ML20035B668
| ML20035B668 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/11/1993 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20035B664 | List: |
| References | |
| PROC-930211, NUDOCS 9304020284 | |
| Download: ML20035B668 (38) | |
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FLORIDA POWER CORPORATION l
Florid 8 CRYSTAL RIVER UNIT # 3 s
P.. O..W~9,. a -r INSERVICE INSPECTION PROGRAM PAGE 1 0F 3 INSERVICE INSPECTION PROGRAM ADMINISTRATIVE CONTROLS l
The Manager, Nuclear Plant Technical Support is the focal point for implementation and control of the Crystal River Unit 3 (CR-3) Inservice Inspection Program, which includes two volumes-this Plan, and the Inservice Inspection Procedure Manual. The Manager, Nuclear Plant Technical Support is responsible for providing interpretations of the Program and assuring the Administrative Controls are implemented.
Changes or revisions to the Program administrative requirements, format, or l
instructions included in the Program may be implemented following review and approval by the Manager, Nuclear Plant Technical Support. The Program will be kept current by Change Notices placed in front of the Listings of Components Subject to Examination (section 6). Since all the Printouts included in the Program Plan are computer-driven, changes placed on Change Notices will be accumulated in front of the Listings of Components Subject to Examination and will be included in the Program the next time a Printout is run. Changes made since the last Printout can be recognized by comparing the date on the Change Notice to the last date shown in the upper left hand corner of the computerized Printout.
Changes or revisions to Non-destructive Examination Procedures and Administrative Procedures implementing the Inservice Inspections and Tests are subject to the review and approval requirements of Technical Specification 6.8.2.lb.
The review cycle shall consist of: an interdepartmental review by a Qualified Reviewer and interdisciplinary review by Qualified Reviewer (s) in interfacing departments, as specified in Administrative Procedures, and approval by the responsible Superintendent or Manager. The PRC shall then l
review the 10CFR50.59 evaluation within 14 days of approval. The procedure review record, documenting this review, shall be placed at the front of the Inservice Inspection Program.
Changes to the Program Listings of schedules may be made at any time to ensure exams are listed properly, rescheduled following an outage, clarified, or upgraded.
Except for typographical errors in listings of schedules, these changes to the program will be documented on a Change Notice and placed in front of the listings of components subject to examination. The Change Notice should show the unique ID number of the weld or component; the date_of the change; and the reason for the change. Changes to the program listing of schedules will be made by the ISI NDE Specialist and reviewed by the Senior Nuclear Results Engineer.
In accordance with AI-701, listing of schedules which are changed extensively are excluded from the revision process.
Common administrative minimum requirements as described in AI-701 which describe the actions necessary to control these two volumes are shown on the following pages.
9304020284 930325 DR ADOCK 05000302 l.
FLORIDA POWER CORPORATION i
Flonicia CRYSTAL RIVER UNIT # 3 Eh0RAPEHF INSERVICE INSPECTION PROGRAM PAGE 2 0F 3 PURPOSE The purpose of this two volume Program is to describe, in detail, the extent
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and frequency of examinations which will be performed during the ten year inspection interval in conformance with the examination requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition thru summer 1983 Addenda.
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REFERENCES i
1.
10CFR50.55a 2.
ASME Boiler and Pressure Vessel Code Section XI 1983 Edition thru summer I
'83 Addenda.
3.
Nuclear Procurement and Storage Manual (NPSM) 4.
Inservice Inspection Section Manual (ISISM) 5.
ASNT, SNT-TC-1A, 1980 Edition 6.
ANSI, N45.2.6 1978 Edition 7.
Reg Guide 1.14 (Reactor Coolant Pump Flywheel Integrity) 8.
Reg Guide 1.26 (Quality Group Classification) 9.
Reg Guide 1.147 (Code Case Acceptability) 10.
Reg Guide 1.150 (RPV Vltrasonic Inspection)
APPROVAL Procedures implementing Inservice Inspections are required by Technical Specification 6.8.2.lb to be reviewed by the Plant Review Committee.
Additionally, the Manuals will be reviewed by responsible ISI NDE Specialist and approved by the Manager, Nuclear Plant Technical Support.
Review and approval will be documented on the front page of each Manual.
1 REVISION Revisions to the Administrative Procedures contained in the manual are reviewed by the responsible ISI NDE Specialist and approved by the Manager, Nuclear Plant Technical Support. This review and approval is documented on the title page of each Administrative Procedure.
1 Revisions to NDE Procedures will be prepared by an individual certified to Level 11 in accordance with SNT-TC-1A and also reviewed by the ISI NDE i
Specialist and approved by the Manager, Nuclear Plant Technical Support.
I In accordance with AI-701, listings of schedules which are changed extensively are excluded from the revision process.
r REVIEW In accordance with AI-701, due to the structure and content of the NDE Program Manuals, periodic review is not required.
FLORIDA POWER CORPORATION Ficnicia CRYSTAL RIVER UNIT # 3 M........ '
INSERVICE INSPECTION PROGRAM i
PAGE 3 0F 3 DEFINITIONS Definitions for the NDE Program Manuals are not consolidated into one section but are shown in Administrative and Technical Procedures where required.
i DISTRIBUTION i
The NDE Program Manuals are distributed by Document Control on a need to know basis to those persons approved by the Manager, Nuclear Plant Technical Support.
l TECHNICAL CONTENT Tables of Contents are included throughout the NDE Program Manuals.
Each Administrative Procedure contains a procedure interface matrix showing t
implementing documents and interfaces.
RELIEF REQUESTS Applicable Relief Requests are included in Section 10 of the Manual only after these requests for Relief have been approved by the NRC.
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FLORIDA POWER CORPORATION
-Flowichs CRYSTAL RIVER UNIT-# 3
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- INSERVICE INSPECTION PROGRAM
. VOLUME II SECTION I INSERVICE INSPECTION PROGRAM This section contain: the Inservice Inspection Program (ISIP). The ISIPois a general document which is provided to the regulatory authorities.
