ML18022A611
| ML18022A611 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 01/28/1988 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML18022A613 | List: |
| References | |
| NLS-88-026, NLS-88-26, NUDOCS 8802030314 | |
| Download: ML18022A611 (818) | |
Text
Carolina Power & Light Company 88020303i4 880i28 JAN 2 8 1988 PDR ADOCK 05000400 8 PDR NLS-88-026 SERIAL:
United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 INSERVICE INSPECTION PROGRAM PLAN - FIRST INTERVAL Gentlemen:
Carolina Power & Light (CP&L) herein submits for your information the Shearon Harris Nuclear Power Plant Ten Year Inservice Inspection Plan for the first 10 year interval. The Plan describes the examinations and schedules for performing ASME code inspections of Class 1,2 and 3 components and supports as required by 10CFR50.55(a).
The Plan also includes relief requests, which pursuant to 10CFR50.55a(g), require NRC approvals The relief requests are based on the experience gained while performing the Preservice Inspection Program (PSI) and parallel the PSI relief requests approved by NRC in the Safety Evaluation Report Supplement No.4 Appendix J. CP&L requests relief be granted by June 22,1988 in order to avoid any adverse impact on the schedule for inservice inspections to be performed during the first refueling outage.
The att:ached plan includes the inspection schedules for each period and refueling outage in the first 10 year interval. The schedule represents a best effort in prescheduling the necessary examinations and is submitted for information only. The schedule, including individual weld selections and examination dates, may be modified as CP&L deems necessary while maintaining compliance with ASME code requirements. Any revisions or additions to the relief requests as submitted herein will be submitted in accordance with 10CFR50.55a(g).
The program summary makes reference to the Piping Flow Diagrams (P&ID's) that were submitted in conjunction with the Preservice Inspection Program. These drawings were submitted by CP&L letter dated June 15,1984 (NLS-234) and should be used in conjunction with the relief request review to the extent necessary.
Carolina Power & Light has reviewed this request in accordance with 10CFR170.12, and a check for $ 150.00 in payment of the required fee is enclosed.
411 Fayettevilte Street ~ P. O. Box 1551 o Raleigh, N. C. 27602 i4dJ Qm> csgoc,<
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" Document Control Des NLS-88-026 / Page 2 Please refer any questions regarding this submittal to Mr. Steven Chaplin at (919) 836-6623.
Yours very truly, S. . mmerman Manager Nuclear Licensing Section SRZ/SDC Enclosure cc: Mr. B. C. Buckley Dr. J. Nelson Grace Mr. G. F. Maxwell
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CONTENTS BOOK 1 Summary Relief Request Component Listing and ISI 10 Year..Plan-(Sorted by Code Category and Item, Numbers 83S-Ol SECTION XI IWB and IWC
. B02-01 Reactor Coolant Pump Flywh'eel %-1.14
'B03-Ol Augmented SER. Que&io'n Augmented FSAR Sec't:ion 6;6.85', 0: F 4'5~0.1'04-Ol B05-01 Augmented FSAR Sec6ion 6-.6.8C O' B06-01 Augmented .FSAR Section '6 6;8D &,F
, B07-01 Augmented FSAR Section 6;6.8E & F SOl-01 Successive Exams I%f9-2420 & IWC-X42'0 BOOK 2 Component Supports IWD and IWF Legends for Relief Request Compdes Exreq Exschd ISI Isometri'c Drawings
" NLS-88-026 t
Document Control Desk
/ Page 3 bcc: Mr. H. R. Banks Mr. R. E. Lumsden Mr. H. W. Bowles Mr. L. H. Martin Mr. R. K. Buckles (LIS)'r.
Mr. C. H. Moseley, Jr.
C. Carmichael (2) Mr. D. C. McCarth~y,,
Mr. R. M. Coats Mr. R; B. Richey Mr. A. B. Cutter/MGZ/EJW/SM Dr. R. B. Starkey, Jr.
Mr. G. L. Forehand Mr. D. L. Tibbitts Mr. B. J. Furr Mr. R. A. Watson Mr. L. T. Gucwa Mr. B. M. Williams Mr. W. J. Hindman Mr. J. L. Willis Mr. D. E. Hollar File: HC/A-2D Dr.. J. D. E. Jeffries File: H-X-0710 Mr. L. I. Loflin
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SUMMARY
The attached describes the Ten Year Inservice Inspection Plan for the Shearon Harris Nuclear Power Plant as required by 10CFR50.55(a) in compliance with Section XI of the ASME Boiler and Pressure Vessel Code. NRC approval is required prior to the fir'st refueling outage.
The Plan describes the examinations and tests that are to be performed on ASME Class 1, 2, and 3 components and their supports including specific requests for relief from Section XI requirements. Also included are the examinations and inspection schedules by which CPBL intends to implement this program. The types of examinations to be performed include surface and volumetric nondestructive examinations, visual examinations, and pressure tests, and eddy current testing of the steam generators. Also described in this plan is.'the Augmented Examination Program covering additional examinations of Class 1, 2, and 3 components as required by various regulatory guidelines which are described therein. The Plan does not include the Pump and Valve Operability Program previously approved (interim) by NRR.
MEM/
SUMMARY
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CAROLINA POWER 6 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT ONE (1) FIRST TEN (10) YEAR INTERVAL ISI PROGRAM PLAN Pursuant to the requirements of 10 CFR 50.55 a(g), inservice examinations of components conducted during the initial 120 month inspection interval shall comply with the. requirements in the latest edition and addenda of the ASME Section XI Code, incorporated by reference in 10 CFR 50, on the date 12 months prior to the date of issuance of the operating license in October, 1986.
Based on the above 10 CFR 50.55 a(g) requirement, the 'SHNPP first ten (10) year inservice inspection program interval will be in accordance with the ASME Section XI Code 1983 Edition, through and including the Summer 1983 addenda. The first ten (10) year interval covers the period from May 2,1987 through May 1,1997. The inspection period dates are as indicated below:
First Inspection Period May 2,1987 to Sept.2',1990 Second Inspection Period Sept.3,1990 to Jan.2,1994 Third Inspection Period Jan.3,1994 to May 1,1997 As permitted by ASME Section XI, the inspection periods above as well as the inspection interval may be decreased or extended (but not cumulatively) by as much as one (1) year to enable an inspection to coincide with a plant outage.
With respect to the examination of piping system welds during the ten (10) year inspection interval, the inspection schedules (attached for information purposes) contain reference to specifically identified welds which should be examined during during each 3 1/3 year period. These have been identified by reference to code item, line number and allotted weld designator given on the system isometric drawings. The welds chosen for examination are selectively distributed within the system boundaries and may be changed at the discretion of CP&L SHNPP ~
Page 1 of 18
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INSERVICE INSPECTION PROGRAM BOUNDARY The ASME Section XI Code Class 1, 2 and 3 boundaries were developed employing the classification guidelines contained in 10 CFR 50.2 (v) for Quality Group A and Regulatory Guide 1.26, Revision 3, for classification of items in Quality Groups B and C. Color-coded piping flow diagrams (P&ID's) identifying the Class 1, 2, and 3 boundaries, were previously submitted to the
'NRC during the preservice program on Unit One (1). In addition, controlled piping flow diagrams (PAID's), which show the ISI boundaries by way of flags, are retained at the plant site.
ASME CLASS ONE (1) PIPING/COMPONENTS For class (1) components (Reactor Pressure Vessel, Steam Generator, Pressurizer) the extent of examinations are based on the requirements of the ASME Section XI Code (Table IWB-2500-1) 1983 Edition, up to and including the Summer 1983 Addenda.
For Class 1 piping welds the extent of examinations are based on the requirements of the ASME Section XI Code (Tables IWB-2500 and 2600),1974 Edition, up to including the Summer 1975 Addenda, as permitted by 10 CFR 50.55a for those facilities whose application for a construction permit was docketed prior to July 1,1978.
The volumetric and surface examination methods utilized on class 1 piping/components will be in accordance with the ASME Section XI Code, 1983 Edition, up to and including the Summer 1983 Addenda and Code Case N335-1, as applicable.
Additionally, Inservice Inspection of the Reactor Pressure Vessel complies with the recommendation of Regulatory
.,Guide 1.150.as .revised by the EPRI ADHOC Committee Report August 1982 with the clarifications and exceptions listed in the SHNPP FSAR page 1.8-187/188 Amendment No. 6.
ASME CLASS TWO (2) PIPING/COMPONENTS Class two (2) piping/components, as attached, were selected for examination based on the requirements of the ASME Section XI Code (Table IWC-2520) 1974 Edition, up to and including the Summer 1975 Addenda,and the Shearon Harris Nuclear Power Plant FSAR (Ref. Attachment One (1) for computations on Class Two (2) systems component selections) .
Class Two (2) piping/components will be exempted in accordance with IWC-1220 from the volumetric and surface examination requirements of IWC-2500. The control of water chemistry to minimize stress corrosion described in paragraph IWC-1220 (C) is not used as a basis for exempting components.
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10 CFR 50.55 a (b) (2) (iv) requires that ASME Code Class 2 piping welds in the Residual Heat Removal (RHR) Systems, Emer-gency Core Cooling (ECCS) Systems, and Containment Heat Removal (CHR) Systems be examined. These systems are exempted by ASME Section XI exclusion criteria in IWC-1220. In order to comply with regulatory inspection requirements, CPaL has selected piping welds in these systems in accordance with the ASME Code and an augmented examination program. (See attach-ment One (1) for a system by system break-down of how the number of components subject to examination were determined, by applying the ASME Section XI Code criteria).
Examination methods utilized on Class Two (2) piping/components will be in accordance with the ASME Section XIAddenda Code, 1983 Edition,'p to and including the Summer 1983 and Code Case N335-1, as applicable.
ASME CLASS THREE (3) INTEGRAL ATTACHMENTS Selection and examination of Class Three (3) integral attach-ments are based on the requirements of the ASME Section XI Code (Table IWD-2500-1), 1983 Edition, up to and including the Summer 1983 Addenda.
AUGMENTED EXAMINATION PROGRAM In addition to the ASME Section XI Code program requirements, the following augmented inspection programs have been included as part of the SHNPP First Ten (10)Year ISI Program submittal:
A) U.S. Nuclear Regulatory Commission Standard Review Plan, Section 3.6.1, "Plant Design For Protection Against Postulated Piping Failures In Fluid Systems Outside Contain-ment" (NUREG-75/087 updated to NUREG-0800, 1981).
B) U.S. Nuclear Regulatory Commission Standard Review Plan, Section 6.6 "Inservice Inspection of Class 2 6 3 components" (NUREG-0800, 1981).
C) U.S. Nuclear Regulatory Commission Regulatory Guide 1.14 "Reactor Coolant Pump Flywheel Integrity."
D) Request for additional information from NRC to CP&L by letter dated October 11, 1983 (Safety Evaluation Report Questions: 250.1, 250.2, and 250.3).
Components of the RHR, ECCS, and CHR Systems (identified as 250.1 welds within this program) were selected based on a 10%
sample criteria of the welds performed during preservice activities. CP&L s position is that a 10% sample criteria is consistent with the requirements of Code Case N-408, "Alternate Rules for Examinations of Class 2 Piping",
Section XI, Division 1.
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The SHNPP FSAR requires high-energy system piping between iso-lation valves, or from the Containment to the first valve out-side Containment for piping without an isolation valve inside Containment, and piping in the break exclusion region, receive an augmented ISI as follows:
(a) Protective measures or structures do not prevent the access necessary for conducting the inservice inspection in accor-dance with Section XI.
(b) One hundred percent of all ASME Class 2 welds that are 3 in. nps (National Pipe Size) for penetration M8, and greater the 4 in. nps for penetration M108 through M110, to the containment isolation vlave will be volumetrically inspected within each inspection interval. (Ref. FSAR Figure 3.6.2-1)
(c) One hundred percent of all pipe welds that are greater than 4 in. nps in the break exclusion region of main steam and feedwater will be 100 percent volumetrically inspected within each inspection interval.
(d) One hundred percent of all welds at penetrations M7, M9 through Mll, and M51 through M53 between containment iso-lation valves will receive a surface inspection within each inspection interval except for the closure plate to pipe welds located outside reactor containment.
(f) Welded attachments, receive surface if any, in the inspection area will examinations.
(g) Guard Pipe is not used on the SHNPP piping system.
(h) For the augmented ISI program, the methods of
'xamination are based on the requirements of the ASME Section XI Code, 1983 Edition Summer 83 Addenda.
REQUEST FOR RELIEF To the maximum extent practical, the arrangement and details of the piping systems and components were designed and fabricated to allow adequate access and clearances for the performance of inservice examinations. However, in some cases examinations will be limited or not practical to perform due to geometric configuration, or plant design precluding physical accessibi-lity.
Generally, these limitations exist at all fi'tting to fitting welds such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface conditions scan do not allow ultrasonic coupling or access for the required length.
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In instances where the location of pipe hangers or equipment supports restricts the access available for the examinations of piping/component welds, examinations will be performed to the extent practical.
In those cases where ASME Section XI Code examinations have been found to be limited or are not practical to perform (areas were identified/documented during preservice activities),
Request for Relief from ASME Code requirements are being submitted as part of this SHNPP Ten Year ISI Program.
For consistency, The Relief Requests have been numbered as submitted and approved in the Preservice Inspection Plan.
COMPONENT SUPPORTS (HANGERS/SNUBBERS)
The ISI Component Support (Hanger/Snubber) Program identifies the components and the examination requirements for component supports within the ISI boundary, as required by IWF-1000 (Table IWF-2500-1) of the ASME Section XI Code, 1983 Code, 1983 Edition, up to and including the Summer 1983 Addenda.
Component Supports were selected for examination based on the criteria of IWF-2510 which states:(a) Component supports selected for examination shall be the supports of those comp-ents that are required to be examined under IWB,IWC and IWD during the first inspection interval. (b) For multiple comp-ents within a system of similiar design, function, and service the supports of only one of the multiple components are required to be examined.
Based on the above criteria, the component supports identified within this program support the IWB,IWC or IWD component directly, or provides support between two (2) major components
'(valve to valve, pump to valve) where the IWB, IWC or IWD component is located.
Snubbers will be functionally tested in accordance with SHNPP Technical Specifications as opposed to ASME Section XI Code requirements, contingent upon NRC approval of Requests for Relief gR1-002, R2-002 and R3-001. Visual Examination (VT-4) will be performed in accordance with the ASME Section XI Code.
SYSTEM PRESSURE TESTS System pressure tests will be performed in accordance with the requirements of the ASME Section XI Code, 1983 Edition, up to and including the Summer 1983 Addenda (Tables IWA-5210-1, IWB-2500-1, IWC-2500-1 and IWD-2500-1). The five types of system pressure tests are as follows:
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(1) Leakage Test- conducted following the opening and reclosing of a system after pressurization to normal operating pressure. This is applicable to Class 1 systems only.
(2) Functional test- conducted at system operating pressure system/components not required to operate during for'hose normal operation. This is applicable to ISI Class 2 and 3 systems.
(3) In-Service Test- conducted while the system is in-service at operating pressure. This is applicable to ISI Class 2 and 3 systems.
(4) Hydrostatic Test- conducted during plant shutdown at a pressure above normal operating pressure or system pressure for which overpressure protection is provided. This is applicable to ISI Class 1,2 and 3 systems.
(5) Pneumatic Test- conducted in lieu of a hydrostatic test for certain ISI Class 2 or 3 systems.
Test Procedures will be utilized for the performance of ASME Section XI Code system pressure tests. Personnel performing visual examinations (VT-2) will be qualified in accordance with the requirements of the ASME Section XI Code, IWA-2300 (3)(C).
EDDY CURRENT EXAMINATION OF STEAM GENERATOR TUBING In accordance with the requirements of ASME Section XI Code, Examination Category B-Q (Item No. B16.20): Steam Generator Tubing in U-Tube Design, SHNPP Technical Specifications will be utilized for the Eddy Current examination of steam generator tubing. The examination results will be evaluated in accordance
'with the acceptance standards of IWB-3521 of the ASME Section XI Code.
As stipulated in the SHNPP Technical Specifications, the following reports will be submitted to the NRC as indicated below:
- a. Within 15 days following the completion of each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator will be reported to the Commission in a Special Report pursuant to Specification 6.9.2; I
- b. The completion results of the steam generator tube inser-vice inspection will be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report will include:
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- 1. Number and extent of tubes inspected,
- 2. Location and percent of wall-thickness penetration for each indication of an imperfection, and
- 3. Identification of tubes plugged.
- c. Results of steam generator tube inspections which fall into Category C-3 will be reported in a Special Report persuant to specification 6.9.2 within 30 days and prior to resump-tion of plant operation. This report will provide a descrip-tion of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent reoccurrence. If Page 7 of 18
Attachment ONE (1)
SHNPP IS I PROGRAM FIRST TEN (10) YEAR INTERVAL
SUMMARY
COMPUTATIONS FOR CLASS TWO (2) SYSTEMS COMPONENT SELECTION Page 8 of 18
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SYSTEM: Auxiliary Feedwater SKETCH AF-008 AF-009 Multiple (3)
AF-010 NO. of WELDS:
C5.11= (79) 6"C.S.welds 27 welds per stream average 27 welds/ 4 intervals 6.75 welds per interval =
Welds to be inspected = 2 welds on Stream "A" 2 welds on Stream "B" 3 welds on Stream "C" SKETCH:
FW-002 FW-003 Multiple (3)
FW-004 NO. of WELDS C5.11= (15) 6"C.S.welds = 5 welds per stream average 5 welds/ 4 intervals = 1.25 welds per interval Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 1 weld on Stream "C" C5.21= (7) 6"C.S.welds = 2 welds per stream average 2 welds/ 4 intervals = 1.00 weld per interval =
Welds to .be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 1 weld on Stream "C" Page 9 of 18
SYSTEM: Chemical and Volume Control
'SKETCH CS-001 CS-002 Multiple (2)
CS-021 NO. of WELDS:
C5.11= (78) 8"S.S.welds 39 welds per stream average 39 welds/ 4 intervals = 10 welds per interval "A"
=
Welds to be inspected = 5 welds on Stream "B"
5 welds on Stream SKETCH CS-001 CS-021 Multiple (3)
NO. of WELDS:
C5.11= (43) 6"S.S.welds = 14 welds per stream average 14 welds/ 4,intervals 3.5 welds per interval =
Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 2 welds on Stream "C" Page 10 of 18
I SYSTEM: Containment Spray "SKETCH:
CT-001 CT-002 Multiple (2)
CT-014 CT-016 NO. of WELDS:
C5.11= (10) 6" S.S.welds = 5 welds per stream average =
5 welds/ 4 intervals = 1.25 welds per interval =
Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" C5.11= (103) 8"S.S.welds = 52 welds per stream average 52 welds/ 4 intervals = 13 welds per interval "A"
=
Welds to be inspected = 6 welds on Stream 7 welds on Stream "B" SKETCH:
CT-007 CT-008 Multiple (2)
NO. of WELDS:
C5.11= (87) 12"S.S.welds = 44 welds per stream average 44 welds/ 4 intervals Welds to be inspected
=
= 6 llwelds welds per interval on Stream "A"
=
5 welds on Stream "B" Page ll of 18
t SYSTEM: Feedwater SKETCH:
FMR-01 FMR-02 Multiple (3)
FMR-03 NO. of WELDS:
C5.21= (55) 16"C.S.welds = 19 welds per system average 19 welds/ 4 interval = 5 welds per interval=
Welds to be inspected = 2 welds on Stream "A" 2 welds on Stream "B" 2 welds on Stream "C" SKETCH:
FW-001 Multiple (3)
NO. of WELDS:
C5.21= (9) 16"C.S.welds = 3 welds per stream average 3 welds/ 4 intervals = 1 weld per interval Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 1 weld on Stream "C" Page 12 of 18
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SYSTEM: Main Steam
'SKETCH:
MS-001 MS-007 Multiple (2)
NO. of WELDS:
C5.11 (8) 6"C.S.welds = 4 welds per stream average 4 welds/ 4 intervals = 1 weld per interval "A"
=
Welds to be inspected = 1 weld on Stream 1 weld on Stream "B" SKETCH:
MS-001 MS-002 Multiple (3)
NO. of WELDS C5.11 (18) 8"C.S.welds = 6 welds per stream average 6 welds/ 4 intervals = 1.5 welds per interval =
Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 1 weld on Stream "C" C5.21 (15) 8"C.S.welds = 5 welds per stream average 5 welds/ 4 intervals = 1.25 welds per interval =
Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 1 weld on Stream "C" SKETCH:
MS-001 Multiple (3)
NO. of WELDS:
C5.21 (6) 12"C.S.welds = 2 welds per stream average 2 welds/ 4 intervals = 1 weld per interval =
Welds to be inspected = 1 weld on Stream 1 weld on Stream nB<<
1 weld on Stream "C" SKETCH:
FMR-01 FMR-02 Multiple (3)
FMR-03 NO. of WELDS:
C5.21 (41) 32"C.S. welds = 14 welds per stream average 14 welds/ 4 intervals = 3.5 welds per interval =
Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 1 weld on Stream "C" Page 13 of 18
l SYSTEM: Main Steam cont.
SKETCH:
MS-001 Multiple (3)
NO. of WELDS:
C5.21 (6) 34"C.S.welds = 2 welds per stream average 2 welds/ 4 intervals = 1.0 weld per interval Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 1 weld on Stream "C" Page 14 of 18
SYSTEM: Residual Heat Removal SKETCH:
CS-002 RH-004 Multiple (2)
NO. of WELDS:
C5.11 (27) 8"S.S.welds = 14 welds per stream average 14 welds/ 4 intervals = 4 welds per interval "A"
=
Welds to be inspected = 2 welds on Stream "B"
2 welds on Stream SKETCH:
CS-002 CS-021 RH-001 Multiple (2)
RH-002 RH-004 SI-008 NO. of WELDS:
C5.11 (114) 10"S.S.welds = 57 welds per stream average 57 welds/ 4 intervals = 15 welds per interval =
Welds to be inspected = 7 welds on Stream "A" 8 welds on Stream "B" SKETCH:
RH-001 RH-002 Multiple (2)
RH-009 RH-010 NO. of WELDS:
C5.11 (41) 12"S.S.welds 20.5 welds per stream average =
21 welds/ 4 "intervals 5.25 welds per interval Welds to be inspected = 3 welds on Stream "A" 3 welds on Stream "B" C5.21 (2) 12"S.S.welds = 1 weld per stream average =
1 weld/ 4 interval= 1.0 weld per interval =
Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" SKETCH:
RH-001 RH-002 Multiple (2)
NO. of WELDS:
C5.11 (14) 14"S.S.welds = 7 welds per stream average 7 welds/ 4 intervals = 1.75 welds per interval =
Welds to be, inspected = 1 weld on Stream "A" 1 weld on Stream "B" Page 15 of 18
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SYSTEM: Safety Injection SKETCH:
SI-025 SI-026 Single (1)
NO. of WELDS:
C5.21 (20) 6"S.S.welds = 20 welds for single stream =
20 welds/ 4 intervals = 5 welds Welds to be inspected = 5 welds on single stream SKETCH:
SI-027 SI-028 Mutiple (2)-Hot Leg NO. of WELDS:
C5.21 (7) 6"S.S.welds = 3.5 welds per stream average 3.5 welds/ 4 intervals = 1 weld per interval =
Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" SKETCH:
SI-024 SI-025 Mutiple (3)-Cold Leg SI-026 NO. of WELDS:
C5.21 (30) 6"S.S.welds = 10 welds per stream average 10 welds/ 4 intervals = 2.5 welds per interval =
Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 1 weld on Stream "C" SKETCH:
SI-025 SI-026 Single (1)
NO. of WELDS:
C5.21 (20) 6"S.S.welds = 20 for single stream =
20 welds/ 4 intervals = 5 welds per interval WELDS to be inspected = 5 welds on sing'le stream SKETCH:
SI-027 SI-028 Multiple (2)- Hot Leg NO. of WELDS:
C5.21 (7) 6"S.S.welds = 3.5 welds per stream average 3.5 welds/ 4 intervals = 1 weld per interval =
Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" Page 16 of 18
~4 SYSTEM: Safety Injection cont.
SKETCH:
SI-024 SI-025 Multiple (3)- Cold Leg SI-026 NO. of WELDS:
C5.21 (30) 6"S.S.welds = 10 welds per stream average 10 welds/ 4 intervals = 2.5 welds per interval Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 1 weld on Stream "C" SKETCH:
SI-009 Single (1)
NO. of WELDS:
C5.11 (4) 8"S.S.welds = 4 welds for single stream 4 welds/ 4 intervals = 1 weld per interval =
Welds to be inspected = l,weld on single stream SKETCH:
SI-008 Single (1)
NO. of WELDS:
C5.11 (8) 10"S.S.welds = 8 welds for single stream =
8 welds/ 4 intervals = 2 welds per interval =
Welds to be inspected = 2 welds on single stream SKETCH:
SI-008 SI-009 Single (1)
NO. of WELDS:
C5.11 (33) 10"S.S.welds 33 welds for single stream =
33 welds/ 4 intervals = 8 welds per interval Welds to be inspected = 8 welds on single stream SKETCH:
SI-008 SI-009 SI-025 Multiple (2)
SI-026 SI-028 NO. of WELDS:
C5--.11 (34) 10"S.S.welds = 17 welds per stream average 17 welds/ 4 intervals = 4.25 welds per interval Welds to be inspected = 2 welds on Stream "A" 3 welds on Stream "B" Page 17 of 18
SYSTEM: Safety Injection cont.
C5.21 "(34) 10"S.S.welds = 17 welds per stream average 17 welds/ 4 intervals = 4.25 welds per interval =
Welds to be inspected = 2 welds on Stream "A" 3 welds on Stream "B" SKETCH:
SI-021 SI-022 Multiple (3)
SI-023 NO. of WELDS:
C5.11 (21) 12"S.S.welds = 7 welds per stream average 7 welds/ 4 interval = 1 .75 welds per interval =
Welds to be inspected = 1 weld on Stream "A" 1 weld on Stream "B" 1 weld on Stream "C" C5.21 (13) 12"S.S.welds 4.33 welds per stream average 4.33 welds/ 4 intervals = 1.08 welds per interval II II Welds to be inspected = 1 weld on Stream A 1 weld on Stream I I B II 1 weld on Stream CII SKETCH:
RH-001 RH-002 Multiple (3)
NO. of WELDS:
C5.11 (42) 14"S.S.welds = 21 welds per stream average 21 welds/ 4 interval = 5.25 welds per interval =
Welds to be inspected = 3 welds on Stream "A" 3 welds on Stream "B" Page 18 of 18
REQUEST FOR RELIEF NO. Rl-001 DELETED IN PRE-SERVICE PROGRAM PAGE 1 OF 1
~ ~
'REQUEST FOR RELIEF NO. Rl-002, COMPONENT STANDARD SUPPORTS (SNUBBERS),,CATEGORY F-', ITEM F3.50 for CLASS ONE (1) SYSTEMS.
IDENTIFICATION OF COMPONENTS:
All hydraulic and/or mechanical snubbers listed on attachment for this relief request.
ASME SECTION XI CODE REQUIREMENT:
IWF-2000 requires visual examination in accordance with Table IWF-2500-1. ZWF-5000 requires functional testing of snubbers in accordance with IWF-5300 (in course of preparation) and IWF-5400.
CODE RELIEF REQUEST:
Relief is requested from the functional test requirements for snubbers per article IWF-5000 of the ASME Section XI Code.
Visual examinations (VT-4) will be performed in accordance with the ASME Section XI Code, which will also satisfy the visual examination criteria of the SHNPP Technical Specifica-tions, as applicable.
ALTERNATE EXAMINATION:
All Shearon Harris component support snubbers will be selected and functionally tested per Section 3/4.7.8 of the Shearon Harris Technical Specifications.
BASIS FOR REQUESTING REZIEF:
The SHNPP Technical Specifications and the ASME Section XI Code are similar in their intent to functionally test snubbers.
The SHNPP Technical Specifications are, however, more restrictive in the selection, as well as the method of testing snubbers for functional adequacy.
CONSTRUCTION CODE EXAMINATION:
Not Applicable TECHNICAL JUSTIFICATION FOR REQUESTING REZIEF:
The Nuclear Regulatory Commission has approved the utilization of SHNPP Technical Specifications for functionally testing snubbers. The utilization of the ASME Section XI Code, to functionally test snubbers, would be less restrictive than performing testing in accordance with SHNPP Technical Specifi-cations.
Page 1 of 2
j< 'ttI 'I II ~
t' It
Rl-002 Cont.
'No impact on plant quality, safety, or reliability is expected as the snubbers will be subject to the functional test require-ments of the SHNPP Technical Specifications.
This Request For Relief (Rl-002) is applicable to the SHNPP Unit 1 First Ten (10) Year Interval Inservice Inspection Program.
Page 2 of 2
E A~+
Rl-002 ATTACHMENT CATEGORY F-C, ITEM F3.50 FOR CLASS ONE (1) SYSTEMS CS-H-00398 RC-H-00221 RC-H"00433 SI-H-00146 SI"H-00961 CS-H-00399 RC-H-00222 RC-H-00435 SI-H-00148 SI-H"00982 CS-H-00736 RC-H-00224 RC-H-00436 SI-H-00149 SI-H-00983 CS-H-02871 RC"H-00225 RC-H-00438 SI-H-00168 SI-H-00989 CS-H-02962 RC-H-00228 RC-H-00440 SI-H-00169 SI-H-01023 CS-H-02983 RC-H-00229 RC-H-00441 SI-H-00171 SI-H-01025 CS"H-03056 RC-H-00230 RC-H-00444 SI-H-00172 SI-H-01036 CS-H-03057 RC-H-00231 RC-H-00447 SI-H-00174 SI-H-01092 CS-H-03208 RC-H"00236 RC-H-00486 SI-H-00175 SI-H-01193 CS-H-03242 RC-H-00238 RC-H"00487 SI-H-00177 SI-H-01574 CS-H-03292 RC-H-00239 RC-H-00491 SI-H-00185 CS-H-03636 RC-H-00244 RC-H-00494 SI-H-00187 CS-H-04418 RC-H-00246 RC-H-00549 SI-H-00188 CS-H-04430 RC"H-00309 RC-H-00550 SI-H-00190 RC-H"00310 RC-H-00552 SI-H-00192 RC-H-00002 RC-H"00311 RC-H-00559 SI-H-00230 RC-H-00006'C-H-00037 RC-H-00312 RC-H-00561 SI-H-00233 RC"H"00314 RC"H-00562 SI-H-00266 RC-H-00038 RC-H-00315 RC-H-00649 SI-H-00275 RC"H-00042 RC-H-00318 RC-H-00664 SI-H-00279 RC-H-00046 RC-H-00324 RC-H-00665 SI-H-00318 RC-H-00048 RC-H-00326 RC-H-00666 SI-H-00321 RC-H-00049 RC-H-00328 RC-H-00667 SI-H-00324 RC-H-00053 RC-H-00330 RC-H-00841 SI-H-00326 RC-H-00054 RC-H"00336 RC-H-00860 SI-H"00357 RC-H-00059 RC-H-00338 RC-H-00861 SI-H-00359 RC-H-00064 RC-H-00340 RC-H-00863 SI-H-00361 RC-H-00065 RC-H-00341 RC-H-00871 SI-H-00373 RC-H-00067 RC-H-00343 RC-H-00920 SI-H-00375 RC-H-00068 RC-H-00348 SI-H-00376 RC-H-00069 RC-H"00349 RH-H-00113 SI-H-00428 RC"H-00070 RC"H-00350 RH-H-00116 SI-H-00430 RC-H-00073 RC-H-00354 RH-H-00118 SI-H-00437 RC-H-00075 RC"H-00356 RH-H-00119 SI-H-00440 RC-H-00077 RC-H-00357 RH-H"00141 SI-H-00498 RC-H-00080 RC-H-00360 RH-H-00142 SI-H-00499 RC-H-00082 RC-H-00361 RH-H-00144 SI-H-00500 RC-H-00083 RC"H"00412 RH-H-00145 SI-H-00501 RC-H-00087 RC-H"00416 RH-H-00146 SI-H-00502 RC-H-00088 RC-H-00417 RH-H-00364 SI-H-00503 RC-H-00089 RC-H-00420 SI-H-00504 RC-H-00090 RC-H"00422 SI-H"00118 SI-H-00506 RC-H-00092 RC-H-00423 SI-H"00119 SI-H-00507 RC-H-00093 RC-H-00426 SI-H-00122 SI-H-00508 RC-H-00095 RC-H-00427 SI-H-00133 SI-H-00599 RC-H-00096 RC-H-00428 SI-H-00141 SI-H-00942 RC-H-00100 RC-H",00429 SI"H-00142 SI-H-00959 RC-H-00220 RC"H"00431 SI-H-00144 SI-H-00960 MEM/Rl-002ATT/2/OS2
REQUEST FOR RELIEF NO. Rl-003, PRESSURE RETAINING CIRCUMFERENTIAL WELDS~ CATEGORY B J ITEM B9 11/ AND BRANCH PIPING CONNECTIONS WELDS, CATEGORY B-J: ITEMS B9.31 IDENTIFICATION OF COMPONENTS:
Pressure retaining circumferential piping welds, and branch pipe connections welds as listed on attachment for this Relief Request.
ASME SECTION XI CODE REQUIREMENTS:
Examination category B-J, Item (s) 9.11 and 9.31 requires a surface (P.T.) and volumetric (U.T.) examination be performed on greater than or equal to 4 in. nominal pipe size circum-ferential piping welds, and branch pipe connection welds on greater than or equal to 4 in. nominal pipe size piping.
CODE RELIEF REQUEST:
Relief is requested from performing 100 percent volumetric (U.T.) examination on greater than or equal to 4 in. nominal pipe size circumferential piping welds and branch pipe connec-tion welds due to pipe configurations (reducer to tee, pipe to tee, pipe to flange ...) not being conducive to 100 percent volumetric (U.T.) examinations.
ALTERNATE EXAMINATIONS:
Piping systems will be subject to system leakage pressure tests and be visually (VT-2) examined during each refueling outage.
Welds will be volumetrically (U.T. ) examined, to the maximum extent possible, in accordance with the Inservice Inspection Program Schedule. In addition, the components will be subject
'o system pressure tests during each refueling outage.
BASIS FOR REQUESTING RELIEF:
Piping weld configurations (reducer to tee, pipe to tee,volume-pipe to flange) are not conducive to performing 100 percent tric (U.T.) examination from both sides of the weld, as required by ASME Section XI (Code Case N-335-1). Some arrange-ments and details of the piping systems and components were designed and fabricated before the access and examination requirements of the ASME Section XI Code, and especially the requirements of Code Case N-335-1 could be applied. Conse-quently some exams are limited or not practical tolimitations perform due to geometric configuration or accessibility. The exist at fitting to fitting joints, where geometry and surface conditions preclude ultrasonic coupling, or access for the required scan length (Ref. Attached computer data indicating the estimates of code requiring examination coverage that may be completed on the individual components requiring relief).
Page 1 of 3
Rl-003 Cont.
CONSTRUCTION CODE EXAMINATIONS:
Volumetric Surface TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF:
Required ASME Section XI Code (Code Case N-335-1) volumetric (U.T.) examinations can not be 100 percent completed on listed piping welds due to piping configurations not being conducive to volumetric (U.T.) examinations.
During preservice activities, examinations in limited areas were accomplished as a best effort attempt to cover as much of the code required area or volume as possible (generally, the weld and base metal of 1 "T" on each side). However, the extent of examination coverage could not be specifically qualified as being 100 percent. These areas where complete examination of 100 percent of the required volume of area could not be achieved are documented on each applicable examination data sheet, and the limited cause noted.
The principal basis of partial examination is to identify the inability to examine 100 percent of the required base metal volume for 1 "T" distance beyond the edge of the weld on a fitting or component. Examples are:
(1) Ultrasonic examination of a pipe to elbow assembly, where scanning on the intrados of the elbow causes decoupling of the sound beam and; (2) A pipe to flange or valve assembly where scanning the entire 'volume on the fitting or component side is limited by configuration. The resulting coverage is such that examination of the weld, heat affected zone and base metal of 1 "T" on indetermined coverage of the base metal on the fitting or component side may be during this pipe side scan, depending on the calibrated sweep length, attentua-tion, joint configuration, etc. However, the volume on the fitting or component side additionally cannot be scanned Code required.
completely for transverse indications when "T" In either case, 100 percent of this 1 volume cannot be assured, thus a partial examination is required as a dis-claimer to having satisfied Code requirments, albeit the intent is satisfied to the extent )
practical.
Specific limitations and restrictions for a 1 examinations are as indicated on the attached computer listing and the specific data sheet.
Page 2 of 3
rt Rl-003 Cont.
No impact on plant quality, safety, or reliability is expected as the systems will be subject to system leakage pressure tests and will be visually (VT-2) examined during refueling outages. Systems will also be subject to hydrostatic testing at the end of the ten (10) year interval.
This Request for Relief (Rl-003) is applicable to the SHNPP Unit 1 First Ten (10) Year Interval Inservice Inspection Program.
Page 3 of 3
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QUERY RESPONSE REPORT HARRIS - IS!
