONE NONE NONE 1&2 CVC/HPSI 2 FCV-62-90 ISI-0430-C SH34 ISI-0431-C SH34 3 GATE N/A N/A NONE .NONE NONE 1& 2 CVC/HPSI 2 FCV-62-91 ISI-0430-C SH34 ISI-0431-C SH34 3 GATE N/A N/A NONE NONE NONE 1 &2 CVC/HPSI 2 FCV-62-93 ISI-0430-C SH17 ISI-0431-C SH17 3 GLOBE N/A N/A NONE NONE NONE 1 &2 CVC/HPSI 2 FCV-62-98 ISI-0430-C SHIS ISI-0431-C SHIS 2 GLOBE N/A N/A NONE NONE NONE 1& 2 CVC/HPSI 2 FCV-62-99 ISI-0430-C SHIl ISI-0431-C SH18 2 GLOBE N/A N/A NONE NONE NONE 1&2 CVC/HPSI 2 LCV-62-132 ISI-0430-C SH26 ISI-0431-C SH26 4 GATE N/A N/A NONE NONE NONE 1&2 CVC/HPSI 2 LCV-62-133 ISI-0430-C SH26 ISI-0431-C SH26 4 GATE N/A N/A NONE NONE NONE 1& 2 FW 2 3-508 CHM-2339-C SH2 CHM-2403-C SH2 16 CKV N/A N/A NONE NONE NONE 1&2 1_21&2 l Ii FW FW FW

__&_2__l_FW 122

__l 2

_2___

3-509 3-S09 3-510___ l_

CHM-2339-C SH2 CHM-233Y-C SH-2 CHM-2339-C____ SH1__

jCHM-2403-C SH2 j16 l__

CHM-2403-C SH2 CHM-2403-C____SH1__l_16__l_CKV 16 CKV

- CKV

_

JN/A N/A l__N/A__l_

j N/A N/A jNU)NtNONE N/A__l__NONE__l__NONE NONE NONE NUNt

_l_NONE_

NONE NU_____t NONE

SQN ASME CLASS I AND 2 VALVES 0-SI-DXI-000-114.3 ATT6 Unit 1 & 2 (UNIT AND UNIT 2) Effective Date: 06-01-2006 Page 7 of 11 UNIT SYSTEM CLASS VALVE ISI DRAWING ISI DRAWING SIZE TYPE GROUP VALVE VALVE VALVE INTEGRAL UNIT 1 UNIT 2 BOLTING

. BOLTING BODY ATTACHMENT

.< 2" > 2" WELDS 1&2 2 .W 3-511 CHM-2339-C SHI CHM-2403-C SHI 16 CKV N/A N/A NONE NONE NONE 1& 2 FW 2 FCV-3-100 CHM-2339-C SHl CHM-2403-C SH1 18 GATE N/A N/A NONE NONE NONE 1&2 FW 2 FCV-3-33 CHM-2339-C SHI CHM-2403-C SH1 18 GATE N/A N/A NONE NONE NONE I &2 FW 2 FCV-3-47 CHM-2339-C SH2 CHM-2403-C SH2 18 GATE N/A N/A NONE NONE. NONE 1&2 FW 2 FCV-3-87 CHM-2339-C SH2 CHM-2403-C SH2 18 GATE NIA N/A NONE NONE NONE 1 &2 Ms 2 1-623 CHM-2340-C SHI ISI-0015-C SH2 321 GKV N/A N/A NONE NONE NONE I &2 MS 2 1-624 CHM-2340-C SH2 ISI-0015-C SH2 32 CKV N/A N/A NONE NONE NONE 1& 2 MS 2 1-625 CHM-2340-C SH2 ISI-Ol5-C SH2 32 CKV N/A N/A NONE NONE NONE 1& 2 MS 2 1-626 CHM-2340-C SH2 ISI-0015-C SH2 32 CKV N/A N/A NONE NONE NONE 1 &2 MS 2 1-512 CHM-2340-C SH2 ISI-0015-C SH2 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-513 CHM-2340-C SH2 ISI-0015-C SH2 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-514 CHM-2340-C SH2 ISI-0015-C SH2 6 SAF N/A N/A NONE NONE NONE 1 &2 MS 2 1-515 CHM-2340-C SH2 ISI-0015-C SH2 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-516 CHM-2340-C SH2 ISI-0015-C SH2 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-517 CHM-2340-C SH2 ISI-0015-C SH2 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-518 CHM-2340-C SH2 ISI-0015-C SH2 6 SAF N/A. N/A NONE NONE NONE 1& 2 MS 2 1-519 CHM-2340-C SH2 ISI-001 5-C SH2 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-520 CHM-2340-C SH2 ISI-0015-C SH2 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-521 CHM-2340-C SH2 ISI-0015-C SH2 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-522 CHM-2340-C SHI ISI-0015-C SHI 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-523 CHM-2340-C SHI ISI-0015-C SH1 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-524 CHM-2340-C SH1 ISI-0015-C SH1 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-525 CHM-2340-C SHI ISI.0015-C SHI 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-526 CHM-2340-C SH1 ISI-0015-C SH1 6 SAF N/A N/A NONE NONE NONE 1&2 MS 2 1-527 CHM-2340-C SH1 ISI-0015-C SH1 6 SAF N/A N/A NONE NONE NONE 1&2 Ms 2 1-528 CHM-2340-C SHI ISI-0015-C SHI 6 SAP N/A N/A NONE NONE NONE 1& 2 MS 2 1-529 CHM-2340-C SH1 ISI-0015-C SHI 6 SAF N/A N/A NONE NONE NONE 1&2 MS 2 1-530 CHM-2340-C SHI ISI-0015-C SH1 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-531 CHM-2340-C SHI ISI-0015-C SHI 6 SAF N/A N/A NONE NONE NONE 1& 2 MS 2 1-619 CHM-2340-C SH1 ISI-0015-C SH1 6 GATE N/A N/A NONE NONE NONE 1&2 MS 2 1-620 CHM-2340-C SH2 ISI-0015-C SH2 6 GATE N/A N/A NONE NONE NONE 1&2 MS 2 1-621 CHM-2340-C SH2 ISI-005b-C S12 6 GATE N/A N/A NUNONE NUNE NONE 1&2 MS 2 1-622 CHM-2340-C SH2 ISI-0015-C SH2 6 GATE N/A N/A NONE N NONE

SQN ASME CLASS I AND 2 VALVES 0-SI-DXI-000-1 14.3 ATT6 Unit I & 2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006 j Page 8of 11 UNIT SYSTEM CLASS VALVE [SI DRAWING ISI DRAWING SIZE TYPE GROUP VALVE VALVE VALVE. INTEGRAL UNIT I UNIT 2 BOLTING BOLTING

. BODY ATTACHMENT

. <= 2V > 2' WELDS 1& 2 MS 2 FCV-1-11 CHM-2340-C SH2 ISI-001 5-C SH2 32 GATE . N/A N/A NONE NONE NONE 1& 2 MS 2 FCV-1-22 CHM-2340-C SH2 ISI-0015-C SH2 32 GATE. N/A N/A NONE. NONE NONE 1&2 MS 2 FCV-1-29 CHM-2340-C SH1 ISI-0015-C SHI 32 GATE N/A N/A NONE NONE NONE 1& 2 MS 2 FCV-1 -4 CHM-2340-C SH1 ISI-0015-C SH1 32 GATE . N/A N/A NONE NONE NONE 1_&2 MS 2 PCV-1-12 CHM-2340-C SH2 ISI-0015-C SH2 6 GATE N/A N/A NONE NONE NONE 1& 2 MS 2 PCV-1-23 CHM-2340-C SH2 ISI-0015-C SH2 6 GATE . N/A. N/A NONE NONE NONE 1_&2 MS

_ 2 PCV-1-30 CHM-2340-C SHI ISI-0015-C SHI 6 GATE N/A . N/A NONE NONE NONE 1&2 MS 2 . PCV-1-5 CHM-2340-C SH1 ISI-0015-C SH1 6 GATE N/A N/A NONE. NONE NONE 1& 2 RHR 2 74-514 CHM-2336-C SH3 ISI-0003-C SH2 8 CKV N/A N/A NONE NONE NONE 1 &2 RHR . 2 .74-515 CHM-2336-C SH3 ISI-0003-C SH3 8 CKV N/A N/A . NONE NONE NONE 18 2 RHR 2 74-520 CHM-2336-C SH3 ISI-0003-C SH2 8 GATE N/A N/A . NONE NONE NONE 1& 2 RHR 2 74-521 CHM-2336-C SH3 ISI-0003-C SH3 8 GATE N/A NIA NONE NONE NONE 1S2 RHR 2 74-524 CHM-2336-C SH3 ISI-0003-C SH2 8 GATE N/A N/A NONE NONE NONE 1& 2 RHR 2.74-525 CHM-2336-C SH3 ISI-0003-C SH3 8 GATE N/A N/A NONE NONE NONE 1°2 RHR 2 FCV-63-172 CHM-2336-C SH4 ISI-0003-C SH5 12 GATE . N/A N/A NONE NONE NONE 1 &2 RHR 2 FCV-63-72 CHM-2336-C SH2 ISI-0003-C SH1 18 GATE N/A N/A NONE NONE NONE 1& 2 RHR 2 FCV-63-73 CHM-2336-C SH2 ISI-0003-C SHI 18 GATE N/A N/A _ NONE NONE NONE 1 &2 RHR 2 FCV-74-16 CHM-2336-C SH3 ISI-0003-C SH2 8 BUTF N/A N/A NONE NONE NONE 1 &2 RHR 2 FCV-74-21 CHM-2336-C SH5 ISI-0003-C SH4 14 GATE NMA N/A NONE NONE NONE 1& 2 RHR 2 FCV-74-28 CHM-2336-C SH3 ISI-0003-C SH3 8 BUTF N/A N/A NONE NONE NONE 1 &2 RHR 2 FCV-74-3 CHM-2336-C SH5 ISI-0003-C SH4 14 GATE N/A N/A NONE NONE NONE 1& 2 RHR 2 FCV-74-32 CHM-2336-C SH3 ISI-0003-C SH2 8 BUTF N/A N/A NONE NONE NONE 18_2 RHR 2 FCV-74-33 CHM-2336-C SH3 ISI-0003-C H2 8 GATE N/A N/A NONE NONE 1 &2 RHR NONE 2 FCV-74-35 CHM-2336-C SH3 ISI-0003-C SH3 8 GATE N/A N/A NONE NONE NONE 18 2 RHR 2 HCV-74-34 CHM-2336-C SH3 ISI-0003-C SH3 8 GATE N/A N/A NONE NONE NONE 1 &2 RHR 2 HCV-74-36 CHM-2336-C SH3 ISI-0003-C SH2 8 GATE N/A N/A NONE NONE NONE 1 &2 RHR 2 HCV-74-37 CHM-2336-C SH3 ISI-0003-C SH3 8 GATE N/A N/A NONE NONE NONE 1& 2 RHR/HPSI 2 74-530 ISI-0430-C SH35 ISI-0431-C SH35 2 GATE N/A N/A NONE NONE NONE 1& 2 RHR/HPSI 2 74-531 ISI-0430-C SH35 ISI-0431-C SH35 2 GATE N/A N/A. NONE NONE NONE 1&2 RHR/HPSI 2 FCV-74-12 ISI-0430-C SH35 151-0431-C SH35 2 GLOBE N/A N/A NONE NONE NONE 1& 2 RHR/HPSI 2 FCV-74-24 ISI-0430-C SH35 ISI-0431-C SH35 2 GLOBE N/A N/A NONE NONE NONE 1&2 SIS _ 2 5 3-bU2 CLM-2333-C SHi iSi-0002-C SHi 12 J CKV N/A NlA NONE NONE NONE 18 2 SIS -2 FCV-63-1 I CHM-2333-C SH6 ISI-0002-C SH1 12 GATE N/A . N/A NONE NONE NONE

SQN ASME CLASS 1 AND 2 VALVES 0-SI-DXI-000-114.3 ATT6 Unit 1 &2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006 Page 9 of 11 UNIT SYSTEM CLASS VALVE [SI DRAWING ISI DRAWING SIZE TYPE GROUP VALVE VALVE VALVE INTEGRAL UNIT I UNIT 2 BOLTING BOLTING

. .

BODY ATTACHMENT

. <= 2" > 2" WELDS 1& 2 SIS 2 FCV-63-11 CHM-2333-C SH6 ISI-0002-C SH3 8 GATE N/A N/A NONE NONE . NONE 1 &2 SIS 2 FCV-63-118 EXEMPT EXEMPT 10 GATE N/A N/A NONE NONE NONE 1&2 SIS 2 FCV-63-67 EXEMPT EXEMPT 10 GATE N/A N/A NONE NONE NONE 1i&2 515 2 FCV-63-8 CHM-2333-C SH6 ISI-0002-C SH3 8 GATE N/A N/A NONE NONE. NONE 1&2 SIS 2 FCV-63-80 EXEMPT EXEMPT 10 GATE N/A N/A NONE NONE NONE 1&2 SIS 2 FCV-63-93 CHM-2333-C SH3 ISI-0002-C SH. 8 GATE N/A N/A NONE NONE NONE 1&2 SIS 2 FCV-63-94 CHM-2333-C SH3 ISI-0002-C SH2 8 GATE N/A N/A NONE NONE NONE 1& 2 SIS 2 FCV-63-98 EXEMPT EXEMPT 10 GATE N/A N/A NONE NONE NONE 1&2 SIS 2 FCV-72-40 CHM-2333-C SH6 ISI-0002-C SH3 8 GATE N/A N/A NONE NONE NONE 1& 2 - SIS 2 FCV-72-41 CHM-2333-C SH6 ISI-0002-C SH3 8 GATE N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 63-524 ISI-0430-C H2 ISI-0431E-C SH2 4 GATE N/A N/A NONE NONE NONE 1& 2 SIS/HpsI 2 63-525 ISI-0430-C SH2 ISI-0431-C SH2 4 GATE N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 FC63-526 ISI-0430-C SH3 ISI-0431-C SH3 4 CKV N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 63-527 ISI-0430-C SH3 ISI-0431-C SH3 4 GATE N/A N/A NONE NONE NONE 1& 2 SIS/HPSI 2 63-531 ISI-0430-C SH23 ISI-0431-C SH22 4 BONNET N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 63-542 ISI-0430-C SH19 ISI-0431-C SH19 GATE N/A N/A NONE NONE NONE 1& 2 SIS/HPSI 2 63-544 ISI-0430-C SH7 ISI-0431-C SH7 2 GATE N/A N/A NONE NONE NONE 1& 2 SIS/HPSI 2 63-546 ISI-0430-C SH22 ISI-0431-C SH22 2 GATE N/A N/A NONE NONE NONE 1& 2 SIS/HPSI 2 63-548 ISI-0430-C SH5 ISI-0431-C SH5 2 GATE N/A N/A NONE NONE NONE 1& 2 SIS/HPSI 2 63-550 ISI-0430-C SH11 ISI-0431-C SHI7 2 GATE N/A N/A NONE NONE NONE 1& 2 SIS/HPSI 2 63-552 ISI-0430-C SH9 ISI-0431-C SH9 2 GATE N/A N/A NONE NONE NONE 1&.2 SIS/HPSI 2 63-554 IS-0430-C SH8 ISI-0431-C SH8 2 GATE N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 63-556 ISI-0430-C SHI ISI-0431-C SHI 2 GATE N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 72-500 ISI-0430-C SH12 ISI-0431-C SH12 3 GATE N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 FCV-63-152 ISI-0430-C SH2 ISI-0431-C SH2 4 GATE N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 FCV-63-153 ISI-0430-C SH2 ISI-0431-C SH2 4 GATE N/A N/A NONE NONE NONE 1& 2 SIS/HPSI 2 FCV-63-156 ISI-0430-C SH2 ISI-0431-C SH2 4 GATE N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 FCV-63-157 ISI-0430-C SH3 ISI-0431-C SH3 4 GATE N/A N/A NONE NONE NONE 1 &2 SIS/HPSI 2 FCV-63-175 ISI-0430-C SH27 ISI-0431-C SH27 2 GLOBE N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 FCV-63-22 ISI-0430-C SH2 ISI-0431-C SH2 4 GATE N/A N/A NONE NONE NONE 1 &2 SIS/HPSI 2 FCV-63-25 ISI-0430-C SH16 ISI-0431-C SH16 4 GATE N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 FCV-63-26 ISI-0430-C SH27 ISI-0431-C SH16 4 GATE N/A N/A NONE NONE NONE 1&2 SIS/HPSI 2 FCV-63-26 ISI-0430-C SH27 ISI-0431-C SH27 2 GLOAE' N/A N/A NONE NONE NONE

SQN - ASME CLASS I AND 2 VALVES 0-SI-DXI-000-114.3 ATT6 Unit 1 & 2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006 Page 10 of 11 UNIT SYSTEM CLASS VALVE ISI DRAWING ISI DRAWING SIZE TYPE GROUP VALVE VALVE VALVE INTEGRAL UNIT 1 UNIT 2 BOLTING BOLTING BODY ATTACHMENT

= 2" > 2" WELDS 1& 2 SIS/HPSI 2 FCV-63-39 ISI-0430-C SH16 ISI-0431-C SH16 4 GATE N/A N/A NONE NONE 1& 2 SIS/HPSI 2 NONE

. FCV-63-4 ISI-0430-C SH27 ISI-0431-C SH27 2 GLOBE N/A N/A NONE NONE NONE 1& 2 SIS/HPSI 2 FCV-63-40 ISI-0430-C SH16 ISI-0431-C SH16 4 GATE NfA N/A NONE NONE 1&2 SIS/HPSI 2 NONE FCV-63-6 ISI-0430-C SH23 ISI-0431-C SH23 4 GATE N/A N/A NONE NONE NONE 1& 2 SISIHPSI 2 FCV-63-7 ISI-0430-C SH23 ISI-0431-C SH22 4 GATE N/A N/A NONE NONE 1&2 AFW 2 NONE 3-830 ISI-0113-C SH13 ISI-0146-C SH13 4 CHK N/A NIA NONE NONE NONE 1& 2 AFW 2 3-831 ISI-0113-C SH15 ISI-0146-C SH15 4 CHK N/A N/A NONE NONE 1& 2 NONE AFW 2 3-832 ISI-0113-C SH16 ISI-0146-C SH16 4 CHK N/A N/A NONE NONE NONE 1& 2 AFW 2 3-833 ISI-0 13-C SH17 ISI-0146-C SH17 4 CHK N/A N/A NONE 1& 2 AFW NONE NONE 2 3-834 ISI-0113-C SH13 ISI-0146-C SH13 4 GATE N/A N/A NONE NONE NONE 1 &2 AFW 2 3-835 ISI-0113-C SH13 ISI-0146-C SH135 4 GATE N/A N/A NONE NONE 1& 2 AFW 2 NONE 3-836 ISI-0113-C SHl6 ISI-0146-C SH16 4 GATE N/A N/A NONE NONE NONE 1& 2 AFW. 2 3-837 IS-0113-C SH17 ISI-0146-C SH17 4 GATE N/A N/A NONE NONE 1&.2 AFW 2 NONE 3-861 151-0113-C SH12 ISI-0146-C SH12 4 CHK N/A N/A NONE NONE NONE 1& 2 AFW 2 3-562 ISI-0113-C SH14 ISI-0146-C SH14 4 CHK N/A N/A NONE NONE 182 AFW 2 NONE 3-871 ISI-0113-C SH13 ISI-0146-C SH13 4 CHK N/A N/A NONE NONE NONE 1 &2 AFW 2 3-872 ISI-0113-C SH14 ISI-0146-C SH14 4 CHK NIA N/A NONE NONE 1 &2 AFW 2 3-873 NONE ISI-0113-C SHl6 ISI-0146-C SH16 4 CHK N/A N/A NONE NONE NONE 1 &.2 AFW 2 3-874 ISI-0113-C SH17 ISI-0146-C SH17 4 CHK N/A N/A 1& 2 NONE NONE NONE AFW 2 3-875 ISI-0113-C SH13 ISI-0146-C SH13 4 GATE N/A N/A NONE NONE NONE 1&2 AFW 2 3-876 ISI-0113-C SH15 ISI-0146-C SH15 4 GATE NIA N/A _NONE NONE NONE 1& 2 AFW 2 3-877 ISI-0113-C SHl6 ISI-0146-C SH16 4 GATE N/A N/A NONE NONE NONE 182 AFW 2 3-878 ISI-0113-C SH17 ISI-0146-C SH17 4 GATE N/A N/A NONE NONE NONE 1 &2 AFW 2 3-891 ISI-0113-C SH18 iSI-0146-C SH18 4 CHK N/A N/A NONE NONE NONE 1 82 AFW 2 3-892 ISI-0113-C SHI1 ISI-0146-C SH18 4 CHK N/A N/A NONE NONE NONE 182 AFW 2 3-921 ISI-0113-C SHI2 ISI-0146-C SH12 4 CHK N/A N/A NONE NONE NONE 1& 2 AFW 2 3-922 ISI-0113-C SH14 ISI-0146-C SH14 4 CHK N/A N/A NONE NONE NONE 1 &2 AFW 2 FCV-1-15 ISI-0113-C SH18 ISI-0146-C SH18 4 GATE N/A N/A NONE NONE NONE 1& 2 AFW 2 FCV-1-16 ISI-0113-C SH18 ISI-0146-C SH18 4 GATE N/A N/A NONE NONE NONE 182 AFW 2 FCV-1-18 ISI-0113-C SH18 ISI-0146-C SH18 4 GATE N/A NIA NONE NONE NONE

SQN ASME CLASS I AND 2 VALVES 0-SI-DXI-000-114.3 ATT6 Unit 1 & 2 (UNIT I AND UNIT 2) Effective Date: 06-01-2006

.Page 11 of II NOTE

1. No examination required due to valve size

SQN LISTING OF DRAWINGS O-SI-DXI-000-114.3 AT17 Unit I & 2 (UNIT 1AND UNIT 2) Effective Date: 06-01-2D06 Page 1 of 8 ATTACHMENT 7 - Listing of Drawings (Unit 1 and Unit 2)

SCIN LISTING OF DRAWINGS 0-SI-DXI-000-114.3 AT-ir7 Unit ' & 2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006 Page 2 of 8 LIST OF DRAWINGS - UNIT I and 2 The drawings listed below are for the performance of ISI examinations. These drawings are issued through Management Services. These drawings shall receive controlled distribution. Individual copies may be obtained from Management services.