The ISIP-provides:
A.
The extent of examinations B.
Examination Boundaries C.
Relief Requests D.
Basis from which the detailed Inservice Inspection Program is established e
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A FLORIDA POWER CORPORATION F9k>rkd8 CRYSTAL RIVER UNIT # 3
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INSERVICE INSPECTION PROGRAM i
VOLUME II SECTION 1 INSERVICE INSPECTION PROGRAM TABLE OF CONTENTS i
STEP DESCRIPTION
. PAGE NO.
1.0 BASIS FOR THE INSERVICE INSPECTION PROGRAM 1
2.0 THE SECOND TEN YEAR INSPECTION INTERVAL 1
l 3.0 APPLICABLE ASME CODE 1
i 4.0 INSERVICE INSPECTION PROGRAM 2
l 5.0 EXTENT OF EXAMINATIONS 2,3 6.0 EXAMINATION B0UNDARIES 3,4 l
7.0 AUGMENTED INSERVICE INSPECTIONS 4
8.0 RELIEF RE0 VESTS 5'
9.0 EXAMINATION MATRIX 5,6,7 10.0 CODE CASES 8
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FLORIDA POWER CORPORATION FlcMicia CRYSTAL RIVER UNIT # 3
[
INSERVICE INSPECTION PROGRAM PAGE 1 0F 8 4
TNSERVICE INSPECTION PROGRAM 1.0 Basis For the Inservice Inspection Proaram (ISIP)
The base document from which the ISI plan, schedule, and program are developed is 10 CFR50.55a(g).
Gilbert Commonwealth was the Architect Engineer for Crystal River Unit 3 during construction.
Florida Power j
Corporation's Nuclear Engineering Group determined the American Society of Mechanical Engineers (ASME) Code Classification of plant components.
NRC Regulatory Guide 1.26 was used during the Florida Power l
Corporation's classification.
j 2.0 The Second Ten Year Inspection Interval 2.1 The commercial operation date for Crystal River Unit 3 was March 13, 1977. The end of the first interval is March 13, 1987, and the Second Ten Year Inspection Interval is March 14, 1987 to March 15, 1997.
2.2 The three 40 month inspection periods during the second inspection interval are as follows:
1st Period:
From March 14, 1987 to July 14, 1990 2nd Period:
From July 15, 1990 to November 15, 1993 3rd Period:
From November 15, 1993 to March 14, 1997 3.0 Applicable ASME Code 3.1 The inservice inspection of ASME Class 1, 2 and 3 components is performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1983 Edition through Summer 1983 Addenda, except where specific written relief from examinations and testings determined to be impractical has been granted by the NRC pursuant to 10 CFR Part 50, Section 50.55a (g) (6) (i).
j 4.0 Inservice Inspection Proaram 4.1 The Inservice Inspection (ISI) Program is a detailed living document r
which is subject to review by regulatory and enforcement authorities having jurisdiction at the plant site.
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i FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT # 3 INSERVICE INSPECTION PROGRAM PAGE 2 0F 8 INSERVICE INSPECTION PROGRAM
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4.2 The ISI Program provides:
1 4.2.I ASME Section XI examination category and item listing 4.2.2 Specific examination identification and location 4.2.3 Weld joint configurations 4.2.4 Nondestructive examination procedures 4.2.5 Ultrasonic calibration standards list 4.2.6 Applicable list of isometric drawings 4.2.7 Listing of augmented inservice inspections 4.2.8 Relief requests 4.2.9 Listing of completed inspections f
4.2.10 Listing of Code Cases used by FPC 4.3 The scheduling of inservice inspections is in accordance with ASME Section XI.
Specific component scheduling is completed by Florida Power Corporation procedures. This form of scheduling provides maximum optimization for performing inspection during normal maintenance activities and maintains exposure as low as reasonably achievable.
l 4.4 Records and reports are prepared in accordance with ASME Section XI IWA-6000.
5.0 Extent of Examinations 5.1 All components are examined in accordance with ASME Section XI, Subsections IWA, IWB, IWC, IWD, and IWF.
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FLORIDA POWER CORPORATION-M CRYSTAL RIVER UNIT # 3 M.........T.
INSERVICE INSPECTION PROGRAM PAGE 3 0F 8 4
INSERVICE INSPECTION PROGRAM 5.1.1 The extent of examinations for ASME Code class 1 and 2 pipe i
welds is determined by the requirements of Tables IWB-2500 and 1
IWB-2600, Category B-J for Class 1, paragraph IWC-1220 Table IWC-2520 Category C-F and C-G, and paragraph IWC-2411 for Class 2 in the 1974 Edition through the Summer 1975 Addenda for ASME Section XI.
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5.2 All ASME Code class 1, 2, and 3 piping components have been reviewed against the respective ASME Section XI IWB-1220, and IWC-1220 and IWD-1220 exemption criteria.
i 5.3 All ASME Code class 3 systems and exempt ASME Code class 1 and 2 components require only visual examination during pressure test.
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5.4 All ASME Code class 1, 2, and 3 components are categorized in accordance with ASME Section XI Table IWB-2500-1, Table IWC-2500-1 and Table IWD-2500-1 respectively.
6.0 Examination Boundaries 6.1 Examination boundaries are those of ASME Code class 1, 2, and 3 installed components, their attachments and supports.
6.2 ASME Code class I, 2, and 3 boundaries are identified on Color Coded i
P&ID's and are located at the Crystal River Unit 3 Station.
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6.3 The following systems or portions of systems are included in the ISI examination boundaries.