RELIEF REQUEST Rl-003: COMPONENTS REQUESTED FOR RELIEF 44444414444t044440444444444 ~ 4440444044404444440444444444404484 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS I I-FMR-03RC-10-19" SW-05 PC, PIPE-PC, NOZ 8-J 89.31 UT-45L CIRC. 67% , AXIAL 50% COMPLETE II-RC-009RC-FW-1 PC,NOZ -PC,PB 89.11 UT-45S CIRC. 67% , AXIAL 50% COMPLETE II-RC-023RC-FW-322 PC,PIPE-PC,VLV 8-J 89.11 UT-455 CIRC. 67% , AXIAL 50% COMPLETE II-RC-023RC-FW-323 PC,VLV -PC,PIPE 8-J 89.11 UT-45S CIRC. 67% , AXIAL 50% COMPLETE II-RC-023RC-FW-325 PC,VLV -PC,PIPE 8-J 89. 11 UT-45S CIRC. 67% , AXIAL 50'L COMPLETE II-RC-023RC-FW-326 PC,PIPE-PC,VLV 8-J 89.11 UT-455 CIRC. 67% , AXIAL 50'A COMPLETE II-RC-023RC-FW-327 PBCC,T -PC,PIPE 8-J 89.11 UT-45S CIRC. 63'YI, AXIAL 63% COMPLETE II-RC-023RC-SW-84 PC,PIPE-PBCC,T 8-J 89. 11 UT-455 CIRC. 80'L , AXIAL 80% COMPLETE II-RC-023RC-SW-85 PBCC,T -PC,PIPE 8-J 89. 11 UT-455 CIRC. 90% , AXIAL 90% COMPLETE II-RC-023RC-SW-86 PC,PIPE-PC,RED 8-J 89.11 UT-45S CIRC. 67% , AXIAL 50% COMPLETE II-RC-023RC-SW"C13 PBCC,TR-PC,PIPE 8-J 89.11 UT-45S CIRC. 73'L , AXIAL 73'A COMPLETE II-RC-023RC-SW-C9 PC,PIPE-PBCC,TR 8-J 89. 1
'I UT-455 CIRC. 87%, AXIAL 87% COMPLETE II-RC-023RC-SW-D12 PBCC,T -PC,PIPE 8-J 89. 11 UT-45S CIRC. 80%, AXIAL 80% COMPLETE II-RC-023RC-SW-08 PC,PIPE-PBCC,T 8-J 89. 11 UT-45S CIRC. 85%" ~ AXIAL 85% COMPLETE II-RC-023RC-SW"D9 PBCC,T -PC,PIPE 8-J 89. 11 UT-45S CIRC. 67'j0, AXIAL 50% COMPLETE II-RC-023RC-SW-Ell PC,PIPE-PBCC,T 8-J 89.11 UT-45S CIRC. 85%, AXIAL 85% COMPLETE II-RC-023RC-SW-E7 PBCC,T -PC,PIPE 8-J 89. 11 UT-45S CIRC. 80%, AXIAL 80'A COMPLETE II-RC-023RC-SW-EB PBCC,T -PC,PIPE 8-J 89. 11 UT-45S CIRC. 70'k, AXIAL 70'N COMPLETE II-RC-023RC-92-2-SW-1 PC,PIPE-PBCC,TR 8-J 89. 11 UT-45S CIRC. 67%, AXIAL 50% COMPLETE II"RC-024RC-FW-318 PBCCeT -PCePIPE 8-J 89.11 UT-45S AXIAL 50% COMPLETE II-RC-025RC-FW-331 PC,NOZ -PC,PIPE 8-J 89.11 UT-45S CIRC. 67'A , AXIAL 50% COMPLETE II-RC-025RC-SW-A3 PC,PIPE-PE,LR 8-J 89.11 UT-45S CIRC. 85%i, AXIAL 85% COMPLETE II-RC-025RC-SW-A4 PE, LR -PC, PIPE 8-J 89. 11 UT-45S CIRC. 85% , AXIAL 85% COMPLETE
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REQUEST FOR RELIEF NO. Rl-004'RESSURE RETAINING WELDS IN REACTOR VESSELS CATEGORY B Ag ITEM(S) Bl llew Bl 12'l Bl.40, AND PRESSURE RETAINING WELDS IN VESSELS OTHER 21'l.22, THAN REACTOR VESSEL, CATEGORY B-B, ITEM(s) B2.11 AND B2.40:
IDENTIFICATION OF COMPONENTS:
Pressure retaining welds in reactor vessel, and in vessels other than reactor vessels, as listed on attachment for this relief request.
ASME SECTION XI CODE REQUIREMENTS:
Examination category B-A, Item(s) Bl.ll, Bl.12, Bl.21, Bl.22 required a volumetric examination, Item B1.40 required volume-tric and surface. Examination category B-B, Item(s) B2.11 and B2.40 requires a volumetric examination.
CODE RELIEF REQUEST:
Relief is requested from 100 percent volumetric (U.T.) exam-inations, due to the pressure retaining welds not being 100 percent accessible over their entire length. Volumetric (U.T.)
examinations are limited because of obstructions such as:
- 1) Welded Plates
- 2) Weld Support Plates
- 3) Nozzle Interference
- 4) Manways
- 5) Lifting Lugs, etc.
BASIS FOR REQUESTING RELIEF:
Numerous obstructions (manways, nozzle, support plates, lifting lugs...) will prevent a 100 percent volumetric (U.T.)
examination of listed pressure retaining welds during Inservice Inspection activities. The listing also indicates the type of obstruction, as well as the size of the obstruction, when applicable. The limitations/obstructions were documented on the applicable preservice data sheet(s) and are available at the plant site for review.
ALTERNATE EXAMINATIONS:
The Reactor Vessel, Pressurizer and Steam Generators pressure retaining welds will be volumetrically (U.T.) examined, to the maximum extent possible, in accordance with the Inservice Inspection Program Schedule. In addition, the components will be subject to system pressure tests during each refueling outage.
Page 1 of 2
a ff'f If ff I 4
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Rl-004 Cont.
CONSTRUCTION CODE EXAMINATION(s):
Volumetric Surface TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF:
Pressure retaining welds in the Reactor Vessel and other vessels (Steam Generators and Pressurizer) were volumetrically (U.T.) examined to the maximum extent possible during pre-service inspection activities. The design of the components present obstructions that will not allow 100 percent volumetric (U.T.) examinations to be performed. The vessels were subject to fabrication/construction code volumetric and surface examinations, as applicable.
No impact on overall plant quality, safety, or reliability is
'xpected, as the welds were subject to extensive construction code examinations. In addition, the pressure retaining welds will be subject to system pressure tests (VT-2 examination) to the maximum extent possible, during each refueling outage.
This Request for Relief (Rl-004) is applicable to the SHNPP Unit 1 First Ten (10) Year Interval Inservice Inspection Program.
Page 2 of 2
4440444444 04440444444404444444444f4t4444044444 444444444'4444ftt4 01/12~ NUTECH/PRISI~
QUERY RESPONSE REPORT PAGE:
HARRIS ISI RELIEF REQUEST Rl-004: COMPONENTS REQUESTED FOR RELIEF 4444444t444044444t44404404440444t40444t4444444044t848444444444444444444404 ~ 4444444t 444444444444444444444444444444444444444444444 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS I I-PZR-01CSW-03 VCSW PZR CSW UT-00 WELDED PLATE (8)--EACH SIDE OF C/L, 4 LOCATIONS-90% COMPLETE I I-PZR-01CSW-03 VCSW PZR CSW UT-45S WELDED PLATE (8)--EACH SIDE OF C/L, 4 LOCATIONS-92% COMPLETE II-PZR-01CSW-03 VCSW PZR CSW UT-60S WELDED PLATE (8)--EACH SIDE OF C/L, 4 LOCATIONS-90% COMPLETE II-PZR-01LSW-06 VLSW PZR LSW UT-00 WELDED SUPPORT PLATE OBSTRUCTION-8"X5";5"FROM C/L-96% COMPLETE II-PZR-01LSW-06 VLSW PZR LSW UT-45S WELDED SUPPORT PLATE OBSTRUCTION--8"XS";5" FROM C/L-99.8% COMP II-PZR-01LSW-06 VLSW PZR LSW UT-60S WELDED SUPPORT PLATE OBSTRUCTION-8-X5",5" FROM C/L-95'A COMPLETE I I-PZR-01STHW-01 VSTHW 8-8 82. 11 UT-00 OBSTRUCTED BY 8 3"X3" WELD PADS 6 5 INSTRUMENT PORTS-88% COMP I I-PZR-01 STHW-01 VSTHW B-B 82.11 UT-455 OBSTRUCTED BY 8 3"X3" WELD PADS 8 5 INSTRUMENT PORTS-94% COMP I I-PZR-01STHW-01 VSTHW 8-8 82. 11 UT-605 LIMITED BY 8 3"X3- WELD PADS,5 INST. PORTS,8 SUPP. SKT.-88% C II-PZR-01STHW-04 VSTHW B-B 82.11 UT-00 LIMITED:4-3"X3" WELD PADS;4-INSTRUMENT PORTS;MANWAY-96% COMP.
II-PZR-01STHW-04 VSTHW 8-8 82. 11 UT-45S LIMITED: 4-3 "X3" WELD PADS, 4-INSTRUMENT PORTS;MANWAY-96'XI COMP.
II-PZR-01STHW-04 VSTHW B-B 82. 11 UT-60S LIMITED:4-3"X3" WELD PADS;4-INSTRUMENT PORTS;MANWAY-96% COMP.
II-RV-001CHW-RV-17 VCHW 8-A 81.21 UT-RVS INTER. BY INST. NOZ 47,48,49,50-95% COMPLETE II-RV-001CSW-RV-02 VCSW 8-A 81.11 UT-RVS NOZZLE INTERFERENCE-96'A COMPLETE I I-RV-001FTHW-RV-18 VFTHW 8-A 81.40 UT-00 LIFTING LUG INTERFERENCE-48% COMPLETE I I-RV-001FTHW-RV-18 VFTHW 8-A 81.40 UT-45S LISTING LUG INTEFERENCE-48% COMPLETE I I-RV-00 IFTHW-RV-18 VFTHW 8-A 81.40 UT-60S LIFTING LUG INTERFERENCE-48% COMPLETE II-RV-001LSW-RV-05 VLSW 8-A 81. 12 UT-RVS FLANGE TAPER 8 NOZZLE INTERFERANCE-98'l0 COMPLETE II-RV-001LSW-RV-06 VLSW 8-A 81.12 UT-RVS FLANGE TAPER 8 NOZZLE INTERFERANCE-98% COMPLETE II-RV-00'IMHW-RV-11 VMHW 8-A 81.228 UT-RVS LIMITED BY CORE SUPPORT LUG-93% COMPLETE II-RV-001MHW-RV-12 VMHW 8-A 81.228 UT-RVS LIMITED BY CORE SUPPORT LUG 8, INST. NOZ. 40 8 50-82% COMPLETE I I-RV-001MHW-RV-13 VMHW 8-A 81.228 UT-RVS LIMITED BY CORE SUPPORT LUG L INST. NOZ. 43 8 46-94% COMPLETE II-RV-001MHW-RV-14 VMHW 8-A 81.228 UT-RVS LIMITED BY CORE SUPPORT LUG 8 INST. NOZ. 48-85% COMPLETE
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QUERY RESPONSE REPORT HARRIS - ISI RELIEF REQUEST R1-004: COMPONENTS REQUESTED FOR RELIEF 4444044044044444044444408 444444444444444444444t044044400444t4444444044t44444444t444 44444444444444484440444444S444444444444444 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS I I-RV-001MHW-RV-15 VMHW 8-A 81.228 UT-RVS LIMITED BY CORE SUPPORT LUG-85% COMPLETE I I-RV"00 IMHW-RV-,I 6 VMHW 8-A 81.228 UT-RVS LIMITED BY INST. NOZ. 41-78% COMPLETE II-RV-001STHW-RV"04 VSTHW 8-A 81.21 UT-RVS LIMITED BY CORE SUPP. LUGS-95'A COMP; SUPPLEMENTAL FULL V 45 II-SG-001SGA-TSTHW-06 VTSTHW 8-8 82.40 UT-00 SHELL SIDE ONLY; INSUL. TABS ( 13) 8 4-24"X24" SUPP. PLTS.-95% C II-SG-001SGA-TSTHW-06 VTSTHW 8-8 82.40 UT-45S 4-24"X24" SUPPORT PLATES-99.7% COMPLETE II-SG-001SGA-TSTHW-06 VTSTHW 8-8 82.40 UT-60S 4-24"X24" SUPPORT PLATES; INSULATION TABS ( 13)-95% COMPLETE II-SG-001SGB-TSTHW-06 VTSTHW 8.-8 82.40 UT-00 4-22"X24- WELDED PLATES ON C/L; 1-3.5"X6.5" CODE PLATE-92% COMP II-SG-001SGB-TSTHW-06 VTSTHW 8-8 82.40 UT-45S 4-22"X24" WELDED PLATES-99.7% COMPLETE II-SG-001SGB-TSTHW-06 VTSTHW 8-8 82.40 UT-60S 4-3"X3" WELDED PLATES ON C/L; 1-3.5-X6.5" CODE PLATE-92% COMP II-SG"001SGC-TSTHW"06 VTSTHW 8-8 82.40 UT-00 4-22"X24" WELDED PLATES; INSULATION TABS (20)-97% COMPLETE II-SG-001SGC-TSTHW-06 VTSTHW 8-8 82.40 UT-45S 4-22"X24" WELDED PLATES-99.8% COMPLETE II-SG-001SGC-TSTHW-06 VTSTHW 8-8 82.40 UT-60S FLANGE: INSULATION TABS (20)-97% COMPLETE
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REQUEST FOR RELIEF NO. Rl-005 (A) VALVE BODIES, EXCEEDING 4 IN NOMINAL PIPE SIZE, CATEGORY B-M-2: ITEM B12.50.
IDENTIFICATION OF COMPONENTS:
Internal surfaces of class one (1) valve bodies, exceeding 4 in. nominal pipe size, as listed on attachment of this relief request.
ASME SECTION XI REQUIREMENT:
Examination category B-M-2, Item B12.50 requires a visual exam-ination (VT-3) of the valve internal surfaces of one valve in each group of valves of the same construction design and manufacturing method that perform similiar functions in the system.
CODE RELIEF REQUEST:
Relief is requested from the code required visual examinations (VT-3) of the internal surfaces of class one (1) valve bodies exceeding 4 in. nominal pipe size, during Inservice Inspection activities.
ALTERNATE EXAMINATIONS:
Components will be subject to system leakage pressure tests and visual (VT-2) examinations during refueling outages. In addition, the class one (1) primary system is continuously monitored for leakage during plant operations, in accordance with SHNPP Technical Specifications.
BASIS FOR REQUESTING RELIEF:
The requirement to disassemble primary system valves for the sole purpose of" performing a visual examination of the internal pressure boundary surfaces is considered by CP&L to be a hard-ship, without any appreciable compensating increase in the level of quality and/or safet'y expected.
Performing these visual examinations, under such adverse conditions such as high dose rates and poor as-cast surfaces, realistically, provides little additional information as to the valve casing integrity. In addition, disassembly of valves may also cause unnecessary damage to occur, due to the disassembly process.
CONSTRUCTION CODE EXAMINATIONS:
Volumetric Surface Page 1 of 2
1 I
Rl-005 (A) CONT.
TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF:
The non-performance of visual examinations (VT-3) on the internal surfaces of safety class one (1) valves, exceeding 4 in. Nominal pipe size, should not have any adverse impact on plant quality, safety, or reliability for the following reasons:
(1) The fabrication methods utilized, as well as the required construction code (ASME SECTION III) examinations confidence level of performed, provides a very high structural integrity and valve performance for long-term plant operations.
h (2) The primary side class one (1) systems are continuously monitored for abnormal leakage during plant operations, in accordance with SHNPP Technical Specifications.
(3) Valves will be subject to system leakage tests, as well as system hydrostatic tests in accordance with the ASME Section XI Code, which will provide added assurance of the structural integrity of class one (1) valves.
(4) Performing these visual examinations, under such adverse conditions such as high dose rates and poor as-cast surfaces, realistically, provides little additional as to the valve casing integrity. In addition,
'nformation disassembly of valves may also cause unnecessary damage to occur, due to the disassembly process.
(5) The disassembly of the majority of the class one (1) valves would require fuel removal, or require the primary system to,be placed in a mid-loop condition (NuReg-1269).
This request for relief (Rl-005(A)) is applicable to the SHNPP Unit 1 First Ten (10) Year Interval Inservice Inspection.
Page 2 of 2
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QUERY RESPONSE REPORT PAGE:
HARRIS ISI RELIEF REQUEST R1-05A: COMPONENTS REQUESTED FOR RELIEF 4j4444444t4t4t44444444444t44444444444444t444444444tt4t4t44444444444444444444t444444444 COMPNOEX COMPbES CATEGO ITEMNO EXSCHD COMMENTS II-RC-0271RC-123 INT AVALINT 8-M-2 812.50 VT-3 II-RC-027 1RC-125 INT AVALINT 8-M-2 812.50 VT-3 II-RC-0271RC-127 INT AVALINT 8-M"2 812.50 VT-3 II-RH-0091RH-39 INT AVALINT 8"M-2 812.50 VT-3 II-RH-0091RH-40 INT AVALINT 8-M-2 812.50 VT-3 II-RH-0101RH-I INT AVALINT 8-M-2 812.50 VT-3 I I-RH-0101RH-2 INT AVALINT 8-M-2 812.50 VT-3 II-SI-0171SI-138 INT AVALINT 8-M-2 812.50 VT-3 II-SI-0211SI-249 INT AVALINT 8"M-2 812.50 VT-3 II-SI-0211SI-250 INT AVALINT 8-M-2 812.50 VT-3 I I-SI-0221SI-251 INT AVALINT 8-M-2 812.50 VT-3 I I-SI-0221SI-252 INT AVALINT 8-M-2 812.50 VT"3 II-SI-0231SI-253 INT AVALINT 8-M-2 812.50 VT-3 II-SI-0231SI-254 INT AVALINT 8-M-2 812.50 VT-3 II-SI-024151-356 INT AVALINT 8-M-2 812.50 VT-3 I I-SI-02415 I-81 INT AVALINT 8-M-2 812.50 VT-. 3 I I-SI-0251SI-357 INT AVALINT 8-M-2 812.50 VT-3 II-SI-0251SI-82 INT AVALINT 8-M-2 812.50 VT-3 I I-SI-0261SI-358 INT AVALINT 8-M-2 812.50 VT-3 I I-SI-026 ISI-83 INT AVALINT 8-M-2 812.50 VT-3 II-SI-0271SI-135 INT AVALINT 8-M-2 812.50 VT-3 II-SI-02715!-I37 INT AVALINT 8-M-2 812.50 VT-3 II-SI-0281SI-134 INT AVALINT 8-M-2 812.50 VT-3
REQUEST FOR RELIEF NO. Rl-005 (B), CATEGORY B-L-1: PRESSURE RETAINING WELDS IN PUMP CASING, ITEM B12.10, AND CATEGORY B-L-2'PUMP CASINGS, ITEM B12.20.
IDENTIFICATION OF COMPONENTS:
Reactor Coolant Pumps A,B,C
'SME SECTION XI CODE REQUIREMENT:
Examination category B-L-1, Item B12.10 requires a volumetric examination on pump casing welds. Examination category B-L-2, Item B12.20 requires a visual examination (VT-3) on the internal surfaces of pumps. Examinations are limited to at least one (1) pump performing similiar functions in each group of pumps performing similiar functions in the system.
CODE RELIEF REQUEST:
Relief is requested from the inservice volumetric and visual examinations (VT-3) of class 1 Reactor Coolant Pump casings, and pressure retaining welds in pump casings.
ALTERNATE EXAMINATIONS:
Components will be subject to system leakage pressure tests during refueling outages, as well as system hydrostatic tests every ten (10) year interval. In addition, subject pumps are continuously monitored in the control room, during pump operations, for bearing temp., flow, vibration, motor current, leakage and seal water flow which will provide early indication of pump degradation.
BASIS FOR REQUESTING RELIEF:
To perform volumetric (radiography) and visual examinations (VT-3) on subject pumps would require disassembly of a least one (1) pump. It is CP&L's position that this disassembly process would be a hardship without any appreciable increase in the level of quality and/or safety expected.
The Reactor Coolant Pumps have undergone very stringent exam-inations and tests as part of the fabrication process, giving a very high confidence level of structual integrity for plant operations. In addition, subject pumps are monitored in the control room, during operation, for performance parameters which provide a continuous status of pump integrity/
operability.
CONSTRUCTION CODE EXAMINATIONS:
Volumetric Surface Page 1 of 2
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Rl-005 (B) CONT.
'TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF:
The non-performance of volumetric and visual examinations, of pump casing welds and pump casings, should not have any adverse impact on plant quality, safety, or reliability for the following reasons:
(1) The fabrication methods utilized, as well as the required construction code (ASME SECTION III) examinations performed, provides a very high confidence level of structual integrity and pump performance for long-term plant operations.
(2) The Reactor Coolant Pumps, being part of the primary system, are continuously monitored for abnormal leakage, utilizing control room instrumentation, during Specifica-plant operation, in accordance with SHNPP Technical tions.
(3) The Reactor Coolant Pumps are monitored in the control room, during operation, for bearing temperature, flow, vibration, motor current and seal water flow, which will provide early detection of pump degradation.
(4) Pump casing base and weld materials utilized for fabrica-tion of the pumps, are widely used in nuclear industry with no known history of degradation or breach of primary system boundary.
(5) Pumps are subject to periodic system leakage/hydrostratic pressure tests to ensure structural integrity.
(6),The disassembly process which may cause unnecessary damage to occur to the pump, requires the expenditure of an estimated 1000 man hours and 50 man-rem dose to disassemb-le, with essentially no compensating increase in plant safety or reliability expected.
This request for relief (Rl-005 (B)) is applicable to the SHNPP Unit (1) First Ten (10) Year Interval Inservice Inspection Program.
Page 2 of 2
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QUERY RESPONSE REPORT PAGE:
HARRIS - ISI RELIEF REQUEST R1-058t COMPONENTS~REQUESTED FOR RELIEF 44444444444i444444444 44444f4I444444t444t44f444444ffft4t44444t444fff4444tkf4f44 4440444444444lgtlllt4IP4444444IIIAI4444444444444444 COMPNOEX COMPOES CATEGO ITEMNO EXSCHO COMMENTS I I-RCP-01RCPA-CASINT TPUINT 8-L-2 812.20 VT-3 I I-RCP-01RCPA-CW-01 TPUMPCW 8-L-1 812. 10 RT I I-RCP-01RCPB-CASINT TPUINT 8-L-2 812. 20 VT-3 II-RCP-01RCPB-CW-01 TPUMPCW 8-L-I 812.10 RT I I-RCP-01RCPC-CASINT TPUINT 8-L-2 812.20 VT-3 II-RCP-01RCPC"CW-01 TPUMPCW 8-L-1 812.10 RT
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REQUEST FOR RELIEF NO. Rl-006, FULL PENETRATION WELDS OF NOZZLES IN VESSELS/ CATEGORY B-D, ITEMS B3.90, B3.110~B3.130/
'AND PRESSURE RETAINING DISSIMILIAR METAL WELDSg CATEGORY B-Fg Item B5.40:
IDENTIFICATION OF COMPONENTS:
Full penetration welds of nozzles in vessels and pressure retaining dissimiliar welds, as listed on attachment for this relief request.
ASME SECTION .XI CODE REQUIREMENT:
Examination category B-D, Item(s) B3.90, B3.110, B3.130 requires an inservice volumetric (U.T.) examination. Examina-tion Category B-F, Item B5.40 requires an inservice volumetric and surface examination.
CODE RELIEF REQUEST:
Relief is requested from 100 percent volumetric (U.T.) examin-ation due to nozzle configurations not being conducive to 100 percent volumetric (U.T.) examination, and/or component obstructions not allowing 100 percent volumetric (U.T. ) exam-nation(s) to be performed (see attached computer listing in-dicating applicable situations for each weld).
BASIS FOR REQUESTING RELIEF:
In accordance with the requirements of ASME Section XI Code, nozzle to vessel welds require volumetric (U.T.) examination from two (2) sides of the weld to be 100 percent complete. Due to nozzle configurations of these components, 100 percent volumetric (U.T.) examinations will be limited, mostly, to the shell-side of the nozzle welds. In addition, shell-side exam-inations will be limited, somewhat, due to obstructions (Insul-ation tabs, heater obstructions). The Pressurizer nozzle to safe-end butt welds are also limited due to nozzle configura-tions and insulation tab obstructions. Volumetric (U.T.)
examinations in limited areas, will be accomplished as a best effort attempt to cover as much of the code required area or volume as possible. The conditions listed on attachment to this relief request, for each component where complete examination of 100% of the required volume or area could not be achieved, were noted during the Preservice Examination Program of SHNPP Unit One (1).. Examiners data sheets for the preservice are available at the SHNPP Site for review.
Page 1 of 2
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Rl-006 Cont.
- ALTERNATE EXAMINATIONS:
Volumetric (U.T.) examinations will be performed to the maximum extent possible from one side of the welds. In addition, comp-onent welds will be subject to system pressure tests during refueling outages in which visual (VT-2) examinations will be performed to the maximum extent possible. Should more advanced volumetric scanning techniques to improve coverage become avai-lable, an evaluation will be performed for possible incorpora-tion into the SHNPP ISZ Program.
CONSTRUTION CODE EXAMINATIONS:
Volumetric Surface TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF:
Nozzle to vessel welds and nozzle to safe-end butt welds are not conducive to the two(2) sided volumetric (U.T.) examina-tion due to nozzle configurations. In addition, obstructions, as part of the component design, prevents accessibility to the weld volume to perform 100 percent volumetric (U.T.) exam-ination.
Components were subject to 100 percent volumetric and surface examinations during fabrication/construction, which provides a very high confidence level of structural intergrity. Compo-nents were also hydrostatically tested at design temperatures and pressures during construction.
No impact on plant quality, safety or reliability is expected, as these., components will be examined to the maximum extent possible, as well as be subject to visual examination (VT-2) during refueling outages, to ensure component intergrity.
This Request for Relief (Rl-006) is applicable to the SHNPP Unit 1 First Ten (10) Year Interval Inservice Inspection Program.
Page 2 of 2
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- NUTECH/PRIS QUERY RESPONSE REPORT PAGE:
HARRIS I SI RELIEF REQUEST R1-006: COMPONENTS REQUESTED FOR RELIEF 4444444444t4444444404444S44444444444444444444044444444444444444444444444444444444444444t COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS II-PZR-01MWTVW-14 VMTHW 8-08 83.110 UT-00 SHELL SIDE ONLY; 20% OBSTRUCTED 7.5" FROM C/L BY TRANS. 30% COMP.
I I-PZR-01MWTVW-14 VMTHW 8-08 83.110 UT-455 SHELL SIDE ONLY; 50'A COMP.
I I - PZR-01MWTVW-14 VMTHW 8-08 83. 110 UT-605 SHELL SIDE ONLY: 20% OBSTRUCTED 7.5" FROM C/L BY TRANS. 30'L COMP.
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444444 04444444444444444444t4404t4444t444444t444444444444444 t 4 4 4 4 4 4 4 4 t 4 4 4 4 4 4 t 4 4 4 4 4 4 t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 44 4 4 4 4 0 4 4 01/l~ NUTECH/PRIS QUERY RESPONSE REPORT PAGE:
HARRIS I SI RELIEF REQUEST Rl-006: COMPONENTS REQUESTED FOR RELIEF COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS I I-PZR-01NTHW-12 VNTVWO 8-08 83. 110 UT-60S SHELL SIDE ONLY-50'/o COMPLETE I I-PZR-01NTHW-13 VNTVWO 8-DB 83. 110 UT-00 SHELL SIDE ONLY-50% COMPLETE I I-PZR-01NTHW-13 VNTVWO B-DB 83.110 UT-45S SHELL SIDE ONLY-50ilo COMPLETE II-PZR-01NTHW-13 VNTVWO 8-DB 83. 110 UT-60S SHELL SIDE ONLY-50% COMPLETE II-RV-001RVNOZAI-N-01 VNOZ 8-DB 83. 95 UT-RVS LIMITED-TRANSDUCER ANGLE ON NOZ RADIUS, RASTER 8-96% COMPLETE II-RV-001RVNOZAO-N-06 VNOZ B-DB 83. 9S UT-RVS LIMITED-NOZZLE KNUCKLE-88% COMPLETE II-RV-001RVNOZBO-N-02 VNOZ 8-DB 83. 9S UT-RVS LiMITED-NOZZLE KNUCKLE-88% COMPLETE II-RV-001RVNOZCO-N-04 VNOZ 8-DB 83. 95 UT"RVS LIMITED-NOZZLE KNUCKLE-88% COMPLETE II-SG-001SGA-CLMWTHW-15 VMTHW 8-DB 83.130 UT-00 SHELL SIDE ONLY; INSULATION TABS (4)-49% COMPLETE II-SG-001SGA-CLMWTHW-15 VMTHW B-DB 83.130 UT-45S SHELL SIDE ONLY-49% COMPLETE II-SG"001SGA-CLMWTHW-15 VMTHW 8-DB 83.130 UT-60S SHELL SIDE ONLY; INSULATION TABS (4)-49% COMPLETE II-SG-001SGA-CLNTVW-12 VNTVWO 8-DB 83. 130 UT-00 SHELL SIDE ONLY; INSULATION TABS (8)-49'k COMPLETE II-SG-OOISGA-CLNTVW-12 VNTVWO 8-08 83.130 UT-455 SHELL SIDE ONLY; INSULATION TABS (8)-49% COMPLETE II-SG-001SGA-CLNTVW-12 VNTVWO B-DB 83. 130 UT-60S SHELL SIDE ONLY; INSULATION TABS (8)-49'A COMPLETE II-SG-001SGA-HLMWTHW"14 VMTHW 8-08 83. 130 UT-00 SHELL SIDE ONLY; INSULATION TABS (5)-43% COMPLETE II-SG-001SGA-HLMWTHW-14 VMTHW 8-DB 83. 130 UT-45S SHELL SIDE ONLY-50% COMPLETE II-SG-001SGA-HLMWTHW-14 VMTHW 8-DB 83. 130 UT-605 SHELL SIDE ONLY; INSULATION TABS (5)-49% COMPLETE II-SG-001SGA-HLNTVW-07 VNTVWI 8-DB 83.130 UT-00 SHELL SIDE ONLY; INSULATION TABS (9)-49K COMPLETE II-SG-001SGA-HLNTVW-07 VNTVWI 8-DB 83. 130 UT-455 SHELL SIDE ONLY; INSULATION TABS (9)-49% COMPLETE II-SG-001SGA-HLNTVW-07 VNTVWI B-DB 83.130 UT-60S SHELL SIDE ONLY; INSULATION TABS (9)-49Va COMPLETE Ii-SG-OOISGB-CLMWTHW-15 VMTHW 8-DB 83.130 UT-00 SHELL SIDE ONLY: INSULATION TABS (4)-49% COMPLETE II-SG-001SGB-CLMWTHW-15 VMTHW 8-DB 83. 130 UT-455 SHELL SIDE ONLY; INSULATION TABS (4)-49% COMPLETE II-SG-001SGB-CLMWTHW-15 VMTHW 8-08 83. 130 UT-605 SHELL SIDE ONLY; INSULATION TABS (4)-49% COMPLETE
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REQUEST FOR RELIEF NO. R1-007 DELETED IN PRESERVICE PROGRAM Page 1 of 1
REQUEST FOR RELIEF NO.R1-008, INTEGRAL ATTACHMENTS FOR
,VESSELS, CATEGORY B-H, ITEM B8.20:
IDENTIFICATION OF COMPONENTS:
Integral welded attachments on Pressurizer, as listed on attachment for this relief request.
ASME SECTION XI CODE REQUIREMENT:
Examination Category B-H, Item B8.20 requires an inservice sur-face or volumetric examination, as applicable, be performed on integral welded attachments to the Pressurizer.
CODE RELIEF REQUEST:
Relief is requested from performing an inservice 100% surface examination on integral attachments to the Pressurizer, due to attachments'onfiguration not allowing access to 1/2 in. of the base material, past the top end of the welds (See attached detail sketch).
ALTERNATE EXAMINATION:
The inaccessible portions of the attachments will be visually (VT-1) examined to ensure"structural intergrity.
BASIS FOR REQUESTING RELIEF:
The design of integral welded attachments on the Pressurizer, will not allow access to 1/2 in. of the base material to facilitate 100% surface examination completion, as required by the ASME Section XI Code.
CONSTRUCTION CODE EXAMINAT10N:
Surface TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF:
The integral welded attachments will be surface examined for essentially 100% of the weld length, as possible. The inaccess-ible portions of the attachments will be visually (VT-1) examined to ensure structural integrity. No impact on plant quality, safety or reliability is expected as the attach-ments will be periodically examined to ensure structural integ-rityo This Request for Relief (Rl-008) is applicable to the SHNPP First Ten (10) Year Interval Inservice Inspection Program.
Page 1 of 1
444t4444 4444044444444 4444444444444fa 44444444444 '4 '4 444444444444 4' 44 01/12~ NUTECH/PRISI PAGE:
QUERY RESPONSE REPORT HARRIS I SI RELIEF REQUEST R1-008: COMPONENTS REQUESTED FOR RELIEF 44444t440t44444tkt444t44404444t44444444444444444444444444444444444444 4444444444444t4444444444444444 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS I I-PZR-01SBW-A1A VI, PSB 8-H 88.20 MT 1/2" BASE METAL PAST TOP END OF WELD OBSTRUCTED I I-PZR-01SBW-A18 VI, PSB 8-H 88.20 MT 1/2" BASE METAL PAST TOP END OF WELD OBSTRUCTED II-PZR-01SBW-A2A VI, PSB 8-H 88.20 MT 1/2" BASE METAL PAST TOP END OF WELD OBSTRUCTED II-PZR-01SBW-A28 VI, PSB 8-H 88.20 MT 1/2" BASE METAL PAST TOP END OF WELD OBSTRUCTED II-PZR-01SBW-A3A VI, PSB 8-H 88.20 MT I/2" BASE METAL PAST TOP END OF WELD OBSTRUCTED II-PZR-01SBW-A38 VI, PSB 8-H 88.20 MT 1/2" BASE METAL PAST TOP END OF WELD OBSTRUCTED II-PZR-01SBW-A4A VI,PSB 8-H 88.20 MT 1/2" BASE METAL PAST TOP END OF WELD OBSTRUCTED II-PZR-01SBW-A48 VI, PSB 8-H 88.20 MT 1/2" BASE METAL PAST TOP END OF WELD OBSTRUCTED
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REQUEST FOR RELIEF NO. R2-001: PRESSURE RETAINING WELDS IN IN PIPING, CATEGORY C-F, ITEM: C5.21; AND INTEGRAL WELDED ATTACHMENTS FOR VESSELS, PIPING, PUMPS AND VALVES'ATEGORY C-C, ITEMS: C3.20 and 3.30.
IDENTIFICATION OF COMPONENTS:
Pressure retaining circumferential piping welds; and integral welded attachments on vessels, piping, pumps and valves as listed on attachment for this relief request.
ASME SECTION XI CODE REQUIREMENTS:
Examination Category C-F, Item C5.21 requires, on pressure retaining circumferential welds in piping > 1/2 in. nominal wall thickness, an inservice surface and volumetric examination be performed. Examination Category C-C, Item(s) C3.20 and C3.30 requires an inservice surface examination be performed on integral welded attachments meeting the following condition:
(1) The attachment base material design wall thickness is 3/4 in. or greater.
CODE RELIEF REQUEST:
Relief is requested from performing 100% volumetric and/or surface examinations on listed circumferential piping welds
(> 1/2 in. nominal wall thickness) and listed integral welded attachments due to component configurations (pumps, valves) not being conducive to examination, and/or structural obstruc-tions (permanent hangers, saddle plates, support structures, or intervening members for other systems) not allowing access-ibility to perform computer 100% surface and/or volumetric examination, listing for component identifica-as applicable (see tion."and predicted completion percentages, based on preservice baseline information, for the appropriate examinations).
ALTERNATE EXAMINATIONS:
Components will be subject to periodic systems pressure tests, as well as periodic hydrostatic and visual (VT-2) examination, to the maximum extent possible. Welds will be volumetrically (U.T.) examined, to the maximum extent possible, in accordance with the Inservice Inspection Program Schedule. In addition, the components will be subject to system pressure tests during each refueling outage.
CONSTRUCTION CODE EXAMINATION:
Volumetric (as applicable)
Surface (as applicable)
Page 1 of 2
A 1g i'1 kW
R2-001 Cont.
TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF Component configurations (pumps, valves) and/or structural obstructions (hangers, saddle plates, support structures) will not allow 100% inservice volumetric and/or surface examination to be performed.
Components were subject to fabrication/construction volumetric and/or surface examinations, as applicable, which provides a high confidence level of structural integrity for long-term plant operations. In addition, in response to NRC question 250.1 and FSAR Section 6.6.8, a large sample of welds in the ECCS, CHR and RHR Systems, as well as No Break Zone Crit-eria components were examined during preservice activities (1,064 examinations including 525 surface and 539 volumetric),
providing additional assurance of structural integrity.
Attached to'his relief request is an itemized listing of components, percentages of completion based on preservice data, and identification of specific reasons as to why a 100% ASME Section XI Code examinations can not be performed. Should more advance nondestuctive method techniques to improve coverage become available, an evaluation will be performed for possible incorporation into the SHNPP ISI Program.
No impact on plant quality, safety or reliability is expected, as subject components will be examined to the maximum extent possible, as well as be subject to periodic pressure tests and visual examinations in accordance with the ASME Section XI Code, to ensure component intergrity.
This Request for Relief (R2-001) is applicable to the SHNPP Unit 1 First Ten (10) Year Inservice Inspection Program.
Page 2 of 2
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QUERY RESPONSE R RT HARRIS - ISI RELIEF REQUEST R2-001: COMPONENTS REQUESTED FOR RELIEF 444t444444t4tftf4444t4ft4444ffkf44f44444404444f44f4444fff4444444tt4444444 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS II-AF-006AF-FW-245 PC,PIPE-PBCC,T FSAR 6.6.88 UT-45S CIRC. 75% , AXIAL 75% COMPLETE II-CS-001CT-SW-J3 PE,LR -PC,PIPE SER 250.1S PT WELD 87% COMPLETE II-CS-006CS-SW-I4 PC,RED -PC,PIPE SER 250.1V UT-45S CIRC. 50% , AXIAL 50% COMPLETE II-CS-007CS-SW-A4 PC,RED -PC,PIPE SER 250.1V UT-455 CIRC. 67% , AXIAL 50% COMPLETE II-CS-021CS-H-0011I(4) PC,PIPE-PI,LUGN C-C C3.20 PT WELD 95'%OMPLETE I I-CSI P-1CSI P-A-WA 'I TI FEET C-C C3.30 PT 80% COMPLETE-PUMP CONFIGURATION I I-CSIP-1CSIP-A-WA2 TIFEET C-C C3.30 PT 78% COMPLETE-PUMP CONFIGURATION II-CSIP-1CSIP-A-WA3 TIFEET C-C C3.30 PT 78% COMPLETE-PUMP CONFIGURATION 8 NOZZLE I I-CSIP-1CSIP-A-WA4 TIFEET C-C C3.30 PT 70% COMPLETE-PUMP CONFIGURATION 8 FLANGED END I I-CSIP-1CSIP-8-WA1 TIFEET C-C C3.30 PT 80% COMPLETE-PUMP CONFIGURATION I I-CSI P-1CSI P-8-WA2 TIFEET C-C C3.30 PT 78% COMPLETE-PUMP CONFIGURATION I I-CSI P-1CSI P" 8-WA3 TI FEET C-C C3.30 PT 75% COMPLETE-PUMP CONFIGURATION 8 NOZZLE I I-CSI P-1CSI P-8-WA4 TI FEET C-C C3.30 PT 80% COMPLETE-PUMP CONFIGURATION I I-CSI P-1CSI P-C-WA1 TIFEET C-C C3.30 PT 70% COMPLETE-PUMP CONFIGURATION 8 FLANGED END I I "CSIP-1CSIP-C-WA2 TIFEET C-C C3.30 PT 80% COMPLETE-PUMP CONFIGURATION I I-CSI P-1CSIP-C-WA3 TIFEET C-C C3.30 PT 75% COMPLETE-PUMP CONFIGURATION 8 NOZZLE I I-CSI P-1CS IP" C-WA4 TIFEET C-C C3.30 PT 70% COMPLETE-PUMP CONFIGURATION 8 FLANGED END I I-CT-014CT-FW-174 PP,FHS -PE,LR SER 250.1V UT-45S CIRC. 67% , AXIAL 50% COMPLETE II-CT-016CT-SW"A3 PE,LR -PC,PIPE SER 250.1V UT-45S AXIAL 99% COMPLETE I I-FMR-01FW-H-0212I (8) PC,PIPE-PI,LUGN C-C '3.20 MT WELD 83%s COMPLETE II-FW-002AF-FW-257 PC,VLV -PC,PIPE C-F C5.21 UT-45S CIRC. 50% , AXIAL 50% COMPLETE II-FW-002AF-FW"257 PC,VLV -PC,PIPE FSAR 6.6.88 UT-45S CIRC. 50% ~ AXIAL 50% COMPLETE II-FW-002AF-FW-258 PC,PIPE-PC,VLV C-F C5. 21 UT-45S CIRC. 67% COMPLETE
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QQL REQUEST FOR RELIEF NO. R2-002, COMPONENT STANDARD SUPPORTS (SNUBBERS), CATEGORY F-C, ITEM F3.50 FOR CLASS TWO (2) SYSTEMS.