Drawing Number Unit I Drawing Number Unit 2 Reactor Vessel ISI-0504-C ISI-0304-C Reactor Vessel Stud

. _ Locations and Details ISI-0504-C ISI-0298-C Reactor Vessel General Arrangement, Seam Welds, and Support ISI-0504-C ISI-0301 -C Reactor Vessel Closu~re Head ISI-0504-C ISI-0300-C Control Rod Drive Housing ISI-0504-C ISI-0392-C Reactor Vessel Inlet Nozzles ISI-0504-C ISI-0297-C Reactor Vessel Outlet Nozzles ISI-0504-C ISI-0097-C Closure Head Penetrations ISI-0504-C ISI-0318-C Auxiliary Head Adapter/UHI Cap Welds ISI-0504-C ISI-0319-C Reactor Vessel Bottom Head' Penetrations Drawing Number Unit 1 Drawing Number Unit 2 Pressurizer ISI-0394-C ISI-0396-C Pressurizer ISI-0394-C IS1-0396-C Pressurizer Manway Bolting ISI-0394-C ISI-0309-A Pressurizer Heate' Penetrations Drawing Number Unit I Drawing Number Unit 2 Steam Generatorn ISI-0397-C ISI-0398-C Steam Generators Tube Sheet Arrangement ISI-0399-C ISI-0401-C Steam Generator ISI-0399-C ISI-0401-C Steam Generator Manway Bolting MSG-0005-A ISI-0350-C Steam Generator/Feed water Transition Spool Piece ISI-0357-A ISI-0358-A Steam Generator Feedwater Ring Header

SQN LISTING OF DRAWINGS 0-SI-DXI-000-114.3 AT1T7 Unit 'I & 2 (UNIT I AND UNIT 2) Effective Date: 06-01-2006 Page 3 of 8 Drawing Number Unit I Drawing Number Unit 2 Heat Exchangers ISI-0290-C ISI-0289-C Residual Heat Removal Heat Exchanger ISI-0226-C ISI-0226-C Gas Stripper and Boric Acid Evaporator Package Support ISI-0216-A ISI-0257-A Non-Regenerative Letdown Heat Exchanger Support ISI-0284-B ISI-0261-B Component Cooling Heat Exchanger ISI-0285-C ISI-0268-C Essential Raw Cooling 'ater Strainer Support ISI-0290-C ISI-0291-C RHR Heat Exchanger Secondary Side Support ISI-0287-C UNIT 1 ONLY Spent Fuel Pit Heat Exchanger ISI-0462-C ISI-0463-C Containment Spray Hleat Exchanger ISI-0458-C ISI-0459-C Seal Water Filter

'ISI-0456-C IS1-0457-C Seal Water Injection Filter IS1-0460-C ISI-0461-C Seal Water Heat Exchanger

SCIN LISTING OF DRAWINGS 0-SI-DXI-000-1 14.3 ATr7 Unit 1 & 2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006 Page 4 of 8 Drawing Number Unit I Drawing Number Unit 2 Piping and Valve Weld Isometrics ISI-0482-C ISI-0008-C Reactor Coolant Piping (Main Loops)

CHM-2333-C ISI-0002-C Safety Injection System ISI-0369-C ISI-0013-C Reactor Coolant System CHM-2335-C ISI-0009-C Chemical and Volume Control System CHM-2336-C ISI-0003-C Residual Heat Removal

._ System CHM-2338-C MSG-0008-C Seal Water Injection (Chemical and Volume Control System)

CHM-2339-C CHM-2403-C Feedwater System CHM-2340-C ISI-0015-C Main Steam System CHM-2422-C ISI-0007-C Containment Spray System ISI-0430-C ISI-0431-C High Pressure Safety Injection System (CS, CVC, RHR, and SI)

ISI-0434-C ISI-0435-C High Pressure Safety Injection System (CS, CVC, RHR, and Sl)(Exclucled I_ Piping)

SQN LISTING OF DRAWINGS 0-SI-DXI-000-1 14.3 ATT7 Unit I & 2 (UNIT I AND UNIT 2) Effective Date: 06-01-2006 Page5of8 Drawing Number Unit I Drawing Number Unit 2 Class I and 2 Piping and Valve Support Drawings I SI-0370-C MSG-001 3-C Reactor Coolant System CIIM-2433-C MSG-001 2-C Chemical and Volume Control System CIHM-2434-C MSG-001 5-C Seal Water Injection (Chemical and Volume Control)

CHM-2435-C MSG-001 0-C Residual Heat Removal

.__System _

CHM-2436-C MSG-0009-C Safety Injection System CIHM-2438-C MSG-001 7-C Main Steam Systern CHM-2439-C MSG-001 6-C Feedwater System CHM-2440-C MSG-001 1-C Containment Spray System ISI-0303-C ISI-0302-C Reactor Coolant System ISI-0321-C (Main Loop)

ISI-0448-C ISI-0449-C High Pressure Safety Injection System (CS, CVC, RHR, and SI)

ISI-01 13-C ISI-0146-C Auxiliary Feedwater System Drawing Number Unit 1 Drawing Number Unit 2 Class 3 Piping and Valve

._ Support Drawings ISI-0113-C ISI-0146-C Auxiliary Feedwater System ISI-0123-C ISI-01 58-C Essential Raw Cooling Water System ISI-0126-C ISI-0154-C Component Cooling Water

.__ .System ISI-0127-C UNIT 1 ONLY Fuel Pool Cooling System ISI-0450-C ISI-0451 -C Air Conditioning Chilled Water System

-SN LISTING OF DRAWINGS 0-SI-DXI-000-114.3 AT17 Unit 1 & 2 (UNIT 1 AND UNIT 2) Effective Date: 06-01-2006 Page 6 of 8 Drawing Number Unit 1 Drawing Number Unit 2 Pumps' ISI-0325-C ISI-0307-C Reactor Coolant Pump Main Flange and Number 1 Seal House Bolt Pattern ISI-Q325-C ISI-0326-C Reactor Coolant Pump Support ISI-0305-B ISI-0306-B Reactor Coolant Pump Motor Flywheel Examination ISI-0353-C ISI-0352-C RHR Pump Support

._ Locations IS1-0474-C ISI-0475-C Turbine Driven Auxiliary

._ Feedwater Pump Support ISI-0476-C ISI-0477-C Motor Driven Auxiliary Feedwater Pump Support ISI-0281-C ISI-0260-C Component Cooling Water

._ Pumps Support ISI -0286-B UNIT 1 ONLY ERCW Pumps Support Locations ISI-0288-B UNIT 1 ONLY Spent Fuel Pump Support ISI-0296-C UNIT 1 ONLY ERCW Screen Wash FPump Support ISI-0325-C UNIT 1 ONLY Reactor Coolant Pump Casing Weld ISI-0470-C ISI-0471-C Safety Injection Pumps ISI-0466-C ISI-0467-C Centrifugal Charging Pumps ISI-0464-C ISI-0465-C Containment Spray Puimps IS1-0472-C ISI-0473-C Chill Water Circulation Pump

SQN LISTING OF DRAWINGS 0-SI-DXI-000-114.3 ATT7 Unit I & 2 (UNIT I AND UNIT 2) Effective Date: 06-01-2006 Page 7 of 8 Drawing Number Unit I Drawing Number Unit 2 Tanks 131-0069-C ISI-0074-C Centrifugal Charging Pump Tank (Formerly BIT Tank)

ISI-0227-B ISI-0227-B Component Cooling Surge

_ _Tank Drawing Number Unit 1 Drawing Number Unit 2 Miscellaneous ISI-0403-C ISI-0403-C Reactor Coolant Pump Flywheel Examinations ISI-0404-A ISI-0405-A Support Acceptance Renges ISI-0402-C ISI-0452-C Valve Interior Examinations ISI -0436-C ISI-0436-C Unit 1 and Unit 2 Piping Support Examination Boundaries ISI-0480-C ISI-0481-C Old ERCW Pumping Station Strainer ISI-0454-C ISI-0455-C Shutdown Board Room Water Chiller ISI-0478-C ISI-0479-C Chilled Water System Air I_ I Separator

SON LISTING OF DRAWINGS O-SI-DXI-000-114.3 ATT7 Unit 1 & 2 (UNIT I AND UNIT 2) Effective Date: 06-01-2D06 Page 8 of 8 ASME Section XI Boundary Classification Drawings List Drawing No. ASME Section XI Boundary Classification Drawings NOTE Refer to TVA Calculation SQN-SQTP-001, "ASME Section Xl Inservice Code Class Boundaries For The Second 10 Year Interval", for drawing boundary classifications. This is to be revised for the third interval.

fI-ISI Segment Boundary Drawings List Drawina No. RI-ISI Seament Boundarv Drawings NOTE Refer to TVA Calculation SQN-MEB-MDNO999-990085 "RI-ISI Piping Segment/Direct Consequence Definition," for RI-ISI segment boundary drawings

SQN SUCCESSIVE EXAMINATIONS O-SI-DXI-000-114.3 ATT13 Unit I (UNIT 1) Effective Date: 06-01-2006 Page 1 of 2 ATTACHMENT 8 - Successive examinations (Unit 1)

SQN SUCCESSIVE EXAMINATIONS O-SI-DXI-000-114.3 ATT8 Unit 1 (UNIT 1) Effective Date: 06-01-2D06 Page 2 of 2 NOTE There are no successive examinations identified for Unit 1 during revision 0 of 0-SI-DXI-000-114.3 for the third interval.

COMPONENT Program Exam Exam Initially Next First Second Third Reference Reference Method Cat. Detected Refueling Period Period Period Drawings Section Unit Outage Unit Unit Unit

_ /Cycle /Cycle /Cycle /Cycle None Identified

. SQN4 SUCCESSIVE EXAMINATIONS O-SI-DXI-000-114.3 ATT9 7 ]

Unit 2 (UNIT 2) Effective Date: 06-01-2C006 Page 1 of 2 ATTACHMENT 9 - Successive Examinations (Unit 2)

SCIN SUCCESSIVE EXAMINATIONS 0-SI-DXI-000-114.3 AT1F9 Unit 2 (UNIT 2) Effective Date: 06-01-2006 Page 2 of 2

'SUCCESSIVE EXAMINATIONS UNIT 2 COMPONEN1 Program Exam Exam Initially Next First Second Third Refe'ence Reference Method Cat. Detected Refueling Period Period Period Dravwings Section Unit /Cycle Outage Unit Unit Unit

_ _/ /Cycle /Ccle y /Cycle RVINT Attachment I VT-3 B-N-1 U2C13 N/A U2C14 U2C16 U2C18 ISI-0298-C-03 Section 1.9 or or or Note: 1 Note: 2 U2C15 U2C17 U2C19 RVCSUPST Attachment 1 VT-3 B-N-3 U2C13Note: N/A U2C14 U2C16 U2C18 ISI-0298-C-03 Section 1.12 3 or or or Note: 1 U2C15 U2C17 U2C19 2-RHRH-481 Note: 4 VT-3 F-A N/A U2C14 N/A N/A N/A ISl-0449-C-41 RCL-CLR-1 Note: 5 VT-3 F-A N/A U2C14 N/A N/A N/A ISI-0321-C-01 RCL-CLR-2 Note: 5 VT-3 F-A N/A U2C14 N/A N/A N/A ISI-0321-C-01 RCL-CLR-3 Note: 5 VT-3 F-A NIA U2C14 N/A N/A N/A ISI-0321-C-01 RCL-CLR-4 Note: 5 VT-3 F-A N/A U2C14 N/A NIA N/A ISI-0321-C-01 NOTES

1) Refer to 0-SI-DXI-000-114.3, Section 7.4.2.A.

2) Reexamine relevant conditions identified in examination report R6747, NOI#

2-SQ-379.

3) Reexamine relevant conditions identified in examination report R6746, NOI#

2-SQ-380.

4) Voluntary successive examination, examine support 2-RHRH-481 in U2C14, refer to NOI# 2-SQ-375, examination report R6659.

5) Supports requiring an additional preservice examination per 0-SI-DXI-000-1 14.3, Section 7.2.D.9. Reexamine the areas examined during U2C13 under work order 04-782190-000.

SQU AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT'TN Unit I Effective Date: 06-01-2006 Page 1 of 41 ATTACHMENT 10 - Augmented Examinations (Unit 1)

SC!N AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 AT1-10 Unit I Effective Date: 06-01-2006 Page 2 of 41 AUGMENTED EXAMINATIONS Augmented examinations are performed in addition to ASME Section XI code requirements. The augmented examinations may be required by the NRC or be self-imposed by TVA. Typical sources include generic letters, IE Bulletins, technical specifications, vendor recommendations, and industry experience. Table A of this attachment provides a schedule for augmented examinations. Responsible organizations requesting inclusion of augmented examinations in this section shall submit a written request to the Component Engineering representative (see C-SI-DXI-000-1 14.3, Section 7.1 1).

Table B of this attachment identifies the augmented piping welds/components under the RI-ISI program, the failure mechanism and if credit is being taken for the examination being performed in accordance with this attachment.

1.0 FEEDWATER NOZZLE-TO-PIPE WELDS AND ADJACENT PIPE/FITTINGS AND NOZZLE AREAS/AUXILIARY FEEDWATER Responsible Organization: Mechanical Design Due to the safety-related ramifications and the assessments concluded in Incident Investigation (II) No. Il-S-92-027 of the steam generator nozzle transition section cracking problem and potential for cracking in adjacent components within the feedwater piping system, TVA will perform augmented examinations as determined by Mechanical Design. This shall include the four feedwater nozzle transition pieces

-andassociated piping components with inspections being performed during the intervals as listed below.

The augmented examination of the steam generator nozzle transition and feedwater piping shall include 100 percent volume of the transition pieces, the nozzle-to-transition piece welds, transition piece-to-elbow welds, 4-inch feedwater/auxiliary feedwater tee-to-pipe welds, and base metal adjacent to each weld for a distance of two wall thicknesses. These welds shall be volumetrically examined by the ultrasonic method and supplemented with radiographic examination when specified by Mechanical Design.

Starting with revision 0 of this procedure for the third interval, the Ultrasonic acceptance criteria shall be in accordance with ASME Section Xl 2001 Edition tnrough the 2003 Addenda, IWC-3514, for Class 2 welds.

The results of the examination will be submitted to Mechanical Design for evaluation and trending of flaw sizes and growth rates. The results of this examination shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 77.

Inspection of the transition pieces, nozzle-to-transition piece welds, transition piece-to-elbow welds, and the associated base metal shall be scheduled for inspection at each consecutive refueling outage unless otherwise revised or waived by Mechanical Design.

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTIO Unit I Effective Date: 06-01-2006 Page 3 of 41 1.0 FEEDWATER NOZZLE-TO-PIPE WELDS AND ADJACENT PIPE/FITTINGS AND NOZZLE AREASIAUXILIARY FEEDWATER (Continued)

Inspection of the 4-inch feedwater/auxiliacy feedwater reducer-to-pipe welds and the associated base metal shall be to the following schedule unless otherwise revised or waived by Mechanical Design.

Loops 2 and 4 are to be inspected each even numbered outage. Initial inspection performed during Cycle 6 Refueling Outage.

Loops 1 and 3 are to be inspected each odd numbered outage. Initial inspection performed during Cycle 7 Refueling Outage.

Feedwater loops that have been replaced with the feedwater thermal liner during and after Unit 1 Cycle 7 will be examined to ASME Section XI requirements with no additional examination requirements or examination volume coverage. All feedwater loops have been replaced with the feedwater thermal liner design. Welds to be examined are nozzle-to-elbow, elbow-to-thermal liner adapter, and thermal liner adapter to pipe weld. Additional examinations may be required by Mechanical Design where further evaluation indicates a potential for cracking in this area of piping.

FEEDWATER NOZZLE TRANSITION PIECE EXAM SCHEDULE The following is a summary of the examinations conducted during successive cycles. The requirements of NRC IE Bulletin 79-13 were satisfied during the Unit 1 Cycle 1 outage.

Cycle Examination Areas 1 IE Bulletin 79-13 completed 2 1 nozzle-to-pipe weld and adjacent pipe and nozzle area 3 1 nozzle-to-pipe weld and adjacent pipe and nozzle area 4 All nozzle transition section pieces and welds 5 All nozzle transition section pieces and welds 6 All nozzle transition section pieces and welds 7 Examined all nozzle transition section pieces and welds for loops 3 and 4. Replaced loops 1 and 2 in Ul C7 with the feedwater thermal liner design 8 Replaced loops 3 and 4 in Ul C8 with the feedwater thermal liner design

References:

1. Incident Investigation (II) No. Il-S-92-027

2. ASME Section Xl 2001 Edition 2003 Addenda

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT10 Unit: 1 Effective Date: 06-01-2006 Page 4 of 41 1.0 FEEDWATER NOZZLE-TO-PIPE WELDS AND ADJACENT PIPE/FITTINGS AND NOZZLE AREAS/AUXILIARY FEEDWATER (c:ontinued)

3. NRC Bulletin 79-13

SCN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTIO Unit I Effective Date: 06-01-2006 Page 5 of 41 2.0 REACTOR COOLANT PUMP FLYWHEEL Responsible Organization: Mechanical Design The augmented examination requirements of the reactor coolant pump flywheel are included in Regulatory Position C.4.b of Regulatory Guide 1.14; (1) an in-place ultrasonic examination of the areas of higher stress concentration at the bore end keyway at approximately 3-year intervals during the refueling or maintenance shutdown coinciding with the ISI schedule as required by Section Xl of the ASMNAE (Code, and (2) a surface examination of all exposed surfaces (exposed areas are considered as those areas accessible for examination without having to remove the flywheel from the housing) and complete ultrasonic examination at approximately 10-year intervals during the plant shutdown coinciding with the ISI schedule as required by Section Xl of the ASME Code (in the event that the motor housing is removed for shop rework, a complete surface and ultrasonic volumetric examination shall be performed). In lieu of Regulatory Guide 1.14 Position C.4.b(1) and C.4.b(2),

a qualified in-place ultrasonic examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the removed flywheels may be conducted at approximately 10-year intervals coinciding with the Inservice Inspection schedule as required by ASME Section Xl per Technical Specification Change TS-01 -13. The 10-year interval was changed to 20-year intervals per Technical Specification Change TS-04-02. This examination is performed in accordance with SQN Technical Specifications and satisfies Surveillance

[Requirement 4.0.5.c.

This augmented examination does not require a special report unless the examination reveals a flaw. The acceptance criteria should be equivalent to those specified for class 1 vessels in the ASME B&PV Code Section III as stated in FSAR subsection 5.2.6. If the examination and evaluation indicate an increase in flaw size Or growth rate greater than predicted for the service life of the flywheel, the results of the examination and evaluation should be submitted to Engineering and NRC For evaluation. Refer to Regulatory Guide 1.14 for information to be included. The examination results shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7.

The flywheel consists of 2 plates, approximately 5 inches and 8 inches thick, bolted together. Each plate is fabricated from vacuum degassed A-533, GR. B, Class 1, steel.