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6.3.1 Main & Reheat Steam I
6.3.2 Feedwater 6.3.3 Emergency Feedwater 6.3.4 Auxiliary Steam 6.3.5 Condensate.
6.3.6 Condensate & Demineralized Water Supply i
6.3.7 Chemical Clean Steam Generators 6.3.8 Domestic Water 6.3.9 Instrument Air Station & Service Air i
6.3.10 Emergency Diesel Generator Fuel Oil Transfer
'i 6.3.11 Emergency Diesel Generator Compressed Starting Air Exhaust i'
6.3.12 Jacket Coolant Flow 6.3.13 Air Cooler Coolant 6.3.14 Nuclear Services Closed Cycle Cooling l
6.3.15 Nuclear Services Decay Heat Sea Water
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6.3.16 Spent Fuel Cooling 6.3.17 Chemical Addition 6.3.18 tiquid Sampling l
FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT # 3 M..........I.
INSERVICE INSPECTION PROGRAM PAGE 4 0F 8 INSERVICE INSPECTION PROGRAM 6.3.19 Nitrogen, Hydrogen & C02 6.3.20 Liquid Waste Disposal 6.3.21 Gas Waste Disposal 6.3.22 Containment Monitoring System 6.3.23 Post Accident 6.3.24 Core Flooding System 6.3.25 Reactor Building Pressure Sensing & Testing 6.3.26 Reactor Building Spray 6.3.27 Reactor Building LRT System & Post Accident Hydrogen Purge System 6.3.28 Post Accident Ventilation System 6.3.29 Chilled Water 6.3.30 Industrial Cooling Water 6.3.31 Control Complex EFIC Room 7.0 Auamented Inservice Inspection 7.1 In addition to the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, additional examinations are scheduled to be performed to satisfy commitments made through Florida Power Corporations j
Compliance or Licensing Departments or which may be required by the Technical Specification.
7.2 The Augmented Inservice Inspections performed at Crystal River Unit 3 are as follows:
1.
Inspection of High Pressure Injection Thermal Sleeves 2.
Reactor Coolant Pump Flywheel Examinations completed in accordance with Regulatory Guide 1.14 - Reactor Coolant Pump Flywheel Integrity.
3.
Visual examination of Emergency feedwater headers, j
4.
Reactor Vessel examinations completed in accordance with Regulatory Guide 1.150.
5.
Reactor Vessel Exams conducted in accordance with the requirements of the '89 Edition of Section XI once 10 CFR 50 has been amended to include Section 50.55 a(g)(ii)(A)(2).
i 6.
Pressurizer Surge Line Inspections performed per Nuclear Operations Engineering recommendation to s3tisfy Pressurizer Surge Line stratification issue.
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FLORIDA POWER CORPORATION Flonicia CRYSTAL RIVER UNIT-# 3 INSERVICE INSPECTION PROGRAM PAGE 5 0F 8 INSERVICE INSPECTION PROGRAM 8.0 Relief Recuests 8.1 When an ASME Section XI Code requirement is determined to be i
impractical, specific written relief is requested from the Nuclear Regulatory Commission.
Each written relief request contains the following:
8.1.1 Component (s) for which relief is requested-8.1.2 The specific ASME Code requirement that has been determined to be impractical 8.1.3 The basis for requesting relief request 8.1.4 The proposed alternate examination 8.1.5 The Implementation Schedule 8.2 Relief Requests submitted to the Nuclear Regulatory Commission are included in Section 10 of this manual after they have been approved.
9.0 Examination Matrix 9.1 The following list contains by category, the number of components, supports, and attachments subject to inspection and the number of components, supports, and attachments to be inspected during the second ten year inspection interval (Inspection Interval 2).
TOTAL CHOSEN ASME CODE CATEGORY TOTAL NUMBER (INTERVAL 2)
B-A 14 8
B-B 23 15 B-D 27 27 B-E 122 32 B-F 92 87 l
B-G-1 314 313 i
B-G-2 48 47 B-H 21 19 i
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FLORIDA POWER CORPORATION M
CRYSTAL RIVER UNIT-# 3 M...........
INSERVICE. INSPECTION PROGRAM PAGE 6 0F 8 l
t INSERVICE INSPECTION PROGRAM 9.0 Examination Matrix 9.1 (CONTINUED)
TOTAL CHOSEN ASME CODE CATEGORY TOTAL NUMBER (INTERVAL 2) l P
B-J 407 116 B-K-1 12 6
B-L-1 8
2 B-L-2 7
2 B-M-1 6
6 B-M-2 4
4 B-N-1 3
3 B-N-2 2
2 r
B-N-3 1
B-0 (LISTED UNDER CATEGORY B-E)
I B-P (ADDRESSED BY HYDR 0 AND SYSTEM LEAK PRESSURE TEST PROGRAMS)
B-Q 24 3
r C-A 32 24 l
C-B 12 6
j C-C 30 11 i
C-D NONE NR C-F 831 148 C-G NONE NR C-H (ADDRESSED BY HYDRO AND SYSTEM LEAK PRESSURE TEST PROGRAMS) i D-A (T0 BE DETERMINED BY FPC) t 9
FLORIDA POWER CORPORATION M
CRYSTAL RIVER UNIT # 3 h..........
INSERVICE INSPECTION PROGRAM PAGE 7 0F 8 INSERVICE INSPECTION PROGRAM 9.0 Examination Matrix 9.1 (CONTINUED)
TOTAL CHOSEN ASME CODE CATEGORY TOTAL NUMBER (INTERVAL 2)
D-B (T0 BE DETERMINED BY FPC)
D-C (T0 BE DETERMINED BY FPC)
AUGMENTED EXAMINATIONS 16 16 F-A:
CLASS 1 3
3 CLASS 2 6
3 CLASS 3 67 12 F-B:
CLASS 1 33 32 CLASS 2 243 85 CLASS 3 469 133 F-C:
CLASS 1 146 (109*)
144 (109*)
)
CLASS 2 174 (85*)
119 (85*)
CLASS 3 87 (15*)
26 (15*)
- Delineates the total number of snubbers included in the count.