IDENTIFICATION OF COMPONENTS:
All hydraulic and/or mechanical snubbers listed on attachment for this relief request.
ASME .SECTION XI CODE REQUIREMENT:
IWF-2000 requires visual examination in accordance with Table IWF-2500-1. IWF-5000 requires functional testing of snubbers in accordance with IWF-5300 (in course of preparation) and IWF-5400.
CODE RELIEF REQUEST:
Relief is requested from the functional test requirements for snubbers per Article IWF-5000 of the ASME Section XI Code.
Visual, Examination (VT-4) will be performed in accordance with ASME Section XI, which will also satisfy the visual exam-ination criteria of the SHNPP Technical Specifications, as applicable.
ALTERNATE EXAMINATION:
Shearon Harris component support snubbers will be selected and functionally tested per Section 3/4.7.8 of the SHNPP Technical Specifications.
BASIS FOR REQUESTING RELIEF:
The SHNPP Technical Specifications and the ASME Section XI Code are similiar in their intent to functionally test snubbers. The SHNPP -Technical Specifications are, however, more restrictive in the selection, as well as the method of testing snubbers for functional adequacy.
CONSTRUCTION CODE EXAMINATIONS:
Not Applicable TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF:
The Nuclear Regulatory Commission has approved the utilization of SHNPP Technical Specification for functionally testing snubbers. The utilization of the ASME Section XI Code, would be less restrictive than performing testing in accordance with SHNPP Technical Specifications.
This Request for Relief (R2-002) is applicable to the SHNPP Unit 1 First Ten (10) Year Interval Inservice Inspection Program.
Page 1 of 1
R2-002 ATTAQBKNT CATEGORY F-C~ ITEM F3.50 FOR CLASS TWO (2) SYSTEMS AF-H-00022 AF-H"00494 BD-H-00421 Cs-H-00108 Cs-H"01103 AF-H-00052 AF-H"00496 BD-H-00422 Cs-H-00149 CS-H-01204 AF-H-00080 AF-H"00498 BD-H-00423 Cs-H-00167 CS-H-01414 AF-H-00286 AF-H-00500 BD-H-00424 CS-H-00168 CS-H-01415 AF-H-00296 AF-H-00653 BD-H-00428 Cs-H-00172 CS-H-01416 AF-H-00298 BD-H-00429 Cs-H-00355 Cs-H-01418 AF-H-00299 BD-H"00002 BD-H-00457 Cs-H-00356 Cs"H-01465 AF-H-00300 BD-H-00004 BD-H-00489 CS-H-00359 CS-H"01594 AF-H-00302 BD-H"00005 BD-H-00491 Cs-H-00360 CS-H-01693 AF-H-00303 BD-H-00009 BD-H-00501 Cs-H-00362 CS-H"02029 AF"H-00311 BD"H-00011 BD-H-00502 Cs-H-00363 Cs-H-02600 AF-H-00312 BD-H"00015 BD-H-00505 Cs-H-00364 Cs"H-02692 AF-H-00313 BD-H"00019 BD-H-00509 Cs-H-00366 Cs-H-02722
,AF"H-00314 BD-H"00022 BD-H-00511 Cs-H-00379 Cs-H"02730 AF-H-00317 BD-H-00023 BD-H-00512 Cs-H-00382 CS-H-02757 AF-H"00320 BD-H-00024 BD-H-00516 Cs-H-00383 Cs-H-02769 AF-H-00326 BD-H-00029 BD-H-00549 Cs-H-00385 Cs-H"02866 AF-H-00327 BD-H-00031 BD-H-00550 Cs"H-00387 Cs-H-02868 AF"H-00328 BD"H"00036 BD-H-00555 Cs-H-00389 Cs-H-02877 AF-H-00333 BD-H-00040 BD-H-00556 Cs-H-00392 Cs-H-02883 AF-H"00334 BD-H-00044 BD-H-00584 Cs"H-00402 CS-H-02885 AF"H-00335 BD-H-00046 BD-H-00586 Cs"H"00403 CS-H-02887 AF-H-00336 BD-H-00048 BD-H-00589 Cs-H-00423 CS-H"02927 AF-H-00338 BD-H-00049 BD-H-00590 Cs-H-00426 Cs"H-02931 AF-H-00339 BD-H"00051 BD-H-00591 Cs-H-00427 CS-H-02935 AF-H-00362 BD-H-00071 BD-H-00592 Cs"H-00432 Cs-H"03048 AF-H-00363 BD"H"00073 BD-H-00593 Cs-H-00535 Cs-H"03049 AF-H-00364 BD-H-00074 BD-H-00594 Cs-H-00659 CS"H"03052 AF-H-00365 BD-H-00077 BD-H-00604 Cs-H-00733 CS-H"03105 AF-H-00366 BD-H-00080 BD-H-00611 Cs-H-00740 Cs-H-03189 AF-H-00367 BD-H-00095 BD-H"00613 Cs-H-00747 Cs-H-03197 AF-H"00368 BD-H-00097 BD-H-00614 Cs-H-00756 Cs-H-03236 AF-H-00369 BD-H-00348 Cs-H-00757 Cs"H"03237 AF-H-00390 BD-H-00349 CC-H-00807 Cs-H"00759 CS-H-03238 AF-H-00391 BD-H"00351 CC-H-00821 CS-H-00760 CS-H"03239 AF"H"00392 BD-H-00353 CC-H-00822 CS-H-00761 CS-H-03240 AF-H-00393 BD-H-00357 CC-H-01868 CS-H-00763 CS-H-03241 AF-H-00425 BD-H-00358 CC-H-01869 Cs-H-00764 Cs-H-03259 AF"H-00428 BD-H-00362 Cs-H-00803 CS-H"03260 AF-H-00431 BD-H-00364 CS-H-00008 Cs"H"00812 Cs-H-03262 AF-H-00436 BD-H-00366 CS-H"00009 Cs-H-00837 CS-H"03598 AF-H-00439 BD-H-00367 CS-H-00010 Cs-H-00862 CS-H-03634 AF-H-00442 BD-H-00371 Cs-H-00020 Cs-H-00867 CS-H-04436 AF-H-00466 BD-H"00373 Cs-H-00025 CS-H-01043 Cs-H-04450 AF-H-00467 BD-H-00375 CS-H"00032 CS-H-01075 CS-H-04468 AF"H-00479 BD-H-00376 Cs-H-00039 Cs-H-01077 Cs"H-04469 AF-H-00481 BD"H-00390 Cs-H-00041 Cs-H-01096 Cs-H"04471 AF-H-00483 BD-H-00412 CS-H-00085 Cs"H-01099 Cs-H"04477 MEM/R2-002/OS2
R2-002 ATTACHMENT CATEGORY F-C~ ITEM F3.50 FOR CLASS TWO (2) SYSTEMS CS-H-04514 FW-H-00215 MS-H-00027 RH-H-00011 SI-H-00026 CS-H-04523 FW-H-00218 MS-H-00028 RH-H-00033 SI-H-00028 FW-H-00219 MS-H-00030 RH-H-00038 SI-H-00030 CT-H-00203 FW-H-00220 MS-H-00032 RH-H"00039 SI-H-00032 CT"H-00220 FW-H"00221 MS-H-00034 RH-H-00042 SI-H-00051 CT-H-00235 FW-H-00222 MS-H-00041 RH-H-00063 SI-H-00058 CT-H-00236 FW-H-00267 MS-H-00049 RH-H-00067 SI-H-00060 CT-H"00273 FW-H"00307 MS-H-00076 RH-H-00072 SI-H-00062 CT"H-00290 FW-H-00456 MS-H-00084 RH-H-00083 SI-H-00096 CT-H-00291 FW-H"00457 MS-H-00092 RH-H-00086 SI-H"00114 CT-H-00301 FW-H-00465 MS-H-00925 RH-H-00107 SI"H-00116 CT-H"00323 FW-H-00466 MS-H-00971 RH-H-00155 SI"H-00131 CT-H-00354 FW-H-00469 MS-H-00972 RH-H-00158 SI"H-00151
""'CT-H-00361 '" FW-H-00470 MS-H-00994 RH-H-00165 SI"H"00156 CT-H-00798 FW-H-00475 MS-H-00995 RH-H-00166 SI-H-00162 CT-H-00864 FW-H-00477 MS-H-00999 RH-H-00167 SI-H-00164 CT-H-00865 FW-H-00479 RH-H-00168 SI-H-00167 CT-H-00871 FW"H"00480 RC-H-00050 RH-H-00169 SI-H-00180 CT-H-00968 FW-H-00515 RC-H-00051 RH-H-00176 SI-H-00181 CT-H"00969 FW-H-00518 RC-H-00162 RH"H-00177 SI-H-00198 CT-H-00972 FW-H-00521 RC-H-00163 RH-H-00178 SI-H-00199 FW-H-00555 RC-H-00164 RH-H-00179 SI-H-00201 FP-H-01392 FW-H-00559 RC-H-00332 RH-H-00188 SI-H-00203 FP-H-02307 FW-H-00560 RC-H-00401 RH-H-00189 SI"H-00222 FW-H-00561 RC-H-00405 RH-H"00206 SI-H-00224 FW-H-00098 FW-H"00571 RC-H-00406 RH-H-00265 SI-H-00235 FW-H-00101 FW-H-00581 RC-H-00409 RH-H-00275 SI-H-00236 FW-H-00103 FW-H-00700 RC-H-00410 RH-H-00290 SI-H-00237 FW-H-00105 FW-H-00710 RC-H-00512 RH-H-00295 SI-H"00238 FW-H-00106 FW-H-00720 RC-H-00528 RH-H-00297 SI-H-00251 FW-H-00108 RC-H-00529 RH-H-00300 SI"H-00254 FW-H-00110 MD-H-01082 RC-H-00537 RH-H-00301 SI-H-00256 FW-H"00113 MD-H-01099 RC-H-00538 RH-H-00302 SI-H-00267 FW-H-00118 RC-H-00544 RH-H-00303 SI"H-00268 FW-H-00120 MS-H-00003 RC-H-00554 RH-H-00307 SI-H-00270 FW"H"00122 MS-H-00004 RC-H-00570 RH"H"00314 SI-H-00272 FW"H-00125 MS-H-00006 RC-H-00602 RH"H-00316 SI-H-00273 FW"H-00126 MS-H"00007 RC-H-00677 RH-H-00350 SI-H;00310 FW-H"00129 MS-H-00008 RC-H-00737 RH-H"00351 SI-H-00312 FW-H-00156 MS-H-00010 RC-H-00807 RH-H-00353 SI-H-00334 FW-H"00184 MS"H-00012 RC-H-00810 SI-H-00344 FW-H-00189 MS-H-00014 RC-H-00869 SI-H-00001 SI-H-00347 FW-H-00190 MS-H-00015 RC-H-00893 SI-H"00005 SI-H"00349 FW-H-00191 MS-H-00016 RC-H-00896 SI-H-00009 SI-H-00381 FW-H"00208 MS-H-00020 RC-H-00897 SI-H-00011 SI"H"00385 FW-H-00211 MS-H-00023 RC-H-00900 SI-H-00020 SI"H-00387 FW-H-00212 MS-H"00024 RC-H-00901 SI-H-00021 SI-H"00389 FW-H-00213 MS-H-00026 RC-H-00904 SI-H-00023 SI-H-00403 MEM/R2-002/OS2
R2-002 ATTACHMENT CATEGORY F-C~ ITEM F3.50 FOR CLASS TWO (2) SYSTEMS SIW-00407 SI-H-01114 SW-H-01900 SIW-00408 SI-H-01130 SW-H-01921 SI-H-00419 SI-H-01160 SW-H-02005 SI"H-00442 SI-H-01161 SW-H-02022 SI-H-00444 SI-H"01182 SW-H-02026 SI-H"00455 SI-H-01184 SW-H"02033 SI-H-00470 SI-H-01185 SW-H-02073 SI-H-00473 SI-H-01191 WG-H-01948 SI-H"00475 SI-H-01192 SI-8-00484 SI-H-01199 WL-H-04680 SI-H-00496 SI-H-01236 SI-H-00511 SI-H-01237 SI-H-00512 SI-H-01257 SI-H-00513 SI-H-01258 SI-H-00515 SI-H-01269 SI-H"00516 SI-H-01275 SI-H-00519 SI-H-01277 SI-H-00520 SI-H"01282 SI-H-00534 SI-H-01285 SI-H-00540 SI-H-01304 SI-H-00541 SI-H-01346 SI-H"00543 SI-H-01428 SI-H-00544 SI-H-01449 SI-H-00545 SI-H-01571 SI-H-00546 SI-H-00554 SP-H-00323 SI-H-00560 SP-H-00324 SI-H-00562 SP-H-00328 SI-H"00565 SP-H-00330 SI-H-00588 SP-H-00346 SI-H-00591 SP-H-00347 SI-H-00593 SP-H"00351 SI-H-00595 SP-H"00353 SI-H-00597 SP-H-00356 SI-H-00629 SP-H"00385 SI-H"00669 SP-H-00386 SI-H-00869 SP-H-00394 SI-H-00870 SP-H-00398 SI-H-00871 SP-H-00399 SI-H-00910 SP-H-00403 SI-H-00940 SP-H-00862 SI-H-00981 SP-H-00886 SI-H-01032 SI-H-01056 SW-H-00217 SI-H-01068 SW-H-00220 SI-H-01076 SW-H-00222 SI-H"01079 SW-H-01888 SI-H"01104 SW"H-01897 MEM/R2-002/OS2
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REQUEST FOR RELIEF NO. R2-003'RESSURE RETAINING CIRCUMFER-
.ENTIAL PIPING WELDSi CATEGORY C-F, ITEM:C5.21.
IDENTIFICATION OF COMPONENTS:
Pressure retaining circumferential piping welds as listed on attachment for this relief request.
ASME SECTION XI CODE REQUIREMENT:
Examination Category C-F, Item C5.21 requires surface and volumetric (U.T.) examination be performed on 1/2 in. nominal wall thickness circumferential piping welds.
CODE RELIEF REQUEST:
Relief is requested from performing 100% volumetric (U.T.)
examination of > 1/2 in. nominal wall thickness circumferential piping welds due to piping configurations (reducer to tee, pipe to tee, pipe to flange...) not being conducive to ultrasonic coupling.
ALTERNATE EXAMINATIONS:
Piping welds will be volumetrically examined to the extent in-dicated on the computer listing for each weld.
BASIS FOR REQUESTING RELIEF:
Piping weld configurations (reducer to tee, pipe to tee, pipe to flange...) will not be conducive to 100% volumetric (U.T.)
examination as required by ASME Section:XI Code and/or Code Case N-335-1, as applicable. The arrangement and details of the piping systems and components were designed and fabricated be-fore the access and examination requirements of ASME Section XI Code, and especially the requirements of Code Case N-335-1 could be applied. Consequently, some examinations will be limited, or not practical to perform due to geometric config-uration or accessibility. The limitations exist at fitting to fitting joints, where geometry and sometimes surface conditions will preclude ultrasonic coupling, or access for the required scan length. Ref. attached computer listing of components, and percentages of completion based on Preservice Baseline Data.
CONSTRUCTION CODE EXAMINATION:
Volumetric Page 1 of 2
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R2-003 Cont.
TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF Required ASME Secti;on XI Code (Code Case N-335-1, as appli-cable) volumetric (U.T.) examination can not be 100% completed on the listed piping welds, for the first ten (10) year ISI interval, due to piping configurations not being conducive to ultrasonic coupling for 100% examination.
In most cases, ultrasonic examination, in limited areas, will be accomplished as a best effort attempt to cover as much of the code required area or volume as possible (generally, the weld and base metal of 1 "T" on each side). These areas where complete examination of 100 percent of the required volume or area could not be achieved are documented on each applicable examination data sheet, and the limited cause noted.
The principal basis of partial examination is to identify the inability to examine 100 percent of the required base metal volume for 1 "T" distance beyond the edge of the weld on a fitting or component. Examples are:
(1) Ultrasonic examination of a pipe to elbow assembly, where scanning on the intrados of the elbow causes decoupling of the sound beam and (2) A pipe to flange on valve assembly where scanning the entire volume on the fitting or component side is limited by configuration. The resulting coverage is such that exam-ination of the weld, heat affected zone and base metal of 1 "T" on indetermined coverage of the base metal on the fitting or component side may be during this pipe side scan, depending on the calibrated sweep length, attentua-tion, joint configuration, etc. However, the volume on the fitting or component side additionally cannot be scanned completely for transverse indications when required "T"
by Code. In either case, 100 percent of this 1 volume cannot be assured, thus a partial examination is required as a disclaimer to having satisfied code requirements, albeit the intent is satisfied to the extent practical.
No impact on overall plant quality, safety, or reliability is expected as subject components will be examined to the maximum extent possible, as well as be subject to periodic pressure tests and visual examinations in accordance with the ASME Section XI Code, to ensure component integrity.
This Request for Relief (R2-003) is applicable to the SHNPP Unit 1 First Ten (10) Year Interval Inservice Inspection Program.
Page 2 of 2
44 4444'44444444t04444t444t40444444444tt4 44444444444044t4444444 44 4 0 4 4 4 4 4 444 4 4 4 4 4 0 4 t 4 4 4 4 4 4 4 4 4 0 4 01/13~ NUTECH/PRIS~
QUERY RESPONSE REPORT PAGE:
HARRIS I SI RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF 4444444444444444444404444 4444444444444404444444444444444444444444444t44444444444444444444444 444444444 f 4 4 4 4 4 4 4 4 4 4 4 4 4 444 4 4 44 4 t 0 4 0 0 0 4 4 0 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS II-AF-005AF-FW-249 PC,VLV -PC,PIPE FSAR 6.6.88 UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-AF-005AF-FW-251 PC,VLV -PC,PIPE FSAR 6.6.88 UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-AF-006AF-FW-246 PC,VLV -PC,PIPE FSAR 6. 6. 88 UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-AF-007AF-FW-239 PC,VLV -PC,PIPE FSAR 6.6.88 UT-455 CIRC. 67% COMPLETE II-AF-007AF-FW-241 PC,VLV -PC,PIPE FSAR 6.6.88 UT-45S CIRC. 67'%OMPLETE II-CS-006CS-FW-102 PC,PIPE-PC,VLV SER 250.1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-103 PC,VLV -PC,PIPE SER 250.1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-104 PC,PIPE-PC,VLV SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW- 105 PC ~ VLV -PC,PIPE SER 250.1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-106 PC,PIPE-PBCC,T SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-122 PC,PIPE-PC,VLV SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-123 PC,VLV -PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-124 PC,PIPE-PC,VLV SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-125 PC,VLV -PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-126 PC,PIPE-PBCC,TR SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-130 PC,VLV -PC,PIPE SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-132 PC,VLV -PC,PIPE SER 250. IV UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-201 PC,PIPE-PC,VLV SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-FW-202 PC,VLV -PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-SW-A3 PF,RFWN-PC,RED SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-SW"D4 PBCC,TR-PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-SW-DS PC,PIPE-PBCC,TR SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-CS-006CS-SW-F3 PBCC,TR-PC,PIPE SER 250. 'IV UT-45S CIRC. 67'%. AXIAL 50% COMPLETE
44444444'4444444444tt44 01/13 NUTECH/PRIS~ PAGE:
QUERY RESPONSE REPORT HARRIS - ISI RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF 4444444404444444000 44444444444t44444444444444444444444444444444444t4444444444444t444t444444%4ft44044 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS II-FW"004AF-FW-276 PC,VLV -PC,PIPE C-F C5. 21 UT-45S CIRC. 67% ~ AXIAL 50% COMPLETE II-FW-004AF-FW-276 PC,VLV -PC,PIPE FSAR 6. 6. 88 UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-FW-004FW-FW-571 PC,PIPE-PC,VLV FSAR 6.6.8C UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-FW-004FW-FW"572 PC,VLV -PC,PIPE FSAR 6.6.8C UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-FW-004FW-SW-C3 PC, PIPE-PE, LR F SAR 6. 6. BC UT-45S CIRC. 67% COMPLETE I I-MS-001MS-SW-A11 PC,PIPE-PC,NOZW FSAR 6.6.8C UT-45S TO BE DETERMINED I I-MS-001MS-SW-A1 'I PC,PIPE-PC,NOZW C-F C5.21 UT-455 TO BE DETERMINED I I-MS-001MS-SW-811 PC,PIPE-PC,NOZW FSAR 6.6.8C UT-45S TO BE DETERMINED I I-MS-001MS-SW-81 1 PC,PIPE-PC,NOZW C-F C5.21 UT-45S TO BE DETERMINED I I-MS-001MS-SW-C11 PC,PIPE-PC,NOZW FSAR 6.6.8C UT-45S TO BE DETERMINED II-MS-001MS-SW-C11 PC,PIPE-PC,NOZW C-F C5.21 UT-45S TO BE DETERMINED II-MS-002MS-FW-566 PC,PIPE-PC,VLV FSAR 6.6.8C UT-45S CIRC. 67'li COMPLETE II"MS-002MS-FW-567 PC,VLV -PC,PIPE FSAR 6.6.8C UT-45S CIRC. 67'/i COMPLETE II-MS-002MS-FW-568 PC,PIPE-PC,VLV FSAR 6.6.8C UT-45S CIRC. 67'Yi COMPLETE II-MS-002MS-FW-690 PC,PIPE-PC,VLV FSAR 6.6.8C UT-455 CIRC. 67% COMPLETE II-MS-002MS-FW-691 PC,VLV -PC,PIPE FSAR 6.6.8C UT-455 CIRC. 67li COMPLETE II-MS-002MS-FW-692 PC,PIPE-PC,VLV FSAR 6.6.8C UT-455 CIRC. 67K COMPLETE II"MS-007MS-FW-678 PC,PIPE-PC,VLV FSAR 6.6.8C UT-45S CIRC. 67% COMPLETE II-MS-009MS"FW-583 PC,PIPE-PC,VLV FSAR 6.6.8C UT-45S CIRC. 67%, COMPLETE II-MS-009MS-FW-586 PC ~ PIPE-PC,VLV FSAR 6.6.8C UT-45S CIRC. 67% COMPLETE II-MS-009MS-FW-589 PC,PIPE-PC,VLV FSAR 6.6.8C UT-455 CIRC. 67% COMPLETE II-RH-001RH-FW-8 PE, LR -VNOZ IAI SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE I I-RH-00 IRH-SW-EB PBCC,T -PF,WNO SER 250. 1V UT-45S CIRC. 67'A, AXIAL 50% COMPLETE
I444 44 44444 44 444 0 44 0 4 444444444 44 4 0 444 4404 44 4'444 t 4 44444 44 i 444 44444444 00 44 44444 44 44'4 4444 4444 444 f 0 444 4 0'444 4444 01/13 NUTECH/PRIS~ PAGE:
4 QUERY RESPONSE REPORT HARRIS ISI 4 RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS I I-RH-001 5 I-FW"9 PBCC,T -PC,PIPE SER 250. IV UT-45S CIRC. 82%, AXIAL 64% COMPLETE II-RH"002RH-FW-21 PE, LR -VNOZ181 SER 250. 1V UT-45S CIRC. 91%, AXIAL 82% COMPLETE II-RH-002RH-SW-85 PE,LR -PC,PIPE SER 250. 1V UT-45S CIRC. 30%, AXIAL 96% COMPLETE II-RH-002RH-SW-ES PBCC, T -PC, TS SER 250. IV UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-RH-002RH-SW-EB PC,PIPE-PBCC,TR SER 250. 1V UT-455 CIRC. 67%, AXIAL 50'L COMPLETE II-RH-002RH-5-2-SW-1 PC,PIPE-PC,PIPE SER 250. 1V UT-45S CIRC. 94%, AXIAL 89% COMPLETE II"RH"002RH"5-6-SW-1 PC,PIPE-PBCC,TR SER 250. 1V UT-455 TO BE DETERMINED II-RH-002RH-5-6-SW-2 PBCC,TR-PC,PIPE SER 250.1V UT-45S TO BE DETERMINED I I-RH-002SI-FW-21 PBCC,T -PC,PIPE SER 250. 1V UT-45S CIRC. 91%, AXIAL 82% COMPLETE II-RH-009RH-FW-14 PC,VLV -PC,PIPE SER 250. 1V UT-50S CIRC. 67%, AXIAL 50'/0 COMPLETE II-RH-009RH-FW-14 PC,VLV -PC,PIPE C-F C5. 21 UT-SOS CIRC 67'A, AXIAL 50'A COMPLETE II-RH-009RH-FW-15 PC,PIPE-PP,FHS SER 250. 1V UT-45S CIRC. 67'L, AXIAL 50% COMPLETE I I-RH-010RH-FW-193 PC,VLV -PC,PIPE SER 250. 1V UT-505 CIRC. 67%, AXIAL 50% COMPLETE I I-RH-010RH-FW-193 PC,VLV -PC,PIPE C-F C5.21 UT-50S CIRC 67%, AXIAL 50% COMPLETE I I-RH-010RH-FW-2 PC,PIPE-PP,FHS SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE I I-SI-003SI-FW-271 PC,PIPE-PC,VLV SER 250. 1V UT-45S AXIAL 50% COMPLETE I I-SI-003SI-FW-272 PC,VLV -PC,PIPE SER 250.1V UT-45S CIRC. 67'A, AXIAL 50% COMPLETE II-SI-003SI-FW-274 PC,VLV -PC,PIPE SER 250.1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE I I-SI-003SI-FW" 275 PC,PIPE-PC,VLV SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-SI-003SI-SW-AB PE,RED -PC,PIPE SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-SI-003SI-SW-87 PBCC,T -PC,PIPE SER 250. 1V UT-455 CIRC. 67'A, AXIAL 50% COMPLETE II-SI-003SI-SW-88 PBCC,T -PC,PIPE SER 250. 1V UT-455 AXIAL 50'XI COMPLETE II-SI"003SI-SW-89 PC,PIPE-PBCC,T SER 250. 1V UT-45S AXIAL 50% COMPLETE
t4f ftt444444t44f t4404t444f f tf ttlt444t444tt44444ttkkt44 tttttf444tt44844444 01/1~ NUTECH/PRIS~
QUERY RESPONSE REPORT HARRIS ISI RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS II-SI-004SI-13-11-SW-5 PE,LR -PC,PIPE SER 250. 1V UT-45S AXIAL 82'll COMPLETE II-SI"OOBSI-FW-450 PC,VLV -PC,PIPE C-F C5.2 I UT-60S AXIAL 67'A COMPLETE II-SI-00851-FW-457 PC,VLV -PC,PIPE C-F CS. 21 UT-605 AXIAL 91% COMPLETE I I-SI-009SI-FW-279 PC,VLV -PC,PIPE C-F CS. 21 UT-50S CIRC. 67ili, AXIAL 50% COMPLETE II-SI-OIOSI-FW-276 PBCC,T -PC,PIPE SER 250. 1V UT-455 AXIAL 50'L COMPLETE
'II-SI-010SI-SW-A3 PC,PIPE-PF,WNO SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE I I-SI-010SI-SW-87 PF,WNO -PC,PIPE SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE I I-SI-0105 I-SW-C7 PBCC,T -PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE I I-SI-010SI-SW-CB PC,PIPE-PBCC,T SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II"SI-010SI- 100-FW-275 PC,RED -PC,PIPE SER 250. IV UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-SI-010SI-99-FW-269 PBCC,T -PC,PIPE SER 250. 1V UT-45S CIRC. 67%, AXIAL 50'A COMPLETE II-SI-010SI-99-FW-270 PC,PIPE-PC,VLV SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE I I-SI-01051-99-FW-271 PC,VLV -PC,PIPE SER 250. 1V UT-45S CIRC. 67%. AXIAL 50% COMPLETE I I-SI-01 15 I-FW-475 PC,PIPE-PC,VLV SER 250. IV UT-45S CIRC. 67%, AXIAL 50% COMPLETE I I-SI-011SI-FW-476 PC,VLV -PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-SI-016SI-FW-36 PC,PIPE-PBCC,T SER 250. 1V UT-455 AXIAL 75% COMPLETE
.II-SI-01651-SW-D4 PBCC,T -PC,PIPE SER 250.1V UT-45S AXIAL 75% COMPLETE I I-SI-0165 I-SW-DS PBCC,T -PC,PIPE SER 250. 1V UT-455 AXIAL 75% COMPLETE I I-SI-019SI-FW-276 PP,FHS -PC,PIPE SER 250.1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE I I-SI-019SI-FW-277 PC,PIPE-PBCC,T SER 250.1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE I I-SI-0195 I-SW-04 PBCC,T -PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE I I-SI-0195 I-SW-05 PBCC,T -PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50'A COMPLETE I I-SI-0215 I-FW-557 PC,VLV -PC,PIPE C-F C5.21 UT-535 CIRC. 67%, AXIAL 50'L COMPLETE
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QUERY RESPONSE REPORT HARRIS I SI RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF 4444t44t4t44t44tt444444t444t4t4t44t444t444ftt4tt440tjtt4t444f4t4t44444444444444t44 4o444o4444444o44o4oo4 i 44 4 4 4 4 o 4 4 o o 4 4 4 4 4 4 o 4 4 4 4 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS I I-SI-026SI-FW-581 PC,PIPE-PC,VLV C-F CS. 21 UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-SI-026SI-FW-582 PBCC,T -PC,PIPE C-F CS. 21 UT-45S CIRC. 67%, AXIAL 50% COMPLETE II-SI-026SI-FW-590 PC,VLV -PC,PIPE C-F C5. 21 UT-60S CIRC. 67o/o, AXIAL 50% COMPLETE II-SI-026SI-FW-59'I PC,PIPE-PC,VLV C-F C5. 21 UT-605 CIRC. 67%, AXIAL 50% COMPLETE I I-SI-0265 I-FW-592 PP,FHS -PC,PIPE C-F C5. 21 UT-605 CIRC. 67%, AXIAL 50% COMPLETE I I-SI-026SI-FW-594 PC,PB -PC,VLV C-F C5. 21 UT-455 CIRC. 67To, AXIAL 50% COMPLETE II-SI-026SI-SW-G3 PC,PIPE-PF,RED C-F CS. 21 UT-60S CIRC. 67%. AXIAL 50% COMPLETE II-SI-026SI-SW-G5 PC,PIPE-PBCC,TR C-F C5. 21 UT-605 CIRC. 67%, AXIAL 50'A COMPLETE II-SI-027SI-FW-606 PC,PB -PC,VLV C-F C5.21 UT-455 CIRC. 67%, AXIAL 50'L COMPLETE I I-SI-027SI-SW-K3 PC,PB -PBCC,T SER 250.1V UT-60S CIRC. 671o, AXIAL 50% COMPLETE II-SI-027SI-SW-K5 PBCC,T -PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE I I-SI-027SI-SW-K6 PBCC,T -PC,PIPE SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE I I-SI-028SI-FW-608 PCS RED -PC,PIPE C-F C5.21 UT-605 CIRC. 67%. AXIAL 50% COMPLETE II-SI-028SI-FW-609 PP,FHS -PC,PIPE C-F C5. 21 UT-60S CIRC. 677o, AXIAL 50o/o COMPLETE II-SI-028SI-FW-610 PC,PB -PC,VLV C-F C5. 21 UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-SI-028SI-SW-A5 PC,PIPE-PBCC,T C-F C5. 21 UT-60S CIRC. 67%, AXIAL 50ol COMPLETE I I-SI-0285 I-SW-A6 PBCC,T -PC,PIPE C-F C5. 21 UT-605 CIRC. 67% ~ AXIAL 50% COMPLETE I I-SI-0285 I-SW-Aj PC,PIPE-PC,RED C-F C5. 21 UT-60S CIRC. 67/o, AXIAL 50% COMPLETE I I-SI-02851-SW-AB PBCC,T -PC,PIPE C-F C5.21 UT-605 CIRC. 67%. AXIAL 50% COMPLETE I I-SI-028SI-SW-A9 PC,PIPE-PC,RED C-F C5. 21 UT-605 CIRC. 67%, AXIAL 50% COMPLETE I I-SI-029SI-SW-C10 PC,PIPE-PBCC AT SER 250. 1V UT-455 CIRC. 67%, AXIAL 50'A COMPLETE I I-SI-029SI-SW-C11 PBCC,T -PC,RED SER 250. 1V UT-45S CIRC. 67%, AXIAL 50% COMPLETE I I-SI-029SI-SW-C12 PBCC,T -PC,PIPE SER 250. 1V UT-45S CIRC. 67'A, AXIAL 50% COMPLETE
404444 144444444444444444444444444444444444444444444444444444 444444444444444444 444444444444444444444444444444'44444 01/13~ NUTECH/PRIS~
QUERY RESPONSE REPORT PAGE:
HARRIS ISI RELIEF REQUEST R2-003: COMPONENTS REQUESTED FOR RELIEF 4444440444t ~ 444444444444t444444444444444444404t44444444444444444444 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS I I-SI-029SI-SW-C14 PC,PIPE-PBCC,T SER 250. 1V UT-45S CIRC. 67'A, AXIAL 50% COMPLETE I I-SI-029SI-SW-C4 PBCC,T "PC,PIPE SER 250. 1V UT-45S CIRC. 67'A ~ AXIAL 50% COMPLETE II-SI-029SI-SW-C5 PBCC,T -PC,PIPE SER 250. 1V UT-45S CIRC. 67'A, AXIAL 50% COMPLETE I I-SI-029SI-SW-C7 PC,PIPE-PBCC,T SER 250. 1V UT-45S CIRC. 67%, AXIAL 5010 COMPLETE II-SI-029SI-SW-CB PBCC,T -PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE II-SI-02951-SW-C9 PBCC,T -PC,PIPE SER 250. 1V UT-455 CIRC. 67%, AXIAL 50% COMPLETE
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I II I
REQUEST FOR RELIEF NO. R2-004, PRESSURE RETAINING WELDS IN PIPING, CATEGORY C-F: ITEMS C5.11 and C5.21.
IDENTIFICATION OF COMPONENTS:
Pressure retaining circumferential piping welds (less than or equal to 1/2 in. nominal wall thickness), and pressure retaining circumferential piping welds (greater than 1/2 in.
nominal wall thickness) as listed on attachment for this relief request.
ASME SECTION XI CODE REQUIREMENTS:
Examination category C-F, Item C5.11 requires a surface exam-ination on circumferential piping welds with less than or equal to 1/2 in. nominal wall thickness. Item C5.21 requires a surface and volumetric examination on circumferential piping welds with greater than 1/2 in. nominal wall thickness.
'ODE RELIEF,. REQUEST:
~
Relief is requested from performing volumetric (U.T.) and/or surface examinations on the listed welds, as these welds are-inaccessible due to being inside of containment penetrations:
flued heads, valve chambers (Ref. attached design detail sketches).
ALTERNATE EXAMINATION:
Components will be subject to periodic system leakage tests and visual (VT-2) examinations to the maximum extent pos-sible. Containment penetrations are also subject to ILRT/
LLRT (10 CFR 50 appendix J) testing on a periodic basis in accordance with SHNPP Plant Technical Specifications.
CONSTRUCTION CODE EXAMINATIONS:
Volumetric BASIS FOR REQUESTING RELIEF:
Component welds are located inside of containment penetrations (flued heads, valve chambers) and are inaccessible for per-forming code required examinations. System leakage/hydrostatic pressure tests will be performed as required to ensure structural integrity. In addition, ILRT/LLRT (10 CFR 50 Appendix J) testing will be performed as required by SHNPP Technical Specifications.
Page 1 of 2
~1 ll I J
I I,
R2-004 Cont.
'TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF:
The design of containment penetrations (flued heads, valve chambers) will not facilitate accessiblity to listed welds to perform code required examinations. No impact on plant quality, safety or reliability is expected, as the welds will be subject to periodic system leakage/hydrostaticin testing, as well as ILRT/LLRT (10 CFR 50 Appendix J) testing accordance with SHNPP Technical Specifications.
This Request for Relief (R2-004) is applicable to the SHNPP Unit 1 First Ten (10) Year Interval Inservice Inspection Program.