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT10 Unit 1 Effective Date: 06-01-2D06 Page 6 of 41 2.0 REACTOR COOLANT PUMP FLYWHEEL (continued)

For the 20-year exam, the IDs shall be:

RCP Motor S/N - SUR (i.e., 4S-81 P352 - SUR)

RCP Motor S/N - VOL (i.e., 4S-81 P352 - VOL)

References:

1. Regulatory Guide 1.14

2. Technical Specification TS-01-13

3. Technical Specification TS-04-02 4 FSAR Subsection 5.2.6

SCN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTi10 Unit I Effective Date: 06-01-2006 Page 7 of 41 3.0 RPV NOZZLE CLADDING Responsible Organization: Mechanical Design EBy memorandum from David E. Labarge NRC to O.D. Kingsley, TVA dated March 15, 1994 (L44 940322 006) Sequoyah Nuclear Plant, Units 1 and 2 Technical Specifications Requirement 4.4.10.b were amended to remove Surveillance Requirement 4.4.10.b [C.1]. The amendments remove the surveillance requirement to perform reactor vessel nozzle inspections at the end of each 10-year inspection interval subject to the commitments to perform the augmented ISI examination as stated below.

TVA has committed to the following requirements:

1. The ultrasonic technique for future examinations shall be at least as sensitive as that used to conduct the examinations during the Unit 1 Cycle 6 refueling outage. [C.1]

2. The examinations performed during the Unit 1 Cycle 6 refueling outage shall serve as the baseline for future examinations. [C.1]

3. The examinations will be performed near the end of the second 10 year ISI interval. [C.1]

.4. All of the detected flaws will be sized regardless of the percent Distance Amplitude Correction Curve (DAC). [C.1]

5. The results of the examination shall be submitted to NRC. [C.1]

ID. The above commitments shall not be removed from the Unit 1, ISI program without notifying NRC. [C.1]

The volumetric examinations of the reactor pressure vessel nozzles will be performed over the same cladded nozzle area equivalent to the area examined during the Unit I Cycle 6 refueling outage. References S57 020401 800 and L 18 C51005 000.

IVA plans to perform a second examination of the Unit I reactor vessel nozzle cladding near the end of SQN second 10-year ISI interval during Ul C14.

The Unit 1 augmented RPV nozzle cladding examinations cannot be deleted from the ISI Program unless NRC approval is obtained through the de-commitment process as defined in SPP-3.3. TVA plans to submit a request to NRC to de-commit from those requirements following the U1 C14 refueling outage examinations.

This augmented examination does not require a special report. Results of the examination shall be reported to the NRC via the ISI Summary Report discussed in C'-SI-DXI-000-1 14.3, Section 7.7.

SQN AUGMENTED EXAMINATIONS (UNIT 1) O-SI-DXI-000-114.3 ATTIO Unit: I Effective Date: 06-01-2006 Page 8 of 41 3.0 RPV NOZZLE CLADDING (continued)

A special preservice examination of the reactor vessel nozzles was conducted to evaluate the extent of underclad cracking. The examination utilized a 700 angle beam and 00 beam manual contact technique. All indications found were demonstrated to be acceptable in accordance with ASME Code Section Xi criteria.

(Reference FSAR Section 5.4.4.1)

References:

1. Technical Specification 4.4.10.b

2. SPP-3.3

3. L44 940322 006

4. S57 020401 800 5 L18 051005 000

6. FSAR Section 5.4.4.1

SON AUGMENTEDEXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT10 Unit 1 Effective Date: 06-01-2006 Page 9 of 41

4.0 CONTROL ROD GUIDE TUBE FLEXURES Responsible Organization: Mechanical Design No augmented examinations are being perform ed on the control rod guide tube flexures in the third interval. This section is being maintained for history in the interval.

Any revisions or waivers of this augmented examination plan as stated in this section shall be the responsibility of the Mechanical Design - Supervisor or his designee.

Due to the removal of the control rod guide tube flexures during the split pin replacement during the U1 C1I (DCN D20919A), this augmented examination is no longer required. The following information is being retained for history during this interval.

Due to the potential of intergranular stress corrosion cracking of guide tube flexures, the control rod guide tube flexure augmented examination plan was initiated during the first inspection interval (see Westinghouse reference memorandums A27 840123 022 and L01 840723 035).

The control rod guide tube flexures shall be visually examined in accordance with visual examination method VT-3 during the second 10 year ISI inspection interval vessel interior examination (Examination Category B-N-1), coincident, when the core barrel is removed. If any flexure heads are discovered to be broken from their stems, the heads should be retrieved and flexureless inserts installed. If flexureless inserts are not installed after a break has occurred, a safety evaluation shall be required to confirm continued safe plant operation. A copy of the VT data sheets shall be forwarded to the appropriate cognizant engineer.

The PRISIM identifiers for the control rod guide tube flexures are:

CRDTUBEFLEX - A07 CRDTUBEFLEX - E09 CRDTUBEFLEX - G05 CRDTUBEFLEX - J 1 CRDTUBEFLEX - L07 This augmented examination is self-imposed by TVA and does not require a report.

Results of the examination shall be included in the ISI Site Final Report discussed in 0-Sl-DXI-000-1 14.2, Section 7.7.

SC!N AUGMENTED EXAMINATIONS (UNIT 1) O-SI-DXI-000-114.3ATTW]

Unit I Effective Date: 06-01-21)06 Page 10 of 41 4.0 CONTROL ROD GUIDE TUBE FLEXURES (continued)

References:

1. A27 840123022

2. L01 840723 035

SON AUGMENTEDEXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTIO Unit I Effective Date: 06-01-2006 Page 11 of 41 5.0 THIMBLE TUBE GUIDE Responsible Organization: Systems Engineering - Instrument/Controls and Electrical (ICE)

Due to the potential thinning of thimble tube guides as reported on NRC Bulletin 88-09 and Information Notice No. 87-44 supplement 1, TVA performed an augmented examination of the thimble tubes using Eddy Current Examination (ET) during the Unit 1 Cycle 4 refueling outage. Background information documents(R.

VW. Fortenberry's July 21, 1988 memorandum to S. J. Smith (S57 880721 821), J. F.

Murdock's June 3, 1988 memorandum to J. B. Hosmer (L29 880531 914), P.G.

Trudel's February 27, 1989 memorandum to M. J. Burzynski (825 890227 002) and Design Change Notice Drawing Deviation F-07706 (B85 911197 124), P.G. Trudel April 20,1998 memorandum to M.J. Burzynski (825 900420 008).

All thimble tubes shall be examined each refueling outage, unless otherwise revised or waived by ICE.

Organization performing examinations shall provide results to Component Engineering to be included in the ISI Site Final Report discussed in O-SI-DXI-000-114.3, Section 7.7.

References:

1. S57 960208 934

2. B38 040322 801

3. NRC Bulletin 88-09

4. Information Notice No. 87-44

5. S57 880721 821

6. L29 880531 914

7. B25 890227 002

8. B85911107 124

9. B25 900420 008

SON AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 AT-iri Unit 1 Effective Date: 06-01-2006 Page 12 of 41 6.0 EXAMINATION OF PIPING CONNECTED TO THE REACTOR COOLANT SYSTEM DUE TO THERMAL STRESSES Responsible Organization: Mechanical Design Ii response to NRC Bulletin due to the potential thermal stresses on unisolable piping attached to the RCS (see NRC Bulletin 88-08), TVA examined the following areas: 1) the four 1.5-inch high head injection lines, 2) the 2-inch pressurizer spray line from the charging path, 3) the 3-inch alternate charging path, and 4) the 3-inch normal charging path. During Cycle 3 shutdown period all of the welds up to the first valve were PT examined, and the 3-inch line was UT examined. The SQN Project Engineer prepared a report to Licensing, who in turn prepared a report to the NRC.

(See memorandums B29 880906 008, S08 880830 843, L44 880824 802, and B25 E;80819 014.)

D)ue to the assessments concluded in Incident Investigation (II) No. Il-S-92-027 of the steam generator nozzle transition section cracking problem and NRC Bulletin 88-08, similar conditions were evaluated for the Chemical and Volume Control System (CVCS), Safety Injection System (SIS) and Reactor Coolant System (FRCS).

Potential for cracking in these systems, in particular the Alternate Charging Line, are the cases that resulted in the cracking of welds at Farley (NRC Bulletin 88-08) and the elbow at Tihange (NRC Bulletin 88-08, Supplement 1). The thermal cycling stresses can be quite severe at these locations with leakage across the closed FCVs, and it is possible for a crack to initiate and grow substantially in a single fuel cycle.

As some of the fatigue crack mechanisms are much more likely than others to occur and result in crack development, a graded approach regarding examination frequency has been recommended by Mechanical Design. This graded approach couples the likelihood of occurrence with the severity of the postulated event. some cf these welds and adjacent base metal were baseline examined during the Unit 1 forced outage due to the feedwater transition piece cracking problem.

IVA will perform augmented examinations of the areas noted during the intervals as listed below, unless otherwise revised or waived by Mechanical Design. Additional welds and/or examination techniques may be added by Mechanical Design where further evaluations indicate a potential for thermal stratification. (see memorandum E;25 931129 001) Following U2C7, this augmented section was revised on March 17, 1997 to remove the supplemental PT examinations, replaced the PT examinations with a UT examination, and removed the socket welded fitting elbows 1-SI-1606/1607 ELBOW, 1-SI-1610/1611 ELBOW, 1-SI-1693/1694 ELBOW, 1-SI-1 697/1698 ELBOW and 1-CVC-2599/2600 ELBOW from the augmented section for examination.

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTIO Unit I Effective Date: 06-01-21)06 Page 13 of 41 6.0 EXAMINATION OF PIPING CONNECTED TO THE REACTOR COOLANT SYSTEM DUE TO THERMAL STRESSES (continued)

Examinations of circumferential butt welds shall be performed by the ultrasonic (UT) examination method. The extent of examination shall include the lower one-third volume of the welds and base metal adjacent to each weld for a distance of two wall thicknesses where accessible (fittings, elbow interdose, and valves may prevent full circumference examination).

Starting with revision 0 of this procedure, the UT acceptance criteria for circumferential butt welds shall be in accordance with ASME Section Xl, 2001 Edition through the 2003 Addenda, IWB-3514 and IWC-3514, for Class I and 2 welds, respectively.

Examination of pipe fittings shall be performed by the UT examination method. The extent of examination shall include the lower one-third volume of the fitting where accessible (Fitting geometry may prevent full examination).

Starting with revision 0 of this procedure, the UT acceptance criteria for the fittings shall be the same as for the adjacent circumferential butt welds in accordance with ASME Section Xl, 2001 Edition through the 2003 Addenda, IWB-3514 and IWNC-3514, for Class I and 2 welds, respectively.

Examination of socket welds shall be performed by the UT examination method.

The extent of examination shall be as specified in the NDE procedure. SQN Mechanical Design shall determine the acceptability of any crack-like indications.

The results of examinations shall be submitted to SQN Mechanical Design for Evaluation and trending. The results of this examination shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-114.3, Section 7.7.

D)uring the third interval, examination of cold leg Loop 1 and cold leg Loop 4 CI/C (circumferential butt) welds and fittings shall be performed during the inspection interval as noted below.

Cold Leg loop 4 - Welds 1-CVCF-246 and 1-CVCS-414, and fitting 1-CVCF-246/CVCS-414 EL: Examine each even numbered RFO beginning with RFO 8 of the second interval (initial examination performed during RFO 6).

Cold Leg Loop 1 - Welds 1-CVCF-213 and 1-CVCF-214, and fitting 1-CVCF-213/214 EL: Examine each odd numbered RFO beginning with RF0 9 of the second interval. (Initial examination performed during RFO 7.)

Examination of pressurizer surge line (circumferential butt welds), welds RC-3'3 and RC-35 shall be performed during the inspection interval as noted below: (Reference 14RC Bulletin 88-11.)

Pressurizer surge line, Weld RC-33, shall be inspected every fourth refueling cutage beginning with refueling outage 10 of the second interval.

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTI7 Unit I Effective Date: 06-01-2006 Page 14 of 41 6.0 EXAMINATION OF PIPING CONNECTED TO THE REACTOR COOLANT SYSTEM DUE TO THERMAL STRESSES (continued)

Pressurizer surge line, Weld RC-35 shall be inspected every fourth refueling outage beginning with refueling outage 12 of the second interval.

Examination of cold leg loops 1, 2, 3, and 4 SI sockets welds shall be performed during the inspection interval as noted below:

Cold Leg Loop 1 SI-1605, 1-SI-1606, and 1-SI-1607: Examine each odd numbered RFO beginning with RFO 9 of the second interval. (initial examination performed during RFO 7).

Cold Leg Loop 2 SI-1610, 1-SI-1611, and 1-SI-1612: Examine each even numbered RFO beginning with RFO 8 of the second interval. (initial examination performed during RFO 6).

Cold Leg Loop 3 SI-1692, 1-SI-1693, and 1-SI-1694: Examine each odd numbered RFO beginning with RFO 9 of the second interval. (initial examination performed during RFO 7).

Cold Leg Loop 4 SI-1697, 1-SI-1698, and 1-SI-1699: Examine each even numbered RFO beginning with RFO 8 of the second interval.

Auxiliary Spray line (CVC socket welds) 1-CVC-2599, 1-CVC-2600 and 1-CVC*-2601 shall be examined each refueling outage beginning with RFO 8 of the second interval. (initial examinations were performed during RFO 6 and RFO 7).

References:

1. NRC Bulletin 88-08

2. NRC Bulletin 88-11

3. Incident Investigation (II) No. I1-S-92-027

4. B29 880906 008

5. S08 880830 843

6. L44 880824 802

7. B25 880819 014

8. B25 931129 001

9. ASME Section Xl 2001 Edition 2003 Addenda

SCQN - AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT710 Unit 1 Effective Date: 06-01-21306 Page 15 of 41 7.0 PRESSURIZER RELIEF LINE REPAIR WELDS AND ADJOINING AREAS Responsible Organization: Mechanical Design The augmented examination requirements of the pressurizer relief line (draw bead welds) are included in the Technical Specifications 4.0.5 and 4.4.3.2.4. The pressurizer relief line repair welds (RCF-24P and RCF-24H) and adjoining areas were examined in accordance with TVA procedure using improved ultrasonic detection and evaluation procedures prior to entering Mode 4 whenever the plant has been in cold shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more if the examination had not been performed in the previous six months. When these 6-month period examinations found the piping free of unacceptable indications for 3 successive inspections, Jhe inspection interval was extended to 36 months intervals (12 months to coincide with a schedule refueling outage). When these 36-month period examinations found the piping free of unacceptable indications for 3 successive inspections, the inspection interval was extended to 80-month periods. The procedures were qualified by demonstrating proficiency in detecting Intergranular Stress Corrosion Cracking (IGSCC). All future examinations of the pressurizer relief line repair welds will be performed using procedures with ultrasonic sensitivities equivalent to those required for detecting IGSCC. Examination boundary after U1 C7 will be full volume. The report shall be submitted with the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7. See examination history below:

Examination History Date Examination Performed Examination Periods 10-20-91 (Examination performed by SI-1 14.1)Start of first 80-month period 09/21/95 (RFO 7 - 48 months) Start 80 month period -see note 1 10/27/01 (RFOI I - 73 months) Start 80 month period - see note 1 10/28/04 (RFO13 - 36 months) Start 80 month period - see note 2 Next 80 month examination (10/04 - 10/1 0) RFO17 NOTES

1) RCF--24P and RCF-24H were examined in RFO 7 (9/21/95)(- 48 months) and we-e examined in RFO 11 (10/27/01 - 73 months) to coincide with Unit 1 RFO in lieu of the 80 month examination (10/91 - 4/98) initial projected schedule.

2) RCF-24P and RCF-24H were examined in RFO 13 (10/28/04 - 36 months) in lieu of the 80 month examination (10/01 - 10/07) initial projected schedule.

References:

SON AUGMENTEDEXAMINATIONS (UNIT 1) O-SI-DXI-000-114.3 ATTIO Unit 1 Effective Date: 06-01-21)06 Page 16 of 41 7.0 PRESSURIZER RELIEF LINE REPAIR WELDS AND ADJOINING AREAS (continued)

1. Technical Specification 4.0.5 and 4.4.3.2.4

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTIO Unilt 1 Effective Date: 06-01-2006 Page 17 of 41 8.0 SAFETY INJECTION AND RHR WELDS AND ADJOINING AREAS, AND RI-ISI REGION 3 WELDS Responsible Organization: Mechanical Design In response to an Intergranular Stress Corrosion Crack (IGSCC) detected during the U~nit 2, Cycle 7 refueling outage (2-SIF-146), Problem Evaluation Report SQ961154PER was initiated to address the corrective actions of this condition. As part of the corrective actions and recurrence prevention, TVA performed an augmented inspection of the areas noted below during the Unit 1, Cycle 8 refueling outage of the second interval.

Weld Number Examination Method 1-RHRF-107 Volumetric 1-SIF-146 Volumetric 1-SIF-185 Volumetric 1-SIF-196 Volumetric 1-SIF-198 Volumetric The examination area, volume and acceptance criteria was in accordance with the requirements of the ASME Section Xl Code 1989 Edition for Category B-J welds.

Ultrasonic examination procedures must be qualified by demonstrating proficiency in detecting Intergranular Stress Corrosion Cracking (IGSCC). UT acceptance criteria shall be in accordance with ASME Section Xl, 1989 Edition, IWB-3514 and IINC-3514, for Class 1 and 2 welds, respectively.

The following welds per (B38 020710 802) require volumetric examination during (or just prior to) the indicated refueling outage. These welds were identified as a result cf the follow up risk informed evaluation for region 3 (S57 011016 800) and other regions addressed in SQ9611 54PER regarding the potential for stress corrosion cracking (SCC) due to multiple weld repairs on the stainless steel pipe welds. The area and volume for the examination are to be in accordance with the RI-ISI program welds. The ultrasonic examination acceptance criteria shall be in accordance with the ASME Section Xl, 2001 Edition through the 2003 addenda, IWNB-3514 and IWC-3514 for class I and Class 2 welds respectively. The type of flaw anticipated is IGSCC of the type seen in 2-SIF-146 during the U2C7 RFO. The area most highly suspected to contain the flaws is adjacent to the weld. The probability of a flaw existing is low. If indications are detected, Mechanical Design will determine further expansions. If there are no indications detected after the last examination cycle, no further examinations are required and this augmented examination sequence may be dropped from the program.

Weld Number Examination Method Cycles RHRF-018 Volumetric 13 and 15 RHRF-022 Volumetric 13 and 15 RHRF-057 Volumetric 13 and 16 RHRF-066 Volumetric 13 and 16

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTIYO Unit I Effective Date: 06-01-2006 Page 18 of 41 8.0 'SAFETY INJECTION AND RHR WELDS AND ADJOINING AREAS, AND RI-ISI REGION 3 WELDS (continued)

SIF-002 Volumetric 13 and 15 SIF-005 Volumetric 13 and 15 SIF-006 see note 1 N/A Inaccessible SIF-015 see note 1 N/A Inaccessible SIF-029 Volumetric 13 and 16 SIF-031 Volumetric 13 and 16 SIF-088 Volumetric 13 and 16 The results of the examination and any examination limitations will be submitted to Mechanical Design for evaluation and trending. The results of this examination shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 77.

NOTE

1. Welds SIF-006 and SIF-015 are inaccessible for examination due to being encased in a penetration. No augmented examination required on these welds due to inaccessibly of the welds. Refer to B38 041206 800. This note was added following U1C13.

References:

1. B38 020710 802

2. S57 011016 800

3. ASME Section Xl 2001 Edition 2003 Addenda 4 B38 961024 800 5 B38 041206 800 6 Problem Evaluation Report SQ961154PER

SCIN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATI710 Unit 1 Effective Date: 06-01-2006 Page 19 of 41 9.0 REACTOR COOLANT PUMP SUPPORT RFesponsible Organization: Civil Design No augmented examinations are being performed on the reactor coolant pump support in the third interval. This section is being maintained for history in the interval.

This augmented examination is no longer required following Ul C11. Refer to memorandum B39 030710 001. The following information is being retained for l istory during this interval.

Ey augmented NDE request from Civil Engineering dated March 1,2000, the support connections on each Reactor Coolant Pump are required to be examined due to examinations performed on Unit 1 during Ul C1 0.

The support bolting on all four reactor coolant pump supports require VT-3 of N-VT-1 examination. The examination area is to include the pin, jam nut, hex nut, and washers shown on elevation B-B on drawing 48N426 at the reactor coolant purnp tie rods (48N423) to the anchor in wall (MK PS-1 through PS-8, 48N433). The type of flaws anticipated are loose nuts and bolts.