NOTE:
Volume II Section 6 of this program contains specific comments related to ASME Code changes, relief requests, etc. which in some cases affected the number of items chosen in a given code category.
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N FLORIDA POWER CORPORAT80N FlCMSCLS CRYSTAL RIVER UNIT # 3 e
.Ih044.N.D..T.
INSERVICE INSPECTION PROGRAM i
PAGE 8 0F 8 l
l INSERVICE INSPECTION PROGRAM 10.
Code Cases The following Code cases have been accepted by Florida Power Corporation to be used during the second interval of operation.
Code Case Description i
N-356 Recertification of Level III personnel by examination on a
(
triennial basis j
N-401-1 Digitized collection and storage of eddy current data N-416 Alternative rules for Hydrostatic testing of repair or replacement of Class II piping N-424 Qualification of visual examination personnel r
N-446 Recertification of visual examination personnel N-460 Alternative examination coverage for Class 1 and Class 2 welds N-498 Alternative rules for 10 year Hydrostatic Pressure testing for Class 1 and Class 2 systems N-491 Alternative rules for examination of Class 1, 2, ar.d 3 and MC component supports of light water cooled power plants f
Copies of accepted Code cases are shown in Section 9 of this manual.
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CHANGE NOTICE UNIQUE ID#
DATE REASON N/A 9/14/92 Added As-built drawings for 18 calibration standards.
Revised Calibration Standard Drawing Table of Contents (Section 4).
B6.7.01 9/15/92 Added "Not Applicable" to Notes column.
Examinations are limited to one valve within each group of valves that are of the same design and perform similar functions.
B6.7.03 9/15/92 Added note in column, " Perform VT-3 during RF-9 on B6.7.04 DHV-1 or DHV-2."
B6.7.05 9/15/92 Added note " Perform VT-3 during RF-9".
Showed exam B6.7.06 as "Not Applicable".
DI.l.254 10/8/92 Showed exam as being scheduled and completed during 2* period, 2* interval.
N/A 10/8/92 Changed Section 5 to show new drawing revisions at i
Table of Contents for Components and Class 1, 2, &
u 3 Piping and Hangers.
N/A 10/13/92 Added Relief Request N-498 to listing of Relief Requests in Section 10.
B2.6.1 1/6/93 Removed B2.6.1 from Program. These Manway Studs had been inspected in RF-VIII.
Item # was for Studs When Removed.
Completed By:
b Date.: JL. // f3 ISI Specialist /
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Reviewed By:
Date: R '/O SgKior Nuclear Results Engineer
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CHANGE NOTICE i
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B2.6.3 8/20/92 Deleted Visual Inspection requirements for Heater Bundle studs l
B2.7.2 and added words "and nuts" and "when removed" to B2.5.2.
B2.11.4 Only 1 unique ID number is assigned for all heater bundle studs and nuts Visual Exam. Deleted B2.6.3, B2.7.2 and 82.11.4 from j
Drawing SK1AC9.
l C2.1.143 8/20/92 RV-178E Changed to ERV-178E.
C2.1.145 8/20/92 RV-178A changed to ERV-178A.
C2.1.146 8/20/92 RV177A changed to ERV-177A.
C2.1.153 8/20/92 RV-54 changed to ERV-54.
C2.1.157 8/20/92 RV-141A changed to EFW-141A.
f B4.10.209 8/20/92 Deleted 84.10.209 and MUH-56 from Plan and from drawing l
hanger removed.
SK102.1 8/20/92 Changed title to show S/G "A" instead of S/G "3A".
t B4.5.198 8/25/92 Deleted surface examination (MT).
B4.5.221 Not required by extent of '74 Edition.
B6.7.02 8/25/92 Changed VT-1 to VT-3
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8 Date:
0 92 Spior Nuclear Results Engineer l
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CHANGE NOTICE UNIQUE DATE REASON ID#
B4.5.194 7/30/92 Changed Iso SK-15.1 to show unique ID B4.5.194 at MK A15 to MK 14 at "A" S/G. Removed B4.5.191 from sketch SK-15.1 only.
B4.5.205 7/30/92 Changed Iso SK-15.1 to show unique ID B4.5.205 at MK B15 to MK 14 at "B" S/G. Removed B4.5.199 from sketch only.
Scheduled B4.5.205 for examination during Interval 2, Period 3.
Removed requirement for examination of B4.5.199 during interval 2, Period 3. B4.5.191 and B.4.5.199 are made totally inaccessible by Whip Restraints.
83.2.1.1 8/4/92 Added B3.2.1.1 thru B3.2.6.1. to show distinct requirement for thru examination of nozzle inner radius section. Added item number 83.2.6.1 as shown by '83 Edition.
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Reviewed By:
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CHANGE NOTICE i
UNIQUE DATE REASON j
ID#
l B4.5.194 7/30/92 Change Iso SK-15.1 to show unique ID B4.5.194 at MK A15 to j
MK 14 at "A" S/G. Remove B4.5.191 from sketch SK-15.1 only.
l B4.5.205 7/30/92 Change Iso SK-15.1 to show unique ID B4.5.205 at MK B15 to MK 14 at "B" S/G. Remove B4.5.199 from sketch only.
Schedule B4.5.205 for examination during interval 2, Period 3.
Remove requirement for examination of B4.5.199 during Interval 2, Period 3. B4.5.191 and B.4.5.199 are made totally inaccessible by Whip Restraints.
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Date:
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Se'rior Nuclear Results Engineer
CHANGE NOTICE UNIQUE DATE REASON i
ID#
B4.9.7 7/21/92 Removed from Database and from Drawing SKH1.1 - hanger l
does not exist.
B4.10.13 7/21/92 Rescheduled for Refuel 9 in accordance with IWB-2420.
j B4.10.228 7/21/92 Removed from database and from drawing SKH-5.1 - lugs do not f
exist.