Page 2 of 2
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QUERY RESPONSE REPORT HARRIS - ISI R2-004:
tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt RELIEF REQUEST COMPONENTS REQUESTED FOR RELIEF ttttttttttttttttttttttttttttttttt COMPNOEX COMPDES CATEGO ITEMNO EXSCHO COMMENTS II-AF-OOBAF-M108-PW-1 PP,FHS-INTERNAL C-F C5.11 SUR II-AF-009AF-M109-PW-1 PP,FHS-INTERNAL C-F C5. 11 SUR II-AF-010AF-M110-PW- I PP,FHS-INTERNAL C"F C5.11 SUR II-80-0078D-M53-PW-1 PP,FHS-INTERNAL FSAR 6.6.8D SUR II-80-00880-M52-PW-1 PP, FHS-INTERNAL FSAR 6.6.8D SUR II-BD-0098D-M51-PW-I PP.FHS-INTERNAL .FSAR 6.6.8D SUR II-CS-089CS-M7-PW-1 PP,FHS-INTERNAL FSAR 6.6.80 SUR II-CT-007CT-FW-37 PC,SDFP-PC,RED C-F C5.11 SUR II-CT-007CT-SW-I3 PC,RED -PC,PIPE C-F C5.11 SUR II-CT-007CT-SW-I5 PC,PIPE-PC,PIPE C-F C5. 11 SUR II-CT-OOBCT-FW-52A PC,SDFP-PC,RED C-F C5.11 SUR II-CT-OOBCT-SW-I3 PC,RED -PC,PIPE C-F C5. 11 SUR II-CT-014CT-M24-PW-1 PP,FHS-INTERNAL C-F CS. 11 SUR II-CT-014CT-M24-PW-1 PP,FHS-INTERNAL SER 250.1V VOL II-CT-016CT-M23-PW- I PP,FHS-INTERNAL SER 250.1V VOL II-CT-016CT-M23"PW"1 PP,FHS-INTERNAL C-F C5. 11 SUR II-FMR-01FW-M4-PW-1 PP,FHS-INTERNAL C-F C5.21 SUR II-FMR-01FW-M4-PW-1 PP,FHS-INTERNAL C-F C5.21 VOL II-FMR-01MS-M3-PW-1 PP,FHS-INTERNAL C-F C5.21 SUR II-FMR-01MS'-M3-PW-1 PP,FHS-INTERNAL C-F C5.21 VOL II-FMR-02FW-M5-PW-1 PP,FHS-INTERNAL C-F C5.21 VOL II-FMR-02FW-M5-PW-1 PP,FHS-INTERNAL C-F C5.21 SUR II-FMR-02MS-M2-PW-1 PP,FHS-INTERNAL C-F C5.21 VOL
444444 14444444444444 4 f444 f 444 4 f 444444 ff 4 f 44444444 44444f 4444 f 444 4 t 4 t 44 f 4 f 0 44+ 444444444444444444444444444444444444 4444 0 1/12 NUTECH/PRIS~ PAGE:
QUERY RESPONSE REPORT HARRIS I SI RELIEF REQUEST R2-004: COMPONENTS REQUESTED FOR RELIEF 44 III 4 0444444 il t 4 4 4 4 t 4 4I 4 4 4I 4 4' 444 i il 4I '4 0 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 0 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 0 4 4 4 0 4 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS II-FMR-02MS-M2-PW-1 PP,FHS-INTERNAL C-F C5.21 SUR II-FMR-03FW-M6-PW-1 PP,FHS-INTERNAL C"F C5.21 SUR II-FMR-03FW-M6-PW-1 PP,FHS-INTERNAL C-F C5.21 VOL II-FMR-03MS"M1-PW-1 PP,FHS-INTERNAL C-F C5.21 SUR II-FMR-03MS-M1-PW-1 PP,FHS-INTERNAL C-F C5.21 VOL I I-RH-001SI-FW" 1A PC,SDFP-PC,RED C-F C5.11 SUR II-RH-00 151-SW-K3 PC,RED -PC,PIPE C-F C5.11 SUR I I-RH-002SI-FW-13A PC,PIPE-PC,SDFP C-F C5.11 SUR II-RH-002SI-SW-K3 PC,RED -PC,PIPE C-F C5.11 SUR II"RH-002SI-SW-K5 PC,PIPE-PC,PIPE C-F CS. 11 SUR II-RH-009RH-M16-PW-1 PP,FHS-INTERNAL C-F C5.11 SUR II-RH-009RH-M16-PW-1 PPeFHS INTERNAL SER 250. 1V VOL I I-RH-010RH-M15-PW" 1 PP,FHS-INTERNAL SER 250. 1V VOL I I-RH-010RH-M15-PW-1 PP,FHS-INTERNAL C-F C5.11 SUR I I-SI-01651-M21-PW-1 PP,FHS-INTERNAL SER 250.1V VOL I I-SI "019SI-M17-PW-1 PP,FHS-INTERNAL SER 250.1V VOL I I-SI-025SI-M13-PW-1 PP,FHS-INTERNAL C-F C5.21 VOL I I-SI-0255 I-M13-PW-1 PP,FHS-INTERNAL C-F C5.21 SUR I I-SI-026SI-M14-PW-1 PP,FHS-INTERNAL C-F C5.21 SUR A
I I-S I-0265 I-M14-PW- I PP,FHS-INTERNAL C-F C5.21 VOL I I-SI-027SI "M20-PW-1 PP,FHS-INTERNAL SER 250. 1V VOL I I-SI-028SI-M18-PW-1 PP,FHS-INTERNAL C-F C5.21 VOL I I-SI-028SI-M18-PW-1 PP,FHS-INTERNAL C-F C5.21 SUR
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QUERY RESPONSE REPORT HARRIS - ISI RELIEF REQUEST R2-004: COMPONENTS REQUESTED FOR RELIEF 444444t448444t4444t444f44444f44444t44ttt4irtft4444444444ftt+fkt444444 4444444444444444t444444444444444f44 COMPNOEX COMPDES CATEGO ITEMNO EXSCHD COMMENTS I I-SI-02951-M22-PW-1 PP, FHS-INTERNAL SER 250. 1V VOL
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REQUEST FOR RELIEF NO. R2-005, PRESSURE RETAINING WELDS IN PRESSURE VESSLESg CATEGORY C A~ ITEM(S) Cl 10/ Cl AND PRESSURE'ETAINING NOZZLE WELDS IN VESSELS, 20'l CATEGORY 30 C-B, ITEM(S) C2.21 AND C2.22; AND INTEGRAL ATTACHMENTS FOR VESSELS, PIPING'UMPS~ AND VALVES'ATEGORY C C~ ITEM C3 10 OF COMPONENTS: 'DENTIFICATION See attached computer listing for identification of components and conditions associated with each component (preservice baseline data was utilized for compiling this computer listing).
ASME SECTION XI CODE REQUIREMENTS:
Examination category C-A, Item(s) Cl.10, C1.20, Cl.30 requires volumetric (U.T.) examination. Category C-B, Item C2.21 requires surface and volumetric; and Item C2.22 requires volu-metric (U.T.). Category C-C, Item C3.10 requires a surface
'examination .be performed.
BASIS FOR REQUESTING RELIEF:
'eld configurations (end cap geometry, flanges, nozzles...)
and obstructions (reinforcement plates, welded attachments, permanent hangers, insulation tabs, access ports...) will prevent 100 percent volumetric (U.T.) and/or surface examinations to be performed during inservice inspection activities. In addition, some nozzles on each steam generator (SG-001 SG (A), (B), (C) MSNIR-15) were designed without a nozzle radius section and the volumetric (U.T.) examination cannot be performed. Volumetric (U.T.) and surface examina-tions in limited areas will be accomplished as a best effort attempt to cover as much of the code required area or volume as possible.
During preservice activities, these areas where complete exam-ination of 100 percent of the required area or volume could not be achieved was indicated and noted to the extent of limita-tions or obstructions on the examiners data sheet. These data sheets are available at the SHNPP Site for review.
ALTERNATE EXAMINATION(s):
Volumetric (U.T.) and surface examinations will be performed to the maximum extent possible during inservice inspection activities, as applicable. Components will be tests subject to periodic system leakage/hydrostatic pressure and visual (VT-2) examinations to the maximum extent possible.
Page 1 of 2
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R2-005 Cont.
CONSTRUCTION CODE EXAMINATIONS:
Volumetric Surface TECHNICAL JUSTIFICATION FOR REQUESTING RELIEF:
Component weld configurations and obstructions will prevent 100 percent volumetric (U.T.) and/or surface examinations during inservice inspection activities. The arrangements and details of the piping systems and components were designed and fabricated before the access and examination requirements of the ASME Section XI Code could be applied. Consequently, some examinations, will be limited, or not practical to perform due to geometric configuration or accessibility (Ref.
attached computer listing of components, limitations and predicted percentages of completion (preservice baseline
..data;was .utilized to compile this listing).
This Request for Relief (R2-005) is applicable to the SHNPP Unit 1 First Ten (10) Year Interval Inservice Inspection Program.
Page 2 of 2
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n'EQUEST FOR RELIEF NO. R3-001, COMPONENT STANDARD SUPPORTS (SNUBBERS)g CATAEGORY F-C, ITEM F3.50 FOR CLASS THREE (3)
SYSTEMS.
IDENTIFICATION OF COMPONENTS:
All hydraulic and/or mechanical snubbers listed on attachment for this relief request.
ASME SECTION XI CODE REQUIREMENT:
IWF-2000 REQUIRES VISUAL EXAMINATION IN ACCORDANCE WITH IWF-2500-1. IWF-5000 requires functional testing of snubbers in accordance with IWF-5300 (in course of preparation) and IWF-5400.
CODE RELIEF REQUEST:
Relief is requested from the functional test requirements for snubbers -per article IWF-5000 of the ASME Section XI Code.
Visual examination (VT-4) will be performed in accordance with the ASME Section XI Code, which will also satisfy the visual examination criteria of the SHNPP Technical Specification, as applicable.
ALTERNATE EXAMINATION:
All Shearon Harris component support snubbers will be selected and functionally tested per section 3/4.7.8 of the Shearon Harris Technical Specifications.
BASIS FOR REQUESTING RELIEF:
The SHNPP Technical Specifications and the ASME Section XI Code are similiar in their intent to functionally test snub-bers. The SHNPP Technical Specifications are, however, more.
restrictive in the selection, as well as the method of testing snubbers for functional adequacy.
CONSTRUCTION CODE EXAMINATIONSn Not applicable TECHNICAL JUSTIFICATION FOR REQUEST RELIEF:
The Nuclear Regulatory Commission has approved the utilization of SHNPP Technical Specification for functionally testing snubbers. The utilization of the ASME Section XI Code, to functionally test snubbers, would be less restrictive than performing testing in accordance with SHNPP Technical Specifications.
Page 1 of 2
R3-001 Cont.
No impact on plant quality, safety, or reliability is expected as the snubbers will be subject to the functional test requirements of the SHNPP Technical Specifications.
This Request for Relief (R3-001) is applicable to the SHNPP Unit 1 First Ten (10) Year Interval Inservice Inspection Program.
Page 2 of 2
R3&01 ATTCHMEHT CATEGORY FW, ITEM F3 50 FOR CLASS THREE (3) SYSTEMS AF-H-00001 CC-H-00391 CC-H-01487 CC-H-02162 PM-H-00232 AF-H"00013 CC-H-00401 CC-H-01489 CC-8-02164 AF-H-00043 CC-H-00417 CC-H-01490 CC-H-02167 RC-H-00279 AF-H-00060 CC-H-00420 CC-H-01491 CC-H-02168 RC-H-00280 AF-H-00167 CC-H-00421 CC-H-01514 CC-H-02171 RC"H-00407 AF-H-00170 CC-H-00427 CC-H-01519 CCW-02178 RC-H-00670 AF-H-00189 CC-H-00457 CC-H"01584 AF-H-00197 CC-H-00459 CC-H-01585 CH-H-00064 SF-H-00470 AF-H-00213 CC-H-00461 CC-H-01587 CH-8-00065 SF-H-00891 AF-H-00232 CC-H-00463 CC-H-01612 CH-H-01739 SF-H-00911 AF-H-00256 CC-H-00465 CC-H-01651 SF-H-00918 AF-H-00274 CC-H-00466 CC-H-01652 CS-H-00490 SF-H-01305 AF-H-00279 CC-H-00476 CC-H"01668 CS-8-00577 AF-H"00398 CC-H-00496 CC-H-01672 CS-H-00583 SW-H-00611 AF-H-00415 -,'CC-H-00501 CC-H"01673 CS"H-00591 SW-H-00629 CC-H-00503 CC"H-01680 CS"H-01309 SW-H-01264 BD-H-00104 CC-H-00566 CC-H-01682 CS-H-01311 SW-H-01293 BD-H-00169 CC-H-00570 CC-H-01683 CS-H-01830 'W-H-01467 BD-H-00196 CC-H-00681 CC-H-01684 CS-H-01960 SW-H-01491 BD-H-00209 CC-H-00692 CC-H-01687 CS-H-02657 SW-H-01824 BD-H"00223 CC"H-00715 CC-H-01733 CS-H-03010 SW-H-01831 BD-H-00237 CC-H-00779 CC-H-01770 CS-H-03113 SW-H-02352 BD-H"00517 CC"H-00882 . CC-H-01780 CS-H"03137 SW-H-02355 BD-H-00518 CC-H.-00910 CC"H-01787 CS"H-03140 SW-H-02597 BD-H-00525 CC"H-00916 CC-H-01788 CS"H"03349 SW-H-02643 BD-H-00527 CC-H-00918 CC-H-01790 SW-H-02800 BD-H"00529 CC-H-00919 CC-H-01838 MS "H"00167 CC-H-00950 CC-H-01912 MS"H-00170 WG-H-01713 BR-H-01564 CC-H-00990 CC"H"01913 MS-H-00171 BR-H-01691 CC-H-01056 CC-H-01914 MS-H-00173 BR-H"01843 CC-H-01440 CC-H-01915 MS-H"00176 BR-H"01844 CC-H-01442 CC-H-01916 MS-H-00185 BR-H"02272 CC-H-01443 CC-H"01925 MS"H-00187 BR-H-02621 CC-H-01444 CC-H-01946 MS-H-00193 CC-H-01446 CC"H"01950 MS-H"00197 CC-H-00005 CC-H-01448 CC"H-01951 MS-H-00198 CC-H-00010 CC-H-01457 CC-H-01955 MS-H-00200 CC-H-00067 CC-H-01459 CC-H"01960 MS-8-00202 CC-H-00074 CC-H-01461 CC-H-02055 MS-H-00410 CC-H-00078 CC"H-01468 CC-H-02056 MS-H-00415 CC-H-00080 CC-H-01471 CC-H-02071 MS-H-00767 CC-H-00082 CC-H-01472 CC"H"02113 MS-H-00769 CC-H-00085 CC-H-01475 CC-H-02148 MS-H-01389 CC-H-00088 CC-H-01476 CC"H-02149 MS-H"01390 CC-H-00093 CC-H-01478 CC-H-02151 MS-H-01391 CC-H-00353 CC-H-01479 CC-H"02153 MS-H-01392 CC-H"00356 CC-H-01480 CC-H-02155 MS"H-01403 CC-H-00357 CC-H-01482 CC-H-02157 MS-H"01406 CC-H-00376 CC-H-01486 CC-H"02160 MEM/R3-001ATT/1/OS2
c 1 SELECTION RECORDS EXAM S COMPNOEX EXREQ CATEGORY EXREQ IT EMNO EXAM EXREQ EXSCHD OUTAGE SELECT REQUEST EXAM EXEMPT EXOATE CREDIT NDEPROC CALSTD COMP SYSTEM COMPOES ACCESS 1 ACCESS 2 ACCESS 3 COMP
- ACCESS 4 ACCESS 5 ACCESS 6 TRANSIN TENRMKS COMP NEWCOMNO ORDER COMPDIA NOMTHCK REFDWG 9 COMP
- OLDCOMNO 10 PICK EXREQ EQS 835-01 11 5770 RECORDS HAVE BEEN SELECTED 12 13 14 SELECTED DATA RECORD FORMAT 15 18 17 ELEMENT LENGTH STARTING COL.
18 19 COMPNOEX 24 1 20 EXREQ 6 25 21 CATEGORY 31 22 EXREQ 37 23 ITEMNO 43 24 EXREQ 49 25 EXSCHD 6 55 28 OUTAGE 6 61 27 SELECT 6 67 28 REQUEST 6 73 29 EXEMPT 79 30 EXDATE 85 31 CREDIT 93 32 NDEPROC 94 33 CALSTD 6 100 34 SYSTEM 3 106 35 COMPDES 15 109 38 ACCESS 2 124 37 ACCESS 2 126 38 ACCESS 3 128 39 ACCESS 4 130 40 ACCESS 5 132 41 ACCESS 6 2 134 42 TRANSIN 1 136 43 TENRMKS 6 137 44 NEWCOMNO 24 143 45 ORDER 4 167 ae COMPDI A 5 171 47 NOMTHCK 5 176 48 REFDWG 16 181 49 OLDCOMNO 24 197 50 51 52 53 54 55 58 57 58 59 eo FORM 0113 {02I83)
tttt t t fthm t t t tttft t t t tt t fthm f t t tt ffOtter tt tt t**tt t t*tt tt t t t t* fthm tent t t t f t t t tt t t t t t t t t t t*tt t t tt t f tt ft tt t t t tt tt tt tt t t t t t t NUTECH CAROLINA POWER 8 LIGHT COMPANY PRI SIN f SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING t t t t t t t t tr f t tt tt t 't COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 1 ASME SECTION. XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 t t t*tft tft t t ft fft f f tt f tftt t tf t t tt ft t t f ft tt ft t it t t t t ft t t t t ftft t t ft t tt t*tt t t t t t t t t f f tt t f t t*ft tt t t tt t ft tftt t t f t t t t t t t t 9
10 CATEGORY B-A PRESSURE RETAINING WELOS IN REACTOR VESSEL 11 ITEM NO. B1. 11 RV CIRCUMFERENTIAL SHELL WELDS 12 13 t t t ft t t 't t *t t t t t t ft t **t t t f t tt t *t t t tt t t t t tt t tt t t t t t t tt t t tt t t t t t t
- t t t t t t t t t tt tt t t t t t t tt tt tt ttt tt t tt t f tt t tt tt t t tt tt 't 't t t t t 14 15 DONE 16 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REOST TIONS NOTES 19 $$$$$$$$$$$$~$$~$$$$$ $$$ $$$ ~$ $~$ $ $$$ $$$$$$ $ $$$$$ $~$$ ~$$ $ $ $ $ '$ $ $ $ $ $ $ $ ~ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RV-001 22 23 CSW-RV-02 C SHELL UT-RVS 1-3-06 167.0 8.000 NO R 1-004 24 CSW-RV-03 ' 1-3-06 157.0 8.000 25 26 tt t t t tt t t tt ttfft tftt t f tt ff ttf tft t t t t t tt f tfUT-RVS SHELL NO t t f 4 t f ft t tfft f f fthm f t t t t tft tt t t t t t t t t t t t tf ftt t t t t tt t t tt t t tt ft t t f tt t t tf tt t t t t 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 5'1 52 53 54 55 58 57 58 59 60 FORM 0113 102I83)
ff t fff f f f 'tf f f ff tf tft tfsf ft f fff tf f tt t t tat t tt t t t t t t t t t' t tf f f ft f ff t ft t f f tt t t t t* t ff t f ft t fff f t fffffft f f f f f tf f t fffft fff t fff NUTECH CAROLINA POWER 8E LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1
fff f 't tf f ff f fff 't ffff COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 2 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12
'f f f tff tf'f ffff ff f tat ft f f tffffff t ff f f tfff ff tf ft t ft tff at tff f t t ft t tffft f t tft fffft t*tfff f f f fft t f t tffff f fff ff 'at t f f t t f fft t 9
10 CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL 11 ITEM NO. 81.12 RV LONGITUDINAL SHELL WELOS 12 13 tf tffff f f f !t t f ft fffffff f f tff t ff f ff f f f t ffffff ff t f fftf fff f t f f f ff f t t ft f ftft ff t ftff f t t f 'f tt ff t f ffftf ffff f 't ff ft t f ff ftf 'f ft
!IE fE EEE 14 15 DONE 16 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT
-- (IN) (IN) ACCESS SELECT- IND REOST TIONS NOTES 19 stats s sssss sss stats s ----ss s == ==== ss ss saEEas sssasaaa EEassas aaaaaa s cssaas 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 LSW-RV-05 L SHELL UT-RVS 1-3-06 155.5 9.500 NO R 1-004 24 25 LSW-RV-06 L SHELL UT-RVS 1-3-06 155.5 9.500 NO R 1-004 26 27 LSW-RV-07 L SHELL UT-RVS 1-3-06 157.0 8.000 NO 28 29 LSW-RV-08 L SHELL UT-RVS 1-3-06 1 57; 0 8 . 000 NO 30 31 LSW-RV-09 L SHELL UT-RVS 1-3-06 157.0 8.000 32 LSW-RV-10 UT-RVS 1-3-06 57 . 0 8 . 000 ff ffff tff at ff tffitf t f f t at tfLfSHELL f ff f tff f tff f tff f f f tfff t tff t tffffff at ff t ft f ftfffff f *tf f f at I f tf f f ffat f ffff 'tf t ff*ftf'f ff fff f 't f 33 1 NO 34 35 36 37 38 39 40 41 42 43
'44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 {02I83)
f tff at f taft t tftff tfat tat tf fff tff f fffff f t ttttff ttff tf f f ttttftftftfsf f tff f tffff tf f aft f ttt tfttftftff tfff tat f f tt t NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 t
PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN : 835-01 PAGE 3 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 sf f sf ff t f *tf *tf f'fft fff f t f ft t t f t t sf f tfff ft ft f tt t fft sf t ft tt ff t t tat t t ft f f ft ft fft f 1 t ff tf t f' ff t f f t*tff t t ft fff ff f t f f t st f t f 9
10 CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL 11 ITEM NO. 81.218 RV CIRCUMFERENTIAL BOTTOM HEAD WELDS f sf ff f ff ft ft f f ft at f sf tftf sf f tat ff t t f f f f f tf t f f st f sf t ff f f f ft fff tf t t f fff f f fff t f t t f f f t f f fff ft f ffffff *tfffft t t f f f t ft ff 'f t ff 12 13 14 15 DONE 18 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 aasssasssssssassssssssss ssaasssssssassa asssss s ssa = = stats fasts ss ss assasasa asssas ass asaaas ssaast aasssr 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: II "RV-001 22 23 CHW-RV-17 C HEAD UT-RVS 1-3-06 125.8 5.375 NO R1-004 24 STHW-RV-04 UT-RVS 1-3-06 157.0 5.375 1-004 f ff tttttff tff f f tat f ttftfsf tat f f tf f f ff tttttt tat tfff tttftttttff tff ttff f ttttfff tf tat f fl*tttftftttttff tff tf ff tftff sf tf f tf 25 STHW NO R 25 27 28 29 30 31 32 33 34 35 35 37 38 39 40 41 42 43 44 45 48 47 48 49 50 5'1 52 53 54 55 58 57 58 59 80 FORM 0113 {02I83)
tt'fft tt t fff tt tt fthm f f tt f t f fthm t tt t ff tt f t f ft tt t ft tt t t t tt t f $ tt f t t fthm tt t ft f f ff tft f f tt t ft f t t t f f ttfff t tff ffff tf f f ttfft f f tt tt NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1
tttfttttfttttft COMPONENT LISTING ANO ISI 10 YEAR PLAN: 83S-01 PAGE 4 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12
'f fff t'f t f t t't f tff 'f ttff t tff tt tf'ff f f't tt t f f t ffft t*tf ff f f f *ft f *tt t t f t t tt t f tt t f f f t t t f f f f t t ff t ff f tt t t t tt t t f t t DATE t t fft f *ft tf t t f f f 9
10 CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL 11 ITEM NO. B1.228 RV MERIDIONAL BOTTOM HEAD WELOS 12 13 ttftftftftftftftttttttftfttftttttffff f tftftftttff tff fftttfff f f tftf f fff tttt ttfttfttttttff tttfttttttftttfffff 14 15 DONE 18 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REIQST TIONS NOTES 19 $ $ $ $ $ $ $ ~ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $$$$$ ~$$$$$ ~$$$ ~$$$~$ $ $ $$$ $$ $$ $ $$$ ~$ $ ~$$~ ~$$~$$$$ $$~$$$ $$$ $ $ $ $ $ $ $ '$$ $ $ $ $ $ ~ $ $ ~
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RV-001 22 23 MHW-RV-11 M HEAD UT-RVS 1-3"06 157.0 5.375 NO R1-004 24 25 MHW-RV-12 M HEAD UT-RVS 1-3-06 157.0 5.375 NO R 1-004 26 27 MHW-RV-13 M HEAD UT-RVS 1-3-06 157.0 5.375 NO R 1-004 28 29 MHW-RV-14 M HEAD UT-RVS 1-3-06 157.0 5.375 NO R 1-004 30 31 MHW-RV-15 M HEAD UT-RVS 1-3-06 157.0 5.375 NO R 1-004 32 33 MHW-RV-16 UT-RVS 1-3-06 157.0 5.375 1-004 34 tttt'fttt'f'ftt'ftttttttft'fttttttttf M HEAD ff tf ttf 'f frff tftffrftttff tf'tftftff tttfttfttff tf tftftttfttff tf tft tfttfttfttftttttf*ff t'ttt NO R 35 36 37 38 39 40 41 42 43 44 45 48 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
fthm f ff tff f fr ttttf*ftff sf tftff ff f tftttt f fr ttfttfff f tttfffff tff sf f f sf fttttttttt tf t f sf f tttffff ft f tt sf fff ttttfffthm tst ttffff 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM
- t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT ff f sf ttl tf 3
4 PLANNING 1
t f tstt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 8 ASME SECTION 'XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 DATE 88/01/12 7
ttft*fttttftttfttttf*stftttfttttttttttttttttttttttttttttttttfftttff ttttttttf THE SUMMER 1983 ADDENDA; INTERVAL 01 ONLY tfttttttttt 9
10 CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL 11 ITEM NO. B1.30F RV SHELL-TO-FLANGE WELD PARTIAL EXAM FROM FLANGE FACE ff t tftf t t st f f tfst tft tft tt t t ff t sf t tff t t tt f t t st t t tttt tt ft tft t t sf st f t tt tt t t t f t f t fr sf t t fr t t t t ft fr sf t tat ft st tt t sf fft fr st t t 12 13 14 15 DONE 18 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssasssssrssrsssss r sar s sssssss = = s ass sas astra fasts assssass ararat sas starts sasss s 20 2I SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 FTSW"RV-01FA FTSW UT"RVS 1-1-01 155.5 9.500 24 25 FTSW-RV-01FB FTSW UT-RVS 1-2-03 155.5 9.500 26 UT-RVS 1-3-06 9.500 27 28 FTSW-RV-01FC IIIIIIfttfIt'fllIf FTSW ftttf t*ftttftttf frffrst*fr stfsf t*ttttt*ttfstaff f tffffttfISS.S tttttttftf ttftf tttttftf tat tf tfNOtfIIIffr sf*fr tsf tf tf'ttt 29 30 31 32 33 34 35 38 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 80 FORM 0113 I02I83)
14 ff tftttftf f fffMrt*ff ttftttfttttftttttfttttt tttt tf tfttttttttft f tf*ftttt*ftt*ftf tErtttttftttfttt tt ttfttttff tfttttt f NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t PLANNING t t t t t f tt t t ft ttt
'El llr IR1E 5 COMPONENT LISTING ANO ISI 10 YEAR PLAN: 83S-01 PAGE 13 6 ASME SECTION. XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 7
f f f tftttftttff ftff tfffff tttftfttftttttfttttftt**tf*ttttttf tf ttftt tttftttfttt tt'ttttftftftfttMrtftff ttff tttf'tff ttftttft 9
10 CATEGORY 8-8 PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV 11 ITEM NO. 82.21 PRZ CIRCUMFERENTIAL HEAD WELOS 12 13 f f *fff t tff t ff tft f tff f ff fft t't f tffft t t tff t fft t tt t t ft t ft t t t t'f ft ft t't t t t t t f t t t t t t *ft t t t tt t t tf f t t t*ft t t t t t t t t t t t f t t tt f f tt t Er 14 15 DONE 16 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT EXAM ECHE- O~UT PRIOR DIAM THOR TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE'ULED INT INT ( IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 SSSSCSEECS ~ $ $ ~ $ $ ~ $ $ $ ~ SSSC $$$$$$$ '
$$$$$$ $$$ ~ $ $ $ $ ~ SCSS $$$ $$$ ~C 'CCCCC ~ $ $ ~ $ $ $ $ $$$~S $$$ CSSCSS CCEECSEE 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 APPLICABLE f Crt t t t ft fft tff t t ffft t fttff f tf ft t f f tf ft t t t f t tt t t t t tt tErf f tff tff tt ff t ft t rlrt tt tt t t t t t t t t t tff f f 23 NOT COMPONENTS 24 t tf tt f ffffffNO f t'Erf t Mr Mrt Mr 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 {02I83)
I
18 I 4ttf f tf444 4 4 444 44444tt44t tf4 ttttttt tttt tttttttttttttfttf4 4ttttf tttftf*44'44 4 ttftt*ftt*f4 4 4 tf444tf4 4 fttttsf tttft 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING f4 4tf 4444444444*4 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 17 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 7
6 44 tfsf 44 44 4 4 4 4 4 tf4 444 44 t st f f i 44 st 4 4 4 4 4 444 4 4 t*4 4 4 tt t tftt t 44444441 t*f tt tat tt t t t t fthm 44 4 4 4 4 4 DATE 444 44 44 4 4 tf f tt 4 4 t 4 hatt t 4
9 10 CATEGORY B-B PRESSURE RETAINING WELOS IN VESSELS OTHER THAN THE RV Il ITEM NO. 82.40 SG PRIMARY SIDE TUBESHEET-TO-HEAD WELDS 12 13 4 4444 4 4 t tt 4 tat 4 4 4 44 4 4 444 4 4 4 4 4 4 4 t t t 4 4 4 4 4 4 4 4 4 4 tt 4 tt t 4 4 4 t 4 t 4 4 4 4 4 t 4t t 4 4 4 4 4 t 4 tt 4 t 4 4 4 4 4 t 4 4 4 4 4 4 4 at 4 4 4 4 t f4 4 4 4 4 4 st 4 4 4 4 t 4 4 4 t 4 4 4 14 15 DONE 16 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT ( IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 asssssssssssssasssssassa assasssssssssas assess asassssssasasasa sess asses saasessa assess sss assess assess assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II"SG"001 22 23 SGA-TSTHW-06 TSTHW UT-00 1-1-01 140.0 5.000 NO R1-004 24 UT-455 1-1-01 R 1-004 25 UT"60S 1-1 "01 R 1-004 26 27 SGB-TSTHW-06 TSTHW UT-00 1-2-03 140. 0 5 . 000 NO R 1-004 28 UT-455 1-2-03 R 1-004 29 UT-60S 1-2-03 R 1-004 30 31 SGC-TSTHW-06 TSTHW UT-00 1-3-06 140.0 5.000 NO R1-004 32 UT-45S 1-3-06 R 1-004 UT-605 1-3-06 R1-004 33 34 4 t'4ttttttttttttttttttfttttttttttt'tfttf44444tf tttttttttttfttttfttttfttttttfttttftet 4tf'4 tttt'4ttttttt 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 102/83)
20 1 1111 1111 1 1 1 1 1 1 1 1 11 111 11 111 11 111 111 11 t 1 1 1 1 1 t 1 1 1 t
- t 1 1 1 1 1 1 1 1 tt t t t t 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 tt 1 t t t 1 t 1 1 t 1' 1 t 1 1 t t 1 1 1 1 1 1 1 1 tt t
- 1 1 1 1 1 1 1 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PR IS IM SHEARON HARRIS NUCLEAR POWER PLANT UNIT 3
4 PLANNING ttttttttttttttttt COMPONENT LISTING ANO ISI 10 YEAR PLAN: 83S-01 PAGE 19 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 1 1 1 1'1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 t 1 1 1 11 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 t t t t*tt 1 1 1 1 1 1 1 1 1 1 1t 1 1 t t 1 1 1 1 1 t 1 1 t 1 1 1 1 t 1 1 1 1 1 1 ttt 1 11 1 1 11 t 11 1 1 1 t t 1 t 1 t 1 1 1 1 t 1 1*
1 9
10 CATEGORY B-B PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV 11 ITEM NO. B2.52 HX PRIMARY MERIDIONAL HEAD WELD 12 13 1 tt 1 1 1 1 1 1 1 t t 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 t 1 1 1 1 1 t t 1 1 1 1 1
- 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 t 1 1 1 1 t t 1 1 1 t 1 1 1 t 1 t 1 1 1 t tt 1 1 1 1 1 1 1 1' 1111111 t1111 14 15 DONE 18 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 18 19 tttt NUMBER Stt ~ tttSt tS ttttm Stt ttttt tttttt tttttt t Sttttt t tt ttttt
~1 ~ ~ ~ tt ttt ttt tt tt ~ ~ 1~ 11tt ttttRS 20 21 SYSTEM : REF'EFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT APPLICABLE NO COMPONENTS 24 11111111111111t1tttttt1t11ttttttttttttttttttt111tttttttttttttttt1t11*t1t1tttttttttttttttttttttttttttt 25 28 27 28 29 30 31 32 33 34 35 38 37 38 39 40 41 42 43 44 45 48 47 48 49 50 51 52 53 54 55 se 57 58 59 80 FOAM 0113 (02I83) 1 4
21 1 t t t t 't tttt tt ttt t ttt t t t t t t t t ttt t t t t t t t tt t t t t t t tt t t t f t t tt t t t t t t t t t t t tt t tt tt t fft t t t t t t t tt t t t t t t t t tt t t t tt t t tt t t tt ttt t t t t t t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM t 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING t t t t *tt t t tt *tt t t t t t 5 COMPONENT LISTING ANO ISI 10 YEAR PLAN: 835-01 PAGE 20 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 7
8 tat 1 t st t t at t t at at tt t tt t t at t t st t tt tt t tt t t tat t t at t t t t t tt st at tt t t t t tt t t t tat t t at t t at atty t t tt ttt 4 t t t t t at tt t t t t t 9
10 CATEGORY B-B PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV 11 ITEM NO. B2.60 HX PRIMARY. SIDE TUBESHEET-TO-HEAD SHELL WELD 12 13 t st st st at st t t st atty t st t t t st st st st tat t t tv st t st t at t st t*ttt t t t t t tat at t t t t t t t t t t t t' t st st t t t t st t t st st st t t st st tt t t t st st t t t t 14 15 DONE 18 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT INO REOST TIONS NOTES 19 srrrrsrssasrsssasssasrss ssasas raaassss ararat sassssssrassssas arras arras rssssras ssassa ass as asa aa ararat 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT 24 APPLICABLE tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt*tttttttttttttttttttttt'ttt NO COMPONENTS 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
22 t t tt l ttt l t tt t
- t tt t t t *t t t t t lt l t lt t t l t t l l l l. *t t l l l t l t l t l l t l t l t l tt t t t l t t t t t t t lll t tt l l t l t ll 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT
't 'l t t t l t t t t t ll l' l
- t
-7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 8 t t t tt t t't t t l 't l t tt 't t t t t t l' t t t t t 'l t ll 'l l tt t l ltt t t t t t t t lt l t t 't 'l *l l l t l t t t t tt 'l t t l 'l t l 't t t 'l t l 't t t ll t l t l tt l t t t tt l tt 'l t t t t 'l t l l t l 9
10 CATEGORY B-B PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV 11 ITEM NO. B2.70 HX PRIMARY SIDE LONGITUDINAL SHELL WELD 12 13 lt tt 'l t tt t l t 't t t t t t t t t t t t t t t t t t t l l t' l t t tt lt t t tt l t lt l t t l tt t t tt t t l t l l l t t tt t t t l l t t t l t t l ll t t l t t t t t ll t t t lll t t t lt t l t l t t l t l t t 14 15 DONE 18 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE OULEO INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 ssssassaasasassssaasssas a sssssss ss s a ssassssssssss stats asass sssssasa aassss sss ssssas asa ss assaas 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 APPLICABLE 23 NOT 24 NO COMPONENTS t t t t l t t l t l t tt lt ll t t l tt l tt t t t t t l t t tt t t t t t t l' t t tt t l t l t t l' l tt l l' llt t l t *t t l' t l t t t t t t lt tt t t t t t tt t t t t t t tt llt t l t lt t t lt l 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60
23 atttttttfttf*ftftfat tat tttt fat t f*ff f taft tf tftttttttttttftttttftttftttttttf t f fat f fat tft aft ttt f att aft ttttfttttttft ft 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3
4 PLANNING f f atttttttf f'tftfttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 22 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 tf t t t 'f t tt t ft ttt
- tft ff f ftt t t t tt t tt t t tt ft t t ft t tt t t t t t t t t t t t t t ft t t t t t t tt t tfft tt t t t t ft t t t t tt ftt f t t ft t t tft t 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE Ml fttft ftf t t t 9
10 CATEGORY B-B PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV 11 ITEM NO. 82.80 HX PRIMARY SIDE TUBESHEET-TO-SHELL WELD 12 13 ttft taft at'ttt'f ttttff ttfttatttttttftattttf tttfttfaft ttt*tft't f tttt*ftf*tff ttfttttttttttttftttt ttttlM'fttff tftttt'tt taft tf t 14
'15 DONE 16 OUTAGE THIS DONE VESS FLNG BASIS PS I 17 COMPONENT COMPONENT EXAM ECHE- CU~TPRICR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULEO INT INT (IN) ----=
(IN) ACCESS SELECT IND REQST TIONS NOTES 19 a a a a a a a at ~ aa aaaaaaaaaaa aa aaaaa aaaaEEaa--------- -------- aaa aaa aa a a a aa a 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 tfttfAPPLICABLE 23 NOT 24 f ttftaft tf tat ttRIftftltttfatf f ttttttttfatE tttlfstaff Erf f ttttttttftfttttat attf ttfIIItttftttft tate f f tttff at tt'ttttff tttt NO COMPONENTS 25 26 27 28 29 30 31 32 33 34 35 38 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I831
25 tttttttttftttfet et t tet t tet tf tttf 11111 tttttttt ttttfttttftttftttf1t tttttftttfetf tttttf 1 1 1 1 1 et ttt1 tf ttfttttsf tfet tet tttt NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 1 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 24 ASME SECTION XI ~ 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t 1 1 't 1 1 1 1 1 1 1 1 t 1 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE tt1 1 t1 1 t t1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1' '1 11 1 1 1 1 11 tt1 9