By augmented NDE request from Civil Engineering dated January 10, 2001, the VT-3 of N-VT-1 examinations are also to include the tack welds on the shims on the struts on all four reactor coolant pumps. Struts are (MK PS-1 through PS-8 on drawing 48N423). Drawing 48N433, note 6, specifies the tack welds on the shims.

The type of flaw anticipated is cracked tack welds on the shims.

The examinations are to be performed during each odd numbered outage beginning with U1 C 11.

Results shall be submitted to Civil Design for evaluation. The results of these examinations were included in the ISI Site Final Report.

References:

I. B39 000305 001

2. B39 010111 001

3. B39 030710 001

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT10 Unit i Effective Date: 06-01-2006 Page 20 of 41 10.0 STEAM GENERATOR CLASS 2 UPPER SUPPORT Responsible Organization: Civil Design No augmented examinations are being performed on the steam generator class 2 LUpper support in the third interval. This section is being maintained for history in the interval.

This augmented examination is no longer required following UI C11. Refer to memorandum B39 030708 001. The following information is being retained for history during this interval.

Ely augmented NDE request from Civil Engineering dated March 5, 2000, the class 2 upper support bolted connections on each steam generator are required to be Examined due to examinations performed on Unit I during UIC10.

The support bolting on all four steam generator class 2 supports require VT-3 Of N-VT-1 examination. The examination area is to include the nuts and bolts in section E-E and E'-E' on drawing 48N427. The type of flaw anticipated is loose nuts and bolts. The examinations are to be performed each odd numbered outage beginning with Ul C 1.

Results shall be submitted to Civil Design for evaluation. The results of these examinations were included in the ISI Site Final Report.

References:

1. B39 000306 001

2. B39 030708 001

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT10 Unit I Effective Date: 06-01-2006 Page 21 of 41 11.0 NUCLEAR EXPERIENCE REVIEW (NER) ITEM SER 00-001 Responsible Organization: Civil Design By augmented NDE request from Civil Design dated February 28, 2001, the NER Item SER 00-001 review requires examination of several Residual Heat Removal System piping circumferential and longitudinal welds. These examinations are to be performed during UlCI1, U1Cl4, U1C17. Aftercycle 17, Civil Design will evaluate the need for future examinations.

Examine 100% of the circumferential and longitudinal welds (RHRF-041, RHRS;-072 and RHRS-071-LS), on the reducing elbow downstream of valve 1-FCV-74-33, elevation 709'0". Examine 100% of the circumferential and longitudinal welds (RHRS-073, RHRF-065 and RHRS-072-LS), on the 12"X12"x8" tee attached to the reducing elbow. Examine the longitudinal weld (RHRS-073-LS) on the next connecting and adjacent 12"x12"x8" tee. Examine 100% of the circumferential and longitudinal welds (SIF-007 and RHRS-100-LS) on the 8"X8"x8" tee at the Safety Injection tie-in located at elevation 700'-0" downstream of RHR HX 1B and valve 1-FCV-74-28. Examine 100% of the circumferential and longitudinal welds (SIF-001 and RHRS-065-LS) on the 8"x8"x8" tee at the Safety Injection tie-in located at elevation 698'-5" downstream of RHR HX IA and valve 1-FCV-74-16.

Llltrasonic (UT) examination method is to be used. The extent of examination shall be in accordance with ASME Section Xl, 2001 Edition through the 2003 Addenda, figure IWC-2500-7 where accessible. Component geometry may prevent full examination.

starting with revision 0 of this procedure, the acceptance criteria shall be in accordance with ASME Section XI, 2001 Edition through the 2003 Addenda, iWVC-3514 for class 2 welds.

Types of flaws anticipated are cracks initiating on the inside diameter due to thermal transient fatigue. The area most highly suspected to contain a flaw is the longitudinal and circumferential welds and heat affected area. There is a low probability of a flaw existing.

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT10 Unil: 1 Effective Date: 06-01-2006 Page 22 of 41 11.0 NUCLEAR EXPERIENCE REVIEW (NER) ITEM SER 00-001 (continued)

SISExamination Instructions:

The RHR piping will be considered operable per the Technical Specifications during the augmented ISI examinations. The support clamp for supports 1RHRH-438 and 1RHRH-439 covers the circumferential weld between the two tees and the longitudinal weld. Since the entire weld must be examined, the support clamp must be disabled and temporarily removed. Work Order (WO) instructions for installation of the temporary support will be provided by Civil Design. The-instructions provided below must be followed in the order shown.

1. Remove the insulation in the area of the weld and the location of the temporary support.

2. Perform the NDE on all required exposed accessible welds with supports I RHRH-438 and 1RHRH-439 in-tact and unaltered.

3. Install the temporary support per engineering instructions provided in WO.

.4. Remove the support clamp for supports I RHRH-438 and 1RHRH-439 in accordance with the WO.

5. Complete the NDE on the remaining welds.

'D. Restore supports 1RHRH-438 and 1RHRH-439 in accordance with the WO.

7. Remove the temporary support from the piping in accordance with the WO.

8. Restore piping insulation.

Results and any examination limitations shall be submitted to Civil Design for Evaluation. Report any indication of thermal fatigue cracking to Civil Design immediately. The results of these examinations shall be included in the [SI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7.

Reference:

1. B39 010228 001

2. NER SER 00-001

3. ASME Section Xl 2001 Edition 2003 Addenda

SON AUGMENTED EXAMINATIONS (UNIT 1) O-SI-DXI-000-114.3ATT10 Unit 1 Effective Date: 06-01-2006 Page 23 of 41 12.0 FREACTOR PRESSURE VESSEL CLOSURE HEAD PENETRATIONS Responsible Organization: Mechanical Design In response to NRC Bulletin 2002-01 and NRC Order on the Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurizer Water Reactors, E.A-03-009 due to the potential reactor pressure vessel (RPV) closure head degradation and reactor coolant pressure boundary integrity, the RPV closure head and closure head penetrations are to be examined per the schedule below.

These examinations may be increased based on the industry experience and/or regulatory commitments.

A Bare Metal Visual (BMV) of 100% of the RPV head/penetrations interface surface (including 360 degrees around each RPV head penetration) will be.

performed starting in Unit 1 cycle 12 and every third refueling outage or five years which ever occurs first. The examination method is a remote visual examination (enhanced VT-2) in accordance with N-VT-1 7 supplemented with additional examination methods deemed necessary by Mechanical Engineering where indications of leakage are noted as "suspect".

EBare Metal Visual - following the Unit I Cycle 12 bare metal visual examinations, the bare metal visual examination will include a 100% visual examination of the RPV head base metal surface and each penetration interface. When the RPV head surface is obscured by support structure interferences which are located at RPVI head elevations down slope from the outermost RPV head penetration, a bare metal visual inspection of no less than 95 percent of the RPV head surface may be performed provided that the examination shall include those areas of the RPV head LIP slope and down slope from the support structure interference to identify any evidence of boron or corrosive product. Should any evidence of boron or corrosive product be identified, RPV head surface shall be examined under the support structure to ensure that the RPV head is not'degraded.

.. A volumetric examination or surface examination or a combination of volumetric and surface examinations will be performed starting in Unit 1 cycle 15 and every fourth refueling outage or every seven years which ever occurs first.

Perform either A, B, or C below.

A. Volumetric examination .- Ultrasonic examination of the RPV head penetration nozzle volume (i.e., nozzle base material) from 2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) to 2 inches below the lowest point at the toe of the J-groove weld on a horizontal plane perpendicular to the nozzle axis (or the bottom of the nozzle if less than 2 inches). In addition, an assessment shall be made to determine if leakage has occurred into the annulus between the RPV head penetration nozzle and the RPV head low-alloy steel.

I SON AUGMENTEDEXAMINATIONS (UNIT I) O-SI-DXI-000-114.3 ATTI Unit i Effective Date: 06-01-2Z06 Page 24 of 41 12.0 REACTOR PRESSURE VESSEL CLOSURE HEAD PENETRATIONS (continued)

e. Surface examination - Eddy current examination or liquid penetrant examination of the entire wetted surface of the J-groove weld and the wetted surface of the RPV head penetration nozzle base material from at least 2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle. axis) to 2 inches below the lowest point at the toe of the J-groove weld on a horizontal plane perpendicular to the nozzle axis (or the bottom of the nozzle if less than 2 inches).

C:. Combination of volumetric examination and surface examination to cover equivalent volumes, surfaces and leak paths of the RPV head penetration nozzle base material and J-groove weld as described in volumetric examination and surface examination above. Substitution of a portion of a volumetric examination on a nozzle with a surface examination may be performed with the following requirements:

1. On nozzle material below the J-groove weld, both the outside diameter and inside diameter surfaces of the nozzle must be examined.

2. On nozzle material above the J-groove weld, surface examination of the inside diameter surface of the nozzle is permitted provided a surface examination of the J-groove weld is also performed.

Refer to NRC order EA-03-009 revised February 20, 2004 for additional details.

NOTE The visual inspections performed during each refueling outage to identify potential boric acid leaks from pressure retaining components above the RPV head are being performed under the boric acid program and are not being maintained under this augmented program.

The areas of leakage shafl be reported to Mechanical Engineering for evaluation.

Type of flaw anticipated is stress corrosion cracking resulting from exposure to primary water chemistry.

The area most likely to contain flaws are the CRDM penetration nozzle base material and areas adjacent to the nozzle interface with the RPV head base material snd the J-groove weld. The probability of a flaw existing is low.

The examination acceptance criteria shall be as directed by Mechanical Engineering.

SON AUGMENTEDEXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT10 Unit 1 Effective Date: 06-01-2006 Page 25 of 41 12.0 REACTOR PRESSURE VESSEL CLOSURE HEAD PENETRATIONS (continued)

Examination results and any examination limitations shall be submitted to Mechanical Engineering for evaluation and trending. The results of these examinations shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7. The reporting required by NRC Order EA-03-009 whill be submitted by Mechanical Engineering separately from the report in 0-SI-DXI-000-114.3, Section 7.7.

Examination History Bare Metal Visual Examination Cycle: U1C12 Examination Date: 03/22/2003 ASME Section Xl Inspection Interval: Second ASME Section XI Inspection Period: Third Next Examination: U1C15 or 03/22/2008 which every occurs first Volumetric or Surface Examination Cycle: Scheduled for U1C15, must be performed prior to 2/11/2008 Examination Date: To be performed ASME Section Xl Inspection interval: Third ASME Section Xl Inspection Period: First Next Examination: U1C19 or seven years from the U1C15 examination which ever occurs first

References:

1. NRC Order EA-03-009, Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head at Pressurized Water Reactors, dated February 11, 2003 and revised February 20, 2004.

2. Letter from Nuclear Institute (NEI) to NEI Administrative Points of Contact, "NRC Meeting on PWR Reactor Pressure Vessel Head Inspection Order",

dated February 25, 2003.

3. S64 020402 801

4. B38 020627 800

5. B38 030623 802

6. B38 040708 800

7. B38 040817 800

8. SPP-9.7

9. NRC Bulletin 2002-01

SON . AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT107 Unit I Effective Date: 06-01-20)06 Page 26 of 41 13.0 REACTOR COOLANT PUMP SHAFTS Responsible Organization: Component Engineering The RCP shaft augmented examination requirements are in accordance with an augmented examination request from Component Engineering dated November 26, 2002. The augmented examination was developed because of the two previous instances of RCP shaft cracking at SQN. The augmented RCP shaft examinations will be performed each refueling outage beginning with the U1 C12 refueling outage.

LUltrasonic examinations will be performed in accordance with NDE procedure N-UT-80 and/or N-UT-83. The entire length of the pump shaft from the top surface of the shaft is to be examined. A graphic illustration of the ultrasonic responses from the shaft at 90 degree increments shall be provided for information. This is not a qualitative examination. The type of flaws anticipated are shaft cracks due to high cycle fatigue. The area most highly suspected to contain the flaws are approximately 118 inches from the top of the shaft at the pin hole locations where the thermal sleeve is secured. The probability of a flaw existing is unknown.

Examination results and any examination limitations shall be submitted to Component Engineering. Report any indication of cracking to Component Engineering immediately. The results of these examinations shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7

References:

1. S57 021126 800

2. S57-060307 800

SCN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT10 Unrit I Effective Date: 06-01-21)06 Page 27 of 41 14.0 EXAMINATION OF ALLOY 600 AND ALLOY 82/182 POTENTIAL LEAK LOCATIONS IN PRIMARY COMPONENTS Responsible Organization: Mechanical Design VWCAP-1 5988-NP has identified generic guidance in developing plant-specific Boric Acid Corrosion Control Programs (BACCP) and procedures. As part of the guidance, PWSCC susceptible Alloy 600 and Alloy 82/182 weld locations in borated systems were identified as a potential leakage path.

Starting in the first period of the third ISI interval, TVA will perform augmented ultrasonic examinations of the areas listed below for Alloy 600/ Alloy 82/182 locations, unless otherwise revised or waived by Mechanical Design. Additional welds and/or examination techniques may be added by Mechanical Design where further evaluations indicate a potential susceptibility. See additional examinations for MRP 2003-039 and NRC Bulletin 2004-01 below.

Examinations of circumferential (dissimilar metal) butt welds shall be performec by the ultrasonic (UT) examination method using techniques and procedures developed under the Performance Demonstration Initiative (PDI). Because of the inherent difficulty in detection of flaws in dissimilar metal welds, the extent of examination shall include the complete weld volume, butter material, and base material for a distance of 1/4 inch from each weld toe or butter interface. Any examination limitations should be noted on the examination report.

If credit will be taken for the RI-ISI Program (Examination Category R-A), the extent of examination shall be increased. The extent of examination for Examination Category R-A shall include the complete weld volume, butter material, and base material for a distance of 1/2 inch beyond each side of the base metal thickness transition or counterbore. For examination category R-A piping welds with no transition or counterbore on the ID, the exam volume shall be increased to include 1/2 inch beyond the weld toe or butter interface.

The type of flaw anticipated is stress corrosion cracking.

The UT acceptance criteria for circumferential butt welds shall be in accordance with ASME Section Xl, 2001 Edition through the 2003 Addenda, IWB-3514, for Class I welds.

SCIN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 AT110 Unit 1 Effective Date: 06-01-2006 Page 28 of 41 14.0 EXAMINATION OF ALLOY 600 AND ALLOY 82/182 POTENTIAL L.EAK LOCATIONS IN PRIMARY COMPONENTS (continued)

Component Alloy 600/ 82/182 Location Method PRZ Nozzle to (see note below) Vessel Weld RCW-24-SE Spray nozzle to safe end UT RCW-15

__ weld RCW-25-SE Safety nozzle to safe end UT RCW-16 weld RCW-26-SE Relief nozzle to safe end UT RCW-17

____ __ weld -

RCW-27-SE Safety nozzle to safe end UT RCW-18

__ weld RCW-28-SE Safety nozzle to safe end UT RCW-19

__ weld RCW-29-SE Surge nozzle to safe end UT RCW-21

____ weld .

NOTE The components specified should be scheduled for examination in conjunction with the adjoining Pressurizer Nozzle to Vessel weld (Exam Category B-D, Item No., B3. 1.1 0).

IVA will perform additional examinations per MRP 2003-039 "Recommendation for Inspection of Alloy 600/82/182 Pressure Boundary Components" and NRC Bulletin 2004-01 "Inspection of Alloy 82/182/600 Material Used in the Fabrication of Pressurizer Penetration and Steam Space Piping Connections at Pressurized Water Reactors". Nozzle/safe ends on the pressurizer safety, spray, relief and surge nozzles shall be visually examined beginning with cycle 13 and each subsequent outage until nozzle weld overlays are completed. The visual examination method is an enhanced VT-2 supplemented with additional examination methods deemed necessary by Mechanical Engineering where indications of leakage are noted as "suspect". The areas of leakage shall be reported to Mechanical Engineering for evaluation. The type of flaw anticipated is stress corrosion cracking resulting from exposure to primary water chemistry. The area most likely to contain flaws are the alloy 600/82/182 materials used at the pressurizer nozzle/safe end interface of the Surge nozzle (1), spray nozzle (1), relief nozzle (1), and safety nozzles (3). The probability of a flaw existing is low.

The results of examinations shall be submitted to SQN Mechanical Design for evaluation and trending. The results of this examination shall be included in the ISI site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7.

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTi10 Uni:I1 Effective Date: 06-01-2006 Page 29 of 41 14.0 EXAMINATION OF ALLOY 600 AND ALLOY 82/182 POTENTIAL LEAK LOCATIONS IN PRIMARY COMPONENTS (continued)

References:

1. B38 030623 801

2. B38 040318 808

3. B38 040719 800

4. WCAP-15988-NP

5. MRP 2003-039

6. NRC Bulletin 2004-01

7. ASME Section XI 2001 Edition 2003 Addenda

8. B38 051209 800

SON AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATri Unit 1 Effective Date: 06-01-2006

. Page 30 of 41 15.0 EXAMINATION OF REACTOR VESSEL HEAD VENT PIPE Responsible Organization: Civil Engineering During the Unit 1, Cycle 12 refueling outage, the Reactor Head Vent Line was visually examined and found to be deformed (bent). Reference 2 indicated that the bent vent pipe would maintain structural integrity for three additional cycles of operation up to cycle 15 refueling outage (Fall 2007).

1. Perform an augmented volumetric examination by using PT, UT, ECT or any combination of these techniques in the cycle 15 refueling outage. The extent of examination shall include from the nozzle J-weld at the RV head l.D.

through the head to the bottom of the 90 degree bend. This may be.

accomplished by utilizing PT, UT, ECT or any combination of these NDE techniques. Any indications evaluated to be cracking shall be reported.

2. In addition, perform a VT-1 inspection of the horizontal vent pipe section from the nozzle to the RV head ventilation shroud including the 90 degree bend above the nozzle in cycle 15 refueling outage. Any indications evaluated to be cracking shall be reported.

Civil Design may elect to extend the inspection interval provided the proper analysis is completed. The extent and areas to be examined may be revised or waived by Civil Design. Additional examination techniques may be added with the consent of Civil Design where further evaluations indicate a potential susceptibility.

The results of examinations shall be submitted to SQN Civil Design for evaluation and trending. The results of this examination shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-114.3, Section 7.7.

NOTES

1) The gross visual inspection through existing openings in the CRD cooling shroud above the reactor vessel head insulation, as discussed in reference 4, is being performed during PM 040851000 and is not being maintained under this augmented program.

2) The gross visual remote video inspection on the portion of the vent line from the head penetration to the bottom of the insulation as discussed in reference 4 is being performed under work orders 03-016266-000 (UIC13) and 03-016267-000 (UIC14) and is not being maintained under this augmented program.

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTI1 Unit: I Effective Date: 06-01-2006 Page 31 of 41

Reference:

I. Request for Augmented Nondestructive Examination (NDE) dated 5/26/03 (B39 030529 001)

2. Westinghouse Letter TVA-03-60, dated 5/13/03

3. PER 03-003991-000

4. B38 031029 802

5. B38 031029 801

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTIO Unit: I Effective Date: 06-01-2006 Page 32 of 41 16.0 REACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS Responsible Organization: Mechanical Design In response to NRC Bulletin 2003-02 for potential leakage from reactor pressure vessel lower head penetrations and the reactor coolant pressure boundary, the RPV lcwer head and lower head penetrations are to be examined per the schedule below.

These examinations may be increased based on the industry experience and/o, regulatory commitments.

. A Bare Metal Visual (BMV) of 100% of the RPV lower head/ penetrations interface surface (including 360 degrees around each RPV lower head penetration) will be performed starting in Unit 1 cycle 13 and every refueling outage thereafter. The examination method is a visual examination (enhanced VT-2) in accordance with N-VT-17 supplemented with additional examination methods deemed necessary by Mechanical Engineering where indications of leakage are noted as "suspect". SQN is to notify the NRC staff in writing of any changes to this requirement commitment prior to implementation.

The areas of leakage shall be reported to Mechanical Engineering for evaluation.

The type of flaw anticipated is stress corrosion cracking resulting from exposure to primary water chemistry.

The area most likely to contain flaws are the lower head incore instrument penetration nozzle base material and areas adjacent to the nozzle interface witi the FRPV lower head base material. The probability of a flaw existing is low.

Examination results and any examination limitations shall be submitted to Mechanical Engineering for evaluation and trending. The results of these examinations shall be included in the ISI Site Final Report discussed in C-SI-DXI-000-1 14.3, Section 7.7.

NOTE During Unit 1 cycle 12 a remote visual (VT) examination was performed on the outside surface of the RPV lower head and thimble tube instrumentation penetrations. This report was filed with the Unit 1 cycle 12 site final report.

