ML20196C501
| ML20196C501 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/09/1988 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20196C493 | List: |
| References | |
| PROC-880209-01, NUDOCS 8802160125 | |
| Download: ML20196C501 (12) | |
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FLORIDA POWER CORPORATION FLORIDA CYRSTAL RIVER UNIT #3 e
e POWER INSERVICE INSPECTION PROGRAM VOLUME II SECTION 1 INSERVICE INSPECTION PLAN This section contains the Inservice Inspection Plan (ISIP). The ISIP is 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 l
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8802160125 880209 PDR ADOCK 05000302 G
PDR 1
FLORIDA POWER CORPORATION
'e FLORIDA CRYSTAL RIVER UNIT #3 POWER INSERVICE INSPECTION PROGRAM
--no VOLUME II SECTION 1 INSERVICE INSPECTION PLAN TABLE OF CONTENTS STEP DESCRIPTION PAGE NO.
1.0 BASIS FOR THE INSERVICE INSPECTION PROGRAM 1
2.0 THE SECOND TEN YEAR INSPECTION INTERVAL 1
3.0 APPLICABLE ASME CODE 1
4.0 INSERVICE INSPECTION PLAN 1
5.0 INSERVICE INSPECTION PROGRAM 2
6.0 EXTENT OF EXAMINATIONS 2,3 7.0 EXAMINATION B0UNDARIES 3,4 8.0 AUGMENTED INSERVICE INSPECTIONS 4'
9.0 RELIEF REQUESTS 5,6 10.0 EXAMINATION MATRIX 7-9 O
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(,j PAGE 1 0F 9 INSERVICE INSPECTION PLAN 1.0 Basis For The Inservice Inspection Program (ISIP)
The base document-fron 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 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 Corporation's classification.
2.0 The Second Ten Year Inspection Interval 2.1 The commerical 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 nonth inspection periods during the second inspection interval are as follows:
U 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) (1).
4.0 Inservice Inspection Plan 4.1 The Inservice Inspection (ISI) Plan is a general document which is provided to the regulatnry authorities.
4.2 The ISI Plan provides:
4. 2.1 Extent of examinations 4.2.2 Examination boundaries d
4.2.3 Relief requests 4.2.4 Basis from which the detailed ISI Program is established.
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PAGE 2 0F 9 INSERVICE INSPECTION PLAN 5.0 Inservice Inspection Program 5.1 The Inservice Inspection (ISI) Program is a detailed living document which is subject to review by regulatory and enforcement authorities having jurisdiction at the plant site.
5.2 The ISI Program provides:
5.2.1 ASME Section XI examination catagory and item listing 5.2.2 Specific examination identification and location 5.2.3 Weld joint configurations 5.2.4 Nondestructive examination procedures 5.2.5 Ultrasonic calibration standards list
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5.2.6 Applicable list of isometric drawings 5.2.7 Listing of augmented inservice inspections 5.2.8 Relief requests 5.2.9 Status of completed inspections 5.2.10 Summary of previous inservice inspections 5.3 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 activites and maintains exposure ALARA.
5.4 Records and reports are prepared in accordance with ASME Section XI IWA-6000, 6.0 Extent of Examinations 6.1 All components are examined in accordance with ASME Section XI, Subsections IWA, IWB, IWC, IWD, and IWF.
6.1.1 The extent of examinations for ASME Code class 1 and 2 pipe welds is
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determined by the requirements of Tables IWB-2500 and 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.
FLORIDA FLORIDA POWER CORPORATION POWER CRYSTAL RIVER UNIT #3 INSERVICE INSPECTION PROGRAM wmno,e (j
PAGE 3 0F 9 INSERVICE INSPECTION PLAN 6.2 All ASME Code class 1, 2, and 3 piping components have been reviewed against the respective ASME Section XI IWB-1220, IWC-1220 and IWD-1220 exemption critera.
6.3 All ASME Code class 3 systems and exempt ASME Code class 1 and 2 components require only visual examination during pressure test.
6.4 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.
7.0 Examination Boundaries 7.1 Examination boundaries are those ASME Code class 1, 2, and 3 installed components, their attachments and supports.
7.2 ASME Code class 1, 2, and 3 boundaries are identified on Color Coded P&lD's and are located at the Crystal River Unit #3 Station.
G 7.3 The following systems or portions of systems are included in the ISI examination boundaries.