10 CATEGORY 8-DB FULL PENETRATION WELDS OF NOZZLES IN VESSELS - PROGRAM 8 11 ITEM NO. 83. 9S RV NOZZLE-TO-VESSEL WELDS, EXAM FROM RV SHELL - PROGRAM B 12 13
- 1' tt1111 '1 1 '1 1 t 1 1 1 1 1 t 1 1 f1 t t f 1 t t 1 t 1 1 1 t 1 1 1' '1 1 '1 1 t1 t1 t1t '1 1 1 1 1' f1 t 1 1 t 1 1 1 1 1 1 1 1 1 1 t 1 1 1 t 1 1 1 1 1 1 1 1 1 I1 1' 1 t t f t f 1 1 1 1 1 1 1 t f1 1 1 1 1 1 1 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 aasssasasassasssss tease aaaaaasaasessss sestet sesassasessssess asses asses seeeesss assess ass assess assess s ease 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RV-001 22 23 RVNOZAI-N-01 NOZZLE UT-RVS 1"3-06 32.68 9.500 NO R1-006 24 25 RVNOZAO-N-06 NOZZLE UT-RVS '-1-01 34.43 9.500 NO R1-006 26 27 RVNOZB I-N-03 NOZZLE UT-RVS 1-3-06 32.68 9.500 NO 28 29 RVNOZBO-N-02 NOZZLE UT-RVS 1-1-01 34.43 9.500 NO R 1-006 30 31 RVNOZC I-N-05 NOZZLE UT-RVS 1-3-06 32.68 9.500 NO 32 33 RVNOZCO-N-04 NOZZLE UT-RVS 1-1-01 34.43 9.500 NO R 1-006 34 ft t t t f f t t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1*1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1*1 1 1 1 1 11 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 st 1 1 1 1 1 1 1 1' 1**11 1 t 1 1 1 1 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FOAM 0113 (02I83)
44 t 4 4 t t f tent t tt tf 4 tt 4 4 4 4 t t t 4 4 4 tt 4 4 f 4 t t f 4 ft If ft f ft t 4 t t 4 ft f t tt t 4 t*tf t t f fft t ft f 4 ft ff t f t t t t ft t t t tf 4 4 t tt f ft 4 ft 4 f' t f t NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 4 SHEARON HARRIS NUCLEAR POWER PLANT " UNIT PLANNING ttttttttff tttf 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 25 6 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING t REVISION NRC1 7
8 tfttftttfttfttftftttttfttttttttttttttttttfttttttttftttftttftt*tfttff off f tttt*fttf f tttttttttttt ttf DATE THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 4 4 44 ttttf88/01/12 ttftftttttt 9
10 CATEGORY B-OB FULL PENETRATION WELDS OF NOZZLES IN VESSELS - PROGRAM B 11 ITEM NO. B3. 10B RV NZLE INSIDE RADIUS SECTION, EXAM FROM NZLE BORE PROGRAM B 12 13 tf 4 fthm tf t**f 4 44 4 4 t 4 f *tt4 4 tt tttt 4 4 4 t f 4 4 4 4 t tff f 4 f t 4 t t 4 t t f 4 tt t 4 t 4 4 t t t ~ t t t t t t 4 t t t 4 f 4 ' tt tt 4 4 t 4 4 4 t 4 4 t f 4 ff f' 444 tf 4 4 ft f 4 4 tf 'f 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 4444444 4444444 44444444 $ 4444444 ~ 44 44 4' $ 4 4444 4 $ 4444 4 44 ~ 44 444444 ~ 444444 44 ~ 444 $ $ ~ ~ $ $ $ 4 ~ 444444 $ $ $ $ 4 ~
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 RVNOZAI-N-01 NOZZLE UT-RVN 1-3-06 32.68 9.500 NO 24 25 RVNOZAO-N-06 NOZZLE UT-RVN 1-1-01 34.43 9.500 NO 26 27 RVNOZBI-N-03 NOZZLE UT-RVN 1-3-06 32.68 9.500 NO 28 29 RVNOZBO"N-02 NOZZLE UT-RVN 1-1-01 34.43 9.500 NO 30 31 RVNOZCI-N-05 NOZZLE UT-RVN 1-3-06 32.68 9.500 NO 32 RVNOZCO-N-04 UT-RVN 1-1-01 34.43 9.500 tft f4 ttt t 4 t tttt t t t t t ft 4 ft NOZZLE 33 NO 34 'f t t tt tt t ttfttt 4 t tt ft f t tt t t f ttt tft t 4 tf 4 t ft t 4 4 t f tt 4 tt t ft t' t tt f f ~ fr t t 4 ft *tt 4 t' t f t t ftt tt t 'f t t t tt ff 35 36 37 38 39 40 41 42 43 45 48 47 48 49 50 51 52 53 54
.55 56 57 58 59 60 FOAM 0113 (02I83)
ff ttt tff tfffff t f tff ff f tfft f t ff f f tf f ft f f t tt t t t f f ff t ffff f tft fft tf f t f f ff f f tf f tff f t f f t tf ft t tf ft f t t f f f ftt ff f f t tttfft 27 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 4 f PLANNING 1
t fft t 'f t f tt 'f ff f fthm f t COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 26 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 t t ft t 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tt t tt t f ttt t t f ft t t t t t tt tt tt t f ftt ft t f tt t tft f fftft t f tfff t't*ft t t ft t tft*ff tt t tt f f fthm t t tftt t tt f t f' tt tfDATE ttt tttt t t ft 9
10 CATEGORY B-DB FULL PENETRATION WELDS OF NOZZLES IN VESSELS - PROGRAM 8 11 ITEM NO. 83. 10S RV NZLE INSIDE RADIUS SECTION, EXAM FROM RV SHELL, PROGRAM 8 12 13 ttttt*tfttttttftttfttttttff f tftttf 'tf f tf f ttf'tfttt f ftfttttttff fthm f ttt f t tttt tttttttttff tftftttfttttftf f f f t f ttft*f*fttttt 14 15 DONE 15 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (1N) ACCESS SELECT IND REQST TIONS NOTES 19 $$~$$$~$$$$~$$$ $ $ $ $$$~$$$$$$$$$$ $ '$$ $ $ $ $ $ $ $ $ $ '$ ~ $ $ $ $ $ $ $ $$$$ $ ' $$$$$ $$$$$~ $$$ ~$$$ $ $$ $ $ '$$ $
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUI!SER : II-RV-001 22 23 RVNOZAI-N-01 NOZZLE UT-RVS 1-3-06 32.68 9.500 NO 24 fthm 25 RVNOZAO-N-06 NOZZLE UT-RVS 1-1-01 34.43 9.500 NO 28 27 RVNOZBI-N-03 NOZZLE UT-RVS 1-3-06 32.68 9.500 NO 28 29 RVNOZBO-N-02 NOZZLE UT-RVS 1-1-01 34.43 9.500 NO 30 31 RVNOZCI-N-05 NOZZLE UT-RVS 1-3-06 32.68 9.500 32 RVS 1-1-01 33 RVNOZCO-N-04 34 ttftttt'ttft'ftttft'f*ttfttt*tf tt'f t*tfttttt UT"tttf NOZZLE tftttfttfttt tff'fff34.43 tf'ft*t9.500 ft ttttttff ttfttt f ttt ff f t ttfttt f ttfff ttftftf ttt NO 35 38 37 38 39 40 41 42 43 44 45 45 47 48 49 50 51 52 53 54 55 55 57 58 59 50 FORM 0113 102I83)
28 ttttttttttttttttttttttttttttttttttttttttttttf.tttttttttttttttttttttttttttttttttt*ttttttttttt NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING t t
- REVISION NRC1 THE'UMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttIttttt*tttttt*ttttttttttttttttttttttttttt 9
10 CATEGORY B-DB FULL PENETRATION WELDS OF NOZZLES IN VESSELS - PROGRAM B 11 ITEM NO. B3. 110 PRZ NOZZLE-TO-VESSEL WELDS - PROGRAM 8 12 13 tt t t t t t tt t tt 't t t t t tt t t t t t t t tt t t t t tt t t t t t t t t t t t t t tt t t ttt tt t t t t t tt tt t tt t t t t t t t t t t t t t tt t tt t tt ttt t tt tt t t t t t tt t t t t t t t t t t tt
'l4 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM IS NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ $ $ ~ &$ $ ~ $ $ $ $ $ ~ $ $ $ ~ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ '
$$$ $$$ $$ $ ~$$$$$$ $ $~$$~ ~$$$$$$ $ gggggg $ $ $ $ $ $ $ $ $ $ $ $ 'ggg $$$
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-PZR-01 22 23 MWTVW-14 MANWAY UT-00 NO R 1-006 24 UT-455 R 1-006 25 UT-605 R 1-006 28 27 NTHW-08 NOZZLE UT-00 1-1-01 14.00 3.000 NO R 1-006 28 UT-455 1-1-01 R 1-006 29 UT"60S 1" 1-01 R 'I -006 30 31 NTHW-09 NOZZLE UT"00 1- 1-01 4.000 2.500 NO R1-006 32 UT-455 1-1-01 R 1-006 33 UT-605 1-1-01 R 1-006 34 35 NTHW-10 NOZZLE UT-00 1-2-03 06.00 2.500 NO R 1 "006 38 UT-455 1-2-03 R 1-006 37 UT-605 1-2-03 R 1-006 38 39 NTHW-11 NOZZLE UT-00 1-2-03 06.00 2.500 NO R1-006 40 UT-455 1-2-03 R 1-006 41 UT-605 1-2-03 R 1-006 42 43 NTHW-12 UT-00 3-06 06.00 2.500 R1-006 44 t tt t t t tt t t rt tt t t rt t t t t t t t t NOZZLE NO t t tt tt t t t t t tt t t t t
- t t t k t t t t t t t. tt t t t t t t tt t t t t t t t tt t t t t t
- t t tt t tt t t tt t t tt tt t t t t t t t t t t t t t t t t t t t t tr 45 48 47 48 49 50 51 52 53 54 55 se 57 58 59 80 FORM 0113 {02I83)
29 1 tt 1 t t t 1 1 f 1 1 1 t 1 1 1 t 1 f 1 1 1 1 1 1 1 1 1 1 1 t 1 1 t 1 t 1 ft 1 t 1 t t 1 t 1 t tt f 1 t 1 1 1 t t 1 1 1 1 1 f 1 1 1 1 1 t 1 1 1 1 1 t
'1 1' 111 t1 1 1 1 1 t1 t1 1 1 tt 1' 111 t t 1 1 ft 1 1 1 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING 1111111111111111111 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 28 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 88/01/12 tflftft1!Irtfrl\1 t tlirtttttfttttttt*1111111 ttttttttttttttfttttfst 1 1 f1ttttttttttttt tat tt'taft 1st 1 11 1st tttf1 1 1 tttftaft 1 trlrllrftftf THE SUMMER 1883 ADDENDA, INTERVAL 01 ONLY DATE 9
10 CATEGORY B-DB FULL PENETRATION WELDS OF NOZZLES IN VESSELS PROGRAM B 11 ITEM NO. B3. 110 PRZ NOZZLE-TO-VESSEL WELDS - PROGRAM B 12
'13 taft*sfsf tttttttttttttff1tttttlrftf1 1 f1tttttttftttttttttttttttttftfttttttttttflrttftttttttaft 14 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) --ACCESS SELECT IND REOST TIONS NOTES 19 assas s sssssss s = asssssass a ssaaas sssaa sasssasass aa s aaasa ~ aaass ssasas ss s aasaas sass 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-PZR-01 22 23 NTHW-12 NOZZLE UT"455 1-3-06 06.00 2.500 NO R 1-006 24 UT-60S 1-3-06 R1-006 25 28 NTHW-13 NOZZLE UT-00 1-3-06 06.00 2.500 NO R 1-006 27 UT-455 1-3-06 R1-006 UT-605 1-3"06 R1-006 sf 1'tftttttttttftttttllrtf 28 29 sf 1 f ff fttfft*fftatsf f tffttfftaft'fair!Irtttttrttttfsf 1*trlr!Ir 30 31 32 33 34 35 38 37 38 39 40 41 42 43 44 45 48 47 48 49 50 51 52 53 54 55 58 57 58 59 80 FOAM 0113 102I83)
30 t t t' ft t t t t t t f t t t t t t t tttft t tt t t t t t tt tt f ttft ftt t t f t tt t tt t t t f tft t t t t t t t t t t t tt ft f ttft tt t t t t tt t t tt t t t t t t t t t t t t t t tt t t' ft t f t 2 NUTECH CAROLINA POWER 8L LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING t t t theft tt t t t t COMPONENT 'LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 29 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 t t*ff fthm't t t tft tf tff ft t tt t t t t tft t tftt t ff t t t t f f t t t t f t' t f t t t' t t t t t f f tt t t t t t tt ft f t t t fthm tt t t f t 9
10 CATEGORY B-DB FULL PENETRATION WELDS OF NOZZLES IN VESSELS - PROGRAM B 11 ITEM NO. B3.120 PRZ NOZZLE INSIDE RADIUS SECTION - PROGRAM B 12 13 ttttfttftttttttftttttttttfttttttttttf tltttttttttttfttttttttttff ttttttttttf*tftt*tt*f ttttftttttff tttftt 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 18 19 ffffff NUMBER f fff fff ~ fffffff fffff fgggfffff fg ffffff15ff f fff Sfffff tff f'f f fff ~
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: II-PZR-01 22 23 NIR-08 NIR UT-IR 1-1-01 14.00 3.000 NO 24 UT-70S 1-1-01 25 26 NIR-09 NIR UT-705 1-1-01 4.000 2.500 NO 27 28 NIR-10 NIR UT-705 1-2"03 06.00 2.500 NO 29 30 NIR-11 NIR UT-705 1-2-03 06.00 2.500 31 32 NIR-12 NIR UT-705 1-3-06 06.00 2.500 NO 33 34 NIR-13 NI R UT-70S 1-3-06 06.00 2.500 NO 35 t t t t t t t f t tf t ttf t tt tt ft t ft t ttfft tt t t tff f tff t t t t t tt ttft t t tt t ttt t t t t tt t' t t t t tt t t t t t f tt t tt tt t tt t t t t f t t tt f tt tt t ft tf t tf t t' t 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 se 57 58 59 60 FORM 0113 (02I83)
32 tfttftt>>f tttt>>f1 ttttttlftfttttfttfttttttttttttttttttttttttttftttttf Fttttttttttt>>tt tf>>>> tf <<tttt f ttttttfttttttttt 1 1 111 NUTECH CAROLINA POWER 8 LIGH'OMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING >>f11 ttf1 ttttttftf 11 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 31 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 88/01/12 ttttt>>t>>ttt>>ttf>>f1 1 11>> tf1>>ttttttt>>'tt'1>>ttttttttt>>tttftf ttt't<<ttftttttttttttttttfttttt>>tf 1>>tttttf ttttf DATE THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 1 >> >><< >>f1>>tf 1111<<11 1 9
10 CATEGORY 8-DB FULL PENETRATION WELDS OF NOZZLES IN VESSELS " PROGRAM 8 11 ITEM NO. 83. 130 SG PRIMARY NOZZLE-TO-VESSEL WELDS - PROGRAM 8 12 13 f >>t 1 t*tf1 1 1 tf1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 f 1 1 t t1 1 f 1 1 f 1 11 tf t 1 1 1 1 1 I 1 1 1 It 1 1 1 tt 1 1 1 1 t t 1 <<<< tf 1 >> tt 1 t 1 1111 t f 1 1 1 1 1 t 1 t1t 1 f 1 t 1 1 1 1 1 '1 1 1 1 1 1 1 1 1 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REOST TIONS NOTES 19 sass>>ass>>ass>>as>>sass>>ass sass>>sass>>sass>> sass>>a sass>>sass>>ass>>as ===== ~ ~ sass>>ass ass>>as sas a>>sass ass>>as >>sass 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-SG-001 22 23 SGB-CLNTVW-12 NOZZLE UT-455 1-2-03 40. 11 5.000 NO R1-006 24 UT-605 1-2-03 R 1-006 25 26 SGB-HLMWTHW-14 MANWAY UT-00 NO R 1-006 27 UT-'45S R 1-006 28 UT-60S R1-006 29 30 SGB-HLNTVW-07 NOZZLE UT-00 1-2-03 40. 11 5.000 ND R 1-006 31 UT-45S 1-2-03 R 1-006 32 UT-60S 1"2-03 R 1-006 33 34 SGC-CLMWTHW-15 MANWAY UT-00 NO R 1-006 35 UT-455 R1-006 36 UT-60S R1-006 37 38 SGC-CLNTVW-12 NOZZLE .UT-00 1-3-06 40. 11 5.000 NO R 1 "006 39 UT-45S 1-3-06 R1-006 40 UT-60S 1-3-06 R 1-006 41 42 SGC-HLMWTHW"14 MANWAY UT-00 NO R 1-006 43 44 ttftf ttff 1 fffffffftffffffffftfff tfff tffftff>>4>>>>>>>>>> 1 1 UT-45S
<<>> >>>>>> >> >>>>>> << >>>>>> >>>>>>>> >>>> >> >>f 1 R1-006 t>>f ffff>>f 1 ff1 1 fff1 >><<>> t<<fftf tttttttf1 fffff1 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60
38 1 tttltttlltttttlttttlttlltlttfit tlttlt*ttttttftttlttlltttttttttlttffatal ttfttlttftttl'ftflttttltff tfl'ttsf 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM
" UNIT 3
4 SHEARON HARRIS NUCLEAR POWER PLANT PLANNING 1
llttltfst tt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 37 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 88/01/12 7
8 ttttlttltllttlttfitltttttiltttlttttttttfttttt*tttttfttttftttttftftftsf ft ttttff sf ttllllttfatflatf tftttttttttttf THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE ttttt f t 9
10 CATEGORY B"E PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS 11 ITEM NO. B4. 12 CONTROL ROD DRIVE NOZZLE PARTIAL PENETRATION WELOS 12 13 t t tati t t tt tlltft t tlt ltlt sf t t tlllltl l t*llfitt t t*tt tt*tt ft fitf t t t tt t t t t t t t t t at f t sf tat t sf sf sf t t t alt fitt t tlat f t at tt t f t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULEO INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sasssssssssasssaassssssa ssasssssssssass ssaass sssasssaaasssssa sssss stats ssassssa sass = == ==== stats asassa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 CRD-01 CRDTVW VT-2ST 04.00 0.619 NO 24 25 CRD-02 CRDTVW VT-2ST '4.00 0.619 NO 26 27 CRD-03 CRDTVW VT-2ST 04.00 0.619 NO 28 29 CRO-04 CROTVW VT-2ST 04.00 0.619 30 31 CRD-05 CROTVW VT-2ST 04.00 0.619 32 33 CRO-06 CRDTVW VT-2ST 04.00 0.619 34 35 CRD-07 CROTVW VT-2ST 04.00 0.619 NO 36 37 CRD-08 CROTVW VT"2ST 04.00 0.619 38 39 CRD-09 CROTVW VT-2ST ~ 04.00 0.619 NO 40 41 CRO" 10 CROTVW VT-2ST 04.00 0.619 42 43 CRO"11 CRDTVW VT-2ST 04.00 0.619 44 45 CRO-12 CROTVW 04.00 0.619 VT"2ST'T-2ST 46 47 CRD-13 CROTVW 04.00 0.619 NO 48 49 CRD-14 CRDTVW VT-2ST 04.00 0.619 50 51 CRD-15 CRDTVW VT-2ST 04.00 0.619 52 04.00 0.619 53 CRO-16 54 tt tf sf at at sf t t tt fittfttlttt tflltttfl'sf f flat f f tt*tt fit tl tifffft st f t litt lt at t f la t tff t IItttlttttf tt at at f at at t fit alt tt'aft CRDTVW VT-2ST NO 55 56 57 58 59 60
39 t t t t t t t t t tt t t t tt t tt t t tt t
- t t tt t t t t t tt t t t tt t t ft t t t t t t t t t tt t t t t t t t' t t t t t t t t 't t t NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 38 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 t t ttt t tt t t 't t t t ttt tt t t t t t' t t t t t tt t t t t t t t t t t t t t t t t t t t t tt t t t tt t t t tt
't 't 't 't t' t' t t t t t t t tt t t t t t t t t t t tt t t! t t tt t t t t t t 't tt tt t t' t t 't t 9
10 CATEGORY B-E PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS 11 ITEM NO. B4.12 CONTROL ROD DRIVE NOZZLE PARTIAL PENETRATION WELDS 12 13 t t t t *t tt t t t t t tt t t t t t t tt tt t t t t t t tt t t t t tt t t t t t t t t t t t t t t t t t' 1 t t t t 't tt t t t t' t t t t t t t t t t t t t t t t t't t *t tt t t' t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 aasrsaass r rs s ss sr ss a rsr a rarer seers asses starters arrear sss assess assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 CRD-17 CRDTVW VT-2ST 04.00 0.619 24 25 CRD-18 CROTVW VT-2ST 04.00 0.619 NO 26 27 CRD-19 CRDTVW VT-2ST 04.00 0.619 NO 28 29 CRD-20 CROTVW VT-2ST 04.00 0.619 NO 30 31 CRD-21 CRDTVW VT-2ST 04.00 0.619 32 33 CRD-22 CRDTVW VT-2ST 04 . 00 0. 619 34 35 CRD-23 CRDTVW VT-2ST .P4.00 0.619 38 37 CRD-24 CRDTVW VT-2ST 04.00 0.619 38 39 CRD-25 CROTVW VT-2ST 04.00 0.619 NO 40 41 CRD-26 CRDTVW VT-2ST 04.00 0.619 42 43 CRO"27 CRDTVW VT-2ST 04.00 0.619 44 45 CRD-28 CRDTVW VT-2ST 04.00 0.619 48 47 CRD-29 CRDTVW VT-2ST 04.00 0.619 NO 48 49 CRD-30 CRDTVW VT-2ST 04.00 0.619 NO 50 51 CRD-31 CRDTVW VT-2ST 04.00 0.619 NO 52 53 CRD-32 CRDTVW VT-2ST 04.00 0.619 NO 54 tttt t ttt t tt t t t tt t ttt t t! ttt t' t tt t 't t t t tt t t t t t t tt tt t t t t *a t t tt t t t tt t t t t tt t t t tt t t t t t t tt t t t t t t tt t t tt t t tt t t t t t t t t t t tt t t t t t t t t 55 56 57 58 59 60 FORM 0113 (02I83)
43 t t t 44 444 44 4 4 4 4 4 44 444 4 4444 4 4 4 4 4 fr tt 4 4 t 4 4 444444
- t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 t t. 4 4 t 4 t. 4
- t 4 4 t 4 4 4 4 t 4 4 4 4 4 4 t 4 4 4 4
444 st 444 4 4 4 4 4 4 44 PAGE REVISION NRC1 f tf 42 4 taft fftfttftf4444444fttttttff tftttff THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY ff tftftffttttfffr 4
DATE 88/01/12 4 fr 4*4 tfttf4*ffff 44444 9
10 CATEGORY B-E PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS 11 ITEM NO. B4.13 INSTRUMENTATION NOZZLE PARTIAL PENETRATION WELDS tf444 4 44tt44tf 4444444444 44444 at ttttf44tt 444*4 tf ttttt4444 4 4 4 4tt4 4 4 4 44 tt tat ttf444444 4 4 4 tf aft ttt4 4 4 12 13 44 4 44 44'tf f4 44444 44444 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 saaaaaaasrs aasasssarssa ssrsaasssssssas asasss sssaasasssssassa arras ssaas assaasss aasrrs rss rsrsss a asa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 INST NOZ-01 ICI NOZ VT-2ST 1-3-06 01.50 0.450 24 25 INST NOZ-02 ICI NOZ VT-2ST 1-3-06 01.50 0.450 NO 26 27 INST NOZ-03 ICI NOZ VT-2ST 1"3-06 01.50 0.450 28 29 INST NOZ-04 ICI NOZ VT-2ST 1-3-06 01.50 0.450 30 31 INST NOZ-05 ICI NOZ VT-2ST 1-3-06 01.50 0.450 NO 32 33 INST NOZ-06 ICI NOZ VT-2ST 1-3-06 01.50 0.450 NO 34 35 INST NOZ-07 ICI NOZ VT-2ST 1-3-06 $ 01.50 0.450 36 37 INST NOZ-08 ICI NOZ VT-2ST 1-3-06 01.50 0.450 NO 38 39 INST NOZ-09 ICI NOZ VT-2ST 1-3-06 01 . 50 0. 450 NO 40 41 INST NOZ-10 ICI NOZ VT"2ST 1-3"06 01.50 0.450 NO 42 43 INST NOZ-11 ICI NOZ VT-2ST 1-3-06 01.50 0.450 NO 44 45 INST NOZ-12 ICI NOZ VT-2ST 1-3-06 01.50 0.450 NO 48 47 INST NOZ-13 ICI NOZ VT-2ST 1-3-06 01 . 50 0. 450 NO 48 49 INST NOZ-14 ICI NOZ VT-2ST 01.50 0.450 NO 50 51 INST NOZ-15 ICI NOZ VT-2ST 01.50 0.450 NO 52 ICI NOZ 0.450 53 INST 54 NOZ-16 tttf tf44 tf44 4 4 4 t tat tf444*st ttttttttfttt44444 4 tftf4 tttftttt01.50 VT"2ST at at f f 4 ttttf44 44f 4 f tf t4t f44 4 44*4 4 4tf ftf4 tt f4 tat tt sf NO 55 56 57 58 59 60 FOAM 0113 (02I83)
44 1 11 t 1 1 tt t 1 1 t 1 1 tt 1 1 t 1 1 1 1 t 1 1 1 1 1 ~ 111 t 1 t 1'. 1 1 tt 1 1 1 t 1 1 t 1 1 1 t 1 t 1 1 t 1 1 1 1 t t 1 t 1 t 1 1 t t 1 1 1 t 1 1 1 t 1 1 1 1 1 1 1 1 1 t 1 1 t 1 1 1 1 1 1 f 1 1 1 t 1 1 1 1 1 1 t 1 t 1'
2 EI!
NUTECH CAROLINA POWER 8E LIGHT COMPANY PRI SIN 3 f SHEARON HARRIS NUCLEAR POWER PLANT - UNIT f 1 1 t 1 1 1 1 tt 1 1 1 1
4 PLANNING 111111 COMPONENT LISTING ANO ISI 10 YEAR PLAN: 835-01 PAGE 43 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL'1 ONLY 88/01/12 tfttfttfftttt*tfttfttfttttttfttt*ttttt*tttttttf*f tttttttttttttt'ttt*tttftftttttttttftttttttfDATE 1tttttttttttf ttf 9
10 CATEGORY B-E PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS 11 ITEM NO. B4. 13 INSTRUMENTATION NOZZLE PARTIAL PENETRATION WELDS 12 13
- 1 1 1 t 1 1 t 1 1 1 1 1 f 1 1 1 t 1 1 t 1 1 1 1 1 t t 1 t 1 t 1 t 1 1 1 1 t 1 t t 1 t 1 1 1 t 1 1 1 1 1 1 1' t t1 1 1 111 1 1 t 1 1, 1111 t 1 t t 1 1 t 1 f 1 1 1 1 1 1 f1 1 1 1 t t t f 1 1 1 t 1 1 1 1 1 1 f1 t 1 f1 1
'14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) ( IN) ACCESS SELECT IND REQST TIONS NOTES 19 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RV-001 22 23 INST NOZ-17 ICI NOZ VT-2ST 01.50 0.450 NO 24 25 INST NOZ-18 ICI NOZ VT-2ST 01.50 0.450 NO 26 27 INST NOZ-19 ICI NOZ VT"2ST 01.50 0.450 28 29 INST NOZ-20 ICI NOZ VT-2ST 01.50 0.450 NO 30 31 INST NOZ-21 ICI NOZ VT-2ST 01.50 0.450 NO 32 33 INST NOZ-22 ICI NOZ VT-2ST 01.50 0.450 NO 34 35 INST NOZ-23 ICI NOZ VT-2ST 01.50 0.450 NO 36 37 INST NOZ-24 ICI NOZ VT-2ST 01.50 0.450 NO 38 39 INST NOZ-25 ICI NOZ VT-2ST 01.50 0.450 40 41 INST NOZ-26 ICI NOZ VT"2ST 01. 50 0. 450 42 43 INST NOZ-27 ICI NOZ VT-2ST 01.50 0.450 44 45 INST NOZ-28 ICI NOZ VT-2ST 01.50 0.450 NO 46 47 INST NOZ-29 ICI NOZ VT-2ST 01.50 0.450 48 49 INST NOZ-30 ICI NOZ VT-2ST 01.50 0.450 50 51 INST NOZ-31 ICI NOZ VT-2ST 01 . 50 0. 450 52 f 1 1 1 1 ICI 01.50 0.450 53 INST NOZ-32 NOZ VT-2ST NO 54 111111 1 1 t 1 1 1 1 1 t 1 ft 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 f 1 1 1 1 t 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 t 1 t 1 1 t 1 1 1 1 1 t! 1 t 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 t 1 t 1 1 1
'1 55 56 57 58 59 eo FoRM 0113 [02I831 1
45 1 f f f tff tfttt tttftttttffthm f ttftttt ttff f f ttt t f fthm tff t f ttttttff t tf tttff ttff tt ttff f tftttt tttttftfff tt ttff fttttff ff t t 2 NUTECH CAROLINA POWER 5 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT 3
4 PLANNING UNIT
'f ttt tfttttfftttttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 44 ASME SECTION XI, 1983 EDITION THROUGH fthmlift AND INCLUDING REVISION NRC1 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY
'tf ttttt'tfttt'lit tf't f ttftftt*tttttftt tttftt'tDATE tttttttt tttft'f t 9
10 CATEGORY B-E PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS 11 ITEM NO. B4. 13 INSTRUMENTATION NOZZLE PARTIAL PENETRATION WELDS t f t f f fff t t t t 't ffffff f ff fff f ~ f f f f t I ff f f f t f t fffff f f t f fft t f f tl t t t ff *tf t 't t t t f fffft f f t t f t f t f t f f f t f t ft ft t t*tt tt fft t 12 13 fr 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 INST NOZ-33 ICI NOZ VT-2ST 01.50 0.450 NO 24 25 INST NOZ-34 ICI NOZ VT"2ST 01.50 0.450 26 27 INST NOZ-35 ICI NOZ VT-2ST 01.50 0.450 NO 28 29 INST NOZ-36 ICI NOZ VT-2ST 01.50 0.450 30 31 INST NOZ-37 ICI NOZ VT-2ST 01.50 0.450 NO 32 33 INST NOZ-38 ICI NOZ VT-2ST 01.50 0.450 NO 34 35 INST NOZ-39 ICI NOZ VT-2ST $ 01.50 0.450 36 37 INST NOZ-40 ICI NOZ VT-2ST 01.50 0.450 38 39 INST NOZ-41 ICI NOZ VT"2ST 01 . 50 0. 450 40 41 INST NOZ-42 ICI NOZ VT-2ST 01 . 50 0. 450 42 43 INST NOZ-43 ICI NOZ VT-2ST 01. 50 0. 450 NO 44 45 INST NOZ-44 ICI NOZ VT-2ST 01.50 0.450 NO 46 47 INST NOZ-45 ICI NOZ VT-2ST 01.50 0.450 NO 48 49 INST NOZ-46 ICI NOZ VT-2ST 01.50 0.450 NO 50 51 INST NOZ-47 . =ICI NOZ VT-2ST 01.50 0.450 52 53 INST NOZ-48 ICI NOZ VT"2ST 01.50 0.450 NO 54 f *tf f *ft t t t t f tt ft tt t t t t ttfftf t t tt f tt tf fttf tffftft f ttt t tt tt t f t t t t t t tft f t t t f f. f ft t f t t t t t t t ttt t t tt t t t t f t t t t t tt 't t t t t 't f tt 55 se 57 58 59 60 FORM 0113 (02I83)
t t t t t tat t t tat tt tt t t t t t t t t t t hatt tt t stat t t t t t t t tt t hatt t t at t t t t t t t tt t tt t st t t tt t t t t t tat t t t t t t t st t t tt t NUTECH CAROLINA POWER & LIGhT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING
- t t t t t t t t t t' t t t t ttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 45 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t t tt tt t t t t t t t t t t t t at tt t at t tt t tt t st t t 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY at t t t t tt tat t t t at t at t t t t t tat at t t t t t tt tat t t t t t t tat f t t t hatt t at tt t t atty at DATE t t t tt t t t t t t 9
10 CATEGORY B-E PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS
, ll ITEM NO. B4. 13 INSTRUMENTATION NOZZLE PARTIAL PENETRATION WELDS 12 13 t t t tt t t t t tt t tt t ttt t 't tt tt t tt t t 't t t tt tt t t t t t t t tt t ttt t tt t tt t t t tt t t t tt t tt t t t t t t t t t tt t t tt t t ttt tt t t tt tt t ttt t t t t tt t t t t tt t' t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REOST TIONS NOTES 19 asssassssrssssassassssss assssasssasssss sasass sssassssssssaaaa sasss arras assssaas ssssaa sss sasaaa ararat sssaas 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RV-001 22 23 INST NOZ-49 ICI NOZ VT-2ST 01.50 0.450 24 25 INST NOZ-50 ICI NOZ VT-2ST 01.50 0.450 NO 26 t t 't t t t t t t t t t t t t tt t t t I tt t t t 't tt t tt t tt t t t t t t t t t t t t t t tttt tttt tt t t t t t t t t t t t t t t t t t tt t t tt t t t t t tt t t t t' t t t t t t t t tt t t t t t t t tt 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 46 49 50 Sl 52 53 54 55 56 57 58 59 60 FORM 0113 (02I831
50 1 t t tff tff f f tff tft t f f f ffftt f tt ff t f t ff f ft tft t f f f t t fft t t t ttt t t f f f tff f t ff v f ftf t t t ttffft t t t t ft t f ff f f ft t t t tft f t f f f t t t f t ft f f 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3
4 PLANNING 1
ttttttftttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 49 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING f . REVISION NRC1 f
THE SUMMER 1983 ADDENDA; INTERVAL 01 ONLY tftt t t f fthm f 't t tt tftt t f'fthm tt t t t t 't 4 f t t f t t tt tt tt t t tfffttt ff tt t t t t t t ft t t t f tf'*tf f tftft ft*fff t t ft t t f t f t t t DATE t t tt tt88/01/12 t t t t t t t ttt 9
10 CATEGORY B-F PRESSURE RETAINING DISSIMILAR METAL WELDS 11 ITEM NO. B5. 30 RV NOZZLE-TO-SAFE END SOCKET WELOS f ttfttttttttfttt f ttttttttttttttttttfttttttt ttttfttttttttttttttttfttttttftttff ttfttft tfttttttfttttttttfttftftttff t 12 13 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM DESCRIPTION DULED INT INT *
(IN) (IN) SELECT IND REQST TIONS NOTES 18 19 f NUMBER ffff fuff f
~ ~ SffffmRRRRIR TYPE ftftt Sf 2 RRRf ~ fff 5 ACCESS tf ~ t ttt t t I tffffffffftt 20 21 SYSTEM : REF .REFERENCE ISOMETRIC NUMBER : REFERENCE 22 24 ffft APPLICABLE 23 NOT fffCOMPONENTS t t ff ff t t f f t f f ff t ftfffNO ff t tt f t t t ffft tff t t t f ff t t f ff t t tt t t tt t tt t t tt t t f f t t f t t t t t t t ft t t t t t f t t tt ft tff f t tt t t ft ft t t t t t f' 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 48 47 48 49 50 51 52 53 54 55 56 57 58 59 60 0
58 1 ttfttflltltltttttttf tttlttlttfltttttttttttt f ttt fitttt ttttttttltllttltt111*11 tt tifftt 1
2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 4 PLANNING COMPONENT LISTING AND .ISI 10 YEAR PLAN: 83S-01 PAGE 57 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 1 1 11 tf1 f tt 1 1 1$ 1 f1 1 1 1 t f1 1 1 1 1 1 1 1 f *1*11 1 f 1 t*t1 1 t*tt 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 tlat 1 1 1 1 1 t t 1 1 1 1 t tf 1 1 1'1 1 ft 1 t t1 1 1 1 1 1 *1 1 t tt 1 1 1 1 t 1 1 tl'1 1 9
10 CATEGORY 8-F PRESSURE RETAINING DISSIMILAR METAL WELDS 11 ITEM NO. 85. 110 HX NOMINAL PIPE SIZE < 4 IN. NOZZLE-TO-SAFE END BUTT WELDS 12 13 1111 1 t 1 1 t t 1 t t 1 t f 1 1 1 t 1 1 1 1 11 1 t 1 1 1 t tt 1 1 1 1 1 t 1 1 t 1 1 t 1 1 1 1 1 t 1 1 1 t 1 1 1 t 1 1 t t 1 1 1 1 1 I 1 t 1 1 f t t t tt tf 1 1 1 t 1 lr 1 1 1 1 1 t 1 1 1 1 1 1 f t ttt t t 1 1 1 1 1 1 1 1 1
'1 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 '1 1 \ 1 $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ ~ '$$ $ ~ 1 ~ $ $ ~ $ $ $ $ $ $ $ $ 1 1 1 1 $$ $ $$$ $$ $$$
20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 1'$
23 NOT APPLICABLE NO COMPONENTS 24 t t t 11 1 111 t f t t t tt t fft t t f 11 1 1 1 111111111 t t ft t t 11111111111 111111 111t t t ft t t t t tttft f f 11 1111111111111 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 58 57 58 59 60 FORM 0113 (02/83)
1 t t st at t t t tt t tat tt t at tat tat tt t t tat t tt t t t ttt st t t t*tt't t tt t t t t tt t t t t t tt t t r t t tt tt t t t tt tt tt st'at t t t t t at t t t t t t t t 't t t t 't t't t t t t t 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWEP. PLANT - UNIT t 4 PLANNING st t tat t st t tat t t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 59 6 ASME SECTION XI. 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL'1- ONLY t t t t 88/01/12 s,7 8 't t t t t t t tt t t t' t t ttt t t t t t t t t t t t t t t t t t t t t t t tt tt t t tt tt t t t t t t t t t t t t t t t t t tt t t tt
- ttt t t t t t t tttt tt ttDATE ttttttttttt 9
10 CATEGORY 8-F PRESSURE RETAINING DISSIMILAR METAL WELDS ll ITEM NO. 85.130 NOMINAL PIPE SIZE >s 4 IN. DISSIMILAR METAL PIPING BUTT WELD 12 13 t t t t t t t t t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t ttt t t t tt t t t tt t tt t t t t t t t t t tt t t t 't 'I t' 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssasasasasassasaassssrss saassrasasrasrs ara s ra srssassas. arras aasss sasraaar ssssrr aas sssass ssasss sssssa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-FMR-01 22 23 RC-10-17-FW-1 RVNOZAO-PIPE PT 1-1-01 29.00 2.330 NO 24 UT-RVN 1-1-01 25 26 RC" 10-17"FW-4 ELB LR -RVNOZAI PT 1-3-06 27.50 2.210 NO 27 UT-RVN 1-3-06 28 29 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-FMR-02 30 31 RC-10-18-FW-1 RVNOZBO-PIPE PT 1-1-01 29.00 2.330 32 UT-RVN 1-1-01 33 34 RC-10-18-FW-4 ELB LR -RVNOZBI PT 1-3-06 27.50 2.210 35 UT-RVN 1-3-06 38 37 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II"FMR"03 38 39 RC-10-19-FW-1 RVNOZCO-PIPE PT 1-1-01 29.00 2.330 NO 40 UT"RVN 1-1-01 41 42 RC- 10 F W-4 ELB LR -RVNOZCI PT 1-3-06 27.50 2.210 NO UT-RVN 1-3-06 43 44 tttttttttttltttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt*tttt'*tttt 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83) tl
1 fttttf'tff1111'11111 111'f 1*1 tff 1*ttff 111 ftftfttfttftf'f1tf'ftff1 tttfttttftttttttt11'fttffftttf1'f*ftf 11 1 f1 tf ffttftttf ftfftt 1 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 1 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING 1 1 1 1 1 1 1 1 1 1 '1 1 1 1 1 '1 1 1 1 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 61 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE'UMMER 1983 ADDENDA, INTERVAL 01'ONLY DATE 88/01/12 7
8 1111111 t 1 1 tf1 1 1 t tf1 tf1 1 1 11 1 tf 1 tf f 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 t tf t 1 t t 1 1 1 f 1 1 1 tf 1 1 tt1 f 1 tf 1 1 t 1 1 1 1 f 1 tf 1 1 1 1 1 1 1 tttf 1 *1 tf1 t t 1 1 1 1 1 1 1 t 1 1 f 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ll ITEM NO. B6. 10 RV CLOSURE HEAD NUTS (>2) 12 13 ttttttfttttfttf1 ttttttttttfttf1 tff1 1 1 1 tftf1 tttt ttttttftttf ttttttttttttf11 ttt f tftftf t tf1 tftf1 1 tt 11 tftf ftttf*f1 1 ttf1 1 1 1 14 15 DONE 18 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE" OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULEO INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ $ $ $ $ $ $ ~ $ $ $ $ $ ~ $ $ ~ S ~ S ~ S ~ S ~ $ $ $ $ ~ $ $ $ $ $ $ $ ~ S ~ SSSS ~ $ $ $ $ $ $ $ $ '$$ $ $ $ $ ~ S ~ $ $ $ $ $ $ $ $ SSSSSSSS ~ $ $ $ S $ $ ~ SSSS'$$ $$$$$ $ $$~$$~
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 RVNUT-15 NUT MT 1-1-01 6.000 57.37 24 25 RVNUT-16 NUT MT 1-1-01 6.000 57.37 28 27 RVNUT-17 NUT MT 1-1-01 6.000 57.37 NO 28 29 RVNUT-18 NUT MT 1-1-01 6.000 57.37 30 31 RVNUT-19 NUT MT 1-1-01 6.000 57.37 NO 32 33 RVNUT-20 MT 1-2-03 6.000 57.37 NO 34 35 RVNUT"21 NUT MT 1-2-03 6.000 57.37 NO 38 37 RVNUT-22 MT 1-2-03 6.000 57.37 NO 38 39 RVNUT"23 NUT MT 1-2-03 6.000 57.37 NO 40 41 RVNUT-24 NUT MT 1-2-03 6.000 57.37 NO 42 43 RVNUT-25 NUT MT .