SON AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT10 Unit 1 Effective Date: 06-01-2006 Page 33 of 41

References:

'I. NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity, dated August 21, 2003

2. Request for Augmented Nondestructive Examination (NDE) Form, dated 10/31/03 (B38 031031 800)

3. PER 03-01084-000 4 L44 050928 092

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTIO Unil: 1 Effective Date: 06-01-2006 Page 34 of 41 AUGMENTED EXAMINATION TABLE A

. FIRST PERIOD SECOND PERIOD THIRD PERIOD COMPONENT PROGRAM EXAM CYCLE CYCLE CYCLE CYCLE CYCLE CYCLE REFERENCE REFERENCE METHOD 15 16 17 18 19 20 DRAWING SECTION NUMBER Feedwater/Auxiliary 1.0 UT X X X X CHM-2339-C Feedwater 4-inch Reducer-to-Pipe welds and the Associated Base Metal Loops 2 and 4 (AFWF-172 and AFWF-150) ' _

Feedwater/Aux liary 1.0 UT X X X CHM-2339-C Feedwater4inch Reducer-to-Pip~

welds and the Associated Base Metal Loops 1 and 3 (AFWF-148 and AFWF-1 88)

Reactor Coolant 2.0 UT, MT see see see see note see X ISI-0305-B Pump Flywheel note note note note see ISI-0403-C note Note: see drawing for examination schedule RPV Nozzle 3.0 UT X ISI-0504-C Cladding Control Rod Guide 4.0 N/A ISI-0504-C-10 Tubes Flexuress see note 1 Thimble Tube Guide 5.0 ET X X X X X X ISI-0504-C-14 Examination of 6.0 Piping Connecled to the Reactor Ccolant System Due to thermal Stressess .

Examination of 6.0 UT X X X CHM-2335-C-1 Circumferentia' Welds 1-CVCF-246, 1-CVCS-414, End fitting 1-CVCF-246/CVCS-414 EL ___

Examination of 6.0 UT X X X CHM-2335-C-1 Circumferential Welds 1-CVCF-213, 1-CVCF-214, aind fitting 1-CVCF-213/214 EL Examination o' 6.0 UT X ISI-0482-C-1 Circumferential Weld RC-33 _ _

Examination of 6.0 UT X ISI-0482-C-1 Circumferential W eld RC-35 _ _ _ _ _ _ _ _ __ _ _ _ _ _ _.___ _ _ _ _

SC!N AUGMENTED EXAMINATIONS (UNIT 1) O-SI-DXI-000-1 14.3 ATTI0 Unit 1 Effective Date: 06-01-2006 Page 35 of 41 AUGMENTED EXAMINATION TABLE A FIRST PERIOD SECOND PERIOD THIRD PERIOD COMPONENT PROGRAM EXAM CYCLE CYCLE CYCLE CYCLE CYCLE CYCLE REFERENCE REFERENCE METHOD 15 16 17 18 19 20 DRAWING SECTION NUMBER Examination of 6.0 UT X X X CHM-2333-C-1 Socket Welds 1-SI-1605, 1-SI-1606, and 1-SI-1607 Examination of 6.0 UT X X X CHM-2333-C-2 Socket Welds 1-SI-161 0, 1-SI-1611, and 1-SI-1 612 _ _ _

Examination of 6.0 UT X X X CHM-2333-C-2 Socket Welds 1-SI-1692, 1-SI-1693, and 1-SI-1694 Examination of 6.0 UT X X .X CHM-2333-C-1 Socket Welds I-SI-1697, 1-SI-1698, and 1-SI-i699 .

Examination of 6.0 UT X X X X X X CHM-2335-C-1 Socket Welds 1-CVC-2599, 1-CVC-2600, and 1-CVC-2601 PRZ Relief line 7.0 UT X ISI-0369-C-3 repair Welds and adjoining areas.

RCF-24P and RCF-24H . ._._. _

Safety Injection and 8.0 N/A CHM-2333-C RHR Welds and see note 1 CHM-2336-C Adjoining Area a 1-RSRF-107, 1-SIF-1 46, 1-SIF-185, 1-SIF-196, and 1-SIF-198

.. 8.0 UT X CHM-2333-C-3 Safety Injection and . CHM-2333-C-6 RHR Welds and CM23--

Adjoining Area i CHM-2336C-3 RHRF-018 CHM-2336-C-5 RHRF-022, ISI-0434-C-5 RHRF-057, RHRF-066, SIF-002, SIF-)05, SIF-029, SIF-031, and SIF-088 Reactor Coolant 9.0 N/A see ISI-0325-C-1 Pump Support note 1 RCP# 1 2 3 and4 Steam Generator 10.0 NIA see ISI-0399-C-2 Class 2 Upper note 1 Support SG# 1,2, 3and 4

SON AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTIO Unit 1 Effective Date: 06-01-21306 Page 36 of 41 .

AUGMENTED EXAMINATION TABLE A FIRST PERIOD SECOND PERIOD THIRD PERIOD COMPONENT PROGRAM EXAM CYCLE CYCLE CYCLE CYCLE CYCLE CYCLE REFERENCE REFERENCE METHOD 15 16 17 18 19 20 DRAWING SECTION NUMBER Examination of 11.0 UT X CHM-2333-C-3 circumferential and CHM-2336-C-3 longitudinal welds due to SER 00-001 RHRF-041 RHRS-072 RHRS-071-LS RHRS-073 RHRF-065 RHRS-072-LS RHRS-073-LS SIF-007 RHRS-100-LS SIF-001 RHRS-065-LS RPV closure head 12.0 VT-2 X . ISI-0504-C-10 and closure head Enhanced penetrations (BMV) .

RPV closure head 12.0 UTor ECT X See ISI-0504-C-10 and closure head and/or PT note penetrations or combination of UT, PT and ECT .

Reactor Coolant 13.0 UT X X X X X X ISI-0325-C-3 Pump Shafts .

Alloy 600 and Alloy 14.0 82/182 Potential Leak Locations in Primary Components .

RCW-24-SE 14.0 UT 15 or 15 or 16 Note: to be RCW-29-SE 16 examined with the nozzle to

._ vessel weld RCW-25-SE 14.0 UT 17 or 17 or 18 Note: to be RCW-26-SE 18 examined with the nozzle to vessel weld RCW-27-SE 14.0 UT 19 or 19 or Note: to be RCW-28-SE 20 20 examined with the nozzle to vessel weld RCW-24-SE 14.0 VT-2 X X X X X X ISI-0394-C-01 RCW-25-SE Enhanced RCW-26-SE RCW-27-SE RCW-28-SE . . _

RCW-29-SE 14.0 VT-2 X X X X X X ISI-0394-C-01 Enhanced Reactor Vesse 15.0 PT, UT or X ISI-0504-C- 1I Head Vent Pipe ECT VENT-1 P . . . _

Reactor Vesse - 15.0 VT-1 X ISI-0504-C-1 1 Head Vent Pipe VENT-1P _P Reactor Vesse 16.0 VT-2 X X X X X X ISI-0504-C-14 Lower Head Enhanced I._____

SON AUGMENTEDEXAMINATIONS (UNIT 1) O-SI-DXI-000-114.3 ATT10 Unit 1 Effective Date: 06-01-21)06 Page 37 of 41 NOTE

1. No augmented examinations are being performed in the third interval.

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTIO Unit 1 Effective Date: 06-01-2006 Page 38 of 41 AUGMENTED EXAMINATIONS TABLE B The welds/components in this table, unless otherwise stated, have been reviewed for augmented examinations in the RI-ISI program. Any examination schedule or method changes for these welds are to be submitted for incorporation in the RI*.ISI periodic and interval updates. Refer to calculation CN-RRA-00-56.

PROGRAM WELD FAILURE EXAM EXAM RI-ISI COMMENTS REFERENCE MECHANISM METHOD FREQUENCY SEGMENT SECTION FOR THE AUGMENTED PROGRAM 1.0 AFWF-172 thermal fatigue UT continuous FW-002 see note 2 (each even numbered outage) 1.0 AFWF-150 thermal fatigue UT continuous AF-022 see note 2 (each even numbered outage) 1.0 AFWF-148 thermal fatigue UT continuous AF-021 see note 2 (each odd numbered

__ outage) 1.0 AFWF-188 thermal fatigue UT continuous FW-003 see note 2 (each odd numbered outage) 6.0 1-CVCF-246 thermal strat UT continuous CH-018 see note 2 (each even numbered outage) 6.0 1-CVCS-414 thermal strat UT continuous CH-018 see note 2 (each even

.n numbered outage) 6.0 1-CVCF-246/ thermal strat UT continuous CH-018 see note 2 CVCS-414 EL (each even numbered outage) 6.0 1-CVCF-213 thermal strat UT continuous CH-019 see note 2 (each odd numbered outage) 6.0 1-CVCF-214 thermal strat UT continuous CH-019 see note 2 (each odd numbered outage) 6.0 1-CVCF-213/ thermal strat UT continuous CH-019 see note 2 214 EL (each odd numbered

_ _ outage) 6.0 RC-33 thermal strat UT continuous RC-039 see note 3 (every forth outage beginning with RO

_ _ _ _ _ __ _ __ _ __ _ __ _ __ _ _ _ _ _1 0) _ _ _ _ _ _

6.0 RC-35 thermal strat UT continuous RC-039 see note 3 (every forth outage beginning with RO

__ . 12) 6.0 1-SI-1605 thermal strat UT continuous SI-069 see note 4 (each odd numbered

_ outage) _

1-SI-1606 thermal strat UT continuous SI-069 see note 4 6.0 (each odd numbered

_ outage) I

SON AUGMENTED EXAMINATIONS (UNIT 1) O-SI-DXI-000-114.3 ATT710 Unit I Effective Date: 06-01-20306 Page 39 of 41 AUGMENTED EXAMINATIONS TABLE B PROGRAM WELD FAILURE EXAM EXAM RI-ISI COMMENTS REFERENCE MECHANISM METHOD FREQUENCY SEGMENT SECTION FOR THE AUGMENTED PROGRAM 6.0 1-SI-1607 thermal strat UT continuous SI-069 see note 4 (each odd numbered

_ _ outage) 6.0 1-SI-1610 thermal strat UT continuous SI-070 see note 4 (each even

_ numbered n_ outage) 6.0 1-Si-1611 thermal strat UT continuous St-070 see note 4 (each even numbered outage) 6.0 1-SI-1612 thermal strat UT continuous SI-070 see note 4 (each even numbered outage) 6.0 1-SI-1692 thermal strat UT continuous SI-071 see note 4 (each odd numbered

__ . outage) 6.0 1-SI-1693 thermal strat UT continuous SI-071 see note 4 (each odd numbered

_ ._ outage) 6.0 1-SI-1694 thermal strat UT . continuous SI-071 see note 4 (each odd numbered

__ . outage) 6.0 1-SI-1697 thermal.strat UT continuous SI-072 see note 4 (each even

.n numbered outage) 6.0 1-SI-1698 thermal strat UT continuous SI-072 see note 4 (each even

__ numbered outage) 6.0 1-SI-1699 thermal strat UT continuous SI-072 see note 4 (each even numbered outage) .

6.0 1-CVC-2599 thermal strat UT continuous CH-020 see note 2 (each outage) 6.0 I-CVC-2600 thermal strat UT continuous CH-020 see note 2 (each outage) 6.0 1-CVC-2601 thermal strat UT continuous CH-020 see note 2

._ (each outage) 7.0 RCF-24P IGSCC UT continuous RC-051 see note 2

. _ __ _(every 80 months) .

7.0 RCF-24H IGSCC UT continuous RC-051 see note 2 (every 80 months) 8.0 1-RHRF-107 N/A N/A N/A SI-056A see note 1 8.0 1-SIF-146 N/A N/A N/A SI-005 see note 1 8.0 I-SIF-185 N/A N/A N/A SI-007 see note 1 8.0 1-SIF-196 N/A N/A N/A SI-057A see note 1 8.0 1-SlF-198 N/A N/A N/A Sl-052 see note 1 8.0 RHRF-018 IGSCC UT RO 13 8 15 RH-004 see note 3 8.0 RHRF-022 IGSCC UT R013 & 15 RH-004 see note 3

SCN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATT10 Unit 1 Effective Date: 06-01-2,006 Page 40 of 41 AUGMENTED EXAMINATIONS TABLE B PROGRAM WELD FAILURE EXAM EXAM RI-ISI COMMENTS REFERENCE MECHANISM METHOD FREQUENCY SEGMENT SECTION FOR THE AUGMENTED PROGRAM 8.0 RHRF-057 IGSCC UT RO 13 & 16 RH-016 see note 2 8.0 RHRF-066 IGSCC UT RO 13 & 16 RH-017 see note 2 8.0 SIF-002 IGSCC UT RO 13 & 15 RH-015 see note 2 8.0 SIF-005 IGSCC UT RO 13 & 15 SI-024A see note 2 8.0 SIF-006 IGSCC N/A INACCESSIBLE SI-024A see note 7 8.0 SIF-015 IGSCC N/A INACCESSIBLE SI-023A see note 7 8.0 SIF-029 IGSCC UT RO 13 & 16 SI-047C see note 3 8.0 SIF-031 IGSCC UT RO 13 & 16 SI-049 see note 3 8,0 SIF-088 IGSCC UT R013&16 . RH-013 see note 2 11.0 RHRF-041 thermal transient UT RO 11, 14, & 17 RH-017 see note 2

__ _ .__ fatigue .

11.0 RHRS-072 thermal transient UT RO 11, 14, & 17 RH-017 see note 2

_ __fatigue 11.0 RHRS-071-LS thermal transient UT RO 11, 14, & 17 RH-017 see note 2 fatigue .

11.0 RHRS-073 thermal transient UT RO 11,14, S 17 . RH-017 see note 2

___ __ fatigue .

11.0 RHRF-065 thermal transient UT RO 11, 14, & 17 RH-017 see note 2

___ _ _ fatigue .

11.0 RHRS-072-LS thermal transient UT RO 11, 14, & 17 RH-017 see note 2

_ _

____.fatigue .

11.0 RHRS-073-LS thermal transient UT RO 11, 14, e 17 RH-017 see note 2

_ _ _ fatigue 11.0 SIF-007 thermal transient UT RO 11, 14, & 17 RH-016 see note 6

_____ _ .fatigue

_ _ . .

11.0 RHRS-100-LS thermal transient UT RO 11,14, & 17 RH-016 see note 2

. __ __ _fatigue .

11.0 SIF-001 thermal transient UT RO 11, 14, & 17 RH-01 5 see note 6

__ _fatigue 11.0 RHRS-065-LS thermal transient UT RO 11, 14, & 17 RH-01 5 see note 2

_ __fatigue 14.0 RCW-24-SE PWSCC UT every 10 years RC-029 see note 2 14.0 RCW-24-SE PWSCC VT-2 RO 13 and each RC-029 see note 2 Enhanced subsequent outage 14.0 RCW-25-SE PWSCC UT every 10 years RC-047 see note 2 14.0 RCW-25-SE PWSCC VT-2 RO 13 and RC-047 see note 2 Enhanced each subsequent outage 14.0 RCW-26-SE PWSCC . UT every 10 years RC-051 see note 2 14.0 RCW-26-SE PWSCC VT-2 RO 13 and RC-051 see note 2 Enhanced each subsequent

__ _outage

SQN AUGMENTED EXAMINATIONS (UNIT 1) 0-SI-DXI-000-114.3 ATTI0 Unit I Effective Date: 06-01-2006 Page 41 of 41 AUGMENTED EXAMINATIONS TABLE B PROGRAM WELD FAILURE EXAM EXAM RI-ISI COMMENTS REFERENCE MECHANISM METHOD FREQUENCY SEGMENT SECTION FOR THE AUGMENTED PROGRAM 14.0 RCW-27-SE PWSCC UT every 10 years RC-049 see note 2 14.0 RCW-27-SE PWSCC Vr-2 RO 13 and RC-049 see note 2 Enhanced each subsequent

____ ___ ____ __ ____ ___ outage 14.0 RCW-28-SE PWSCC UT every 10 years RC-048 see note 2 14.0 RCW-28-SE PWSCC VT-2 RO 13 and RC-048 see note 2 Enhanced each subsequent

.o outage 14.0 RCW-29-SE PWSCC UT every 10 years RC-039 see note 4 14.0 RCW-29-SE PWSCC VT-2 RO 13 and each RC-039 see note 8 Enhanced subsequent outage 15.0 Reactor mechanical PTIUT/ETI RO 15 RC-035 see note 2 Vessel Head VT-1 Vent Pipe

_ VENT-1 P .

NOTES

1) Augmented examination completed. No further credit to be taken in the RI-ISI program following the second period of the second interval.,

2) Low safety significant segment, examined for augmented examination credit only.

3) High safety significant segment, examined for RI-ISI and augmented examination credit.

4) High safety significant segment, this examination for augmented examination credit only.

5) Note 5 not used.

6) Low safety significant segment, examined for RI-ISI (delta .risk) and for augmented examination credit.

7) Low safety significant segment, welds identified as inaccessible for examination in UIC13.

8) Examination for RI-ISI credit for R014 and later is to be addressed in the next RI-ISI update for the third interval, second period. Credit is being taken only for the augmented examination in cycle 14 and later.

SQW AUGMENTED EXAMINATIONS (UNIT 2) O-SI-DXI-000-114.3 ATTH]l Unit 2 Effective Date: 06-01-2006 Page 1 of 41 ATTACHMENT 11 - Augmented Examinations (Unit 2)

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATT11 Unit 2 Effective Date: 06-01-2006 Page 2 of 41 AUGMENTED EXAMINATIONS Augmented examinations are performed in addition to ASME Section Xl code requirements. The augmented examinations may be required by the NRC or be self-imposed by TVA. Typical sources include generic letters, IE Bulletins, technical specifications, vendor recommendations, and industry experience. Table A of this attachment provides a schedule for augmented examinations. Responsible o ganizations requesting inclusion of augmented examinations in this section shall submit a written request to the Component Engineering representative (see 0-SI-DXI-000-114.3, Section 7.11).

Table B of this attachment identifies the augmented piping welds/components Lnder the RI-ISI program, the failure mechanism and if credit is being taken for the examination being performed in accordance with this attachment.

1.0 FEEDWATER NOZZLE-TO-PIPE WELDS AND ADJACENT PIPE/FITTINGS AND NOZZLE AREAS/AUXILIARY FEEDWATER Responsible Organization: Mechanical Design Clue to the safety-related ramifications and the assessments concluded in Incident Investigation (II) No. 1I-S-92-027 of the steam generator nozzle transition section cracking problem and potential for cracking in adjacent components within the feedwater piping system, TVA will perform augmented examinations as determined by Mechanical Design. This shall include the four feedwater nozzle transition pieces and associated piping components with inspections being performed during the intervals as listed below.

The augmented examination of the steam generator nozzle transition and feedvater piping shall include 100 percent volume of the transition pieces, the nozzle-to-transition piece welds, transition piece-to-elbow welds, 41-inch feedwater/auxiliary feedwater tee-to-pipe welds, and base metal adjacent to each weld for a distance of two wall thicknesses. These welds shall be volumetrically examined by the ultrasonic method and supplemented with radiographic examination when specified by Mechanical Design.

starting with revision 0 of this procedure for the third interval, the Ultrasonic acceptance criteria shall be in accordance with ASME Section Xl 2001 Edition 2003

/Addenda, IWC-3514, for Class 2 welds.

The results of the examination will be submitted to Mechanical Design for evaluation and trending of flaw sizes and growth rates. The results of this examination shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 77.

Inspection of the transition pieces, nozzle-to-transition piece welds, transition piece-to-elbow welds, and the associated base metal shall be scheduled for inspection at each consecutive refueling outage unless otherwise revised or waived by Mechanical Design.

SON AUGMENTEDEXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATTll Unit 2 Effective Date: 06-01-2006 Page 3 of 41 1.0 FEEDWATER NOZZLE-TO-PIPE WELDS AND ADJACENT PIPE/FITTINGS AND NOZZLE AREAS/AUXILIARY FEEDWATER (continued)

Inspection of the 4-inch feedwater/auxiliary feedwater reducer-to-pipe welds and the associated base metal shall be to the following schedule unless otherwise revised or waived by Mech/Nuc Engineering.

Loop 2 is to be inspected each outage. Initial inspection performed during Cycle 6 refueling outage.

Loops 4 is to be inspected each even numbered outage. Initial inspection performed during Cycle 6 Refueling Outage.

Loops 1 and 3 are to be inspected each odd numbered outage beginning with the Cycle 7 Refueling Outage.

Feedwater loops that have been replaced with the feedwater thermal liner during and after Unit 2 Cycle 6 will be examined to ASME Section Xl requirements wit: no additional examination requirements or examination volume coverage. Feedwater loops 2.and 3 have been replaced. Welds to be examined are nozzle-to-elbow elbow-to-thermal liner adapter, and thermal liner adapter to pipe weld. Additional examinations may be required by Mechanical Design where further evaluation indicates a potential for cracking in this area of piping.