B2.6.1 7/21/92 Deleted words "when removed"in comments column and rescheduled for Refuel 9 in accordance with IWB-2420.
X0.3.1 7/21/92 Rescheduled for Refuel 9 - changed comments column to show X0.3.2 Refuel 9, not required in Refuel 8.
X0.3.3 X0.3.4 B1.5.1.46 7/21/92 Rescheduled for Refuel 9 in accordance with IWB-2420.
through B1.5.1.69 2
C2.1.136 7/21/92 Rescheduled for Refuel 9 in accordance with !WB-2420.
C1.2.2B 7/23/92 Rescheduled for Refuel 9 in accordance with IWB-2420.
i C2.1.11/
//23/92 Rescheduled for Refuel 9 in accordance with IWB-2420.
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Date: 7 M 95 Completed By:
ISI Specialist
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CHANGE NOTICE UNIQUE DATE REASON ID#
SKH-224 6/30/92 Changed S\\W-308 to S\\W-46. Changed reference CHHE-1A to Sheet 1 CHHE-1B and CHHE-1B to CHHE-1A. Items were incorrectly shown on drawing.
SKH-219 6/30/92 Changed valve SWV-357 to S\\W-57. Item was incorrectly Sheet 1 shown.
Volume 2 6/30/92 Added description for use of isometric sketches.
Section 5 D.1.1.593 6/30/92 Selected D.1.1.594 for examination in lieu of D.1.1.593.
Changed drawing SKH-226-1 to show unique ID. D.1.1.594 at SWA-82 and changed program plan to select D.1.1.594 for Exam 2nd period,2nd interval. D.1.1.593 was assigned to a penetration with fire proofing and was totally inaccessible.
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7 Completed By:
ISI Specialist
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Date:
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SeTiior Nuclear Results Engineer
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CHANGE NOTICE UNIQUE DATE REASON ID#
B4.5.152 6/17/92 Rescheduled for 3rd Period in accordance with Table IWB-2412-84.5.153 1.
B4.10.1 l
B4.5.200 MT B4.5.200 UT Hangers B4.10.160 B4.10.231 C2.6.265 l
C2.6.409 C2.6.414 C2.6.423 D1.1.254 D1.1.364 D1.1.367 l
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Sen6r Nuclear Results Engineer
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CHANGE NOTICE UNIQUE DATE REASON i
ID#
B4.1.58 6/15/92 Eliminated item B4.1.58 from Program Plan and from drawing SK17-1, item is less than 4".
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l B4.1.57 6/15/92 Changed size to <4".
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9 J.4E6 k 6/15/92 Eliminated B4.1.72 from Program Plan and from Drawing SK1f-1) f 6Y4 7%
Item is <4".
B4.1.71 6/15/92 Changed size to <4".
C24T7 6/15/92 Moved unique ID C2.1.117 to weld 26A on isometric sketch C2_/./
SK103.1. Weld 27B is at a restraint and cannot be examined. In accordance with Table IWC 2500-1(d). Weld at structure j
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discontinuity.
D1.1.413 6/16/92 Change Program Plan and SKH-219.1 to show SWR-621 as being SWR-521.
D1.1.439 6/16/92 Change Program Plan and SKH-221.1 to show SWH-152 as being l
SWR-152.
N/A 6/16/92 Change sketch SKH-212 Sheet 1 to show valves on chiller suction CHHE-1A as being CHV-14 and CHV-64. Sketch was labeled incorrectly A
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Date: f[/7 82- __
Sengr Nuclear Results Engineer
CHANGE NOTICE t*
UNIQUE i DATE REA3ON ID#
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B6.7.2 5/29/92 Changed scheduled VT-rof DHV-4 from 3rd period to 2nd period in accordance with IWB-2420.
B4.5.199 6/11/92 Rescheduled B4.5.199 for 3rd period in accordance with IWB-2412-1.
N/A 6/10/92 included all pipe database and component support database for Period 2 Interval 2 to include changes made to schedule.
84.5.191 6/11/92 Scheduled B4.5.194 at Mk A15 to Mk 14 for examination this outage in lieu of B4.5.191. B4.5.191 is made totally inaccessible by whip restraint in accordance with Table IWB-2500-1(d).c4rd-J D1.1.111 A 3/15/92 Deleted hanger SWR-117 from Program Plan and from isometrics sketch SKH-206.1. Hanger does not exist.
D1.1.400 6/15/92 Deletec' hanger SWR-136 frorn Program Plan and from Isometric Sketch SKH-218.1. Hanger does noyxisty pys -
B1.12.1 6/15/92 VT-3 was shown in VOL columrts-moved to VT column.
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, B2.3.1 6/15/92
, *
- B-E hdf B2.3.1 Showed as:
Sitf j
Const. Id.
Cf4G Cat.
Item #
0*g 4T Mat Spec h 5.T.
Per.
Int.
Top. %ddle & Bottom HtrC M
IW 20 5K1AC9 2 SA21 NA 2
3 2
l B5.3.01 6/15/92 Deleted top casing weld B5.3.01 thru 5.3.04 r-n SK-1AC12 and l
thru showed flange bolting as being B5.3.01 thru B5.3.04. Drawing B5.3.04 was incorrect.
B4.10.2 ?4 6/15/92 Deleted from Program Plan and from SKH-1.1 DHA-2 is not
{
installed.
l 84.1.28 6/15/92 Changed Cal Block from 40753 to 40720. Cal Block 40753 was incorrect.
B.4.6.6 6/15/92 Changed item number to B9.32 and eliminated UT, item is less than 4" diameter. Showed size as 2.5".
j SK19.1 j6/15/92 Changed Ref. at 2 " press spray line from SK11-1 to SK12-1.
'E Completed By:
y Date:
6, 7
J-
/
151 Specialist Reviewed By:
Date:
- / '7/ f 2.