t; 1-2-03 6.000 57.37 NO 44 45 RVNUT-26 NUT MT 1-2-03 6.000 57. 37 NO 48 47 RVNUT-27 NUT MT 1-2-03 6.000 57.37 NO 48 49 RVNUT-28 NUT MT 1-2-03 6.000 57.37 NO 50 51 RVNUT-29 NUT MT 1-2-03 6.000 57.37 NO 52 1-2-03 53 RVNUT-30 54 fr rf tf tf t tf1 1 1 1 1 1 rlr1 111 1 11111 NUT tf1 1 1 1t 1 frf1 1 MT 1 1 fr 1 1 1 1'1 1 1 tf 1 11 1111 tf1 1111 tf6.000 1 57.37 1 tt 1 1 1 ft 1 1 1 NO 11111111111111111111111111111111 tf 1111 t 55 55 57 58 59 80
63 4 44 4 4 4 tf4 4 4444 444 44444 4 f4 ttftf 4 444 4 tf4 4 4444 444 444 4 ttttttttttt4 tttftt4ttf 4 tf 444 44444 4 4 f4 44 4 4 t4f 4 4 4 4 44 444 ttftf 4 4 4 4 44 4 NUTECH CAROLINA POWER 8 LIGHT COMPANY PR IS IM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 4 4 fr 4 4 4 lit 4 4 4 4 4 4 4 llr 4 4 llr 4 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 62 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
'4 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 4 4 4 4 4 4 4 4 4 4 4 4 4' 4 4 4 4 tt 44 4 t t4 4 4 4 4 4'4 4 444 4 tf 4 t 4tr 4 4 4 f tt 4 4 4 4 t f4 4 4 4 4 4 4 tf tf t 4t4 4 44 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ll ITEM NO. B6. 10 RV CLOSURE HEAD NUTS () 2")
4*t 4 4 4 4 4 t 4 4 t f4 444 tt 4 4 4't4 4 4 tt 4 4 tf tf 4 t4 4 *4ttffat tt 4 4 4tf 4 4 4 4 4 4 4 4 ttt 44 4 4 4f 4 4 4 4 4 tf'4 4 4 t 4 4 4 4 t 4 4 tt 4 4*t 4 t 12 13 4 44 4 4 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 $ $ $ $ $ ~ $ $ $ $ ~ $ $ $ $ $ ~ 4 ~ $ $ $ $ $ ~ $ $ ~ 4 ~ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ 4$ $ $ $ $ ~
$ $ '$ 4 $ $ '$$ $ $ $ $ $ $ ~ $ $ ~ 4 ~ $ $ $ $ $ $ $ $ $ $ $ $ ~ 4 ~ ~ $ $ $ $ $ $ $ ~ $ $
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 RVNUT"31 NUT MT 1-2-03 6.000 57.37 NO 24 25 RVNUT"32 NUT MT 1-2-03 6.000 S7.37 NO 26 27 RVNUT-33 NUT MT 1-2-03 6.000 S7.37 NO 28 29 RVNUT-34 NUT MT 1-2-03 6.000 57.37 NO 30 3'I RVNUT-35 NUT MT 1-2-03 6.000 57.37 NO 32 33 RVNUT-36 NUT MT 1-2-03 6.000 57.37 NO 34 35 RVNUT-37 NUT MT 1-2-03 6.000 57.37 NO 36 37 38 RVNUT-38 NUT MT 1-2-03 6.000 57 '7 NO 39 RVNUT-39 NUT MT 1-3-06 6.000 57.37 NO 40 41 RVNUT-40 NUT MT 1-3-06 6.000 57.37 NO 42 43 RVNUT-41 NUT MT 1-3-06 6.000 57.37 NO 44 45 RVNUT"42 NUT MT 1-3-06 6.000 57.37 NO 46 47 RVNUT-43 NUT MT 1-3-06 6.000 57.37 NO 48 49 RVNUT-44 NUT MT 1-3-06 6.000 57.37 NO 50 51 RVNUT-45 NUT MT 1-3-06 6.000 57.37 NO 52 1-3-06 6.000 57.37 53 RVNUT-46 54 4tttttttftf4 4tftttftttttttftftff4tftttfftff4tftftttttttttfftfftfttttftf4 NUT MT ttttfttftttttfttttfttffttffftftf4fttfff4ftttt NO 55 56 57 58 59 60 FORM 0113 (02183)
64 tt t
- t t t t t t t t t t t t tt t t tt t t t t t t t t t t t t t t t' t tt ft t t tt t t t t t t t t t *t
- t t t t t t t tt t t t t t t t t t t t t t tt t t t t t t t t t tt t t tt t t t t t t t t t t t t t 2 NUTECH CAROLINA POWER Sr LIGHT COMPANY PRISIM t 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING t t t 4 tt t t t t t t t t t t't t t COMPONENT, LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 63 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 lt THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 ttt t tttt t t t t' t t tttt t t t t t' t t t t t ttt t tt t t tt t t t tt t t t t t t t t tt tt t t t tt t t tt t t t t tt t ttt t ttttt t t t t t t t' t t t t t t t t tt t t t t t tt tt 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6. 10 RV CLOSURE HEAD NUTS (> 2")
12 13 t t t t t tt t t t t t t t t t tt t tt t tt t t t t t t t t t t t t t 't t t t t t t t t t t t It tt tt t t t t t' t t t' t t t t t tt tt t t t t t t t t t t t t t t t t tt t t t t tt t t t t t t t t t t t t tt
- 0 * 't tr 14 15 DONE 18 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULEO INT INT (IN) (IN) ACCESS SELECT INO REOST TIONS NOTES 19 $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ $$$$$$ $ $ $ ~ $ $ $ '$$ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ '$$ $ $ $ $ $ ~ $ $ $ $ $$$ $$ $$$$~$
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 RVNUT-47 NUT MT 1"3-06 6.000 57.37 NO 24 25 RVNUT-48 NUT MT 1-3-06 6.000 57.37 NO 28 27 RVNUT-49 NUT MT 1-3-06 6.000 57.37 NO 28 29 RVNUT-50 MT 1-3-06 6.000 57.37 NO 30 31 RVNUT-51 NUT MT 1-3-06 6.000 57.37 32 33 RVNUT-52 NUT MT 1-3-06 6.000 57 '7 34 35 RVNUT-53 NUT MT 1-3-06 6.000 57.37 38 37 RVNUT-54 NUT MT 1-3-06 . 6.000 57.37 NO 38 39 RVNUT-55 NUT MT 1-3-06 6.000 57.37 40 4'1 RVNUT-56 NUT MT 1-3-06 6.000 57.37 NO 42 43 RVNUT-57 NUT MT ,
1-3-06 6.000 57.37 NO 44 45 RVNUT-58 NUT MT 1"3-06 6.000 57.37 NO 48 t t t t ttt t t t t t t t tt tr t tttt t t tt t tt t t tt t t t *t t ttt t t t t t t t tt t t
- t tt t tt t t tt t t t t t t t t tt t t t t t t t t ttt t t t t t t t t t t tt tt t tt t t t t t t' t tt t tt *
't 47 48 49 50 51 52 53 54 55 se 57 58 59 80 FORM 0113 (02I83) t
66 4111 f ttt 4 11'4 1 1 1 1 4f 1 4 f 4 1 1 1 1 1 414 1 1 1 1 1 t 1t 1 t 4 f 1 1 t 1 1 t 1 t 1 4 t 1 1 1 4 tt 441 1 1 1 4 1 4 t 4 1 4 1 1 at 1 tt t tt4 4 t 144 1 4 1 1 1 1 1'1 4 1 4 1 1 4 1 t 4t t 4 NUTECH CAROLINA POWER 8 LIGH1'OMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t 1 tttt 1
PLANNING t 41 1 1 1 4 t 4 4 1 st 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 65 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 7
8 4 144 st 4 44t41 tt4114 1 14411114 1 tf44 11 tf4 4411 st st 4tf 1411 44144 4441 4*4tttf44114 tttt tttt4ttttttff tftf114tt4144ttf 4ttt*ttftt 9
10 CATEGORY 8-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. 86. 30 RV CLOSURE STUDS, WHEN REMOVED (> 2")
t4 44 1 4 1 4 1 44 4'1 1 tftf 1 f 'tf 1 t 1 1 '1 1 4 1 4 4 1 4 1 rt t t tt4 f 1 1 1 1 1 4 4 1 4 t t t 1 4 1 4 1 14 1 1 4 1 f 1 1 1 1 t 1 1 It t 4 t 4 1 1 1 11 1 4 1 4 1 4 1 1 4 1 4 1 tt 1 t t 4 1 1 1 1 11 tf 4 4 f 1 1 12 13 1 1 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssssass ssssssss sassssassssssaa ss s assssaasas ass 1 sasas assassss 1 1st- aaa ss 1 1 sss 1 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 RVSTUD-S1 STUD MT 6.000 57.37 NO 24 UT-00 25 26 RVSTUD-S2 STUD MT 6.000 57.37 27 UT-OO 28 29 RVSTUO-01 STUD MT 1-1-01 6.000 57.37 NO 30 UT-00 1-1-01 31 32 RVSTUD-02 STUD MT 1-1-01 6.000 57.37- NO 33 UT-00 1-1-01 34 35 RVSTUD-03 STUD MT 1-1-01 6.000 57.37 NO 36 UT-00 1-1-01 37 38 RVSTUD-04 STUD MT 1-1-01 6.000 57.37 39 UT-00 1- 1-01 40 41 RVSTUD-05 STUD MT 1-1-01 6.000 57.37 NO 42 UT-00 1-1-01 43 44 RVSTUD-06 STUD MT .
1-1-01 6.000 57.37 t UT~
45 1-1-01 46 I t t t f t t f t t t t t 1 4 1 4 1 1 tr 4* 1 1 4 4 1 1 1 1 1 1 1 4 1 1 tr 1 1 4 1 4 1 1 1 1 1 1 4 4 1 1 1 1 4 1 4 1 4 1 1 4 1 1 t. 4 4 1 4 4 1 1 1 4 1 1 1 4 4 4 4 1 1 1 1 1 4 1 1 1 4 1 4 4 1 1 4 1 1 '1 1 1 1 1 1 1 4 4 4 1 1 '1 1 1 1 1 47 48 49 50 51 52 53 54 55 58 57 58 59 60 FORM 0113 {02I83)
67 ff 'f 't f 'f f t f f ff f t f fftt f ffft
- a fft f fff t ft f f f f t t 'f t t t 't*'t*tft tf *tff t t fft ft 'f f t t t t t 't fft f f f f fft ff *tft f ff f f 'l ff 'f f t 't f f f fff f f f fft t 'l CAROLINA POWER Er LIGHT COMPANY PRISIM t'UTECH SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83$ -01 PAGE 66 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
- THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 ffff tt f f ff f tff t at f f ff f sf at t f tan t ff t t sf fft ffft t t*tff fff *at f ft f f t f t*tf ft f' f f ff f t f f tf ff tat'at f' at f fff f at ft f fft f f 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. 86. 30 RV CLOSURE STUDS, WHEN REMOVED () 2")
12 13 ff f l ff tfff tfffffft f at f f at ff fff t ffff ft f fff f f t f f t t t tt f f f ft tff ff tft t*f t f f t fff f f f f f f tfff f ft ft f *tf f t t tt tff f t t ft f t*tttffft 14 15 DONE 18 OUTAGE THIS DONE BOLT BOLT BASIS PSI COMPONENT SCHE" OUT/ PRIOR DIAM LNTH TRV RELIEF EXEMP- PROGRM
'8 17 NUMBER COMPONENT DESCRIPTION EXAM TYPE OULEO INT INT (IN) (IN) ACCESS TO SELECT IND REQST TIONS NOTES 19 sssssssss sassssssaaaaa asaaassaasassas aasass saasaasasasasass stats stats assaasss aaaaas aas asst s asasas asasss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RV-001 22 23 RVSTUD-07 STUD MT 1-1-01 6.000 57.37 NO 24 UT-00 1- 1-01 25 28 RVSTUD-08 STUD MT 1-1-01 6.000 57.37 NO 27 UT "00 1" 1-01 28 29 RVSTUD-09 STUD MT 1-1-01 6.000 57.37 NO 30 UT-00 1-1-01 31 32 RVSTUD-10 STUD MT 1-1-01 6.000 57.37 33 UT-00 1- 1-01 34 35 RVSTUD-11 STUD MT 1-1-01 $ .000 57.37 NO 35 UT-00 1- 1-01 37 38 RVSTUO-12 STUD MT 1-1-01 6.000 57.37 NO 39 UT-00 1-1-01 40 41 RVSTUD-13 STUD MT 1-1-01 6.000 57.37 NO 42 UT-00 1-1-01 43 44 RVSTUD"14 STUD MT 1-1-01 6.000 57.37 45 UT-00 1- 1-01 48 ff ff tff ff f f tff tff f f f f tff tft ttt tfff ft tat ttt t tfff t ttfat tff ft t f tft f fft tfff f tff t f ff t sf f f ft fff ttt tff t t f t' f ftff t'f f f f t t ft f at 47 48 49 50 51 52 53 54 55 58 57 58 59 80 FORM 0113 102I831
~,
69 ft 't tft t t t ftt t t tt t t f t t t t t tt t t t t t t t t f t t t t t f t t t t t t t t t ttt t t t t t ft t t t t t t t t t t t t t ft t t tt tt t t t f tt t t t t ft t t tt t t t t t t t t tt t t t t
- tt t t f NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT " UNIT PLANNING 1
ttttfttfttftttftttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 68 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t t t tt 88/01/12 t t t t ttt tt
- t ft t t t t t f t t tt t t t tt t t tt t tf t t t ttt t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t tt t t t t ff t t f *t t t t t t t ft t t f t t t DATE tt t t t t t ft t t 9
10 CATEGORY B"G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. 86. 30 RV CLOSURE STUDS. WHEN REMOVED (> 2")
12 13 f tt t tt f t ftt tt t t t t t t t f ft tt t t t f t f ttft f t tt t t t t t t t t t t t t t tf t tt tt t t t t t t t f t t f t t t t tf t t t t t t tt f tt t f t t f t t tt t t tt t t t t' t t 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT INO REOST TIONS NOTES 19 sssasssssaasssssrsssssss saaaasassssas s sassssssssass ssass rafts asrssaaa saa sr rsa ss sss sasass ararat 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RV-001 22 23 RVSTUD-23 STUD MT 1-2-03 6.000 57.37 NO 24 UT-00 1-2-03 25 26 RVSTUD-24 STUD MT 1-2-03 6.000 57.37 27 UT-00 1-2-03 I 28 29 RVSTUD-25 STUD, MT 1-2-03 6.000 57.37 30 UT-00 1-2-03 31 32 RVSTUD-26 STUD MT 1-2-03 6.000 57.37 NO 33 UT-00 1-2-03 34 35 RVSTUD-27 STUD MT - 1-2-03 6.000 57.37 NO 36 UT-00 1-2-03 37 38 RVSTUO-28 STUD MT 1-2"03 6,.000 57.37 NO 39 UT-00 1-2-03 40 41 RVSTUD-29 STUD MT 1-2-03 6.000 57.37 NO 42 UT-00 1-2-03 43 44 RVSTUD-30 STUD MT 1-2-03 6.000 57.37 NO UT-00 1-2"03 45 46 ff *frt t*ft sf t f t sf t f f t tfft tat f t st t t tat t t tt tt t t t fr t t t tt't f t t ft f t tt t t t t t t tat t f t t t tt t t tt f t sf fr t t t' t t ft tt ft t t t ft 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FOAM 0113 (02I83)
78 1 4114111 t 1 1 11 1 1 1 1 1 tf1 1 t at t 1 41 1 1 t 1 1 1 1 tt 4 1 t 1 1 4 1 1 tft 1 1 t 1 1 1 4 14 1 1 1 1 1 1 1 1 1 1 1 t 4 1 1 4 1 4 1 1 1 1 1 t 1 4 t 1 4 1 1 1 1 1 1 1 1 4 '1 11 tf4 4* 1*1 41 t1t14ttt1 2 NUTECH CAROLINA POWER 8r LIGHT COMPANY PRI SIN 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4
- PLANNING 41111 t 1 4 1 t ft 1 1 t 4 1 1 1 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 77 ASME SECTION XI . 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 1 1 111 1 1 1 4 11 1 1 1 tf1 st 1 11 tf 1 1 4 f 11 t 1 41 1 1 1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tf t tf 414 1 1 1 f4 tf1 1 1 1 t*11 1411 11 1 4 **111 141 1 1 t1 1tt4 t tf1 f 1 11 1 11 1111 DATE 11 1 1 1 tf88/01/12 1 1 t f1 1 11 4 44 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6. 40 RV THREADS IN FLANGE (> 2")
atty 1 1 1 1 1 1 4 1 1 t 1 41 t 1 11 1 t f 1 f 4 1 1 1 1 t1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 t 1 1 tf1 1 tt 1' 12 13 1 t1 1 1 4 1 4t t tt t4 1 1 1 1 1 1 1 1 1 t*141 1 1 t 1 1 f 1 1 1 1 1 1 1 1 1 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND RE@ST TIONS NOTES 19 ssasasasaasaaasaaa saaaa asaaasaassassss sasaas sasaasaasssssssa sssaa sssaa asa sass asassa sas asaass ssssss ssasas 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV"001 22 23 RVFT-33 FLG THR UT-RVS 1-3-06 ,
6.000 57.37 NO 24 UT-00 25 26 RVFT-34 FLG THR UT-RVS 1-3-06 , 6.000 57.37 NO 27 UT-00 28 29 RVFT-35 FLG THR UT-RVS 1-3-06 6.000 57.37 30 UT-00 31 32 RVFT"36 FLG THR UT-RVS 1-3-06 6.000 57.37 33 UT-00 34 35 RVFT-37 FLG THR UT-RVS 1-3-06 6.000 57.37 NO 36 UT-00 37 38 RVFT-38 FLG THR UT-RVS 1-3-06 6.000 57.37 39 UT-00 40 41 RVFT-39 FLG THR UT-RVS 1-3-06 6.000 57.37 42 UT-00 43 44 RVFT-40 FLG THR UT-RVS 1-3-06 6.000 57.37 UT-00 45 46 4f 141441 41 4ttf 1st 14 1 11 11 4*'4114t44ttf tf*f1 t f41 f tf41 1411 1 1 f 4 st f4 f4 41 414111 f tf1 f 4 114ttrf 11 st 4 tf111 11 111141rtttt'trf tt 47 48 49 50 51 52 53 I 54 55 56 57 58 59 60 FORM 0113 (02I831 1
82 111 t 1 1 t 1 1 1 f t 1 1 1 1 1 1 1 1 1 1 t 1 1 1 t 1 tf 1 1 1 1 1 1 t 1 1 t f 1 1 t 1 f 1 1 1 t t t f t ft 1 t 1 t 1 t 1 t t 1 t t 1 1 1 1 1 f 1 '1 111 t11111t1t1111t111 t111 1 111111111t11 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 1 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT
1111111 1111 11 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88 01 12 / /
t t 1 1 1 t 1 1 1 1 1 1 1 1 1 t 1 1 t 1 1 t t 1 1 1 1 1 t 1 tt 1 1 1 t 1 1 1 1 1 1 t 1 1 1 1 1 1 1 f 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t t 1 1 1 1 1 1 1 1 t 1 1 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6. 50 RV CLOSURE WASHERS, BUSHINGS (> 2")
f1 f 1 1 1 f1 t tftf 1 1 1 1 1 1 1 1 t tt 1 11 1 1 11 1 f 1 1 1 1 1 1 t 1 1 1' tt t 1 1 1 1 1 t 1 1 1 off 1 1 1 1 1 11 1 tf 1 1 1 1 1 1 t 1 tf 12 13 1111 1111 1 t1111 111111111 1 1 111 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES '$
19 $ $ $ $ $ $ 'SSSSSCSCCSSSSSSS $$$$$$$$$$$$$$~ S~S~$$ $ $ $ $ ~ $ $ ~ $ $ ~ 'R ~ S ~ $ $ $ ~ R ~ SSC ~ S $$~S ~$$$ $$$$$$ $$$ $$$$ RSS S $
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 RVWSH-51 WASHER VT-1 6.000 57.37 NO 24 25 RVWSH-52 WASHER VT-1 6.000 57.37 NO 26 27 RVWSH-01 WASHER VT" 1 1-1-01 6.000 57.37 NO 28 29 RVWSH-02 WASHER VT- 1 1-1-01 6.000 57.37 NO 30 31 RVWSH-03 WASHER VT-1 1-1-01 6.000 57.37 32 33 RVWSH-04 WASHER VT-1 1-1-01 6.000 57.37 34 35 RVWSH-05 WASHER VT-1 1-1-01 6.000 57.37 36 37 RVWSH-06 WASHER VT-1 1-1-01 6.000 57.37 NO 36 39 RVWSH-07 WASHER VT-1 1-1-01 6.000 57.37 NO 40 41 RVWSH-08 WASHER VT-1 1-1-01 6.000 57.37 NO 42 43 RVWSH-09 WASHER VT-1 1-1-01 6.000 57.37 44 45 RVWSH-10 WASHER VT-1 1-1 "01 6.000 57.37 NO 46 47 RVWSH-11 WASHER VT-1 1-1-01 6.000 57.37 NO 48 49 RVWSH-12 WASHER VT-1 1-1-01 6.000 5I.3/ NO 50 51 RVWSH-13 WASHER VT-1 1-1-01 6.000 57.37 NO 52 53 RVWSH-14 54 1 1 1 tf 11111 tf1 1 1 11 f tft*ttfWASHER 1 VT-1 1-1-01 f1 f1 tttf f1ftt*111 t f1 tttttt tf1 ttff1t f1 ttfttttttf11 111
. 6 000 57 37 1 ttt tt ttt ttt ttttttt ttt tt tt 11 NO ttttttf tf1 1 55 56 57 58 59 60 FOAM 0113 (02I83) 0
84 tt t t
- t t t tt t t t t t t t t t tt ttt t t tt tt t t t tt t t t t t t t t f t tt t tt t t t t t t t t t t tt t t t tt t t t t t t t tt t' t t t t t t NUTECH CAROLINA POWER Er LIGHT COMPANY PR IS IM SHEARON HARRIS NUCLEAR POWER PLANT UNIT PLANNING t tat t tt tt t tt t t t COMPONENT'ISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 83 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 tt tt t t t t t t t t tt tt tt t t t t tt t t t t' tt THE t t tt SUMMER t t tt t t t t t t t t t t t t tt t t t t t' t t t t t t tt t t' t ttt ttt tt t t t t t t t t t t t t t t t t t t t' 't t t' 't t t t tt 4r 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6. 50 RV CLOSURE WASHERS, BUSHINGS (> 2")
12 13 t t t t t t t t t t t t t tt tt t t t t t tt t t t t t t t t t t tt
- tt t ttt t t t t t t t t t t t t tt t tt ttt t t t t t t tt tt t t tt t t t t t t tt t t tt t t t t t' t t t t t 't 't t t *'tt tt t t t 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssssssssssssssssssssasas ssaas asa assas sssaas ssasssssassassss assas sasss -=-===== ===== ss a sass ssssss ssasss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I -RV-001 22 23 RVWSH-31 WASHER VT" 1 1 "2-03 6.000 57.37 NO 24 25 RVWSH-32 WASHER VT-1 1-2-03 6.000 57.37 28 27 RVWSH-33 WASHER VT-1 1-2-03 6.000 57.37 NO 28 29 RVWSH"34 WASHER VT-1 1-2-03 6.000 57.37 30 31 RVWSH-35 WASHER VT-1 1-2-03 6.000 57.37 NO 32 33 RVWSH"36 WASHER VT-1 1-2-03 6.000 57.37 NO 34 35 RVWSH-37 WASHER VT-1 1-2-03 6.000 57.37 NO 38 37 RVWSH-38 WASHER VT-1 1-2-03 6.000 57. 37 NO 38 39 RVWSH"39 WASHER VT-1 1-3-06 6.000 57.37 NO 40 41 RVWSH-40 WASHER VT- 1 1 "3-06 6.000 57.37 NO 42 43 RVWSH-41 WASHER VT-1 1-3-06 6.000 57.37 44 45 RVWSH-42 WASHER VT-1 1-3-06 6.000 57.37 46 47 RVWSH-43 WASHER VT-1 1-3-06 6.000 57.37 48 49 RVWSH-44 WASHER VT-1 1-3-06 6.000 57.37 50 51 RVWSH-45 WASHER VT-1 1-3-06 6.000 57.37 52 1"3-06 57.37 t t ttt t t tt t tt t tt t t t t t ttt t t t t t t ttt t t t tt tt t 6.000 53 RVWSH-46 VT-1 NO 54 t t t t t t t ttt t tt t t t tt t tt t tt t WASHER tt t t t't t tt t t tt tttt t ttt t ttt t tt t t t t t tt t t t t t t t t t tt t t t t t t 55 58 57 58 59 60 FOR 0113 (02I83) 2 .
85 444 4 t4tff4tff tttfttfttttttat ttt4ttttttt t tt tttf aft ttttt tttttttt44444 f 444444 44 f 4 4tf*fttttf4 4 tttttftf4 4t4 4 tf4 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 4 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 4 44 44 4 444 4 444 4 4444 4 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 84 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DAT E 88/01/12 f t t t t f t t t t t 4 4 4 4 4 4 fr 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 t. 4 4.4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4
- 4 9
10 CATEGORY 8"G-1 PRESSURE RETAINING BOLTS OREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. 86. 50 RV CLOSURE WASHERS, BUSHINGS () 2")
12 13 4 t4 4 4 4 4 '4 4444444444444 ft 4 t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 t 4 4 4 4 4 4 4 t 4' 4 t44 444 '4 4 '4 44444444444444444444 '4 *4 4 4 4 4 4 4 4 t 4 '4 4 4 4 4 4 4 4 4 4 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE" OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sssaassssaasassssssssrss raassasassaasas ararat asaaaaassassaaas ===== arras asssrsas ararat sss saaass sssssa aassss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I -RV-001 22 23 RVWSH-47 WASHER VT-1 1-3-06 6.000 57.37 .NO 24 25 RVWSH-48 WASHER VT-1 1-3-06 6.000 57.37 28 27 RVWSH-49 WASHER VT-1 1-3-06 6.000 57.37 NO 28 29 RVWSH-50 WASHER VT-1 1-3-06 6.000 57 3I ~ NO 30 31 RVWSH-51 WASHER VT-1 1-3-06 6.0QO 57.37 32 33 RVWSH-52 WASHER VT-1 1-3-06 6.000 57.37 34 35 RVWSH-53 WASHER VT" 1 1-3-06 IG.OQQ 57. 37 36 37 RVWSH-54 WASHER VT-1 1-3-06 6.000 5I 3I ~ NO 38 39 RVWSH-55 WASHER VT"1 1-3-06 6.000 57.37 NO 40 41 RVWSH-56 WASHER VT-1 1-3-06 6.000 5I 37 ~
42 43 RVWSH-57 WASHER VT-1 1-3-06 6.000 57.37 NO 44 VT-1 1-3-06 6.000 57.37 ttr'tfttttf44444 444444444444 f4tffrtftat ttt4 4 4 tttftf tan 4tf tttt*444 444 44 ttftf ttftttf4 44 4 tttfttf44 ttttfttttf 45 RVWSH-58 WASHER NO 48 ttrttf It*4444 tl!444 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 t02I831
86 t t t t at t t t t t t t at t t t t t t t t t t t t t t t t t t 4 t t t tt t t t tt t t tt t tt t t t t t t t t tt t tt t t t tt t t t t t t t t t t t t t t t t t t t tt t t t t t t t t t t t t t t t tt t t t NUTECH - CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 t
t PLANNING 't t t t t t t t t 't t t t' t t t t t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE . 85 8 ASME SECTION,.XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 8 *tt t t t t tt t ttt t t ttt t t tt t t t tt t tt tt tt t t tt t t t t 1 t tt t t t t t t t t t t t t t t tt t tt tt t t t t t t t t t t tt tt tt t t t t tt t t t tt t tt tt t t t tt t tt tt t tt t t t t t 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6. 60 PRZ BOLTS AND STUDS (> 2")
12 13 t t t t t t t t t tt t t t t t t tttt t t t t tt t t t t t tt t t t t t t t tt t t t t t t t t t t tt tt t tt t t t t t t t ttt tt t t t t ttt t t t t t t t tt t tt t tt t tt t t t t t t t t t ttt t t tr tr 14 15 DONE 18 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssasssasasasassssasasasa aaaasassaaassas sassss assssasaasass aa aa asaaa aassaaas sss ====== as assas ~
20 2'I SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT 24 APPLICABLE ttttttttttttttttttttttt*ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt'ttttttttttttttttt NO COMPONENTS 25 28 27 28 29 30 31 32 33 34 35 38 37 38 39 40 41 42 43 44 45 48 47 48 49 50 51 52 53 54 55 se 57 58 59 80
87 t'at t't t't t t tlt tl t ttltl $ tat tittle t st l tlt t t tl f ftl l t t t*l illtt tt t l t fr t still et t t t*tlst t littt t sf f$ t $ tf$ tlt t fst t t f t*ttt NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1
f ttttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 86
- ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t t ft t 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t l f fitt l t t lt f t t t t st t et tt t t le t t t t $ $ **tla t $ t st st *t t t f t t f l t t l*t$ t t t t l t l t t t $ ll t $ t t f t f t l t $ l t $ l' tt $ t t t t t $ $ DATE l t t t l tt $
9 10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6. 70 PRZ FLANGE SURFACE WHEN CONNECTION DISASSEMBLED () 2")
12 13 stall'tet fr t t tt t l t t lett t t t elf et $ llt $ $ t t ltt tt tltt t t $ t ll t $ $ t tifft tt t t t ill mt t t t t le t t tlat t t l et mt t t l f t t le t t f littsf l et t tft 14 15 DONE 18 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 ssssssassaaaaassasasssrs esssmsaeeassssa arrear ===- mr sssraass sear sears ssassess ====== -== sesame smarm- seamer 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT 24 APPLICABLE st lt l*tl tf llt l f ffalls ft f llfitt*ll t l t t llt t t t sf t tlt f l tlf
- NO COMPONENTS
$ $ et *f f t f t $ t t tt $ ff tiff$ t el t t t l t t t t t t f le t $ t 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 102I831
88 1 1 t111111 t111t1111 1111 1' 111 t 1 1 1 t 1 1 1 1 t t 1 1 1 1 1 1 1 1 t 1 t tt 1 1 t 1 1 1 1 1 t t t 1 t 1 1 t 1 1 1 1 t 1 1 1 t 1 t 1 1 1 t 1 1 1 1 1 1 t 1 t t 1 1 1 tt t 1 tt 1 1 t 1 1 1 1 1 1 1 t 1 t 1 1 1 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT " UNIT 4 PLANNING 1 1 1 1 1 1 1 1*1 1 1 1 1 1 1 1 1 1 5 COMPONENT-.LISTING ANO ISI 10 YEAR PLAN: 835-01 PAGE 87 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 8 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1' 1 t 1 t 1 1 t 1 t 1 1 t 1 1 1 1 1 1 t t t 1 *1 t t t 1 1 1 1 1 1 1 1 1 1
- 1 1 1 1
- 1 1 t 1 1 t 1 1 1 1 1 1 1 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. BG. 80 PRZ NUTS. BUSHINGS, AND WASHERS (> 2")
12 13 1 t t11
'1 '1 1 1 1 1 1 tt 1 1 1 '1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t. 1 1 1 t 1 t 1 1 1 1 1 1 1 t 1 t 1 1 1 1 1 1 1 1 1 1 1 1 t t 1 1 1 t t t t t t 1 t 1 1 1 tt 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1' 1 '1 1 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV'RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND RFOST TIONS NOTES 19 asasasaaasssasssassassaa sssaaasaaasasaa ass sa asses assassssas seats eases easseass assess sea sse 1 ~ 1 sass 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT APPLICABLE NO COMPONENTS t t t t t 24 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 4 1 1 1 1 t t1 1 11 1 1 1 1 1 1 1 1 1 11tt 1 1 t1 1 1 1 1 1 1 1 1 1 1 11 11 11 1 1 1 1 1 1 1 1 11 t1t1 1 1 1 1.