7.3.1 Main & Reheat Steam 7.3.2 Feedwater 7.3.3 Emergency Feedwater 7.3.4 Auxiliary Steam 7.3.5 Condensate 7.3.6 Condensate & Denineralized Water Supply 7.3.7 Chemical Clean Steam Generators 7.3.8 Domestic Water 7.3.9 Instrument Air Station & Service Air 7.3.10 Emergency Diesel Generator Fuel Oil Trcnsfer 7.3.11 Emergency Diesel Generator Compressed Starting Air Exahust 7.3.12 Jacket Coolant Flow 7.3.13 Air Cooler Coolant 7.3.14 Nuclear Services Closed Cycle Cooling 7.3.15 Nuclear Services Decay Heat Sea Water 7.3.16 Spent Fuel Cooling 7.3.17 Chemical Addition 7.3.18 Liquid Sampling 7.3.19 Nitrogen, Hydrogen & C02 7.3.20 Liquid Waste Disposal O
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FLORIDA FLORIDA POWER CORPORATION POWER CRYSTAL RIVER UNIT #3 INSERVICE INSPECTION PROGRAM mounen n
PAGE 4 0F 9 INSERVICE INSPECTION PLAN 7.3.21 Gas Waste Disposal 7.3.22 Containment Monitoring System 7.3.23 Post Accident 7.3.24 Core Flooding System 7.3.25 Reactor Building Pressure Sensing & Testing 7.3.26 Reactor Building Spray 7.3.27 Reactor Building LRT Systen & Post Accident Hydrogen Purge system 7.3.28 Post Accident Ventilation System 7.3.29 Chilled Water 7.3.30 Industrial Cooling Water 7.3.31 Control Complex EFIC Room 8.0 Augmented Inservice Inspection 8.1 Augmented Inservice Inspections (AISI) are not ASME Section XI Code requirements but are 1) additional examinations, or 2) increased inspection frequency or combinations of both which are requested by the. Nuclear i
Regulatory Commission..
8.2 When examination components fall into the scheduled testing of both ISI and A!SI, credit for both requirements are taken (no double testing).
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8.3 The Augmented Inservice Inspections required at Crystal River Unit #3 are as follows:
TYPE DESCRIPTION 1
Eddy Current inspection of Steam Generator Tubes 2
Ultrasonic Inspection of Upper Core Barrel Bolts 3
Ultrasonic Inspection of Lower Core Barrel Bolts 4
Ultrasonic Inspection of Lower Thermal Shield Studs S
Ultrasonic Inspection of Upper Thermal Shield Bolts 6
Ultrasonic Inspection of SSHT Bolts and Studs 7
Ultrasonic Inspection of Flow Distributor Bolts 8
Ultrasonic Inspection of Guide Block Bolts 9
Inspection of High Pressure Injection Thermal Sleeve
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PAGE 5 0F 9 INSERVICE INSPECTION PLAN 9.0 Relief Requests 9.1 When an ASME Section XI Code requirement is determined to be impractical, specific written relief is requested from the Nuclear Regulatory Comission. Each written relief request contains the following as a minimum:
9.1.1 Identification of component (s) for which relief is requested 9.1.2 The specific ASME Code requirement that has been determined to be impractical 9.1.3 Florida Power Corporation, Crystal River Unit #3, relief justification (s) information for requesting relief.
9.1.4 Specific alternative inspection (s) in lieu of ASME Section XI Code requirement (s).
p 9.2 The following is a list of Relief Requests, which have been granted for the
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first interval. Second interval relief requests will be submitted through the Florida Power Corporation licensing department and included in this inservice inspection plan after approval by the NRC.
Date Relief Rrlief Request No.
Subject
_ Granted 010 Makeup and Purification System 07-25-80 Makeup Pump Suction Piping 020 Closure head and vessel cladding of 02-22-83 interior surf aces of Reactor Vessel, Vessel Head, Pressurizer, and 0TSG.
030 Nozzles in the Reactor Vessel, the 04-27-83 Pressurizers, Steam Generator and Heat Exchanger.
040 Repair Program 07-13-83 050 Rector Vessel, Pressurizer, and Steam 07-13-83 Generator.
060 Branch Connection Welds 07-13-83 070 Valve or Pump Welds 07-13-83
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FLORIDA FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT #3 POWER INSERVICE INSPECTION PROGRAM
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Q PAGE 6 0F 9 INSERVICE INSPECTION PLAN 9.0 Relief Request,(cont'd)
Date Relief Relief Request No.