Se[br Nuclear Results Engineer
CHANGE NOTICE UNIQUE DATE REASON ID#
B4.1.13 6/5/92 Deleted examinations from Examination Program Plan. These B4.1.14 examinations are exempt per IWB-12 (b) 1. 36uer#o 84.1.15 W M 20 #' M S'OS* N b ' 9h B4.1.16
,. B4.1.17 B4.1.18 B4.1.19 B4.1.20 B4.1.21 B4.1.22 B4.1.23 B4.1.24 B4.1.29 B4.1.30 B4.1.31 B4.1.32 B4.1.33 B4.1.34 B4.1.35 B4.1.36 64.1.37 B4.1.38 B4.1.39 B4.1.40 B4.1.45 B4.1.46 B4.1.47 B4.1.48 B4.1.55 B4.1.56 B4.1.59 B4.1.60 B4.1.73 B4.1.74 ll Completed By:
&Ibeb Da.c: 0/
98-ISI Specialist
/
6 /N!ft Reviewed By:
N O
Date:
S(Mior Nuclear Results Engineer
' ~
CHANGE NOTICE UNIQUE DATE REASON ID#
MUH-16 5/28/92 Changed MUH-16 to MUH-6 on drawing and in Program Plan.
MUH-16 was labeled incorrectly. (Dwg. SKH7-2).
SK1AC8 6/3/92 Changed isometric sketch Mk number at lower head to shell.
Mk #6 to 1 should be Mk #6 to 4. Also changed Program Plan to show Mk #6 to 4 at B2.1.11A.
SKH5 6/3/92 Showed valve on SKH5 Sheet 2 at Class 1 & 2 line break as Sheet 2 being MUV-160 for clarification.
1 i
G![ FA Completed By:
~
~.d; Date:
4 151 Specialist
/
Reviewed By:
8 Date: 86 P-Segor Nuclear Results '. og eer
CHANGE NOTICE UNIQUE DATE REASON i
ID#
B4.10.139 5/18/92 Scheduled hanger for examination Interval 2, Period 2, to coincide with examination of attachment welds B4.9.9 on SK4-3 l
sheet 1.
B3.10.2 5/19/92 Corrected Const ID ST, configuration and bolt size for 3.10.2 B3.10.7 and 3.10.7. These were incorrectly shown on SK1AC-6.
Changed isometric sketches.
B2.8.1 5/19/92 Deleted all exarns with even numbers.100% coverage can be i
thru achieved by doing exams from the lug side. Scheduled B2.8.16 remaining exams for 2nd period.
B4.1.56 5/20/92 Changed isometric sketch SK11-1 to delete B4.5.56 and add i
B4.1.56. Isometric was incorrect.
C1.2.5A 5/21/92 Deleted from
- Drawing and from Program Plan.. In vessels of C1.2.5B similar design, size and service the required exams may be C1.2.6A limited to one vessel '83 Edition.
C1.2.6B SK1AC6 5/21/92 Changed drawing to reflect correct axis. Axis were reversed on SK1AC7 top head detail.
SK118-1 5/21/92 Added unique ID #C2.1.726 to drawing. Uniqce ID number l
was not shown.
I SKH-107-2 5/28/92 Changed isometric sketch to delete F\\W-162 and add EFV-56 i its place. Added tee downstream of EFH-72. Added PI-305-9 to show Ref. Iso.._rc'os>dra c//strda.t(s 5/dousc;-
lF !
r N/A 5/28/92 Changed heading on isometric sketches SK107-1, SK107-2, SKH107-1, SKH107-2, SK108-1, SK108-2, SKH108-1, SKH108-2.
Heading should show EFW in lieu of FW. Changed Class 2 l
piping Table of Contents.
A9 !fd--
Completed By:
/
/ME Date:
15i Specialist
/
/
i Reviewed By:
Date: 8 28 f &
S$6ior Nuclear Results Engineer l
I CHANGE NO'llt;E UNIQUE DATE REASON ID#
B4.5.369 5/15/92 Changed Isometric sketch SK17 Sheet 1 to show unique ID b4.5.370 numbers at MK 63 to MK 63. Unique ID numbers were shown incorrectly.
P t
1 P
Completed By:
Ih,b Date: 6
/
7A ISI Specialist
[
Date: 5592 Reviewed By:
_$dnior Nuclear Results Engineer
1 CHANGE NOTICE 4
UNIQUE DATE REASON l
ID#
B4.5.387 5/12/92 Added calibration block #40770. Block was not shown in i
Program Plan.
l SK210 5/12/92 Changed Isometric sketches to move S\\W-46 and S\\W-308.
Sheet 1 Valves were incorrectly drawn on original sketches.
SK224 Sheet 1 C2.1.135 5/13/92 Changed weld ID to C2.1.185. Weld ru was incorrect on isometric sketch-=d ;n P.c,gan, Nea 9-SK110 5/13/92 Added Unique ID #C2.1.170 at DH 70. Unique ID number Sheet 2 was not shown on original drawing.
1 i
i 1
I 9
7 m
P
!9J-Completed By:
A Date: e1 151 Specialist
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/
f /'//f2 Reviewed By:
[
Date:
Sstior Nuclear Results Engineer
d
.~
CHANGE NOTICE UNIQUE DATE REASON ID#
C2.1.125 5/8/92 Add Cal Block 40772 C2.1.129 5/8/92 Add Cal Block 40773 C2.1.131 C2.1.136 C2.1.141 C2.1.212 5/8/92 Add Cal Block 40771 B4.1.74 5/8/92 Add Cal Block 40753 B2.8.1 5/8/92 Add Cal Block 40752 B2.8.2 B2.8.8 B2.8.16 CAL BLOCKS WERE NOT SHOWN IN ORIGINAL PROGRAM PLAN.