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATT11 Unit 2 Effective Date: 06-01-2006 Page 4 of 41 1.0 FEEDWATER NOZZLE-TO-PIPE WELDS AND ADJACENT PIPE/FITTINGS AND NOZZLE AREAS/AUXILIARY FEEDWATER (continued)

FEEDWATER NOZZLE TRANSITION PIECE EXAM SCHEDULE The following is a summary of the examinations conducted during successive cycles.

The requirements of NRC IE Bulletin 79-13 were satisfied during the Unit 2 Cycle 1 outage.

Cycle Examination Areas 1 IE Bulletin 79-13 completed 2 1 nozzle-to-pipe weld and adjacent pipe and nozzle area 3 All nozzle transition section pieces and welds 4 All nozzle transition section pieces and welds 5 All nozzle transition section pieces and welds 6 All nozzle transition section pieces and welds for loops 1 and 4.

Loops 2 and 3 replaced in U2C6.

7 All nozzle transition section pieces and welds for loops 1 and 1*

8 All nozzle transition section pieces and welds for loops I and z*

9 All nozzle transition section pieces and welds for loops 1 and L.

10 All nozzle transition section pieces and welds for loops 1 and 4.

11 All nozzle transition section pieces and welds for loops 1 and 4.

12 All nozzle transition section pieces and welds for loops 1 and 4.

13 All nozzle transition section pieces and welds for loops 1 and 4.

References:

1. Incident Investigation (II) No. 1I-S-92-027

2. ASME Section Xl 2001 Edition 2003 Addenda

3. NRC Bulletin 79-13

SCN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATTH7 Unit 2 Effective Date: 06-01-2D06 Page 5 of 41 2.0 REACTOR COOLANT PUMP FLYWHEEL Fesponsible Organization: Mechanical Design The augmented examination requirements of the reactor coolant pump flywheel are included in Regulatory Position C.4.b of Regulatory Guide 1.14; (1) an in-place ultrasonic examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals during the refueling or maintenance shutdown coinciding with the ISI schedule as required by Section Xi of the ASMIE C:ode, and (2) a surface examination of all exposed surfaces (exposed areas are considered as those areas accessible for examination without having to remove the flywheel from the housing) and complete ultrasonic examination at approximately 10-year intervals during the plant shutdown coinciding with the ISI schedule as required by Section Xl of the ASME Code (in the event that the motor housing is removed for shop rework, a complete surface and ultrasonic volumetric examination shall be performed). In lieu of Regulatory Guide 1.14 Position C.4.b(1) and C.L.b(2),

a qualified in-place ultrasonic examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (magnetic particle arnd/or liquid penetrant) of exposed surfaces of the removed flywheels may be conducted at approximately 10-year intervals coinciding with the Inservice Inspection schedule as required by ASME Section Xl per Technical Specification Change TS-01 -13. Starting with revision 21 of this procedure the 10-year interval was changed to 20-year intervals per Technical Specification Change TS-04-02.

This examination is performed in accordance with SQN Technical Specifications and satisfies Surveillance Requirement 4.0.5.c.

This augmented examination does NOT require a special report unless the examination reveals a flaw. The acceptance criteria should be equivalent to those specified for the class 1 vessels in the ASME B&PV Code Section III as stated in the FSAR subsection 5.2.6. If the examination and evaluation indicate an increase in flaw size or growth rate greater than predicted for the service life of the flywheel, the results of the examination and evaluation should be submitted to Engineering and the NRC for evaluation. Refer to Regulatory Guide 1.14 for information to be included. The examination results shall be included in the ISI Site Final Report ciscussed in 0-SI-DXI-000-114.3, Section 7.7.

The flywheel consists of 2 plates, approximately 5 inches and 8 inches thick, bolted together. Each plate is fabricated from vacuum degassed A-533, GR. B, Class 1, steel.

For the 20-year exam, the IDs shall be:

RCP Motor SIN - SUR (i.e., 4S-81 P352 - SUR)

RCP Motor S/N - VOL (i.e., 4S-81 P352 - VOL)

SCN AUGMENTED EXAMINATIONS (UNIT 2) O-SI-DXI-000-114.3 ATT'l Unit 2 Effective Date: 06-01-2D06 Page 6 of 41 2.0 REACTOR COOLANT PUMP FLYWHEEL (continued)

References:

1. Regulatory Guide 1.14

2. Technical Specification TS-01 -13

3. Technical Specification TS-04-02

4. FSAR Subsection 5.2.6

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATITll Unit 2 Effective Date: 06-01-2D06 Page 7 of 41 3.0 FRPV NOZZLE CLADDING Responsible Organization: Mechanical Design By memorandum from David E. Labarge NRC to O.D. Kingsley, TVA dated March 15, 1994 (L44 940322 006) Sequoyah Nuclear Plant, Units 1 and 2 Technical Specifications Requirement 4.4.10.b were amended to remove Surveillance Requirement 4.4.10.b [C.1]. The amendments remove the surveillance requirement to perform reactor vessel nozzle inspections at the end of each 10-year inspection interval subject to the commitments to perform the augmented ISI examination as stated below.

TVA has committed to the following requirements:

1. The volumetric examinations of the reactor pressure vessel nozzles will be performed over the same cladded nozzle areas required by American Society of Mechanical Engineers Code. [C.1]

2. The ultrasonic technique for the Unit 2 Cycle 6 refueling outage examinations and future examinations will be at least as sensitive as that used to conduct the examinations during the Unit 1 Cycle 6 refueling outage. [C.1]

3. The examinations to be performed during the Unit 2 Cycle 6 refueling outage will serve as the baseline for future examinations. [C. 1]

4. All of the detected flaws will be sized regardless of the percent Distance Amplitude Correction Curve (DAC). [C.1]

5. The results of the examination will be submitted to NRC. [C.1]

6. The above commitments will NOT be removed from the Unit 2, ISI program without notifying NRC. [C.I]

IVA performed a second examination of the Unit 2 reactor vessel nozzle cladding curing U2C13 at the end of SQN second 10-year ISI interval. The extent of examination was the length and depth sizing of all the flaws identified during the previous examination in U2C6 using a NDE procedure qualified in accordance with ASME Section Xl, Appendix VIII, Supplement 4. (Refer To B38 050412 800)

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATTIT Unilt 2 Effective Date: 06-01-2006 Page 8 of 41 3.0 RPV NOZZLE CLADDING (continued)

The Unit 2 augmented RPV nozzle cladding examinations cannot be deleted from the ISI Program unless NRC approval is obtained through the de-commitment process as defined in SPP-3.3. TVA plans to submit a request to NRC to de-commit from these requirements following the unit 1 cycle 14 (U1C14) refueling outage.

This augmented examination does NOT require a special report. The results of this examination shall be submitted to SQN Mechanical-design for evaluation and trending. Results of the examination shall be reported to the NRC via the ISI Summary Report discussed in 0-SI-DXI-000-114.3, Section 7.7.

A special preservice examination of the reactor vessel nozzles was conducted lo evaluate the extent of underclad cracking. The examination utilized a 700 angle beam and 00 beam manual contact technique. All indications found were demonstrated to be acceptable in accordance with ASME Code Section Xl criteria.

(Reference FSAR Section 5.4.4.1)

References:

1. Technical Specification 4.4.10. b

2. SPP-3.3

3. L44 940322 006

4. B38 050412 800

5. FSAR 5.4.4.1

SCQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATTTV]

Unit 2 l Effective Date: 06-01-2006 Page 9 of 41 4.0 CONTROL ROD GUIDE TUBE FLEXURES Responsible Organization: Mechanical Design No augmented examinations are being performed on the control rod guide tube flexures in the third interval. This section is being maintained for history only in the third interval.

Due to the removal of the control rod guide tube flexures during the split pin replacement during the U2Cl 1 (DCN D20920A), this augmented examination is no longer required. The following information is being retained for- history during this interval.

Due to the potential of intergranular stress corrosion cracking of guide tube flexures, the control rod guide tube flexure augmented examination plan was initiated during the first inspection interval (see Westinghouse reference memorandums A27 840123 022 and L01 840723 035).

The control rod guide tube flexures shall be visually examined in accordance with visual examination method VT-3 during the second 10 year ISI inspection interval vessel interior examination, (Examination Category B-N-1), coincident, when the core barrel is removed (Examination Category B-N-3). If any flexure heads are discovered to be broken from their stems, the heads should be retrieved and flexureless inserts installed. If flexureless inserts are NOT installed after a break has occurred, a safety evaluation shall be required to confirm continued safe plant operation. A copy of the VT data sheets shall be forwarded to the appropriate cognizant engineer.

The PRISIM identifiers for the control rod guide tube flexures are:

CRDTUBEFLEX - A07 CRDTUBEFLEX - E09 CRDTUBEFLEX - G05 CRDTUBEFLEX - Ji1 CRDTUBEFLEX -LOT This augmented examination is self-imposed by TVA and does NOT require a report.

References:

1. A27 840123 022

2.

L01 840723 035

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATT711 Unit 2 Effective Date: 06-01-2006 Page 10 of 41 5.0 THIMBLE TUBE GUIDE Responsible Organization: Systems Engineering- Instrument/Controls and Electrical (ICEf)

Background Information:

Clue to the potential thinning of thimble tube guides as reported on NRC Bulletin 88-09 and Information Notice No. 87-44 supplement 1, TVA performed an augmented examination of the thimble tubes using Eddy Current Examination (ET) during the Unit 2 Cycle 3 refueling outage. Background information documents (R. W. Fortenberry's July 21, 1988 memorandum to S. J. Smith (S57 880721 821) and J. F. Murdock's June 3,1988 memorandum to J. B. Hosmer (L29 880531 914), P. G. Trudel's February 27, 1989 memorandum to M. J. Burzynski (825 890227 002) and Design Change Notice Drawing Deviation F-07706-A (885 911107 124).

All thimble tubes shall be examined each refueling outage, unless otherwise revised or waived by ICE.

Organization performing examinations shall provide results to ICE and Component Engineering. Component Engineering is to include the results in the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7.

References:

1. S57 960208 934

2. B38 040322 801

3. NRC Bulletin 88-09

4. Information Notice No. 87-44

5. S57 880721 821

6. L29 880531 914

7. B25 890227 002

8. B85 911107 124

SON AUGMENTEDEXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATH]1 Unit 2 Effective Date: 06-01-2006 Page 11 of 41 6.0 EXAMINATION OF PIPING CONNECTED TO THE REACTOR COOLANT SYSTEM DUE TO THERMAL STRESSES Responsible Organization: Mechanical Design In response to NRC Bulletin due to the potential thermal stresses on unisolable piping attached to the RCS (see NRC Bulletin 88-08), TVA examined the following areas: 1) the four 1.5-inch high head injection lines, 2) the 2-inch pressurizer spray line from the charging path, 3) the 3-inch alternate charging path, and 4) the 3-inch normal charging path. During Cycle 3 shutdown period all of the welds up to te first valve-were PT examined, and the 3-inch line was UT examined. The SQN Project Engineer prepared a report to Licensing, who in turn prepared a report to the NRC. (See memorandums B29 880906 008, S08 880830 843, L44 880824 802, and E825 880819 014.)

Due to the assessments concluded in Incident Investigation (II) No. II-S-92-027 of the steam generator nozzle transition section cracking problem and NRC Bulletin 88-08, similar conditions were evaluated for the Chemical and Volume Control System (CVCS), Safety Injection System (SIS) and Reactor Coolant System (RCS).

Potential for cracking in these systems, in particular the Alternate Charging Lina, are the cases that resulted in the cracking of welds at Farley (NRC Bulletin 88-08) and the elbow at Tihange (NRC Bulletin 88-08, Supplement 1). The thermal cycling stresses can be quite severe at these locations with leakage across the closed FCVs, and it is possible for a crack to initiate and grow substantially in a single fuel cycle.

As some of the fatigue crack mechanisms are much more likely than others to occur end result in crack development, a graded approach regarding examination frequency has been recommended by Mechanical Design. This graded approach couples the likelihood of occurrence with the severity of the postulated event. Some of these welds and adjacent base metal were baseline examined during the Unit 2 Cycle 5 outage due to the Unit 1 feedwater transition piece cracking problem.

IVA will perform augmented examinations of the areas noted during the intervals as listed below, unless otherwise revised or waived by Mechanical Design. Additional vields and/or examination techniques may be added by Mechanical Design where further evaluations indicate a potential for thermal stratification. (see memorandum E825 931129 001) Following U2C7, this section was revised on 03/17/1997 in the second interval to remove the supplemental PT examinations, replaced the PT examinations with a UT examination, and removed the socket welded fitting elbows 2-SI-1124/1125 ELBOW, 2-SI-1816A/1817A ELBOW, 2-SI-1895/1896 ELBOW, 2-SI-1 899/1900 ELBOW and 2-CVC-1 745/1746 ELBOW from the augmented section for examination.

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATT7 Unit 2 Effective Date: 06-01-21006 Page 12 of 41 6.0 EXAMINATION OF PIPING CONNECTED TO THE REACTOR COOLANT SYSTEM DUE TO THERMAL STRESSES (continued)

Examinations of circumferential butt welds shall be performed by the ultrasonic (UT) examination method. The extent of examination shall include the lower one-third volume of the welds and base metal adjacent to each weld for a distance of two wall thicknesses where accessible (fittings, elbow interdose, and valves may prevent full circumference examination).

Starting with revision 0 of this procedure, the UT acceptance criteria for circumferential butt welds shall be in accordance with ASME Section Xl, 2001 Edition 2003 Addenda, IWB-3514 and IWC-3514, for Class I and 2 welds, respectively.

Examination of pipe fittings shall be performed by the UT examination method. The extent of examination shall include the lower one-third volume of the fitting where accessible (Fitting geometry may prevent full examination).

Starting with revision 0 of this procedure, the UT acceptance criteria for the fittings shall be the same as for the adjacent circumferential butt welds in accordance with ASME Section Xl, 2001 Edition 2003 Addenda, IWB-3514 and IWC-3514, for Class 1 and 2 welds, respectively.

Examination of socket welds shall be performed by the UT examination method.

The extent of examination shall be as specified in the NDE procedure. SQN Mechanical Design shall determine the acceptability of any crack-like indications.

The results of examinations shall be submitted to SQN Mechanical Design for evaluation and trending. The results of this examination shall be included in the ISI site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7.

During the second and continuing in the third interval, examination of cold leg L.oop 1 and cold leg Loop 4 CVC (circumferential butt) welds and fittings shall be performed during the inspection interval as noted below.

Cold Leg loop 4 - Welds 2-CVCF-244E and 2-CVCF-244F, and fitting 2-CVCF-244E/244F EL: Examine each even numbered RFO beginning with RFO 8 of the second interval (initial examination performed during E/C forced outage during 1993).

Cold Leg Loop 1 - Welds 2-CVCF-213 and 2-CVCF-214, and fitting 2-CVCF-213/214 EL: Examine each odd numbered RFO beginning with RFO 7 of the second interval.

Examination of pressurizer surge line (circumferential butt welds), welds RC-33 and FRC-35 shall be performed during the inspection interval as noted below: (Reference NRC Bulletin 88-11.)

SCN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3AT 11 Unit 2 Effective Date: 06-01-2006 Page 13 of 41 6.0 EXAMINATION OF PIPING CONNECTED TO THE REACTOR COOLANT SYSTEM DUE TO THERMAL STRESSES (continued)

Pressurizer surge line, Weld RC-33, shall be examined every fourth refueling outage beginning with refueling outage 10 of the second interval.

Pressurizer surge line, Weld RC-35 shall be examined every fourth refueling outage beginning with refueling outage 12 of the second interval.

Examination of cold leg loops 1, 2, 3, and 4 SI sockets welds shall be performed during the inspection interval as noted below: - -

Cold Leg Loop I SI-1 124, 2-SI-1 125, and 2-SI-1 126: Examine each odd numbered RFO beginning with RFO 7 of the second interval (initial examination performed during E/C forced outage during 1993).

Cold Leg Loop 2- 2-SI-1816A, 2-SI-1817A, and 2-SI-1818A: Examine each even numbered RFO beginning with RFO 8 of the second interval (initial examination performed during E/C forced outage during 1993).

Cold Leg Loop 3-2-SI-1894, 2-SI-1895, and 2-SI-1896: Examine each odd numbered RFO beginning with RFO 7 of the second interval (initial examination performed during E/C forced outage during 1993).

Cold Leg Loop 4-2-SI-1899,2-SI-1900, and 2-SI-1901: Examine each even numbered RFO beginning with RFO 8 of the second interval (initial examination performed during E/C forced outage during 1993).

Auxiliary Spray line (CVC socket welds) 2-CVC-1 745, 2-CVC-1 746, and 2-CVC-1747 shall be examined each refueling outage beginning with RFO 8 of the second interval. Initial examinations were performed during RFO 6 and RFO 7 of the second interval.

References:

1. NRC Bulletin 88-08

2. NRC Bulletin 88-11

3. Incident Investigation (II) No. Il-S-92-027

4. B29 880906 008

5. S08 880830 843

6. L44 880824 802

7. B25 880819 014

8. B25 931129 001

9. ASME Section Xl 2001 Edition 2003 Addenda

SCN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATT'V]

Unit 2 Effective Date: 06-01-21306 Page 14 of 41 7.0 CENTRIFUGAL CHARGING PUMP INJECTION TANK (CCPIT)

(:2-TNK-63-7) WELD BIT-4 Responsible Organization: Civil Design By augmented NDE request from Civil Engineering dated July 2,1996, the Centrifugal Charging Pump Injection Tank (former Boron Injection Tank) is required to be examined due to additional pressure cycles added per DCN S09712)

In 1994, a planar flaw was detected in the bottom head to shell weld of the CCFPIT.

This flaw was evaluated by Westinghouse Energy Systems and found to be acceptable for the 40 year plant life based on design cyclic loading. Due to the increase in number of design pressure cycles, the flaw must be reevaluated to ensure that the anticipated increase in pressure cycles will NOT propagate the flaw beyond an acceptable depth. The ASME Section Xl requirements to examine this component in the next interval could change therefore in order to ensure Design Basis Calculations (SCG-4M-01031 and SQN-DES1 -5), these examination requirements are part of the Augmented Section.

IVA performed an augmented.ultrasonic examination of weld BIT-4 during the first period for the second interval. The examination volume and acceptance criteria were in accordance with the ASME Section Xl Code 1989 Edition for Examination Category C-A welds. The planar flaw dimension (length and depth) was compared to previous results by an NDE Level Ill.

IVA will perform an augmented ultrasonic examination of weld BIT-4 during the first period for the third and fourth inspection intervals. The examination volume and acceptance criteria was in accordance with the ASME Section Xl Code 2001 Edition 2003 Addenda for Examination Category C-A welds unless otherwise revised or waived by Civil Design. The planar flaw dimension (length and depth) shall be compared to previous results by an NDE Level Ill.

Results shall be submitted to Civil Design for evaluation and trending. The results of this examination shall be included in the ISI Site Final Report discussed in C'-SI-DXI-000-114.3, Section 7.7.

References:

1. NOI-2-SQ-293

2. SQ9406252PER

3. Design Basis Calculation SCG-4M-01031

4. Design Basis Calculation SQN-DES1-5

5. B39 960703 001

6. ASME Section Xl 2001 Edition 2003 Addenda

SON AUGMENTEDEXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATTTV Unit 2 Effective Date: 06-01-2D066 Page 15 of 41 8.0 REACTOR COOLANT PUMP SUPPORT Responsible Organization: Civil Design No augmented examinations are being performed on the reactor coolant pump supports in the third interval. This section is being maintained for history only in the third interval.

This augmented examination is no longer required following U2C1 1. Refer to memorandum B39 030710 001. The following information is being retained for history during this interval.

By augmented NDE request from Civil Engineering dated September 28, 1998, the support connections on each Reactor Coolant Pump are required to be examined due to examinations performed on Unit 1 during U1C9.

The support bolting on all four reactor coolant pump supports require VT-3 of N-VT-1 examination. The examination area is to include the pin, jam nut, hex nut, and washers shown on elevation B-B on drawing 48N426 and the nut and bolt connecting the reactor coolant pump tie rods (48N426) to the anchor in wall (detail A through E, 48N433 and 48N423). The type of flaws anticipated are gap between nut and bracket, and corrosion on studs and nuts. The examinations are to be performed during U2C9, U2C1 0 and each odd number outage beginning with U2C1.

By augmented NDE request from Civil Engineering dated March 16, 2000, the U2C1 0 examination is also to include the tack welds on the shims at the reactor coolant pump struts. Struts are MK PS-1 through PS-8 on drawing 48N423.