Subject Granted 080 Integrally lleided Support Attachments 07-13-83 (Examination Category B-K-1) 085 Class 2 Piping Welds in Pipes with Nominal llall Thickness 0.5 inch or less 090 Test condition holding time for non-07-13-83 insulated components 095 Class 2 Components 07-13-83 100 Class 1,2, and 3 piping 03-08-85 105 Hydrostatic Test Requirements
~03-08-85 110 Control rod drive mechanism housing 06-27-85 (FSAR Figures 3-65 and 3-66) Class 1 130 Reactor Coolant Pump 06-27-85 (FSAR Figure 4-7) Class 1 140 Rector Vessel Support Skirt 06-27-85 150 Core Flood Nozzle-To-Safe End and Safe End-To-Pipe Welds.
210 Main feedwater piping and main steam 04-08-82 line between the steam generator and the first upstream isolation valve.
(Class 2) 4 220 Core Flood, Decay Heat and Hakeup l
Piping j
230 Code Case N-424 (7-18-85), Qualification of Visual Examination Personnel,Section XI, Oivision 1
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FLORIDA FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT e3 PO]{R INSERVICE INSPECTION PROGRAM e
V PAGE 7 0F 9 INSERVICE INSPECTION PLAN 10.0 Exanination Matrix 10.1 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 B-G-1 314 313 B-G-2 48 47 B-H 21 19 i
B-J 407 116 B-X-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 B-N-3 1
1 B -0 (LISTED UNDER CATEGORY B-E) i
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FLORIDA CRYSTAL RIVER UNIT #3 g&
POWER INSERVICE INSPECTION PROGRAM
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"^oe 8 or 9 INSERVICE INSPECTION PLAN 10.0 Examination Matrix (cont 'd )
10.1 (cont'd)
TOTAL CHOSEN ASME CODE CATEGORY TOTAL NUMBER 11NTERVAL2)
B-P (ADDRESSED BY HYDR 0 AND SYSTEM LEAK PRESSURE TEST PROGRAMS B-Q (ADDRESSED UNDER AUGMENTED EXAMINATIONS)
C-A 32 24 C-B 12 6
C-C 30 11 C-D NONE NR C-F 831 148 C-G NONE NR~
C-H (ADDRESSED BY HYDR 0 AND SYSTEM LEAK PRESSURE TEST PROGRAMS) 0-A (T0 BE DETERMINED BY FPC.)
0-8 (T0 BE DETERMINED BY FPC.)
0-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 d5
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INSERVICE INSPECTION PLAN 10.0 Examination Matrix (cont 'd )
10.1.
(cont'd)
TOTAL CHOSEN ASME CODE CATEGORY TOTAL NUMBER (INTERVAL 2)
F-B: (cont'd)
CLASS 3 469 133 F-C:
CLASS 1 146 (109*)
144 (109*)
CLASS 2 174 (85*)
119 (85*)
CLASS 3 87 (15*)
26 (16')
- 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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O, ATTACHMENT-ADMINISTRATIVE CONTROLS The Nuclear Technical Support Superintendent is the focal point for implementation and control of the Crystal River Unit 3 (CR-3) Inservice Inspection Program, which includes this Plan, and the Inservice Inspection procedures used at CR-3.
The Nuclear Technical Support Superintendent provides interpretations of the Program and Procedures and assures the administrative controls described below are implemented.
Procedures implementing the Inservice inspections and tests shall be subject to the review and approval requirements of Technical Specification 6.8.2.
Additionally, all changes to the procedures implementing the requirements in the Program are evaluated to identify new Relief Requests and to identify changes to the Program and Plan.
If the proposed procedure change causes the ISI activities described by the Program to be conducted differently than described in the Program document, then the Procedure change shall not be implemented at CR-3 until the Nuclear Technical Support Superintendent has approved the Program change.
Changes to the Program shall be evaluated to identify new or revised Relief Requests.
Non-Relief Request changes to the Program shall be reviewed and approved by the Nuclear Technical Support Superintendent prior to implementation.
Typically, Relief Requests are approved by the NRC prior to implementation.
However, early implementation of some relief requests is allowable provided the Code required inspection can be performed at a later date but still l
within the schedule required by the Code in the ovent that l
NRC approval is not granted.
Changes to the Program that
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do not require a
Relief Request may be implemented
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following review and approval by the Nuclear Technical Support Superintendent.
Annually, changes to the Plan shall be submitted to the NRC, if changes have occurred during the year.
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