Completed By:
Date:
/0 9J-ISI Specialist
/
//!@2 Reviewed By:
_Serfor Nuclear Results Engineer Date:
.~
CHANGE NOTICE UNIQUE DATE REASON ID#
B5.3.01 4/1/92 Rescheduled all Reactor Coolant Pump Bolting Visual Exams for i
Thru Second Period. Bolting was originally examined 2nd period of B5.3.04 First Interval.
f t
4 i
e Completed By:
\\//
b Date:
kl
!SI SpecYalisT
/
s [f!92 Reviewed By:
Date:
Se(rior Nuclear Results Engineer j
4 CHANGE NOTICE UNIQUE DATE REASON ID#
C2.2.86 4/29/92 Changed Isometric Sketch SK-111 Sheet 2 to delete welds.
3 C2.2.87 C1.1.5 4/29/92 Deleted "B" and "C" identifiers for unique ID on isometric sketch thru and changed sketch to show welds on primary side of decay C1.1.8 heat coolers. (Sketch 1-AC11).
C1.1.4 4/29/92 Changed isometrics sketch to delete identifiers "A", "B", and "C".
(Sketch 1-AC7)
C1.1.1 and 4/29/92 Changed isometric sketch to delete "A", "B", and "C" identifiers.
C1.1.2 (Sketch 1-AC6)
SK1 AC5 4/29/92 Deleted unique ID numbers and arrows. Visual Exams are shown on Hydrostatic Test Program.
B1.1.3A 4/29/92 Showed unique ID# as being 180* to O' B1.1.38 Showed unique ID# as being 180* to O' B1.12.1 Added unique ID# for mark 36 to mark 37 (SK1-AC2)
B1.1.3 4/29/92 Showed unique ID# for mark A1 to mark A1 B1.1.5 Showed unique ID# for mark A2 to mark A2 B1.1.6 Showed unique ID# for mark A2 to mark A2 B1.5.1.46 4/29/92 Revised isometric sketch to show peripheral CRDM's scheduled thru for examination (SK-11AC4)
B1.5.1.69 i
A Completed By-1 \\/ 6Lblt Date:
EQ ha s.
~ 5tTpecialist
/
)
1
- /!Jo 2 Reviewed By:
E Date:
Sedor Nuclear Results Engineer
h CHANGE NOTICE UNIQUE DATE REASON ID#
Relief 4/21/92 Deleted Relief Requests. Code Cases were already approved in Request Reg. Guide 1.147, Rev. 6. See Safety Evaluation for 2nd ten-
- 88-030 year interval ISI Plan dated 4/13/92.
& 88-040 t
t Completed By:
Y Date:
M 91.-
ISI Spec'ialist
/
'/
/
t/!'J772 Reviewed By:
Date:
S(dor Nuclear Results Engineer 6
=
i CHANGE NOTICE I
UNIQUE DATE REASON ID#
B1.3.2.1 3/11/92 Added magnetic particle examination and scheduled all flange to head welds for 2nd interval 3rd period in accordance with 1983 Edition requirements. Item was not required in 1974 Edition and had not been scheduled.
i P
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Completed By:
/
1 Date:
ISI Specialist
/
Reviewed By:
Date: 1 d 8
SeMor Nuclear Results Engineer I
9 CHANGE NOTICE UNIQUE DATE l REASON ID#
B1.9.1.01 3/27/92 Deferred to end of ir.spection interval - 2nd interval, 3rd period t
thru in accordance w;th 1983 Edition requirements.
B1.9.1.20 r
r i
Completed By:
hv Date: 8
/9A e
151 specialist'
/
/
Reviewed By:
Date: 3 30 f3 8'enior Nuclear Results Engineer
s i
CHANGE NOTICE UNIQUE DATE.
REASON ID#
Section 9 2/21/92 Listing of Hydrostatic and Pneumatic Examination boundaries, of along with listing of Hydrostatic and Pneumatic Test Pressures Volume 2 and temperatures and associated flow diagrams has been deleted. These are now shown in the Hydrostatic Test Program Manual.
B1.3.2A 2/21/92 Deleted 0 to 120 and added 10 to 31 to show area examined B1.3.2B 2/21/92 Deleted 120 to 340/ added 42 to 50 to show area to be examined B1.3.2C 2/21/92 Deleted 240 to 360/added 50 to 10 to show area to be i
examined B1.5.1.01 2/21/92 Changed category and item number to conform to '83 edition.
thru showed configuration as CRDM housing.
B1.5.1.45 B1.5.1.46 2/21/92 Scheduled Peripheral CRDM's for examination thru l
81.5.1.69 i
B1.5.2.01 2/21/92 Deleted instrumentation nozzle visual exams. These are shown thru in Hydrostatic Test Program.
B1.5.2.52 B1.5.2.01 2/28/92 Deleted item ' numbers from schedule. These instrumentation thru nozzle visual exams are shown in Hydrostatic test program and B1.5.2.52 completed by SP-207 - Class 1 System Hydrostatic test.
l 1
B1.6.1 3/2/92 Added new relief request #90-10 thru i
B1.6.4 l
B1.8.5.1 3/2/92 Deleted exams and added note - not required by '83 Edition.
thru i
81.6.5.59 B1.12.1 2/21/92 Changed category item # and method to conform to '83 edition deleted Rfr #140 and added Rfr #90-060. Scheduled 3rd period, 2nd interval.
i e
/&lI4ch Date:
8 A
Completed By:
N ISI Specialist
/
)
Reviewed By:
Date:
3/3d2 Sullior Nuclear Results Engineer
i 3
J l
CHANGE NOTICE UNIQUE DATE REASON ID#
B1.15.1 A 2/21/92 Deleted Rfr# 101 - shown incorrectly and Rfr #020 no longer B1.15.1 B applies 2nd intewal.
B1.15.1 C B2.1.3 2/28/92 Deleted from schedule '83 Edition requires only 1 foot of one thru weld per head.