Crawing 48N433, note 6, specifies the tack welds on the shims. The type of flaw anticipated is cracked tack welds on the shims. These examinations are to be performed during U2C1 0 and each odd number outage beginning with U2C1 1.

Results shall be submitted to Civil Design for evaluation. The results of these examinations were included in the applicable ISI Site Final Report.

References:

1. B39 980928 001

2. SQ981354PER

3. B39 990513 001

4. B39 000316 001

5. B39 010111 002

6. B39 030710 001

9. SPP-9.7

SCN AUGMENTED EXAMINATIONS (UNIT 2) O-SI-DXI-000-114.3 ATTW]

Unit 2 Effective Date: 06-01-21306 Page 16 of 41 9.0 STEAM GENERATOR CLASS 2 UPPER SUPPORT Responsible Organization: Civil Design Ey augmented NDE request from Civil Engineering dated September 29, 1998, the class 2 upper support bolted connections on each steam generator are required to be examined due to examinations performed on Unit 1 during U1 C9.

The support bolting on all four steam generator class 2 supports require VT-3 of N-VT-1 examination. The examination area is to include the nuts and bolts in section E-E and E'-E' on drawing 48N427. The type of flaw anticipated is loose nuts and bolts. The examinations are to be performed during U2C9, U2C1 0 and each odd number outage beginning with U2C1 1.

Results shall be submitted to Civil Design for evaluation. The results of these examinations shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-114.3, Section 7.7.

References:

1. B39 980929 001

2. B39 990513 001

3. B39 010111 002

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATI-11 Unit 2 Effective Date: 06-01-2006 Page 17 of 41 10.0 NUCLEAR EXPERIENCE REVIEW (NER) ITEM SER 00-001 Responsible Organization: Civil Design Ely augmented NDE request from Civil Design dated February 28, 2001, the NER

%'ER 00-001 review requires examination of several Residual Heat Removal System piping circumferential and longitudinal welds. These examinations are to be performed during U2C1 1, U2C14, U2C17. After cycle 17, Civil Design will evaluate the need for future examinations.

Examine 100% of the circumferential and longitudinal welds (RHRF-041, RHRS'-072 and RHRF-041 -LS), on the reducing elbow downstream of valve 2-FCV-74-33, elevation 709'0". Examine 100% of the circumferential and longitudinal welds (RHRS-073, RHRF-065 and RHRS-072-LS), on the 12"X12"x8" tee attached to the reducing elbow. Examine the longitudinal weld (RHRS-073-LS) on the next connecting and adjacent 12"x12"x8" tee. Examine 100% of the circumferential and longitudinal welds (SIF-007 and RHRS-100-LS) on the 8"X8"x8" tee at the Safety Injection tie-in located at elevation 700'-0" downstream of RHR HX 2B and valve 2-FCV-74-28. Examine 100% of the circumferential and longitudinal welds (SIF-001 and RHRS-065-LS) on the 8"x8"x8" tee at the Safety Injection tie-in located at elevation 698'-5" downstream of RHR HX 2A and valve 2-FCV-74-16.

Ultrasonic (UT) examination method is to be used. The extent of examination shall be in accordance with ASME Section Xl, 2001 Edition 2003 Addenda, figure IWC-2500-7 where accessible. Component geometry may prevent full examination.

Starting with revision 0 of this procedure, the acceptance criteria shall be in accordance with ASME Section Xl, 2001 Edition 2003 Addenda, IWC-3514 for class 2 welds.

Types of flaws anticipated are cracks initiating on the inside diameter due to thermal transient fatigue. The area most highly suspected to contain a flaw is the longitudinal and circumferential welds and heat affected area. There is a low probability of a flaw existing.

1I3 Examination Instructions:

The RHR piping will be considered operable per the Technical Specifications during the augmented ISI examinations. The support clamp for supports 2RHRH-438 and 2RHRH-439 covers the circumferential weld between the two tees and the longitudinal weld. Since the entire weld must be examined, the support clamp must be disabled and temporarily removed. Work Order (WO) instructions for installation of the temporary support will be provided by Civil Design.

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 AT 11 Unit 2 Effective Date: 06-01-2006 Page 18 of 41 10.0 NUCLEAR EXPERIENCE REVIEW (NER) ITEM SER 00-001 (continued)

The instructions provided below must be followed in the order shown.

1. Remove the insulation in the area of the weld and the location of the temporary support.

2. Perform the NDE on all required exposed accessible welds with supports 2RHRH-438 and 2RHRH-439 in-tact and unaltered.

3. Install the temporary support per engineering instructions provided in WO.

4. Remove the support clamp for supports 2RHRH-438 and 2RHRH-439 in accordance with the WO.

5. Complete the NDE on the remaining welds.

6. Restore supports 2RHRH-438 and 2RHRH-439 in accordance with the WO.

7. Remove the temporary support from the piping in accordance with the WO.

8. Restore piping insulation.

Results and any examination limitations shall be submitted to Civil Design for Evaluation. Report any indication of thermal fatigue cracking to Civil Design immediately. The results of these examinations shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7.

Reference:

1. B39 010228 002

2. NER SER 00-001

3. ASME Section Xl 2001 Edition 2003 Addenda

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 AT111 Unit 2 Effective Date: 06-01-2006 Page 19 of 41 11.0 SAFETY INJECTION AND RHR WELDS AND ADJOINING AREAS, AND RI-ISI REGION 3 WELDS Responsible Organization: Mechanical Design The following welds per (B38 020710 802) require volumetric examination during (or just prior to) the indicated refueling outage. These welds were identified as a result cf the follow-up risk informed evaluation for region 3 (S57 011016 800) and other regions addressed in SQ961154PER regarding the potential for stress corrosion cracking (SCC) due to multiple weld repairs on the stainless steel pipe welds. The area and volume for the examination are to be in accordance with the RI-ISI program welds. The ultrasonic examination acceptance criteria shall be in accordance with the ASME Section Xl, 2001 Edition 2003 addenda, IWB-3514 and I'NC-3514 for class 1 and Class 2 welds respectively. The type of flaw anticipated is IGSCC of the type seen in 2-SIF-146 during the U2C7 RFO. The area most highly suspected to contain the flaws is adjacent to the weld. The probability of a flaw existing is low. If indications are detected, Mechanical Design will determine further expansions. If there are no indications detected after the last examination cycle no further examinations are required and this augmented examination sequence may be dropped from the program.

Weld Number Examination Method Cycles RHRF-034 Volumetric 12 and 14 RHRF-045 Volumetric 12 and 14 RHRF-046A Volumetric 12 and 14 RHRF-105 Volumetric 13 and 15 SIF-038 Volumetric 12 and 14 SIF-062 Volumetric 12 and 14 SIF-131 Volumetric 12 and 14 SIF-142 Volumetric 12 and 14 SIF-150 Volumetric 13 and 15 SIF-162 Volumetric 13 and 15 SIF-165 Volumetric 13 and 15 SIF-170 Volumetric 13 and 15 SIF-189 Volumetric 13 and 15 SIF-219 Volumetric 13 and 15 SIF-226 Volumetric 13 and 15 The results of the examination and any examination limitations will be submitted to Mechanical Design for evaluation and trending. The results of this examination shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-114.3, section 7.7.

SC!N AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATT11 Unit 2 Effective Date: 06-01-21)06 Page 20 of 41 11.0 SAFETY INJECTION AND RHR WELDS AND ADJOINING AREAS, AND RI-ISI REGION 3 WELDS (continued)

References:

1. B38 020710 802

2. S57 011016 800

3. ASME Section XI 2001 Edition 2003 Addenda

SCQN AUGMENTED EXAMINATIONS (UNIT 2) O-SI-DXI-000-114.3 ATTllt Unit 2 Effective Date: 06-01-2006 Page 21 of 41 12.0 REACTOR PRESSURE VESSEL CLOSURE HEAD PENETRATIONS Responsible Organization: Mechanical Design InI response to NRC Bulletin 2002-01 and NRC Order on the Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurizer Water Reactors, EA-03-009 due to the potential reactor pressure vessel (RPV) closure head degradation and reactor coolant pressure boundary integrity, the RPV closure head and closure head penetrations are to be examined per the schedule below.

These examinations may be increased based on the industry experience and/or regulatory commitments.

A Bare Metal Visual (BMV) of 100% of the RPV head/penetrations interface surface (including 360 degrees around each RPV head penetration) will be performed starting in Unit 2 cycle 11 of the second interval and every third refueling outage or five years which ever occurs first. The examination method is a remote visual examination (enhanced VT-2) in accordance with N-VT-1 7 supplemented with additional examination methods deemed necessary by Mechanical Engineering where indications of leakage are noted as "suspect".

Bare Metal Visual - following the Unit 2 Cycle 11 of the second interval bare metal visual examinations, the bare metal visual examination will include a 100% visual examination of the RPV head base metal surface and each penetration interface. When the RPV head surface is obscured by support structure interferences which are located at RPV head elevations down

.slope from the outermost RPV head penetration, a bare metal visual inspection

.of no less than 95 percent of the RPV head surface may be performed provided that the examination shall include those areas of the RPV head up slope and down slope from the support structure interference to identify any evidence of boron or corrosive product. Should any evidence of boron or corrosive product be identified, RPV head surface shall be examined under the support structure to ensure that the RPV head is NOT degraded.

A volumetric examination or surface examination or a combination of volumetric and surface examinations will be performed starting in Unit 2 cycle 14 and every fourth refueling outage or every seven years which ever occurs first.

Perform either A, B or C below.

SCQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATT-11 Unit 2 Effective Date: 06-01-2006 Page 22 of 41 12.0 REACTOR PRESSURE VESSEL CLOSURE HEAD PENETRATIONS (continued)

a. Volumetric examination - Ultrasonic examination of the RPV head penetration nozzle volume (i.e., nozzle base material) from 2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) to 2 inches below the lowest point at the toe of the J-groove weld on a horizontal plane perpendicular to the nozzle axis (or the bottom of the nozzle if less than 2 inches). In addition, an assessment shall be made to determine if leakage has occurred into the annulus between the RPV head penetration nozzle and the RPV head low-alloy steel.

b. Surface examination - Eddy current examination or liquid penetrant examination of the entire wetted surface of the J-groove weld and the wetted surface of the RPV head penetration nozzle base material from at least 2 inches above the highest point of the root of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis) to 2 inches below the lowest point at the toe of the J-groove weld oln a horizontal plane perpendicular to the nozzle axis (or the bottom of the nozzle if less than 2 inches).

c. Combination of volumetric examination and surface examination to cover equivalent volumes, surfaces and leak paths of the RPV head:.

penetration nozzle base material and J-groove weld as described in volumetric examination and surface examination above. Substitution of a portion of a volumetric examination on a nozzle with a surface examination may be performed with the following requirements:

(1) On nozzle material below the J-groove weld, both the outside diameter and inside diameter surfaces of the nozzle must be examined.

(2) On nozzle material above the J-groove weld, surface examination of the inside diameter surface of the nozzle is permitted provided a surface examination of the J-groove weld is also performed.

Refer To NRC order EA-03-009 revised February 20, 2004 for additional details.

SCN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATT-11 Unit 2 Effective Date: 06-01-2006 Page 23 of 41 12.0 REACTOR PRESSURE VESSEL CLOSURE HEAD PENETRATIONS (continued)

NOTE The visual inspections performed during each refueling outage to identify potential boric acid leaks from pressure retaining components above the RPV head are being performed under the boric acid program and are NOT being maintained under this augmented program - - -

The areas of leakage shall be reported to Mechanical Engineering for evaluation.

Type of flaw anticipated is stress corrosion cracking resulting from exposure to primary water chemistry.

The area most likely to contain flaws are the CRDM penetration nozzle base material and areas adjacent to the nozzle interface with the RPV head base material and the J-groove weld. The probability of a flaw existing is low.

The examination acceptance criteria shall be as directed by Mechanical Engineering.

Examination results and any examination limitations shall be submitted to Mechanical Engineering for evaluation and trending. The results of these examinations shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7. The reporting required by NRC Order EA-03-009 will be submitted by Mechanical Engineering separately from the report in 0-SI-DXI-000-114.3, Section 7.7.

References:

1. NRC Order EA-03-009, Establishing Interim Inspection Requirements for Reactor Pressure Vessel Head at Pressurized Water Reactors, dated February 11, 2003 and revised February 20, 2004.

2. Letter from Nuclear Institute (NEI) to NEI Administrative Points of Contact, "NRC Meeting on PWR Reactor Pressure Vessel Head Inspection Order", dated February 25, 2003.

3. S64 020402 801

4. B38 020627 800

5. B38 030623 802

6. PER 02-004487-000

7. B38 040708 800

8. B38 040817 800

9. SPP-9.7 10 NRC Bulletin 2002-01

SON AUGMENTEDEXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATTW]

Unit 2 - Effective Date: 06-01-21006 Page 24 of 41 12.0 REACTOR PRESSURE VESSEL CLOSURE HEAD PENETRATIONS (continued)'

Examination History Bare Metal Visual Examination Cycle: U2C11 of the second interval Examination Date: 05/20/2002 ASME Section Xl Inspection Interval: Second ASME Section XI Inspection Period: Second Next Examination: U2C14 of the third interval or 05/20/2007 which every occurs first Volumetric or Surface Examination Cycle: Scheduled for U2C14 of the third interval, must be performed prior to 2/11/2008 Examination Date: To be performed ASME Section XI Inspection interval: Third ASME Section XI Inspection Period: First Next Examination: U2C18 or seven years from the U2C14 examination which ever occurs first

SON AUGMENTEDEXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATTH11 Unit 2' Effective Date: 06-01-20D06 Page 25 of 41 13.0 REACTOR COOLANT PUMP SHAFTS Responsible Organization: Component Engineering The RCP shaft augmented examination requirements are in accordance with an augmented examination request from Component Engineering dated November 26, 2002. The augmented examination was developed because of the two previous instances of RCP shaft cracking at SQN. The augmented RCP shaft examinations will be performed each refueling outage beginning with the U2C12 refueling outage in the second interval.

Ultrasonic examinations will be performed in accordance with NDE procedure N-UT-80 and/or N-UT-83. The entire length of the pump shaft from the top surface of the shaft is to be examined. A graphic illustration of the ultrasonic responses from the shaft at 90 degree increments shall be provided for information. This is NOT a qualitative examination. The type of flaws anticipated are shaft cracks due to high cycle fatigue. The area most highly suspected to contain the flaws are approximately 118 inches from the top of the shaft at the pin hole locations where the thermal sleeve is secured. The probability of a flaw existing is unknown.

Examination results and any examination limitations shall be submitted to Component Engineering. Report any indication of cracking to Component Engineering immediately. The results of these examinations shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-114.3, Section 7.7

References:

1. S57 021126 800

2. S57 060307 800

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-1 14.3 ATT11 Unit 2 Effective Date: 06-01-2,006 Page 26 of 41 14.0 EXAMINATION OF ALLOY 600 AND ALLOY 82/182 POTENTIAL LEAK LOCATIONS IN PRIMARY COMPONENTS Responsible Organization: Mechanical Design VVCAP-1 5988-NP has identified generic guidance in developing plant-specific EBoric Acid Corrosion Control Programs (BACCP) and procedures. 'As part of the guidance, PWSCC susceptible Alloy 600 and Alloy 82/182 weld locations in borated systems were identified as a potential leakage path.

starting in the first period of the third ISI interval, TVA will perform augmented ultrasonic examinations of the areas as listed below for Alloy 600/ Alloy 82/182 locations, unless otherwise revised or waived by Mechanical Design. Additional welds and/or examination techniques may be added by Mechanical Design where further evaluations indicate a potential susceptibility. See additional examinations for MRP 2003-039 and NRC Bulletin 2004-01 below.

Examinations of circumferential (dissimilar metal) butt welds shall be performed by the ultrasonic (UT) examination method using techniques and procedures developed under the Performance Demonstration Initiative (PDI). Because of the inherent cifficulty in detection of flaws in dissimilar metal welds, the extent of examination shall include the complete weld volume, butter material, and base material for a cistance of 1/4 inch from each weld toe or butter interface. Any examination limitations should be noted on the examination report.

If credit will be taken for the RI-ISI program (Examination Category R-A), the extent of examination shall be increased. The extent of'examination for Examination Category R-A shall include the complete weld volume, butter material,' and base material for a distance of 1/2 inch beyond each side of the base metal thickness transition or counterbore. For examination category R-A piping welds with no transition or counterbore on the ID, the exam volume shall be increased to include 1/2 inch beyond the weld toe or butter interface.

The type of flaw anticipated is stress corrosion cracking.

The UT acceptance criteria for circumferential butt welds shall be in accordance with ASME Section Xi, 2001 Edition 2003 Addenda, IWB-3514, for Class 1 welds.

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATTTV1 Unit 2 Effective Date: 06-01-2006 Page 27 of 41 14.0 EXAMINATION OF ALLOY 600 AND ALLOY 82/182 POTENTIAL LEAK LOCATIONS IN PRIMARY COMPONENTS (continued)

Component Alloy600/ 82/182 Location Method PRZ Nozzle to (see note below) Vessel Weld RCW-24-SE Spray nozzle to safe end UT RCW-15

__ weld RCW-25-SE Safety nozzle to safe end UT RCW-16

__ __ weld -

FRCW-26-SE Safety nozzle to safe end UT RCW-17 weld RICW-27-SE Relief nozzle to safe end UT RCW-18 weld RCW-28-SE Safety nozzle to safe end UT RCW-19

__ weld FCW-29-SE Surge nozzle to safe end UT RCW-21

_ __ __ __ _ _ _ _ _ w e ld_ _ _ _ _ _ _ _ _ _ _ _ _

NOTE The components specified should be scheduled for examination in conjunction with the adjoining Pressurizer Nozzle to Vessel weld (Exam Category B-D, Item No., B3. 1 0).

TVA will perform additional examinations per MRP 2003-039 "Recommendation for Inspection of Alloy 600/82/182 Pressure Boundary Components" and NRC Bulletin 2004-01 "Inspection of Alloy 82/182/600 Material Used in the Fabrication of Fressurizer Penetration and Steam Space Piping Connections at Pressurized Water Reactors". Nozzle/safe ends. on the pressurizer safety, spray, relief and surge nozzles shall be visually examined beginning with cycle 13 of the second interval and each subsequent outage until nozzle weld overlays are completed. The visual examination method is an enhanced VT-2 supplemented with additional examination methods deemed necessary by Mechanical Engineering where indications of leakage are noted as "suspect". The areas of leakage shall be reported to Mechanical Engineering for evaluation. The type of flaw anticipated is stress corrosion cracking resulting from exposure to primary water chemistry. The area most likely to contain flaws are the alloy 600/82/182 materials used at the pressurizer nozzle/safe end interface of the surge nozzle (1), spray nozzle (1), relief nozzle (1), and safety nozzles (3). The probability of a flaw existing is low.

The results of examinations shall be submitted to SQN Mechanical Design for evaluation and trending. The results of this examination shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-114.3, Section 7.7.

SON AUGMENTEDEXAMINATIONS (UNIT 2) O-SI-DXI-000-114.3 ATTII7 Unit 2 Effective Date: 06-01-2006 Page 28 of 41 14.0 EXAMINATION OF ALLOY 600 AND ALLOY 82/182 POTENTIAL LEAK LOCATIONS IN PRIMARY COMPONENTS (continued)

References:

1. B38 030623 801

2. B38 040318 808

3. B38 040719 800

4. WCAP-1 5988-NP

5. MRP 2003-039

6. NRC Bulletin 2004-01

7. ASME Section XI 2001 Edition 2003 Addenda

8. B38 051209 800

SCN AUGMENTED EXAMINATIONS (UNIT 2) O-SI-DXI-000-114.3 AT11 Unit 2 Effective Date: 06-01-2006

. -Page 29 of 41 15.0 EXAMINATION OF REACTOR VESSEL HEAD VENT PIPE Responsible Organization: Civil Engineering

[uring a forced outage in January 2003, the Unit 2 Reactor Head Vent Line was visually examined and found to be deformed (bent). Reference 4 indicated that the bent vent pipe would maintain structural integrity for the remaining cycle of operation for two additional cycles of operation up to cycle 14 refueling outage (Fall 2006).

1. Perform an augmented volumetric examination by using PT, UT, ECT or any combination of these techniques in the cycle 14 refueling outage. The extent of examination shall include from the nozzle J-weld at the RV head l.D. through the head to the bottom of the 90 degree bend. This may be accomplished by utilizing PT, UT, ECT or any combination of these NDE techniques. Any indications evaluated to be cracking shall be reported.