25 26 27 28 29 30
'2 31 33 34 35 38 37 38 39 40 41 42 43 44 45 4e 47 48 49 50 51 52 53 54 55 56 57 58 59 eo FORM 0113 (02I831 1
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91 tf 4 4 4 ff4 4 4 4 444 t f ft 4 4 f 4 4 4 4 4 tt f t 4 4 t t t t t 4 4 4 4 4 4 t 4 t t f4 t t 4 4 t t tt f t 4 t t t t t t tt f t t t ffft f ft t t t t t 4 t t t tf 4 4 4 4 f 4 4 4 t if4 f 4 4 4 4 t 4 4 4 f 4 4 f 4 f 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT " UNIT 1 4 PLANNING t
't 4 4 4 t 4 4 t rlt 4 'f 4 4*ft 4 4 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 90 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t 88/01/12 ff tf f ffff tttff tf tttf f4 tttf tfttfftfftff4 tttf tffttt'tttfttfftftftttftttttftttt'tfftffDATE fttff4 4
~
THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 7
8 tttffrlrtrlrffrftffttfttf tffttfrlttf 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. 86. 110 SG NUTS, BUSHINGS, AND WASHERS (> 2")
ttftf4 4 ttff t f4 tftftff 4 4 4 tftf 4 ff tftff t tfttttftf tttttt 4 tttttftftfttftf tttf4 4 tt t 4 tt*f4 4 4 4 4 4 tf4 f 4 tttf4 4 tffthm fff ttt 12 13 4 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ $ $ $ $ $ 4$ ~ $ 4444 ~ $ $ ~ $ 4444 $ $ ~ $ $ $ ~ $ $ $ $ $ 4$ $ 4$ $ $ 4 ~ $ $ ~ 4$ $ '4$ 4 ~ $ $ 4II 4~$$4 ~$$$$ ~4~4~4~4 4~$$~4 ~$4 ~ $ 4444 $ 4 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT APPLICABLE NO COMPONENTS 24 t
- 4 4 4 4 4 4t f4 4'4 f tftf4 4 4 4 tft f tfff 4 t 4 4 4 4 ff 4 t 4 4 4 t 4 4 4 t t t 4 t t 4 t 4 4 4 f *4 tft ft 4 4 4 f f 4 4 t t 4 t 4 t 4 4 4 4 4 t 4 tt f t 4 4 4 4 4 4 t t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 f '4 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 80 FORM 0113 (02I83)
t'HE 92 taft tftfttlftff t st ttf f atf f at at ttttttt ttttttttttttsf tfttt at f ttttttttttttttttt t ttttttftt tfst tttf t tat tttttf ttft tat 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRI SIN SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3
4 f PLANNING f tf f tat at ff f tff f tf f COMPONENT LISTING ANO ISI 10 YEAR PLAN: 83S-01 PAGE 91 f ASME SECTIONXI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 SUMh1ER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 ff f f t tl t' f ltd t ffff
- f *tf ft f t't t f f f f at f t at f f ft t f ft f ff ft t at f f f ft tat tt t t f t t t t't t lfl f ff tf f 9
10 CATEGORY 8-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. 86. 120 HX BOLTS AND STUDS (> 2 )
12 13 f f sf sf ttttf fat fff fftat ttftaft'ttttftat f tat f f tttttttttfttftttttttttttttttttffttftff tttff tttff tf sf tttf ttf*ttttttftttff tf 14 15 DONE 18 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 $$$$$ $ $$$ $$$$$$$$ $$$$$$$ $~$ sass $$ $~$ $ $ $$ '
aaaasasa ssssss saa aassss $ $ $ $ $ $ $ $ $ $ $ $
20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT 24 at tfAPPLICABLE f f tff t fff tt*a f ft ft f f fNO COMPONENTS t fff t f fft f ft tff sf t t**ft f t a*t fft ltd ft tt tf f at l tf tfff tf t f t f f at tt t tt t t tf sf f t t t ft ft t t t'f ff f ffff sf f 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 4e 47 48 49 50 51 52 53 54 55 se 57 58 59 80 FORM 0113 (02I83) 0
93 1 1 1 1 1 1 1 1 <<1 1 1 1 1 1 1 1 <<1 << t t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t P t 1 1 <<<<<<1 1' 11 <<<<1 1 <<1 <<* 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1
- t 1 1 1 1 1 <<1 1 1 1 1 1 1 1 1 t 1 t 1 1 1 1 1 1 1 1 '1 <<1 1 2 NUTECH CAROLINA POWER Er LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 92 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA. INTERVAL 01 ONLY DATE 88/01/12 t
1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 t 1 1 1 1 1 1 1 1 t 1 1 1 1 << t
- 1 1 1 1 <<1 1 1 1 1 1 <<1 1 <<1 1 1 1 1 1 1 1 t <<<< t 1 1 1 <<1 1 1 1 1 <<<<' 1 1 1 1 1 <<1 <<<<<< t <<<<<<1 1 1 <<1 <<1 <<'1 <<1 1 <<1 1 1 <<1 1' 1 1 1 <<1 1 1 '<<
9 10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. BB. 130 HX FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2")
12 13 1 1 1 1 *1 t t 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1'* 1 1 1 1 1 t 1 t 1 1 1 1 1 1 1 1 t 1 1 1 1 <<1 t 1 1 t 1 1 1 1 1 1 1 1 t 1 1 1' 111111111111111 t1 1 1 1 1 1 1 1' 1 1 1 1 1 1 <<1 1
- 1 1 1 1 1 <<1 1
- 1 1 1 1 1 1 1 1 1 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 $ $ $ $$$$$$$$$$$$ $$ $~$$$$$$~$$$$ $$$$$$ $$$ $$~$ ~$$$$$~$$ ~$$$$ $$$$$ $$$$ $$$$ $$ $$$ ~ $$$$ $$$~$$ $$$ $$~
20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT APPLICABLE NO COMPONENTS 24 1 1 1 1 1 t tt t t t 11111 111 1 1 1 11 11 1 11111 1 1 1 1 1 1 1 t t t t 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 t 1 1 t t t t 1 t t t 1 1 1 1 t 1 t 1 1 t 1 <<1 1 1 1 1 1 1 1 1 1 t 1 1 <<1 1 << t 1 1 1 1 t 1 1 1 1 t t 1 1 1 1 1 1 t 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
94 1
t It'ift t t tt t t tt t t t tt t t tt t t t t fthm't t t t t't t t t t t t tt t tt ftt t tt tt t f t f tt t t t t t t t t t t t tftff fitt tf ttf t tt ft ft t f ft tfift t t t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3
4 PLANNING 1
tttff tff f tffff ttft 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 93 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 ~
tt t 't t t ft 'f t f 'f t t tt t t t tr f tr f t t t ft t t t ttf t ttt t t t t tt tt t t t t t t ft t t ft ttff t t f t f t tf t t t t tt ftt t ft tt t f t f t t ttt tt t t t ff 't t t t tt t t t t t t t'
9 10 CATEGORY B-G" 1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. BS. 140 HX NUTS, BUSHINGS, AND WASHERS (> 2")
~ 12 13 tff t t ft tt ttt t t t t tt f f f t ftt t t t t tt t tfft t t fff t t t t f tt t ft t t t t t ttt t f 4 t t t Std t t f t t Art t f tft t tt t tt t t tt t f t tt t t t t tt ftt ft t tt t fr 14 15 DONE 15 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM DESCRIPTION TYPE OULED -INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 18 19 f~ f ~ f' ffSffS NUMBER 5 ff ~ f' f f ff ff f ff f f f f f f f ff Iffff
~ ~ ~ ~ Zf f fff fff fS f f f 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT 24 APPLICABLE ttttttttttf ttttftttfttttttttftttfttt'ttf*ttttttttttt*tfttttfttttfttttfttttttttftttt'tttttttfftftfttttttttttttttttfttftf NO COMPONENTS 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 58 57 58 59 60 FORM 0113 (02I831 0
95 1
tttttttttttttftttrlrf tttttftffttfttttftttttttttff tttftttttttttttttfttftttftfttttttttftttttttttttfttf sf f1 tt1 1
NUTECH CAROLINA POWER & LIGHT COMPANY PRI SIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1
- PLANNING 1 t1 '1 111 t1 Ilt 1 111 f tt 1 tlt 1 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 94 ASME SECTION XI, 1983 EDITION THROUGI.I ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 1 f 1 1 1 1 ft 1 1 f 1 1 1 1 1 1 f 1 1 t f t 1 1 1 1 1 1 1 1 1 1' 1 1 1 1 1' 1 1 1 1 1 1 1 1 t ff f f t t f 1 1 1 1 1 1 1 1 1 1 1 1 1' 1 1
- 1 I 1 1 f **ff 1 1 1 1 1 1 t 1 1 1 1 1 1 ft t 1 f 1 1 f 1 1 1 1 1 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 12 ITEM NO. B6. 150 PIPING BOLTS AND STUDS ()2) 13
- 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 t t 1 1' 111111 t 1 1 1 1 1 1 1 1 1 1
- 1 1 1 t 1 1 1 t 1 t 1 1 1 1 1 1 1 1 1 1 1 1 t t 1 f 1 1 1 1 1 tt 1 t 1 1 1 1 t 1 1 1 1 *1 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 saasssasaaassssaasasssss aasasssssxrssrx s rrrr axrasx ss s saaaa arras ssrrasaa ssasas ass rarsas ss 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 APPLICABLE
- f1f1 tst st sf 11 1 ttttftat ttftf tf ttftttt tat tat 1 sttttttt ttttttt1ttfttt1 f1tt tttttt tttf*11tf 11111tt ttt tttf1 11 st tt f ttf1 1st t 23 NOT NO COMPONENTS 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 102I83)
1 t Ar 11 t 1 1 1 1 1 1 t 1 t 1 t 1 1 t 1 1 tt 1 1 t 1 t 1 1 t t tt 1 1 1 1 t t t 1 1 t 1 1 t 1 t 1 1' '1 111111111 t1 1 1t1 t1 t1 1 1 1 11 1 t111 t1 1 1 1 1 1 1 t '1 1 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 1 1 1 1 1 1 1 1 1 1 't 1 1 1 1 1 1 1 1 COMPONENT LISTING ANO ISI 10 YEAR PLAN: 83S-01 PAGE 95 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
- THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 1 f*1't sf tf 1 1st 11 11 1 1111111 tftttf ttttttsf 1st tt f 1 ttstt tf tf 1 tf1 1 tttfttttftf 1 ttt sf 1 ttttf 1 1 1 1 tfst f1f 1 ttftfst fr1Ar*ttfrttt A fr 1 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6. 160 PIPING FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2A) 12 13 t 1 f 1 f 11 1 1 1 1 1 t 1 1 f 1 1 f 1 t 1 t1 1 f tt 1 1 tat tt f t1f 1 1 1 1 f 1 1 t 1 tt 1 1 t 1 t t 1 t 1 4 f t 1 tArt1 t 1 1 1 1 1 1 1 1't 1 1 f 1 f 1 t 1 1 t 1 1 Art 1 f f 1 1 1 1 1 1 1 1 11 t t 1 1 1 1 t 1 f 1 1 1 t 14 15 OONF.
16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 araarrsssasrsrsssssarsss ssaassssssssass = ~ s as arras s ~ s s r ~ assr a sf fr:rAr rcarsa rss ararat s .ra=- starrs 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT APPLICABLE COMPONENTS 24 11 t t t 1f 1 1 1 1 1 1 1 t tf1 1 NO11 t t 1 f1 1 1 t sf 1 t t Ar 111 sf 1 t 1' 11111 ft 1 1 1 t t1 1 1 1 t 1 1 1t t1 t 1 1' st 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 t1 1 1 1 1 1 1 1 1 1 1 1 f 1 1'1 1'
25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 0
98 1 11 111111 1 1 11 t 1 1 1 1 1 1 1 1 t 1 1 1 1 t 1 t 1 1 1 f tt 1 1 t 1 1 1' 1 t11 1 11 11 11 1 t1 1' 1' 1111 t 1 1 1 1 1 1 1 1 1 1 1 t 1 1 t 1 t 1 1 1 1 t 1 1 1 1 1 1 1 1 t 1 1 1 tt 1 1 1 t 1 t 1 1 1 *1 1 t t 1 t 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 1 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING 11t t*tt tt *t 1 11 11 1 11 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 97 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
,7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 .
8 tt 11111 tf 1 1 1 f 1 1 1 t 1 1 1 1 1 f 1 1 t fr t t t tt t t 1 1 1 1 t 1 1 1 11 1 1 et 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1 t 1 t 1 1 1 1 1 t 1 11 1 1 1 1 1 t 1 1 1 1 t1 1 t 1 1 1 1 1 t 1 1 1 1 1 1'1 1 1 1 1 1 t 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 1 11 ITEM NO. B6. 180 PUMP BOLTS AND STUDS .(> 2")
12 13 sttf 11 1 11 tfat ttttf ttf1 1 1tf tff tf1ttf tttttttt1 1 fattest'tttttt tet ttttf tf t tftt f1 et tf1tttf tet f1 1tf tttftt taft tet tttftatttt et 14 15 DONE 18 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 asssssrassasasssasasssaa reassess assess assess sassssssssssseae asses arras arrester s sara ass saasrr assess rasaaa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RCP-01 22 23 RCPA"FBOLT-01 HOS BLT UT-OUT 1-3-06 NO 24
~ 25 RCPA-FBOLT-02 HOS BLT UT-OUT 1-3-06 NO 26 27 RCPA-FBOLT-03 HOS BLT UT-OUT 1-3-06 NO 28 29 RCPA-FBOLT-04 HOS BLT UT-OUT 1-3-06 NO 30 31 RCPA-FBOLT-05 HOS BLT UT-OUT 1-3-06 NO 32 33 RCPA-FBOLT-06 HOS BLT UT-OUT 1-3-06 34 35 RCPA-FBOLT-07 HOS BLT UT-OUT 1-3-06 36 37 RCPA-FBOLT-08 HOS BLT UT-OUT 1-3-06 38 39 RCPA-FBOLT-09 HOS BLT UT-OUT 1-3-06 NO 40 41 RCPA-FBOLT-10 HOS BLT UT-OUT 1-3-06 42 43 RCPA-FBOLT-11 HOS BLT UT-OUT 1-3-06 44 45 RCPA-FBOLT-12 HOS BLT UT-OUT 1-3-06 46 47 RCPA-FBOLT-13 HOS BLT UT-OUT 1-3-06 48 49 RCPA-FBOLT-14 HOS BLT UT-OUT 1-3-06 NO 50 51 RCPA-FBOLT-15 HOS BLT UT"OUT 1-3-06 52 UT-OUT 1-3-06 53 54 RCPA-FBOLT-16 tttttttftttttff1f1 f1 tttf ttttttttf HOS BLT ttttttttftttttttttf1 ttttf tf ttttttttttf1*1 ttttttftat tttttttttttttttttttftttttttt*11 NO 55 56
'57 58 59 60 FORM 0113 (02I83)
101 444 44 4 4 tt t 444 4 4 4 t4 4 4 4t 44444 444 4 tttt 44 4 4t 4tt t 4 4 tt44tt 4 tt tt 4 t4 4t 4f tf444 4 4 4 t*4t4 4t 4 t4t t tf4 t4 4 4 4 444 4 4 tttt 4 4 4 4 4 tt 4t t4 4 4 4't 4 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1
- PLANNING 4444444444444444444 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 100 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA. INTERVAL 01 ONLY 88/01/12 4* 4 4 4 4 4 4 4 4 4 4 4 tr 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 t 4 4 4 4 t 4 4' 4 4 4 4 4 4 4 4 4 4 4 4' tt 4' 44 t 4 4 4 4 4 *4 4 4 4 4 4 4 t 4 4 4 4 4 4 tr 4 4 4 4 4 4 DATE 4 4 tl tr 4 4 4 4 4 4 4 4 4 4 4 4 9
10 CATEGORY 8-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ll ITEM NO. B6. 180 PUMP BOLTS AND STUDS (> 2")
12 13 44444 t 4 t 4 4 4 4 4 4 4 4 4 4 4 4 t. 4 t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4
- 4 4 4 4 4 4 4' 44444444444 t 4 4 4 4 4
- 4 4 4 4 4 4 44 4 4 4 4 t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM 'CHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT . INT (IN)'$ (IN) ACCESS SELECT IND REOST TIONS NOTES 19 $ $ $ $ $ $ $ $ ~ $ $ $ ggggggggg $ $$ '
ggggggg ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $$$$ $$$$$ $$$$$ $ $ $$$$$$ $~$ $$$$$$ $~$$$$ $$ $
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RCP-01 22 23 RCPC-FBOLT-01 HOS BLT UT-OUT NO 24 25 RCPC-FBOLT-02 HOS BLT UT-OUT NO 26 27 RCPC-FBOLT-03 HOS BLT UT-OUT NO 28 29 RCPC"FBOLT-04 HOS BLT UT-OUT NO 30 31 RCPC-FBOLT"05 HOS BLT UT-OUT NO 32 33 RCPC-FBOLT-06 HOS BLT UT-OUT 34 35 RCPC-FBOLT-07 HOS BLT UT-OUT NO 36 37 RCPC-FBOLT-08 HOS BLT UT-OUT NO 38 39 RCPC-FBOLT-09 HOS BLT UT-OUT NO 40 41 RCPC-FBOLT-10 HOS BLT UT-OUT 42 43 RCPC-FBOLT-11 HOS BLT UT-OUT NO 44 45 RCPC-FBOLT-12 HOS BLT UT-OUT NO 46 47 RCPC-FBOLT-13 HOS BLT UT-OUT NO 48 49 RCPC-FBOLT-14 HOS BLT UT-OUT 50 51 RCPC-FBOLT-15 HOS BLT UT-OUT NO 52 53 RCPC-FBOLT-16 HOS BLT UT-OUT NO t t t t t t t 54 4 '4 4 4 4 4 4 '4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 '4 4 4 4 4 4 4 4 4 4 4 4 4 55 56 57 58 59
.80 FORM 0113 102I83)
102 I*Itttttttftttfttttfttttt tfttttttftf1tttt1ttf t1tt1 11 1 I tttttttttftf11 111'f1 t1ttf1 1111 tttttttfttff1 1f ttfI 1111111tf It ttf 1 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT UNIT I PLANNING 1
1111111111111tf ttft 5 1 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 101 6 ASME SECTION XI, 1883 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 ttt1 f1 I t ttftfIftfItft tfIfIItf'ttff tfIt t III111 tt fIIII fftIII taft tttttf ttftfI It f1 tf fIts 1 t 1 tf1 I f1 1st tt I t ttfI f1 tftftf I tt1 tf 7 DATE 8
9 10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ll ITEM NO. B6. 180 PUMP BOLTS ANO STUDS (> 2")
12 13 11 I 1 1 f 1 I 1 1 1 I 1 1 1 1 1 I 1 1 I' 1 I 1 1 1 1 tt 1 t11 1 t 1 tI 1 1 t 1 1 I 1 1 1 1 1 1 I 1 1 1 1 I 1 t 1 I 1 I f 1 1 1 1 1 1 1 1 f tt 1 t I 1 t I 1 1 1 tI I I 1 1 t 11 1 I 1 I 1 I 1 f It I t t I 1 1 1 t 1 't 1 1 1
'1 l4 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 r COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 saassaaasasssassssssasss assssssssasssss ssasas saassssssasssaa- ---== =-=== ======== sss sass aaasas ssasss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RCP-01 22 23 RCPC-FBOLT-17 HOS BLT UT-OUT NO 24 25 RCPC-FBOLT-18 HOS BLT UT-OUT 26 27 RCPC-FBOLT-19 HOS BLT UT-OUT NO 28 29 RCPC-FBOLT-20 HOS BLT UT-OUT NO 30 31 RCPC-FBOLT-21 HOS BLT UT-OUT NO 32 33 RCPC-FBOLT-22 HOS BLT UT-OUT 34 35 RCPC-FBOLT-23 HOS BLT UT-OUT NO 36 RCPC-FBOLT-24 37 I*f1 If1st tttttfttfHOS tttfI IttItftfUT-OUT ttfBLT tttfttfttf1111 ttfttttff1 ttttfttftttttf'f1ttttftttf1ttf NO ttfttII'tttfttttttttftt 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 s 57 58 59 60 FORM 0113 102I83)
- 0
103 f tf tat f f tftff tff f ff tftttfffff f f tf tt t f f f ff ft f tat f fff ttt t f tt f tt tttttfttff f tttft f tttttt tttftttt f f f ff tttff f f f ff f fffff tat t NUTECH CAROLINA POWER Er LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING t at t tt t t t t t t t f COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 102 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 t ft ftf t t tfft t ft t 't t ftt t 't f t t f t f ft fft t t t t t f f t t t ftt t tf tft t tt t t 't ft t t t tf f t ft ft t tt tt 'f f f t t' t t t t ft 't t ft f' DATE t t t f ft t t t f tt f 't tt 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6.190 PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2 )
12 13 t tt t t f t at f ff ff aft aft t tat t t tttft t ft t t t fr t t t f f fffff t f f ft t t t t f at tt t tan fr tat t tat f tt sf at t t f tt t t t ft ft t t t t t t ft t f t f ff t f at tftf 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 ssasssssssssssssasssasss sasrssarssassss strata aaaaasaasasxar r sa as sassa sssaasar ssaass sas rasssa sassar sa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RCP-01 22 23 RCPA-FTHR-01 FLG THR VT-1 1-3-06 NO 24 25 RCPA-FTHR-02 FLG THR VT-1 1-3-06 NO 28 27 RCPA-FTHR-03 FLG THR VT-1 1-3-06 NO 28 29 RCPA-FTHR-04 FLG THR VT-1 1-3-06 NO 30 31 RCPA-FTHR-05 FLG THR VT-1 1-3-06 NO 32 33 RCPA-FTHR-06 FLG THR VT-1 1-3-06 NO 34 35 RCPA-FTHR-07 FLG THR VT-1 1-3-06 NO 36 37 RCPA-FTHR-08 FLG THR VT-1 1-3-06 NO 38 39 RCPA-FTHR-09 FLG THR VT-1 1-3-06 NO 40 41 RCPA-FTHR-10 FLG THR VT-1 1-3"06 NO 42 43 RCPA-FTHR-11 FLG THR VT-1 1-3-06 NO 44 45 RCPA-FTHR-12 FLG THR VT-1 1-3-06 NO 4e 47 RCPA-FTHR-13 FLG THR VT-1 1-3-06 48 49 RCPA-FTHR-14 FLG THR VT-1 1-3-06 NO 50 51 RCPA-FTHR-15 FLG THR VT-1 1-3-06 NO 52 RCPA-FTHR-16 VT-1 1-3-06 53 54 tt fr t tt t fr fr t aft t t f tft at tlatFLG THR NO t ff fr ft at f f t f fr f tat t f at t t t f *ft at fr fr ft ff sf aft t tt ft t f fr t t f t t tff frff t f f t at f t fr tat at t sf tt fr t at 55 ee 57 58 59 60 FOllM 0113 102I83)
fft'tfttftttfff tftfttfttttttff'f f tttf ttf tf'tff f tttttftttftttffff ttttftftttttttttttttff ttttftftff ttfttt t'tttfff tttff t'ttff t NUTECH CAROLINA POWER 8c LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT " UNIT PLANNING t t' t f f ff f t fff t t t tt f COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 103 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12, tff'tttff'ftftfttff f f tt'fffttfff tff f tfffffff ttftf f ttttff tttttfttff f tfttftftttftff ftttff tfff tttttft tttfttttttttf ttftftf*t 9
'10 CATEGORY 8-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. 86. 190 PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2")
12 13 fff f f f t tff t ff fff f ff t ff t t t f fff tfff ffft f tt tft t t ft t t tt fthm t ftt ft t*ttt ft t t t t ft f ff f f f t t ff t hatt tftt t t t t ffft f f f t' tt f f t'f f ft f t ff 14 15 DONE 15 OUTAGE THIS DOME BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES'9
$~$$~$$$$$$ ~$~$$$ ~$~$ $$ ~$$~$$$$$$$$$ $$ ~$$$$$ $ ~$
~ $$~ $~$$ $ ~$~$ $ $$$ $ $$$$ $$ $$$ $$~ $$$ $$$ $~$$$$ $$$$ ~$
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RCP"01 22 23 RCPA-FTHR-17 FLG THR VT" 1 1-3-06 24 25 RCPA-FTHR-18 FLG THR VT-1 1-3-06 25 27 RCPA-FTHR-19 FLG THR VT-1 1-3-06 28 29 RCPA-FTHR-20 FLG THR VT-1 1-3-06 30 31 RCPA-FTHR-21 FLG THR VT-1 1-3-06 32 33 RCPA-FTHR-22 FLG THR VT-1 1-3-06 34 35 RCPA-FTHR-23 FLG THR VT-1 1-3-06 35 37 RCPA-FTHR-24 FLG THR VT-1 1-3-06 NO 38 39 RCPB"FTHR-01 FLG THR 'VT-1 40 41 RCPB-FTHR-02 FLG THR VT-1 NO 42 43 RCPB-FTHR-03 FLG THR VT-1 NO 44 45 RCPB-FTHR-04 FLG THR VT-1 45 47 RCPB-FTHR-05 FLG THR VT-1 NO 48 49 RCPB-FTHR-06 FLG THR VT-1 50 51 RCPB-FTHR-07 FLG THR VT-1 NO 52 RCPB-FTHR-08 VT-1 f f ttffff tfff f tff ff f ff f f f f tffff ff f tttffffffff f f ttfttff tfttfff f f f tfff ttft tf tttttff ff tfff tf f tff f f f f f f tt ttft ttfttff ttff ft 53 FLG THR NO 54 55 se 57 se 59 50 FORM 0113 (02I53) t 0
105 t t t t tt t tt t t t ttt t tt t tt t ttt t t t t t t t t **t t t t t t t tt t tt t tt t t t t t t t t t t t tt t t ttt t t ttt t t t t t tt tt tt t t t t t t t t t t t t t t t t t t t t t 't tr 2 NUTECH CAROLINA POWER Er lIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 4 PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 104 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 7
8 ttt t ttttt t t tt tt tt t t t t t tttt ttttttt tt t t tt t t ttt t t t t tttt t t tt t t ttttt t t't t 4'ttt tttt tttt ttt t tttt t ttt tttt t tttt t DATE t t t t tttt t tt ttt t t 10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. 86. 190 PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2N) 12 13 tttttttt*ttttttttttttttttttttttttttttttttt*tt*tttttttttt*ttttttttttttttttttttttttttttttttttttttttttt 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULEO INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RCP-01 22 23 RCPB-FTHR-09 FLG THR VT" 1 24 25 RCPB-FTHR-10 FLG THR VT-1 NO 26 27 RCPB-FTHR-11 FLG THR VT-1 NO 28 29 RCPB-FTHR-12 FLG THR VT-1 NO 30 31 RCPB-FTHR-13 FLG THR VT-1 32 33 RCPB-FTHR-14 FLG THR VT-1 NO 34 35 RCPB-FTHR-15 FLG THR VT-1 NO 36 37 RCPB-FTHR-16 FLG THR VT-1 NO 38 39 RCPB-FTHR-17 FLG THR VT-1 NO 40 41 RCPB-FTHR-18 FLG THR VT-1 NO 42 43 RCPB-FTHR-19 FLG THR VT-1 NO 44 45 RCPB-FTHR"20 FLG THR VT-1 NO 46 47 RCPB-FTHR-21 FLG THR VT-1 48 49 RCPB-FTHR-22 FLG THR VT-1 50 51 RCPB-FTHR-23 FLG THR VT-1 NO 52 ttt ttrttttt tttt t tttt t ttttt tttttttttt t tttt tt t t tt t t tt tfttttt*ttttt ttt t tttt t t tt t t tt ttt tt ttt tttt ttttt ttt t t tt t tt t t ttt tttt'tt 53 RCPB-FTHR-24 FLG THR VT-1 NO 54 55 56 57 58 59 60 FORM 0113 (02I83)
106 1 t tt t t tttt t t t t tt t ttt t t t t t t t t t t t t t t tt tt t t t t t t t t t t t tttt t tt t t t t t t t t t t t t t t tt tt tt ttt t tt t t t t tt t t t t tt t tt t tt t tt t t f t t t t t t t t t t' t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING tt t t t t t t t tt t t t t t t t t COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 105 ASME SECTION, XI ~ 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 t t tt tt t t t t t t tt t t t tt t t t t t t t t ttt tt t t t t t t tt t t t t t t tt t t t tt tt t tt ttt t t t tt t t t t t t tt tt t t t t' tt t'
- t t t tt tt t t t tt t 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6. 190 PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2")
12 13 t t tt t t 't 't t t t t t t t tt t t t t t tt t
- t t tt t tt t t t t t tt tt t ttt t t t ttt t t tt t tt tt t t t t t t t t t t t t tt t tt t t t ttt t t t t t t t t t t t t tt t t tt t tt t t t t t t t t t t t t 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM DESCRIPTION INT INT (IN) (IN) SELECT IND REQST TIONS NOTES 18 19 tttttttttttttttttttttttt tttttttttStt tg NUMBER t
TYPE
~ ttt t OULED t 'C SR I ACCESS tt glttStt ttt tttt ttttt tttttt 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RCP-01 22 23 RCPC-FTHR-01 FLG THR VT-1 24 25 RCPC-FTHR-02 FLG THR VT-1 26 27 RCPC-FTHR-03 FLG THR VT-1 28 29 RCPC-FTHR-04 FLG THR VT-1 NO 30 31 RCPC-FTHR-05 FLG THR VT-1 32 33 RCPC-FTHR-06 FLG THR VT-1 34 35 RCPC-FTHR-07 FLG THR VT-1 36 37 RCPC-FTHR-08 FLG THR VT-1 38 39 RCPC-FTHR-09 FLG THR VT-1 40 41 RCPC-FTHR-10 FLG THR VT-1 42 43 RCPC-FTHR-11 FLG THR VT-1 44 45 RCPC-FTHR-12 FLG THR VT-1 46 47 RCPC-FTHR-13 FLG THR VT-1 48 49 RCPC-FTHR-14 FLG THR VT-1 50 51 RCPC-FTHR"15 FLG THR VT-1 52 53 RCPC-FTHR-16 FLG THR VT-1 NO 54 t t tt tt t t t t' t t tt tt t t t t t t t t t tt t tt t tt tt t' t 't t t t ttt t tt t t t t t t t t t t t t t t t t tt t t t t 't t tt ttt t t ttt t t t t 't t t' t t' t t t t t t t t t t ttt tt 55 56 57 58 59 60
107 t t ttt t t t t t t t t ttt t t t tt tt t t t t t t tt t t t t t t t tt t tt t t tt t t t t tt t t t t t t t t t t t t t t tt t t t t t t t t t t t t t t t t t t t t tt t t t t t t t t t tt t t t t t t t t t t t tt t't NUTECH CAROLINA POWER=E LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1
tt t t st t tt t t tat t t st t COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 106 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t DATE 88/01/12 t *t t t t tt t tt t t t t t t t t t t t t t t t t t t t t t t t t t t t tt t t t tt t t t t t t t t tt tt t t
- t tt tt t t t t t t tt t t t t t t t
- t t t
- t t t' t t 9
10 B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER t'ATEGORY 11 ITEM NO. B6. 190 PUMP FLANGE SURFACE WHEN CONNECTION DISASSEMBLED (> 2" )
t tat t t t t t tt t t tat t t st t t t tt t t t t t t t t t at st t tt t t t tt I t at t t t t t t t t t hatt at t t t t st t st t t at t st t t't tt t t t t t t'tt 12 13 t t st st 14 15 DONE I6 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT INO REOST TIONS NOTES 19 aaaaaaar a aar == ~ ar r a aa r a aa araaarrr raaarr aaa raraaa raaaaa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RCP-01 22 23 RCPC-FTHR-17 FLG THR VT-1 NO 24 25 RCPC-FTHR-18 FLG THR VT-1 NO 28 27 RCPC-FTHR-19 FLG THR VT-1 NO 28 29 RCPC-FTHR-20 FLG THR VT-1 NO 30 31 RCPC-FTHR-21 FLG THR VT-1 NO 32 33 RCPC-FTHR-22 FLG THR VT-1 34 35 RCPC-FTHR-23 FLG THR VT-1 NO 36 37 RCPC-FTHR-24 FLG THR VT-1 NO 38 t t t tt t tt t tt t t t t tt t tt tt tt t tt t t t tt tt t t t t t t t t t t
- tt t t t t t t t t t t t t t t t t t tt t t t t t t t t tf t tt t t't t t t t tt t t t 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83I
110 1 11 tf*f1 tf11 1 1 1 1 tf1 1 tftftf1 1 111 1 ttf1 ttf tf tttt1 ttf1 tftf*tftttf tf tf 1ttf tf1 tttf11 1 tfttf 1 1 1 11 1 1 11 11 tf1 tf 11 tf 11111 t1 1 at tf1 1 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1=
4 PLANNING 111111111 t11 111t1 1t COMPONENT LISTING AND ISI 10 YEAR PLAN : 83S-01 PAGE 109 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 1 11 1 1 '1 tf1'1 tt'1 1 1 tf1 1 tf 1 t 1 111111111111111111 tt 1 tf1 t 1 111111 tf 111 t t f 1 1 1 tf 1 1 1 f 1 1 1 t 1 1 1 1 1' 11111111111 t111111 1111 1 1f 9
10 CATEGORY B-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6.220 VALVE FLANGE SURFACE WHEN CONNECTION DISIASSEMBLED (> 2")
12 13 sf tf 1 1 1 1 1 111'ttf tf tttttttttftttt f ftf11 tfff111 ftff1 1 1 111 tttf tf 1 11111 tf 1111 tf1 1 1 1 1 tf tf'11 14 15 DONE 18 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS, NOTES 19 ssssssssaaaasssasssssasa sssssssssssssas ssaasa aaaasassasssssss ===== = s s ssssaa sssssa ssa ~ assss ssasaa ssaass 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 APPLICABLE ft 1 1 1 1 11 1'1 1 1 1 tf 1 1 1 1 1 1 1 f1 t*f1 1 1 1 tf 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 t 1 11 1 1 1 1 1 1 t 1 1 1 1 1 1 st 1 11 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 tf 23 NOT NO COMPONENTS 24 tf1 1 1 1 t '1 11111111 25 26 27 28 29 30 31 32 33 34 35 38 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60
.0
111 f4 tttt t 4 4 t 4 4 t 4 *t4 t tft tfit 4 t t f 4 4 tft 4 t t f tt t t 4 t t f 4 4 4 tft 4 4 4 t 4 4 4 4 4 t 4 tt f 4 tft t't 4 4 4 4 2 NUTECH CAROLINA POWER & LIGHT COMPANY PR IS IM 3 SHEARON HARRIS NUCLEAR POWER PLANT " UNIT 4 PLANNING 1
f 4 f 4 4 4 f4 f 4*t4 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 110 ASME SECTION XI. 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 f4f f 4 4f 4 4 4 tt f ttf ttftftf tttttf f tft f ttftttftff ttttftf ttf4 tf4 4 4 f t f ttt tftf 4 f4 44 4 f4 4 4 t f 4 *ttff4t*f4 9
10 CATEGORY 8-G" 1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. B6.230 VALVE NUTS, BUSHINGS, AND WASHERS () 2")
12 13 tfttf'tttttttttttfttttttftf4 tffttttfttttfttfttt'ttfftttf4 tttf44 ttf4 444 tfttff4 tftttttttfttf4tf4 ftf4'4 f f4 4 ttftftftttt 4 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 444444444444444 ~ 44444444 44 ~ 444 ~ 44444444 4 ~ 4444 ~4 ~ 4444 4444 ~ 4444444 444444 444 444444 4444 ~ 4 444444 20 2'I SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT APPLICABLE 24 tftf f f f t 4 4 4 4 4 4 4 4 444 4 4 NO COMPONENTS tf 4444 tf tf 4 44444 4 tftf 4444 tf4 4 4 4 t 4 tf4 4 ttf4 tft 4 4 t t 4 4 4 t f 4 4 4 *4 4 4 tf4 4 4 4 4 4 444 4'4 4 4 tf4 tt t tf 4 4 4 4 4 4 4 t 4 4 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 102I83)
112 sf f et f f f f ffftf et ftt tf fftff 'f t f f t f t t f ff f' fff et f f t 4 ft t 4f f f sf ft t ff f t t f f f t t fft t f t f ff f t f ted f t t t tt f f tt t ft t f fthm t tf ff t sf ff f 't f t NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 5 'f COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 111 6 t ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMFR 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12.