B2.1.8 B2.4.251 3/3/92 Added Pressurizer surge line inspections per Nuclear B2.4.253 Operations Engineering recommendation. Ref. NRC Sulletin 88-B2.4.254 11.
B3.1.1 A 2/21/92 Rescheduled welds to be completed during last period in B3.1.1 B accordance with code requirement.
B3.1.1 C B3.1.3 2/28/92 Deleted from schedule '83 Edition show exams may be B3.1.4 limited to one vessel among a group of vessels performing a similar function 83.7.2 2/28/92 Deleted. '83 Edition-in multiple vessels of similar design, size, and service, the examination is limited to the attachment welds of one vessel.
B4.1.18, 2/21/92 Deleted Rfr #60. Does not apply 2nd interval 20,22,24, 30,32,34, 36,38,40, 72,74 B4.1.26 2/21/92 Deleted Rfr #60. Does not apply 2nd interval B4.1.28 2/21/92 Deleted Rfr #60. Does not apply 2nd interval B4.1.4 2/21/92 Deleted Rfr #60. Does not apply 2nd interval B4.1.42 2/21/92 Deleted Rfr #60. Does not apply 2nd interval B4.1.44, 2/21/92 Deleted Rfr #60. Does not apply 2nd interval.
46,48,50, 58,60,62 B4 1.6 2/21/92 DeletegRfr #60. Does not apply 2nd interval kB h 1
Date: 8k/f>-
Completed By:
ISI SfcIcialist
/
Reviewed By:
_Y u Date: 8192' SVnior Nuclear Results Engineer
l u
o.
CHANGE NOTICE i
n.
UNIQUE DATE REASON ID#
I B4.5.242 2/21/92 Deleted Rfr #70. Does not apply 2nd interval B5.6.01 3/2/92 Added Rfr #90-50 granted.
thru B5.7.08 B5.6.03 3/2/92 Deleted Rfr #130. No longer applies.
B5.6.04 85.7.03 i
B5.7.04 l
B5.10.1 3/2/92 Scheduled RCP exams - UT and PT items had not been thru scheduled. Added note under comments.
B5.10.8
)
B6.1 3/2/92 Added items from '83 Edition and showed not applicable.
thru B6.5 C1.1.1 A 2/21/92 Scheduled for 3rd period in accordance with code C1.1.18 requirements.
C1.1.1C C1.1.2A 2/21/92 Deleted 1/3 each period and scheduled for 3rd period.
C1.1.2B C1.1.2C C1.1.4 2/28/92 Rescheduled. These exams were originally completed in the third period of the first interval.
C1.1.4A, 2/21/92 Deleted A, B, & C - Welds were originally examined during the C1.1.4 B, last period of the fir:;t interval.
C1.1.4 C C1.1.5 A 3/2/92 Deleted 1/3 each period and scheduled for 3rd period. Items C1.1.5 B were scheduled incorrectly.
C1.1.5C r
C1.1.6A 3/2/92 Deleted 1/3 each period and scheduled for 3rd period. Items f
C1.1.6B were scheduled incorrectly.
C1.1.6C r
i d h VM$.
WfA Completed By:
Date:
ISI Specialist
/
Reviewed By:
Y Date:
3h2.-
I Sdfor Nuclear Results Engineer
~
i j
=
a CHANGE NOTICE UNIQUE DATE REASON ID#
C1.1.7A 3/2/92 Deleted 1/3 each period and scheduled for 3rd period, items C1.1.78 were scheduled incorrectly.
C1.1.7C C1.1.8A 3/2/92 Deleted 1/3 each period and scheduled for 3rd period. Items C1.1.8B were scheduled incorrectly.
C1.1.8C t
C2.2.86 3/2/92 Deleted items from program plan. Elbow contains no welds.
C2.2.87 H0.01 2/21/92 DELETED - hydrostatic Tests are listed and scheduled in the l
thru Hydrostatic Test Program Manual i
H0.89 X0.1 and 2/21/92 Deleted Steam Generator "A" and "B" tubes. Examination of X0.1.1 Steam Cenerator tubes is addressed by Tech Specs.
i X0.1 2/28/92 Deleted augmented E/C exams on steam generator tubes.
X0.1.1 These exams are completed in accordance with Tech Specs.
j X0.2.1 3/2/92 Deleted exams on bolting. These augmented exams were thru performed 1st interval to satisfy MAR requirements. Exams not X0.2.8 required for second interval, j
- i X0.3.1 2/28/92 Scheduled Thermal sleeves for examination during 2nd period thru of 2nd Intervalin accordance with recommendations by X0.3.4 HPl/MU nozzle task force.
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i P
[
\\
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I Completed By-
/Yb.
Date:
Y JL ISI Specialist
/
Reviewed By:
D Date:
8 f2-Sen#r Nuclear Results Engineer I
P
e
- { '
CHANGE NOTICE UNIQUE DATE REASON ID#
N/A 3/4/92 Deleted Proc"in fields and deleted all procedure numbers.
Procedure numbers are no longer applicable.
B1.8.1.00 3/5/92 Organized schedule for examination of Reactor Vessel closure thru studs, closure nuts, threads in flange stud holes, and closure B1.8.1.59 washers and bushings, All exams had been shown for third B1.8.2.00 period or not shown. Rescheduled all for 1/3 each scheduled thru refuel.
B1.8.2.59 B1.8.4.00 thru B1.8.4.59 B1.9.1.01 thru B1.9.1.60 81.10.1.01 thru B1.10.1.60 B 1.8.5.1 3/5/92 Showed UT of closure nuts as not required by '83 Edition.
thru B1.8.5.59
>j i
i
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/
i /JN-.4
? !EE Date:
Completed By:
ISI' Specialist
/
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Reviewed By:
Date:
Y 92-Sedfor Nuclear Results Engineer
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