2. In addition, perform a VT-1 inspection of the horizontal vent pipe section from the nozzle to the RV head ventilation shroud including the 90 degree bend above the nozzle in cycle 14 refueling outage. Any indications evaluated to be cracking shall be reported.

C;ivil Design may elect to extend the inspection interval provided the proper analysis is completed. The extent and areas to be examined may be revised or waived by Civil Design. Additional examination techniques may be added with the consent of Civil Design where further evaluations indicate a potential susceptibility.

The results of examinations shall be submitted to SQN Civil Design for evaluation and trending. The results of this examination shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-1 14.3, Section 7.7.

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATT1-Unit 2 Effective Date: 06-01-2006 Page 30 of 41 15.0 EXAMINATION OF REACTOR VESSEL HEAD VENT PIPE (continued)

NOTES

1) The gross visual inspection through existing openings in the CRD cooling shroud above the reactor vessel head insulation, as discussed in reference 4, is being performed during PM 040142000 and is NOT being maintained under this augmented program.

2) The gross visual remote video inspection on the portion of the vent line from the head penetration to the bottom of the insulation as discussed in reference 4 was performed under work orders 03-015526-000 (U2C12) and 03-016265-000 (U2C13) in the second interval and is NOT being maintained under this augmented program..

References:

1. Request for Augmented Nondestructive Examination (NDE) dated .5126103 (B39 030529 001)

2. Request for Augmented Nondestructive Examination (NDE) dated 11/14/03 (B39 031114 001)

3. PER 03-000029-000

4. B38 031029 802

SON AUGMENTED EXAMINATIONS (UNIT 2) O-SI-DXI-000-114.3 ATT-11 Unit 2 Effective Date: 06-01-2D06 Page 31 of 41 16.0 REACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS Responsible Organization: Mechanical Design In response to NRC Bulletin 2003-02 for potential leakage from reactor pressure vessel lower head penetrations and the reactor coolant pressure boundary, the RPV lower head and lower head penetrations are to be examined per the schedule below.

These examinations may be increased based on the industry experience and/or regulatory commitments.

A Bare Metal Visual (BMV) of 100% of the RPV lower head/ penetrations interface surface (including 360 degrees around each RPV lower head penetration) will be performed starting in Unit 2 cycle 13 and every refueling outage thereafter. The examination method is a visual examination (enhanced VT-2) in accordance with N-VT-17 supplemented with additional examination methods deemed necessary by Mechanical Engineering where indications of leakage are noted as "suspect". SQN is to notify the NRC staff in writing cf any changes to this regulatory commitment prior to implementation The areas of leakage shall be reported to Mechanical Engineering for evaluation.

The type of flaw anticipated is stress corrosion cracking resulting from exposure to primary water chemistry.

The area most likely to contain flaws are the lower head incore instrument penetration nozzle base material and areas adjacent to the nozzle interface with the RPV lower head base material. The probability of a flaw existing is low.

Examination results and any examination limitations shall be submitted to Mechanical Engineering for evaluation and trending. The results of these examinations shall be included in the ISI Site Final Report discussed in 0-SI-DXI-000-114.3, Section 7.7.

NOTE During Unit 2 cycle 12 refueling outage in the second interval a remote visual (VT) examination was performed on the outside surface of the RPV lower head and thimble tube instrumentation penetrations. This report was filed with the Unit 2 cycle 12 site final report.

References:

1. NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity, dated August 21, 2003

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATT1i1 Unit 2 Effective Date: 06-01-2006 Page 32 of 41 16.0 REACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS (continued)

2. Request for Augmented Nondestructive Examination (NDE) Form, dated 10/31/03 (B38 031031 800)

3. PER 03-01084-000

4. L44 041019 008

SCN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATrl11 Unit 2 Effective Date: 06-01-2D06 Page 33 of 41 16.0 REACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS (continued)

Augmented Examination Table A FIRST PERIOD SECOND PERIOD THIRD PERIOD COMPONENT PROGRAM EXAM Cycle Cycle Cycle Cycle Cycle Cycle REFERENCE REFERENCE METHOD 14 15 16 17 18 19 SECTION DRAWING NJMBER Feedwater Nozzle to Pipe Welds 1.0 UT X X X X X X CHMI-2403-C Transition Piece and Transition Piece to Elbow and Associated Base Material Loops 1 and 4 (FDF-01 1, FDF-01OA, FDF-022, and F'DF-021A) __.____

Feedwater/Aux liary Feedwater 1.0 UT X X X X X X CHMI-2403-C 4-inch Reducer-to-Pipe Welds and the Associated Base Metal Loop 2 (AFWF-099)

Feedwater/Aux liary Feedwater 1.0 UT X X X CHM-2403-C 4-inch Reducer-to-Pipe Welds and the Associated Base Metal Loop 4 (AFWF-078)

Feedwater/Aux liary Feedwater 1.0 UT X X X CHM-2403-C 4-inch Reducer-to-Pipe Welds and the Associated Base Metal Loops 1 and 3 (AFWF-077 and AFWF-116) _____ _ -

Reactor Coolart Pump Flywheel 2.0 UT, MT see see see see see see IlS-C-306-B note note note note note note ISI-C*403-C Note: see drawing for examination

. -. schE dule RPV Nozzle Cladding 3.0 UT X ISI-C297-C

.ISI-C298-C

_SI-_0392-C Control Rod Giide 4.0 N/A N/A N/A N/A N/A N/A N/A ISI-097-C Tubes Flexures See note Thimble Tube Guide 5.0 ET X X X X X X IS1-0319-C Examination of Piping 6.0 Connected to the Reactor Coolant System Due to Thermal Stresses Examination of Circumferential Welds 6.0 UT X X X ISI4)009-C-2 2-CVCF-244E, 2-CVCF-244F, and fitting 2-CVCF-244E/244F EL _ _ _

Examination of Circumferential Welds 6.0 UT X X X ISI-0009-C-2 2-CVCF-213, 2-CVCF-214, and fitting .

2-CVCF-213/214 EL .

Examination of Circumferential Welds 6.0 UT X X ISI-00O8-C-1 RC-33 . . . ._- _ __

Examination of Circumferential Welds 6.0 UT X ISVI-0008-1

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Augmented Examination Table A FIRST PERIOD SECOND PERIOD THIRD PERIOD COMPONENT PROGRAM EXAM Cycle Cycle Cycle Cycle Cycle Cycle REFERENCE REFERENCE METHOD 14 15 16 17 18 19 SECTION DRLAWING

_ _ N JMBER Examination of Socket Welds 6.0 UT X X X ISI-0002-C-8 2-SI-1124, 2-SI-1125, and 2-SI-1i126 . . . . . .-

Examination of Socket Welds 6.0 UT X X X ISI-)002-C-9 2-SI-1816A, 2-:;l-1817A, and 2-SI-181 8A . .

Examination of Socket Welds 6.0 uT X X X ISI-C002-C-10 2-SI-1894, 2-SI-1895, and 2-SI-1896 Examination of Socket Welds 6.0 UT X X X ISI-C002-C-1 1 2-SI-1899, 2-SI-1900, and 2-SI-1901 Examination of Socket Welds 6.0 UT X X X X X X ISI-0009-C-2 2-CVC-1745, 2.CVC-1746, and 2-CVC-1747 _ ___

Examination of Weld 7.0 UT C14 C14 ISI0074-C-1 BIT-4 or or

. C15 C15 Reactor Coolart Pump Support 8.0 N/A N/A N/A N/A N/A N/A N/A ISI0326-C-1 RCP# 1, 2, 3, and 4 See note 1 Y

Steam Generator Class 2 Upper Support 9.0 VT-3 X X ISI40401-C-2 SG# 1, 2, 3, ani44 _

Examination of circumferential and 10.0 UT X X ISI-0002-C-2 longitudinal welds due to SER 00-001 1S14003-C-2 RHRF-041 ISI-0003-C-3 RHRS-072 RHRF-041 -LS RHRS-073 RHRF-065 RHRS-072-LS RHRS-073-LS SIF-007 RHRS-1 00-LS SiF-001 RHRS-065-LS Safety Injection and RHR 11.0 UT X IS1I0002-C-1 Welds and Adjoining Areas, and RI-ISI ISI-0002-C-4 Region 3 Welds. ISI-0002-C-5 RHRF-034 ISI-0003-C-2 RHRF-045 ISI-0003-C-3 RHRF-046A ISI-0431 -C-3 SIF-038 SIF-062 SIF-131 SIF-142 . . _ -

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Augmented Examination.

Table A FIRST PERIOD SECOND PERIOD THIRD PERIOD COMPONENT PROGRAM EXAM Cycle Cycle Cycle Cycle Cycle Cycle RE rERENCE REFERENCE METHOD 14 15 16 17 18 19 SECTION . .AWING NUMBER

_

Safety Injection and RHR 11.0 UT X ISI-0002-C-6 Welds and Adj ining Areas, and Rl-ISI ISI-0003-C-6 Region 3 Welds ISI-0431-C-1 RHRF-105 ISI-0431 -C-5 SIF-1 50 ISI-1)431 -C-11 SIF-1 62 SIF-1 65 SIF-170 SIF-189 SIF-219 SIF-226 _

RPV closure head and closure head 12.0 VT-2 X ISI-0097-C-1 penetrations (EMV) Enhanced RPV closure head and closure head 12.0 UT or ECT X ISI-0097-C-1 penetrations and/or PT or combination of UT.PT, and ECT Reactor Coolant Pump Shafts 13.0 UT X X X X X X ISI-0307-C-2 Alloy 600 and Alloy 821182 Potential 14.0 Leak Locations in Primary Components RCW-24-SE 14.0 UT C14 C14 Ncte: to be RCW-29-SE or or examined C15 C15 wvith the nozzle to ves.sel weld RCW-25-SE 14.0 UT C16 C16 or Note: to be RCW-26-SE or C17 examined C17 vrith the nazzle to vessel weld RCW-27-SE 14.0 UT C18 C18 Ncte: to be RCW-28-SE or or examined C19 C19 with the nozzle to ve!sel weld RCW-24-SE 14.0 VT-2 X X X X X X ISI-1396-C-01 RCW-25-SE RCW-26-SE Enhanced RCW-27-SE RCW-28-SE . _

RCW-29-SE 14.0 VT-2 X X X X X X ISI-0396-C-01 Enhanced Reactor Vessel Head Vent Pipe 15.0 PT. UT. or X VENT-1 P ECT ISI-0097-C-2 Reactor Vessel Head Vent Pipe 15.0 VT-1 X VENT-1 P I _ ISI4)097-C-2 Reactor Vessel Lower Head 16.0 VT-2 X X X X X X ISI-0319- C-1 Enhanced

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 AT11 Unit 2 Effective Date: 06-01-2006 Page 36 of 41 16.0 REACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS (continued)

NOTES

1) No augmented examinations are being performed in the third interval.

SCIN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATTTV]

Unit 2 Effective Date: 06-01-2006 Page 37 of 41 16.0 FtEACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS (continued)

Augmented Examinations Table B The welds/components in this table, unless otherwise stated, have been reviewed for augmented examinations in the RI-ISI program. Any examination schedule or method changes for these welds are to be submitted for incorporation in the RI-ISI periodic and interval updates. Refer to calculation CN-RRA-00-56.

PROGRAM WELD FAILURE EXAM EXAM FREQUENCY RI-IS1 COMMENTS REFERENCE MECHANISM FOR METHOD SEGMENT SECTION THE AUGMENTED PROGRAM 1.0 FDF-01 1 thermal fatigue UT continuous FW-001 see note 2 (each outage) 1.0 FDF-01 OA thermal fatigue UT continuous FW-001 see note 2 (each outage) . _

1.0 FDF-022 thermal fatigue UT continuous FW-004 see note 2 (each outage) 1.0 FDF-021 A thermal fatigue UT continuous FW-004 see note 2 (each outage) 1.0 AFWF-099 thermal fatigue UT continuous FW-002 see note 2 (each outage) 1.0 AFWF-078 thermal fatigue UT continuous AF-022 see note 2 (each even numbered outage) 1.0 AFWF-077 thermal fatigue UT continuous AF-021 see note 2 (each odd numbered outage) 1.0 AFWF-1 16 thermal fatigue UT continuous FW-003 see note 2 (each even

._ numbered outage) 60 2-CVCF-244E thermal strat UT continuous CH-018 see note 2 (each even numbered outage) 6.0 2-cvcF-244F thermal strat UT continuous CH-01 8 see note 2 (each even numbered outage)

. 2-CVCF- thermal strat UT continuous CH-018 see note 2 6.0 244E/244F EL (each even numbered outage) 6.0 2-CVCF-213 thermal strat UT continuous CH-019 see note 2 (each odd numbered outage) 6.0 2-CVCF-214 thermal strat UT continuous CH019 see note 2 (each odd numbered outage) 6.0 2-CVCF- thermal strat UT continuous CH-019 see note 2 213/214 EL (each odd numbered outage)

SCQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATITTV Unit 2 Effective Date: 06-01-2D06 Page 38 of 41 16.0 REACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS (Continued)

Augmented Examinations Table B PROGRAM WELD FAILURE EXAM EXAM FREQUENCY RI-ISI COMMENTS REFERENCE MECHANISM FOR METHOD SEGMENT SECTION THE AUGMENTED PROGRAM 6.0 RC-33 thermal strat UT continuous RC-039 see note 3 (every forth outage beginning

._ with RO 10) 6.0 RC-35 thermal strat UT continuous RC-039 see note 3 (every forth outage beginning

._ with RO 12) 6.0 2-SI-1 124 thermal strat UT continuous Sl-069 see note 4 (each odd numbered outage) 6.0 2-SI-1 125 thermal strat UT continuous SI-069 see note 4 (each odd numbered outage) 6.0 2-SI-i 126 thermal strat UT continuous SI-069 see note 4 (each odd numbered outage) 6.0 2-SI-1816A thermal strat UT continuous SI-070 see note 4 (each even numbered outage) 6.0 2-SI-1817A thermal strat UT continuous Sl-070 see note 4 (each even numbered outage) 6.0 2-SI-1818A thermal strat UT continuous Sl-070 see note 4 (each even numbered outage) 6.0 2-SI-1894 thermal strat UT continuous St-071 see note 4 (each odd numbered outage) 6.0 2-SI-1895 thermal strat UT continuous SI-071 see note 4 (each odd numbered outage) 6.0. 2-SI-1896 thermal strat UT continuous Sl-071 see note 4 (each odd numbered outage) 6.0 2-SI-1899 thermal strat UT continuous Sl-072 see note 4 (each even numbered outage) 6.0 2-SI-1900 thermal strat UT continuous SI-072 see note 4 (each even numbered outage) . -

6.0 2-SI-1901 thermal strat UT continuous SI-072 see note 4 (each even numbered outage) 6.0 2-CVC-1745 thermal strat UT continuous CH-020 see note 2 (each outage) 6.0 2-CVC-1746 thermal strat UT continuous CH-020 see note 2

._ (each outage) 6.0 2-CVC-1747 thermal strat UT continuous CH-020 see note 2 (each outage) 7.0 BIT-4 N/A UT every 10 years N/A monitor flaw in CCI'ST, no credit to be taken in the

._ Rl-ISI program

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATTII Unit 2 Effective Date: 06-01-2006 Page 39 of 41 16.0 REACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS (continued)

Augmented Examinations Table B PROGRAM WELD FAILURE EXAM EXAM FREQUENCY RI-ISI COMMENT T REFERENCE MECHANISM FOR METHOD SEGMENT SECTION THE AUGMENTED PROGRAM . . -

10.0 RHRF-041 thermal transient UT RO 11, 14, & 17 RH-017 see note 2 fatigue . -

10.0 RHRS-072 thermal transient UT RO 11, 14,8 17 RH-017 see note 2 fatigue . -

10.0 RHRF-041-LS thermal transient UT RO 11, 14, & 17 RH-017 see note 2 fatigue .

10.0 RHRS-073 thermal transient UT RO 11,14, 8 17 RH-017 see note 2 fatigue 10.0 RHRF-065 thermal transient UT RO 11, 14, 8 17 RH-017 see note 2 fatigue 10.0 RHRS-072-LS thermal transient UT RO 11, 14,8 17 RH-017 see note 2 fatigue 10.0 RHRS-073-LS thermal transient UT RO 11, 14, & 17 RH-017 see note 2 fatigue 10.0 SIF-007 thermal transient UT RO 11,14,8 17 RH-016 see note 6 fatigue ._.

10.0 RHRS-100-LS thermal transient UT RO 11, 14, & 17 RH-01 6 see note 2 fatigue .

10.0 SIF-001 thermal transient UT RO 11,14,8 17 RH-015 see note 6 fatigue . -

10.0 RHRS-065-LS thermal transient UT RO 11,14, 8 17 RH-015 see note 2 fatigue . __

11.0 RHRF-034 IGSCC UT RO 12 8 14 RH-009 see note 2 11.0 RHRF-045 IGSCC UT RO 12 & 14 RH-017 see note 2 11.0 RHRF-046A IGSCC UT RO 12& 14 RH-008 see note 2 11.0 SIF-038 IGSCC UT RO 12 & 14 Sl-050 see note 3 11.0 SIF-062 IGSCC UT RO 12 & 14 SI-037 see note 2 11.0 SIF-131 IGSCC UT RO 12& 14 SI-004 see note 3 11.0 SIF-142 IGSCC UT RO 12& 14. Sl-009 see note 2 11.0 RHRF-105 IGSCC UT RO 13 8 15 SI-059 see note 3 11.0 SIF-150 IGSCC UT RO 13 8 15 SI-022 see note 2 11.0 SIF-162 IGSCC UT RO 13 & 15 Sl-006 see note 2 11.0 SIF-165 IGSCC UT RO 13 & 15 SI-014 see note 2 11.0 SIF-170 . IGSCC UT RO 13 8 15 Sl-002 see note 3 11.0 SIF-189 IGSCC UT RO 13& 15 SI-066 see note 2 11.0 SIF-219 IGSCC UT RO 13 & 15 SI-033 see note 2

SQN AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 ATI711 Unit 2 Effective Date: 06-01-2006 Page 40 of 41.

16.0 REACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS (continued)

Augmented Examinations Table B PROGRAM WELD FAILURE EXAM EXAM FREQUENCY RI-ISI COMMENTS REFERENCE MECHANISM FOR METHOD SEGMENT SECTION THE AUGMENTED PROGRAM 11.0 SIF-226 IGSCC UT RO 138 15 SI-033 see note 2 14.0 RCW-24-SE PWSCC UT every 10 years RC-029 see note 2 14.0 RCW-24-SE PWSCC VT-2 RO 13 and RC-029 see note 2 Enhanced each subsequent

._ . outage 14.0 RCW-25-SE PWSCC UT every 10 years RC-048 see note 2 14.0 RCW-25-SE PWSCC VT-2 RO 13 and RC-048 see note 2 Enhanced each subsequent

. outage 14.0 RCW-26-SE PWSCC UT every 10 years RC-049 see note 2 14.0 RCW-26-SE PWSCC VT-2 RO 13 and RC-049 see note 2 Enhanced each subsequent outage 14.0 RCW-27-SE PWSCC UT every 10 years RC-051 see note 2 14.0 RCW-27-SE PWSCC VT-2 RO 13 and RC-051 see note 2 Enhanced each subsequent outage 14.0 RCW-28-SE PWSCC UT every 10 years RC-047 see note 2 14.0 RCW-28-SE PWSCC VT-2 RO 13 and RC-047 see note 2 Enhanced each subsequent

. _ outage 14.0 RCW-29-SE PWSCC UT every 10 years RC-039 see note 4 14.0 RCW-29-SE PWSCC VT-2 RO 13 and RC-039 see note 7 Enhanced each subsequent outage 15.0 Reactor Vessel mechanical PT/UTIETI RO 14 RC-035 see note 2 Head Vent VT-I Pipe VENT-I P

SON AUGMENTED EXAMINATIONS (UNIT 2) 0-SI-DXI-000-114.3 AT11 Unit 2 Effective Date: 06-01-2006 Page 41 of 41 16.0 REACTOR PRESSURE VESSEL LOWER HEAD PENETRATIONS (continued)

NOTES

1) Note 1not used.

2) Low safety significant segment, examined for augmented examination credit only.

3) High safety significant segment, examined for RI-ISI and augmented examination credit.

4) High safety significant segment, this examination for augmented examination credit only.

5) Note 5not used.

6) Low safety significant segment, examined for RI-ISI (delta risk) and for augmented examination credit.

7) Examination for RI-ISI credit isto be addressed in the next RI-ISI update for the third interval, second period. Credit is being taken only for the augmented examination in cycle 14 and later.

v t e Letter Sequence Other
TAC:MB1566, (Open) TAC:MB1567, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML061210105
MONTHYEAR2006-04-21 [Table View]

ML061210105

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