7 f fffff f t f f tfff fft f ff f et f *ftet t fff ff ffft tft ffft f t ff f f f ff ff ftf tf t et t' f f f f ff f f st f sf fff t' f f f f ff ft f f et t t f t*ft t f tf et t f f f t tf 9
10 CATEGORY 8"G-2 PRESSURE RETAINING BOLTS. TWO'NCHES AND LESS IN DIAMETER 11 ITEM NO. 87.10 REACTOR VESSEL BOLTS, STUDS, ANO NUTS (< 2")
12 13 ff f t t f fft t t tt f t ft t tff f' f f f t t t f ff f ft f t f t ffff f ff f f ftf t t ft t f f t t fff t ft tt t f t t f f t t t f. fff t. f t ftfff f t f f f t f ft fff *fft t ff f t 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 assasssasassssssassssass ssssssssssssssr eraser sressraeasssssss seers eases easassra erases sss assess assess assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RV-001 22 23 BCONO-A(3) C BOLT VT-1 1-1-01 0.750 03.50 NO 24 25 BCONO-8 3 C BOLT VT-1 1-2-03 0.750 03.50 NO 26 27 BCONO-C(3) C BOLT VT-1 1-3-06 0.750 03.50 NO 28 29 BCONO-D 3 C BOLT VT-1 1-3-06 0.750 03.50 NO 30 f f ff ft fff ff ftff ff ff f t t fff ff ffft f f ff r f f fft t ff ft f ff f t f ft ft ff ff t tf ff fff ff f f f f f t t f f f ff f fff f f ff f fffff t f fffff f ft f f fft t ff f 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 <02I83)
113 ff f f et t f la f elf tie tf le fff lIl tt t l tie elf tlt t t t l tf f l f et f f f f le ff le f ft t tt f t ft t f l f le tl f fillffff tfff f f l'ff l'ftie f llfff f ft t ff f ff NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING f f f f fff tff et f COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 112 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 et ft THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY f l f t t f f t iftat fill'f'le l f f f el ft f t f f t ft f f f f l f l ff f f f t f lit *tl t l lff l le ft ft l t f l l88/01/12 l f t t l f t l t f f l f l f l f f t 'l 'l f ft f ft f ft t 'l f t l fDATE ll t f t f ll f f l f 9
10 CATEGORY B-G-2 PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER 11 ITEM NO. 87.20 PRESSURIZER BOLTS, STUDS. AND NUTS ((a 2")
f t'littfff lff el f ft ff tff f tffr f f f f f t t t t tie ffft ft tt l f f t f f t f et t f fff f t f ff tet lft f illtfff f f lltff *ff l f flitf f f et flitt tie f f f tfff l 12
- 13 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 asssasasaesssssseaasssss arssrrsee erase seater sees s = = seers seers stresses arrear ssr saaaar seers = ee 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-PZR-01 22 23 MB-( 1-5) BOLT VT-1 1-1-01 1.880 08.00 NO 24 25 MB- 11-16 BOLT VT-1 1-3-06 1.880 08.00 NO 26 MB-(6-10) 1-2-03 27 28 f tttftttffff filllitfff let BOLT VT-1 1 . 880 08. 00 el f f ff elf elf et le ttftf ff tiffflitf ftf le et fr f frff*tt tftttftf ff f f f tff ttfttft tf f ttf its elf f f f fff NO 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 102I83)
118 t t t ttt t tt t t t t t tt ttt ttt t 't t t t t tt t *t t t t t t t t t tt tt t t tt t t t t t t t tt t t t t t t t tt t t t t t tt t tt t tt t t tt t t t t t t tt tt t NUTECH CAROLINA POWER Er LIGHT COMPANY PRIS IM SHEARON HARRIS NUCLEAR POWER -PLANT - UNIT ttttttt 1
PLANNING COMPONENT "LISTING ANO ISI 10 YEAR PLAN : 83S-01 PAGE 117 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 t t t t tt t t t t tt t t t t tt t t t t t t t t tt t t t t tt t t tt t t t t t t t t t t t t t t t t t t t t t t t t tt t t t ttt t t t tt t t t t tt t t t t t t t t t t tt t tt t t t t t t t tt ttt t t t t t t t t tr 9
CATEGORY B-G-2 PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER 10 11 l2 ITEM NO. B7.30 STEAM GENERATOR BOLTS, STUDS, AND NUTS (<<2)
'l3 t t t t tt t t t 1 t t t t t t t t t t tt t t t t t t t t t t t t t t t t tr t t t ttt t tt t t t t t 1 t t t t tt tt t tt t tt tr t tt t tt t tt t t t t 1 t 1
14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS 'SI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 16 NUMBER DESCRIPTION TYPE DULED INT INT ( IN) ( IN) ACCESS SELECT IND REQST TIONS NOTES 19 ~ assasssaaasasassasasass sssssrssrsssars assess sssasrrsaarss ss rase = ss ss assess raa rr rr assess assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-SG-001 22 23 SGC-CLMB-01 BOLT VT-. 1 1-3-06 1.880 07.50 24 25 SGC-CLMB-02 BOLT VT-1 1-3-06 . 1.880 07.50 NO 26 st 27 SGC-CLMB-03 BOLT VT-1 1-3-06 1.880 07.50 NO
'26 29 SGC-CLMB-04 BOLT VT-1 1-3-06 1.880 07.50 30 31 SGC-CLMB-OS BOLT VT-1 1-3-06 1.880 07.50 NO 32 33 SGC-CLMB-06 BOLT VT-1 1-3-06 1.880 07.50 34 35 SGC"CLMB-07 BOLT VT"1 1-3-06 1.880 07.50 36 37 SGC-CLMB-08 BOLT VT-1 1-3-06 1.880 07.50 NO 36 39 SGC-CLMB-09 BOLT VT- 1 1-3-06 1.880 07.50 NO 40 41 SGC-CLMB-10 BOLT VT-1 1-3-06 1.880 07.50 NO 42 43 SGC-CLMB-11 BOLT VT-1 1-3-06 1.880 07.50 44 45 SGC-CLMB-12 BOLT VT-1 1-3-06 1.880 07.50 NO 46 47 SGC-CLMB-13 BOLT VT-1 1-3-06 1.880 07.50 46 49 SGC-CLMB-14 BOLT VT-1 1-3-06 1.880 07.50 NO 50 51 SGC-CLMB-15 BOLT VT-1 1-3-06 1.880 07.50 52 53 SGC-CLMB-16 VT-1 1-3-06 1.880 07.50 tt tt tt t'st ttttBOLT t t tttt t tttt tttt NO 54 tat at tat't t tat tt ttttttt t st tt ttt t tat t t t t t tt*tt't st tt t*t t t tt tt t st st t tattests atty t tat 55 56 57 56 59 60 FORM 0113 {02l63)
119 t tt t t 't t 't t t 't tt tt t ttt t t' t t t t t tt t t t tt t t t tt t tt t tt t t *tt t tt t t tt t t t t t t t t t t t t tt t t tt t t tt t t t t t t t t t t ttttt t t t t t t t tt tt t t t t t t t t 't 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3
4 PLANNING 1
ttttttttttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 118 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t
- t t t 88/01/12 7
8 t t tt t ttt 't t 't t t t t tt t t t t ttt t t t t t t t t t t t t t t t tt t tt t t t tt tt t t t' t tt t t tt t t tt t t t t tt t t tt t t t t tt t t t tt t t tt tt t t DATE tt tt t t t t t tt 9
10 CATEGORY 8-G-2 PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER 11 ITEM NO. B7.30 STEAM GENERATOR BOLTS, STUDS,'ND NUTS (<s 2 )
12 13 tet et et t tt t tt t t tt t tet et et et t t et t ttt t t t t t t et st t tt t tt t t et t et et tt t et tt t et t t t tt t tt tt t et et et t et t t tt t et t et t t t t t tet st 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sassssssssasssssssaessse ssassssssssassa seater ssrsesasessessss rarer tress arear s r aa aaa rearer steers assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-SG-001 22 23 SGC-HLMB"01 BOLT VT-1 1-3-06 1.880 07.50 NO 24 st 25 SGC-HLMB-02 BOLT VT-1 1-3-06 1.880 07.50 NO 26 27 SGC-HLMB"03 BOLT VT- 1 1-3-06 1.880 07.50 NO tttttttttt 28 29 SGC-HLMB-04 BOLT VT-1 1-3-06 1.880 07.50 30 31 SGC-HLMB-05 BOLT VT"1 1-3-06 1.880 07.50 NO 32 33 SGC-HLMB-06 BOLT VT- 1 1-3-06 1.880 07.50 34 35 SGC-HLMB-07 BOLT VT-1 1-3-06 "'1
. 880 07 . 50 NO 36 37 SGC-HLMB-08 BOLT VT-1 1-3-06 1.880 07.50 NO 38 39 SGC-HLMB-09 BOLT VT-1 1-3-06 1.880 07.50 40 41 SGC-HLMB-10 BOLT VT-1 1-3-06 1.880 07.50 NO 42 43 SGC-HLMB-11 BOLT VT-1 1-3-06 1.880 07.50 NO 44 45 SGC-HLMB-12 BOLT VT-1 1-3-06 1.880 07.50 NO 46 47 SGC-HLMB-13 BOLT VT-1 1-3-06 1.880 07.50 NO 48 49 SGC-HLMB-14 VT-1 3-06 1.880 07 50 F NO BOLT'OLT 50 51 SGC-HLMB-15 VT- 1 1-3-06 1.880 07.50 NO 52 53 SGC-HLMB-16 VT"1 1-3-06 1.880 07.50 BOLT et'ttt t t tt t tt t tt t t t tet et st t t tttt NO 54 tttt t t't tt t t tt tt t t ttttet st t t t tt t t t tet t et tt t tt tt tt tt t tt t t t t tet't st t't t t t t t'tet 55 56 57 58 59 60 FORM 0113 102I83)
120 t t t t tt t tt t tt t tt t t t t t t t t t t tt t t tt t t tt t t t tt t' t t t t t
- t t t t t t t t t t t t t t t t tt ttt t t ttt tt t t t t t ttt t tt t tt t t t t t NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING t t t t t t t t t t t t tt 't t t t' COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 119 ASME SECTION XI. 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL Of ONLY DATE 88/01/12
- t t t tt t' t 't t t t t t t t t t t t t t t t t tt t t t tt t t t tttt tt t t t t t t t t t t t t t t tt tt t t ttt t tt t t t t **t t t *'tt t tt t t t tt t t t t t t t t t t t t t' t t t tt t tt t t t t t 9
10 CATEGORY B-G-2 PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER 11 ITEM NO. B7.40 HEAT EXCHANGER BOLTS, STUDS, ANO NUTS (<s 2")
tt tt t t tt t tt t t t t
- t t t t t t *t t t t t t t t t t tt t t tt t tt t t t t t t t tt t t tt t t t t t tt t t t t t t t t t ttt t t t t t tt t tt t t t tt t t
- tt t tt tt t t t t t t t t tl t t t t t tt t 12
\3 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssssssassasssssssaaas aaassxsasssssss asssaa sssssassasss sas as ass ssssssxs ssssss sss sssass ssssaa sassas 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT 24 APPLICABLE tttttttttttttttttttt*tttttttttttttt'ttttttttttttttttttttttttttttt'ttttttttttttttttttttttttttttttttt NO COMPONENTS
~
25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 58 57 58 59 eo FORM 0113 (02I83)
121 1 tttt 't t t t t tt 't tt t tt t t t t t t tt t t tt t t t tttt t tt t t t t ttt t t t t t tt t tt tt t t t t t tt t t t t t t t t t t t t t t t tt t t tt t t t t t t t t t t t t t t t t t tt t tttt t' tt t 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING t t t t t t at t t t t t t t t at t COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 120 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t 't tt 't t 't tt ttt t 't tt t t tt t t t t tt tt tt t t t t t t t t t t t t t t t t t t t t tt t t t t t tt t t tt t t t t t tt r t t' t t t t t t tt t t t t t t t' t t t t t tt t t t tt t t t t 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONI Y DATE t t' t tt t t t t t 9
10 CATEGORY B-G-2 PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER 11 ITEM NO. 87.50 PIPING BOLTS, STUDS, AND NUTS (<a 2")
tt r tttt t t t t t 't t tt tt t ttt t t t t t t t t t tt t t tt t tt tt t t t t t t t t t tt t t t tt t t t tt t tt tt t t t t t t tt t tt t t t t t t t t t t tt t t tt t t tt t tt t tt t t t t t tt
- t tt t 12 13 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 assessee aas s sears reassess erases sss arrear ====== === s 20 21 SYSTEM : CS CHEMICAL ANO VOLUME CONTROL ISOMETRIC NUMBER : II"CS-088 22 23 CS"545-F"01 (4) FLG CON VT-1 1-1-01 NO 24 25 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER: II-CS-103 28 27 CS-492-F-01 (4) FLG CON VT-1 1"3-06 NO 28 29 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER: II-CS-107 30
.31 CS-593-F-01 (4) FLG CON VT- 1 1-2-03 32 33 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-008 34 35 RC-30-F-01 (8) FLG CON VT-1 1-3-06 0.875 36 37 RC-32-F-01 8 FLG CON VT-1 1-3-06 1. 125 NO 38 39 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RC-010 40 41 RC-52-F-01 8 FLG CON VT-1 1-1-01 0.875 42 43 RC-54-F-01 (8) FLG CON VT-1 1-1-01 1. 125 44 45 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: II-RC-011 46 47 RC-41-F-01 (8) FLG CON VT-1 1-2-03 0.875 NO 48 49 RC-43-F-01 8 FLG CON VT-1 1-2-03 1. 125 NO 50 ttt t t t tt t t t t t t tt t t t t tt r t ttt t t t tt t t' t t 't t tt t ttt t' t t tt t t tt tt t t t t t t t t t tttt t t t t tt t t t tt t t tt t t t t t, t t t t t t t t t t t t t t t t t t t tt tt t t t t 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
124 t t t tt t tt t t t t t t tt t tt t t' t t t t t t t t t t t t t t t t t t t t t t t
- t tt tt t tt t t t tt t t t t t tt t t t t t tt t t t t t t t t tt tt tt tt tt t t t tt t t ttt t t tt t t' t t t' t t t NUTECH CAROLINA POWER & LIGHT COMPANY PRI 5 IM SHEARON HARRIS NUCLEAR POWER PLANT -, UNIT 1 PLANNING 't t t tt t t tt tt t t t t t' tt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 123 6 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA, INTERVAL 01'ONLY DATE 88/01/12 8 t tt t tt t t t t tt ttt t t t tt t t t t t t t t t t t t t tt t ttt t t
- tt t t t t t t t t t t t tt ttt t t tt t t tt t t tt tt t t t t t t t t t t tt t t t ttt t t t t t tt t t t tt t t t t t t t' t tt 9
10 CATEGORY B-G-2 PRESSURE RETAINING BOLTS, TWO INCHES ANO LESS IN DIAMETER 11 ITEM NO. 87.60 PUMP BOLTS, STUDS, ANO NUTS (<$ 2")
t tt t tt t t hatt t tt tt t t tt t t t t tt tt t tt t t t t t t t t t tt t t tt t t t t t t t tttt t tt t t t tt t hatt t t t t t t*tt tt tr tt t t 1 t t tt t t t t t*tt t hatt t t t t tt t t tt t tt t t 12 13 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 $$$$$ $$$$$$$ $ $$$ $$ $$$$$$$ '$ $ $ $ $ '$$ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ $ ~ $ ~ $ $ $ $ $ $ $$$ $ ~$~$$~ $$~$$ $$~$$$
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: II-RCP-01 22 23 RCPB-CSBOLT-8 SEL BLT VT-1 1-2-03 1.500 08.00 24 25 RCPB-SBOLT 12 SEL BLT VT-1 1-2-03 2.000 08.00 26 27 RCPC-CSBOLT"1 SEL BLT VT-1 1-3-06 1.500 08.00 NO 28 29 RCPC-CSBOLT-2 SEL BLT VT-1 . 1-3-06 1.500 08.00 NO 30 31 RCPC-CSBOLT-3 SEL BLT VT-1 1-3-06 1.500 08.00 NO 32 33 RCPC-CSBOLT-4 SEL BLT VT-1 1-3-06 1.500 08.00 34 35 RCPC-CSBOLT-5 SEL BLT VT-1 1-3-06 1.500 08.00 NO 38 37 RCPC-CSBOLT-6 SEL BLT VT-1 1-3-06 1.500 08.00 NO 38 39 RCPC-CSBOLT-7 SEL BLT VT-1 1-3"06 1.500 08.00
~ 40 41 RCPC-CSBOLT-8 SEL BLT VT-1 1-3-06 1.500 08.00 42 43 RCPC-SBOLT( 12) BLT VT-1 1-3-06 2.000 08.00 NO 44 ttt t t t t t tt t t t ttt t t t t tt SEL t t tt t
- t t tt t tt tt tt t t t t t t t t t t t t t t t ttt t t t tt t tt t t tt t t t t t t t
- t t t t t t t t tt tt tt tt t t ttt t t ttt t t tt 't tt t t t t 45 48 47 48 49 50 51 52 53 54 55 56 57 58 59 60 0
125 t t tt 4 t t t tt t*tt t t t t t t t t tft t tt t tt t t t'*tt t t tt t t t t t t tt tt t t t t t tt t t t tt t t t t t t tt t' tt t t tt t t t tt t t 4 tt 0 tt t t t t 4 tt t*ttt t t t t t t t t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRI SIN 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 PLANNING 1
t t t t tt 't t t t t t t t t t t t t COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 124 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t t t t t 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t tt t t t t tt t t t t t 't t t t tt tt t t t tt t t t tt t t tt t tt t t' t t tt t t 't t t t t tt t t t t t tt t t t t t t t t t t t tt t t t t t t t t t t tttt t t t t t t t DATE t t t t t t t tttt 9
10 CATEGORY 8-G-2 PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER 11 ITEM NO. 87.70 VALVE BOLTS, STUDS, AND NUTS ((- 2 )
12 13 t ttt t t t' tt tt t t tt t t t tt t t t t t t t t tt t t t t t
- t t t *t t t *t t t t t' t t t t t tt t t t t tt t t t t tt t tt tt t tt t t 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 20 21 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-094 22 23 CS-483 VBB(12) BON BLT VT"1 1-2-03 0.625 03.25 NO 24 25 CS-486 VBB 12 BON BLT VT-1 1-2-03 0.625 03.25 NO 26 27 SYSTEM: CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-097 28 29 CS-1 VBB 6 BON BLT VT-1 1-2-03 1.250 05.75 30 31 CS-2 VBB(6) BON BLT VT-1 1-2-03 1.250 05.75 NO 32 33 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-102 34 35 CS-497 VBB(12) BON BLT VT-1 1-3-06 ."0.625 0-..25 36 37 CS-500 VBB 12 BON BLT VT-1 1-3-06 0.625 03.25 38 39 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-CS-097 40 4'I RC-38 VBB 14 BON BLT VT-1 1-2-03 0.750 05.00 42 43 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-008 44 45 RC-37 VBB 14 BON BLT VT-1 1-3-06 0.750 05.00 NO 46 47 RC-54 VBB( 14) BON BLT VT-1 1-3-06 0.750 05.00 NO 48 49 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-010 50 1-1-01 t t t t tt t' t t tt t
- tt t t t tt t tt t t t t *t t t t t t t 0.750 05.00 RC-41 VBB(14) VT-1 t t t t BLT NO 51 52 t t t tt t tt 't t t t t rt tt t t t t t tr tt t BON t t tt t t t t' t t t t t t t t t t tt t t tt t t t tt t t tt tt tt t t ttt t t t t t t t t t 53 54 55 56 57 58 59 60 FORM 0113 102I831
127 tt t t t t t t t' t t t t t t t t t t t tt t t t t tt tt t t t t t t' t t t t tt t t t t t t t t t t t tt tt t t t t t t t t t tt t tt t t t t t t t t t tt t t t t t t t t t t t t t t t NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t t t *t t t t t t' t t t t t t t 't t 1
PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 126 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 ll! 't THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tt 4 4 t t t t tt t tt t t 't tttt t t t t t t t t t t t t t t t t t t t t t t t t t tt *'tt t t t t t t t t t t t t t t t t t t' 't t t' 't t 't *0 **tt t tt t t tt t t t t tt t 't t t DATEt t t tt 88/01/12 t t t
- t t tt t t t 9
10 CATEGORY B"G-2 PRESSURE RETAINING BOLTS, TWO INCHES AND LESS IN DIAMETER 11 ITEM NO. 87.70 VALVE BOLTS, STUDS, AND NUTS ((- 2")
12 13 t t t t t t t tttt t. t t t t t t t t t t t t t t t t tt t t t tt t. t t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t tt t t t t t t tt t' 14 15 DONE 16 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RC-027 22 23 RC-125 VBB(8) BON BLT VT-1 1-3-06 NO 24 25 RC-127 VBB 8 BON BLT VT-1 1-3-06 NO 26 27 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER : II-RH-009 28 29 RH-39 VBB 18 BON BLT VT-1 1-2-03 1.625 10.50 30 31 RH-40 VBB(18) BON BLT VT-1 1-2-03 1.625 10.50 32 33 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-010 34 35 RH-1 VBB(18) BON BLT VT-1 1-2-03 -w1. 625 10. 50 38 37 RH-2 VBB 18 BON BLT VT-1 1-2-03 1.625 10.50 NO 38 39 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-017 40 41 SI-138 VBB 16 BON BLT VT-1 1-3-06 1.000 05.50 42 43 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-021 44 45 SI-249 VBB 18 BON BLT VT-1 1-3-06 1.625 08.80 NO 46 47 SI-250 VBB(18) BON BLT VT-1 1-3-06 1.625 08.80 NO 48 49 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: II-SI"022 50 SI-251 VBB( 18) BON BLT VT-1 1-2-03 1.625 08.80 NO t tt
- t t t tt t t t t t t t t t t t t 't t tt t t t tt t t t t t t t tt tt t tt t t t t t t tt t t t t t t t t t tt t t t' t t t t tt t tt 't t tt tt t tt t 't t 't t tt t t t t t t t t t t 51 52 53 54 55 56 57 58 59 80 FORM 0113 (02I831
131 sf ff st sf f sf at tat sf sf f ttt t t 4 fff f fft st f st f f t f tt ftf f t ff f t fff t tf ft t tt t f *Er f f f f ft 1 fff f t f tf t t t fff f t f it Ert f f f tt t t t tt tf t t I sf *ft NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING t t *tf f ff f t' t t t f f llr COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 130 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 sf t fff st sf f ff f tff ff sf f sf tft tf f t fff tf f f t f f f ff t st f f tfsf tt f f tt t f tf t tat ft sf f f t f t f sf f f ff f *ff t f t Art tat sf tf f f tt f ff tf ff f tf sf t E
9 10 CATEGORY B-H INTEGRAL ATTACHMENTS FOR VESSELS ll ITEM NO. BB. 10 RV INTEGRALLY WELDED ATTACHMENTS f ff f tat f t fffft ffftf fft tf f f f t 't f 't t't t t 'f f f f f' f f f f t t f f f fff f f f ff 't ff t 't f f t t t t f ff f ff f f ft t f ft fff f t f f f fff f fff t' 12 rlr rlr rlr 13 Mr 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM ECHE- OO~TPRIOR OIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 aasasaassssasaaaa s sass asassssasssssas sass as ~ assss ssass assssass ssaaEEs a asa as ssaasa sas sa 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 APPLICABLE sf f f tff f ff f f f fff tff f tt ftt t ft t Ittf f Era f t ~ t f t ff ft f t t t tEr ff f t ff tt t t sf t ft t sf t iff t f f t t t Crt f f sf sf fft t tf t t t t f sf sf fft t f ft f 23 NOT NO COMPONENTS 24 25 28 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 {02I83)
132 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 t 1 t 1 1 1 1 1 1 1 1 1 1 1 1 11 1 Std 11 1 1 11 tt1 1 1 1 1 1 t1 1 1 1 1 1 t 1 1 1 1 *1 1 1 1 1 t NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 f 1 1 1 11 ttt ttt1tttf11 1
PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S"01 PAGE 131 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL'1 ONLY DATE 88/01/12 tt*11 fr f 1 1 tf1 1 1 tt 1 1 1 11 1 1 1 1 f 1 1 1 1 1 1 t tf 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 *t1 1 1 1 1 1 11'1 1 1 1 1'*1 1 11 1 1 1 1 1 tt 1111 tt 11 1 1 1 11 1 1 11 t t f1 1' 1 1*t 1 1 1 1 1 f1 1 tf 9
10 CATEGORY 8-H INTEGRAL ATTACHMENTS FOR VESSELS 11 ITEM NO. 88.20 PRZ INTEGRALLY WELDED ATTACHMENTS 12 13 ttttttttfttttttftttttttttf f1 f1 tf'tttttttttt1 tttf tfttf 11111 1 11 1 1 ttttttftf f ttf tttttff fttf1ttf tftftttf1 1 1 1 11 1'1111'ttttt 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 $ $ $ $ $ $ $ ~ $ $ $ $ $ ~ $ $ $ ~ $ $ $ ~ 1 ~ 1 ~ $ ~ 1 ~ $ $ '$$ $ ~ $ $ $ $$$$$$ $$~$ $$$$$$$ $~$$$ ~$~$~ $~1~1 ~$$~$$ ~1 ~$$$ ~1 ~1~ $$$$$$ 1 ~$$~1 $$~$$$
20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: II-PZR-01 22 23 I,LUG-A5 LUG MT 1-1-01 092. 1 4.000 NO 24 25 I,LUG-A6 LUG MT 1-1-01 092. 1 4.000 NO 26 27 I,LUG-A7 LUG MT 1-1-01 092. 1 4.000 28 29 I,LUG-AB LUG MT 1-1-01 092.1 4.000 30 31 I, PSC-21A PZR COL MT 1-1-01 87.00 1.500 NO 32 UT-00 33 UT-455 34 UT-605 35 36 I,PSC-21B PZR COL MT 1-2-03 87.00 1.500 NO 37 UT-00 38 UT-455 39 UT-60S 40 41 I, PSC" 21C PZR COL MT 1-3-06 87.00 1.500 42 UT-00 43 UT-455 44 UT-60S 45 t 1 1 1 1 1 f1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 t 1 1 1 1 1 1 1 t 1 1 1 1 1 t 1 1 t f 1 1 1 t t 1 1 1 1 t 1 1' 111111 f1 1 1 1 1 1 t 1 1 1 1 1 1 1 1' '1 111 t 1 *1 1 1 1 1 1 t '1 111 '1 1 t 46 47 48 49 50 51 52 53 54 55 58 57 58 59 60 FORM 0113 (02/83) 0
133 t 't tt tt t t 't t t t ttt t t t t tt t tttt t tt tt t t t t t t 't 't t tt t t t t t t t t t t t tt t t t t t t t t t t t t t t tt t tt t t tt t t t t t t t tt t t t t t t t t t t t t t t t tt t t t t t t t t t t t t t NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t 't t t t t t t tt t t t tt t
- t t 1
PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 ~ PAGE 132 6 ASME SECTION XI, 1983 FOITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 t t tt t t tt t t t tt tt tt t ttt tt t t t tt t t t t t tt t ttt t t t tt tt t tt t t t t t t t tt t t t t t t t t tt t t tt t t t tt t t t t t t tt tt t' t t' t t ttt
- t. t 9
10 CATEGORY B-H INTEGRAL ATTACHMENTS FOR VESSELS 11 ITEM NO. B8.20 PRZ INTEGRALLY WELDED ATTACHMENTS 12 13 t *t t t' 't t t ttt t tt t ttt t ttt t tt t t t t t t t t t ttt tt t t t t t t tt t' t t t t t t t tt t t t t t t t ttt t t t' t t t t tt t t t t t t t tt ttt t t t t t t t t t t t' t t t t t t t t t t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 seasssssssaassaa assess sssassessssssss assess sasseseseseeesss tasse aa sa a asses a sass sas ass = s ass esses 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-PZR-01 22 23 SBW-A1A PZR SUP MT 1-2-03 092. 1 2.000 NO R 1-008 24 25 SBW-A 18 PZR SUP MT 1-2-03 092. 1 2.000 NO R 1-008 26 27 SBW-A2A PZR SUP MT 1-2-03 092. 1 2.000 NO R1-008 28 29 SBW-A28 PZR SUP MT 1-2-03 092. 1 2.000 NO R 1-008 30 31 SBW-A3A PZR SUP MT 1-3-06 092. 1 2.000 NO R 1-008 32 33 SBW"A38 PZR SUP MT 1-3-06 092. 1 2.000 NO R 1-008 34 35 SBW-A4A PZR SUP MT 1-3-06 'b92. 1 2.000 NO R1-008 35 37 SBW-A4B 1-3-06 092. 2.000 NO R 1-008 t t t t t t t t t tt t t t t t t tt tt t t t t PZR SUP MT t t tt t tt t t t t tt ttt t t t t t t tt t t tt t t t t t t t t tt t t t t tt t tt t t t t t t t t t t t t t t t t t t t tt t t t t t t tt t t tt t' t t t t t t t t t t 1
38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 58 57 58 59 60 FOAM 0113 (02I83)
136 f'fff f fff t'tf tff tffftftff tttffff tfttff ftftftttttttttttttttttttttttttftf ttftttfttttt't*tt'ttfftftf*ff ttff f tf tttftttttff f tt 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM
- UNIT 3
4 tr SHEARON HARRIS NUCLEAR POWER PLANT PLANNING 1
f tttfttfttftf'tttttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 135 6 ASME SECTION XI. 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAl 01 ONLY DATE 88/01/12
'8 ft f tf f t f ffft ffff Iff t f f f fff t ft f fff t ft f ft f f fff f f t ff f t t t f t f ff f f t tft t t t t ft t t t t t t t t f tf fft t t f ft t tf ff ff f tftt f t f t t f t t t trt ff t t f 7
9 10 CATEGORY B"J PRESSURE RETAINING WELDS IN PIPING ITEM NO. 89.11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >f 4 IN.
12 13 fr t f t t f t tft t tft t tf fffft t f f f fffft f t t t fthm f t t t t tf f tt t t ft fft t t t t t f t f t tft t t t t f tt fr t ft ff tf f f t f f ft t f t t t t it t tf ff t ft t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM DULEO INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 18 19 NUMBER Sffffffffffffffffffff ff f DESCRIPTION f f ff
~ '
TYPE f f f f ffff fffffffff'Ctf f ff fff ~ f ffffff 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I "FMR-01 22 23 RC-10-17-SW-L1 PIPE -RED ELB PT 29.00 2.330 NO 24 UT-45L 25 28 RC-10-17-FW-2 RED ELB-SGANOZI PT 1-1-01 29.00 2.330 27 UT-45L 1-1-01 R 1-003 28 29 RC 17-F W-3 SGANOZO-ELB LR PT 31.00 2.480 NO 30 UT-45L R 1-003 31 32 RC-10" 17-FW-6 ELB LR -PIPE PT 31.00 2.480 NO 33 UT-45L 34 35 RC-10-17-SW-N5 PIPE -ELB LR PT 1-2-03 31.00 2.480 NO 38 UT"45L 1-2-03 37 38 RC-10-'17-FW-7 ELB LR -PIPE PT , 31.00 2.480 NO 39 UT-45L 40 41 RC-10-17-SW-06 PIPE -ELB LR PT 31.00 2.480 NO 42 UT-45L 43 44 RC-10-17-FW-8 ELB LR -RCPANI PT 31.00 2.480 NO 45 UT-45L R 1-003 46 f ff f f ff f ff f t*fff ft fff t ffft f t f t f t f t f f ft ft f fff t tftt fff f t f tftf f f tt ff t t f f f t tt ffffff t ftff t t t*tft ff f ftftf ff f' f f f 'f tf t f ff ttf t 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02183) 0
137 t tt t t tt t t t t t t 't tt t t t 't t t t t t t tt t t 't t t t t t t t t' t t t tt t t t t tt tt t tt tr 't t tt rt t t t t t t t t t t t t t t t t t t t t t t * 't t t t tt t t tt t tt t t t t t t t 't 't t 't t t t t t t t t NUTECH CAROLINA POWER Er LIGHT COMPANY PR IS IM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t t t tt t t t tat t mt tat mt 1
PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S"01 PAGE 138 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1883 ADDENDA, INTERVAL 01 ONLY 1 DATE 88/01/12 8 t t tt tt t t tt t t tt t t t t t tt t t t tt t t t t t t t t t t t' t t t t t t t t tt t tt t t tt t t t t t *t t t
- t t t t t t t t ttt t 't t 9
10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9. 11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE )r 4 IN.
12 13 tt tt t rt t tt t t t t tr t t tt tt tt t t tt t t t tt t t tt t t t ttt t t t t t t tt tt t t t t t t t t t t t t t t t tt t t t t t t tt t t tt t t t t t t t tt t tt t t tt t' t I t t t tt t t tt t t t t t t t tr 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 r mss same sss ararat s s s ss ss = a aa marts sara samsssaa stars aaa smarts assama mrm 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-FMR-01 22 23 RC-10-17-FW-5 RCPANO -PIPE PT 1-2-03 27.50 2.210 NO 24 UT-45L 1-2-03
~ 25 26 RC 17-SW" P 1 PIPE -ELB LR PT 27.50 2.210 NO 27 UT-45L 28 29 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-FMR-02 30 31 RC-10-18-SW-K1 PIPE "RED ELB PT 29.00 2.330 32 UT-45L 33 34 RC-10-18-FW-2 RED ELB-SGBNOZI PT 29.00 2.330 NO 35 UT-45L R 1-003 36 37 RC-10-18-FW-3 SGBNOZO-ELB LR PT 1-2-03 31.00 2.480 NO 38 UT-45L 1-2-03 R1-003 39 40 RC-10-18-FW"8 ELB LR -PIPE PT 31 . 00 2. 480 NO 41 UT-45L 42 43 RC-10-18-SW-I5 PIPE -ELB LR PT 31.00 2.480 NO 44 UT-45L 45 46 RC-10-18-FW-7 ELB LR -PIPE PT 31. 00 2. 480 NO 47 t t t t t t t. t *t' t tt t t t t t t t t t t t t tt tt t t t t t t t t t t t tt t tt t t t t t tt t t tt t t tt t t tt t tt t t t t t t t t t t t t t 48 49 50 5'I 52 53 54 55 56 57 58 59 60 FORM 0113 {02183)
-140 t t t tt t t at t*t t't t t t tt t t at at at t tat t at t t t t t t t t tt t t t t t t hatt at t t t t t tat t t t tt t t tt t t t at t t t t t t t t t tttt t t tt t tt tt t t t t t t t t t t t t t t t t t t NUTECH CAROLINA POWER & LIG.'iT COMPANY PRISIM .
SHEARON HARRIS NUCLEAR POWEP. PLANT PLANNING UNIT ttttttttttttttttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 139 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA. INTERVAL 01 ONLY DATE 88/01/12 t tat tat stat tat t*t*tt t t*ttt t*ttt*ttt at t t t t t t at t t t t tat t t tat t t t at at t at t at t t t t t t t t t t t t t tt t t t t t t tt t t't t t't t t a
8 9
10 CATEGORY B-U PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. B9. 11 CIRCUMFERENTIAL WELOS IN PIPING, NOMINAL PIPE SIZE )s 4 IN.
t t t t t t t t tt tt t t tt t tt t t t t t ttt t t t t t t ttt t t t *t t t t ttt tttt t t t t t tt t t t tt tt tt t t t t t t t tt t tt t t t t. tt t t t t t I t t t t t t t tt t. t t t t t t t t tt t tt
- t t 12 13 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 ssssassasssssssasassssss sasssaaarisssasa asasss saasasaassssssaa assaa asa a aaaas ~ ssassa ssa assaaa asaasa sassss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RC-009 22 23 RC-FW-1 NOZZLE -P BEND UT-455 1-3-06 14.00 1.406 NO R 1-003 24 25 RC" SW-8 13 P BEND -P BEND PT 14.00 1.406 28 UT-455 27 28 RC-FW-2 P BEND -P BEND PT 14.00 1.406 NO 29 UT-455 30 31 RC-SW-A12 P BEND -P BEND PT 14.00 1.406 32 UT-455 33 34 RC-FW-3 P BEND -SAFEENO PT 14.00 1.406 35 UT-455 36 37 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-022 38 39 RC-FW-456 SAFEENO-P BEND PT 1-3-06 06.00 0.719 40 UT-455 1-3-06 41 42 RC-149-1-SW-2 P BEND -ELB LR PT 1-3-06 06.00 0.719 NO 43 UT-45S 1-3-06 44 4 45 RC-SW-A6 ELB LR -PIPE PT 1-3"06 06.00 0.719 NO 46 UT-455 1"3-06 R 1-003 47 *tt t t t t t t tt t t t t t t t tt t t t t tt t t t t tt t t t t t t t t tt tt t t tt t t t t t t t t tt tt t t tt t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t tt t t t t tt t t t t t tt t tt t t t 48 49 50 51 52 53 54 55 58 57 58 59 60 FORM 0113 {02I83) r 0
143 t tt tt t tt tt t t t t tt t t t tt t t tt t tt t ttt t tt t t t tt tt t t tt t t t t t t t t t t tt t t t t tt t t t t t t tt t t tt t t t t t t t t tt t t tt t t t t t tt tt t t t t tt tt t t t t 't tt t t t NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM t' SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t tt t t t t t' t t t t t tt t t t 1
PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 142 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 t t t 't t t t t t t tt t I t t 't t tt tt t t t t t t t t t t t tt t t t t t t t t t t t t tt t t t t t t t t t t t tt tt t t tt t t t t t t t t tt tt t t tt t tt t t t t t t t t t t t tt t t t tt t t t t' t t t 9
10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9. 11 CIRCUMFERENTIAL WELOS IN PIPING, NOMINAL PIPE SIZE )t 4 IN.
12 13 t tt t t t t t ttttt t t tt t tt t tt tt t t tt t t t tt t t t t tt t t t t t t t t t t t tt ttt t t t tt tt t t t t t t t t t t t' t tt t t t t tt t t tt 1 t t t t tt t t t t t t t tt t t t t t t t tt t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM DESCRIPTION DULED INT INT (IN) (IN) SELECT IND REOST TIONS NOTES 18 19 tst ~ tstst tttt\
NUMBER
~ tmtt ~ tt ~ tttt tt ~ ~ $ $ ~ ting TYPE ggts'Ss tt 'RSg CR'SIR 5 t I ~
ACCESS
~ tttttt ttt tt'SCttt Sttt tR 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-023 22 23 RC-SW-E12 PIPE -PIPE UT-455 04.00 O.S31 24 25 RC-SW-E11 PIPE "TEE PT 04.00 0.531 NO 26 UT-45S R 1-003 27 28 RC-SW-E7 TEE -PIPE PT 04.00 0.531 NO 29 UT-455 R1-003 30 31 RC-SW-E6 PIPE -REDUCER PT 04.00 0.531 NO 32 UT-45S 33 34 RC-SW-E8 TEE -PIPE PT 04.00 0.531 NO 35 UT-45S R 1-003 ae 37 RC-SW-E9 PIPE -ELB LR PT 04.00 O.S31 NO 38 UT-455 39 40 RC-SW-E 10 ELB LR "PIPE PT 04.00 0.531 NO 41 UT-455 42 43 RC-FW-322 PIPE -VALVE PT 04.00 0.531 44 UT-455 R1-003 45 46 RC-FW-323 VALVE -PIPE 04.00 0.531 tttttttttt tt t't tt tttt t t*tttt t ttt t t t tt t tttttt t tt t t t tttttt t ttttttttt t t t'4 t t t tt t tttt t t tt tt tt tt t tt t t tt t tt tttt ttttttttt tttt t PT NO 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
145
'<< t << t tt t t t << tt t t << t t t t <<<< t t t t ttttt t t tt
- tt t t t t t << t t t t t t tt t << t t t t t t t t << t tt tt t << t t t t << t t t t' t t << t <<<< t t t t t << t t t t << t << tt t t <<'t t t t << t t << t t t NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM t SHEARON atHARRIS NUCLEAR POWER PLANT UNIT PLANNING 1
ttttttttttttfttt<<'<<t COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 144 ASME SECTION XI, 1983 EDITION THROUGH -"" 0 INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12
<< tat <<t t <<t'<<t << << t t t tt t t t at<<<<t<<at t t t tt t t<< t<<<<a st t << <<a t tt <<<<t tt t t t t << << << tat << << <<<<<<t << tat 0 << tat <<a<<tert <<<<<< t tat t t << t*t*t << t t+ tat*<<<< t t t 9
10 CATEGORY B-U PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. 89. 11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >s 4 IN.
12 13 tt t t t t t << tt t t tt t ttt t tt t tt t t << t t t t t t t t t t tt t t t t t ttt << tt t tt t tt t tt t << t tt t << tt t t t t t t t t t t << t tt <<<< tt t t *t tt t t t t
- t tt t << t t t t t << t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUh1BER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sass<<stars<<sr<<asar<<sar<<a assr<<sass sass<< arras rsrrasrasssaass arras arras art<<sass as<<sar sra ss raa as<<sar <<<<assr 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-023 22 23 RC-SW-C13 RED TEE-PIPE UT-45S 1-1-01 06.00 0.718 NO R 1-003 24 25 RC-FW-324 PIPE -ELB LR PT 1" 1-01 06.00 0.718 NO 28 UT-45S 1-1-01 27 28 RC-SW-83 ELB LR -PIPE PT 1-1-01 06.00 0.718 NO 29 UT-45S 1-1-01 30 31 RC-SW-84 PIPE -TEE PT 1-1-01 06.00 0.718 NO 32 UT-45S 1-1-01 R 1-003 33 34 RC-SW-85 TEE -PIPE PT 1-1-01 06.00 0.718 NO 35 UT-45S 1-1-01 R 1-003 36 37 RC-SW-86 PIPE -REDUCER PT 06.00 0.718 38 UT"45S R 1-003 39 40 RC-FW-327 TEE -PIPE PT 1-1-01 06.00 0. 718 NO 41 UT-45S 1-1-01 R 1-003 42 43 RC-SW-A3 P BEND -REDUCER PT 1-1-01 06.00 0.718 NO 44 UT-4SS 1-1-01 45 1-1-01 t t t t t t t t t t t tt t tt t << tt t t t t t t t t << t t t <<' << t t t t t t tt t t << t t t t t <<<< t tt t t t t 04.00 0.531 48 RC-SW"A4 REDUCER-P BEND PT NO 47 << <<* t << t t t << t << t t t t t t t << t t t t t t t tt t tt t t t t tt t t t t t t t t t t << t t <<<< t 48 49 50 5'I 52 53 54 55 56 57 58 59 60 FOAM 0113 (02I83)
150 f f ff fff f fffff f fffft ft t ft fff t ft t t ffff t f *ff t 'f t t f f t f 't ft ff t t t f f fftt 't t f t f t t t t t ft 't 't t t f t f f t f't t ff t 't f f t 't ff t' f t t t t ff t' t' ff t' tf t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT UNIT 3
4 PLANNING 1
tttttttfftfff ttff ttf COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 149 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 f f I'fff t trtft tff sf f f fff f t f t t*fft ft f fft f f t fr ft f t f t ffff t f f fftt ft f tt t tff f f ft ff f tft fff t f *a ftffft t tf ft f f ff t f fff t f f t f f fff f fr rlr 9
10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING f 11 ITEM NO. B9.11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE )a 4 IN. f 12 13 ff tt f ff f t t ff tftff tftff ff tff ffftt tt ff fftf t t f t tf t t ff t f tft tffff t tt t f t t t t t t fft f tf t ff f f ff f t tt t tft f t *ff ff ffff f tftf ft f fff t t f 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sasasss sssasssa sss saassaasaa ~ saaas aaasaa aasaaasaa aaaa- asaas -==----- sass saa asaasa assssa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC"025 22 23 RC-FW-331 NOZZLE -PIPE PT 1-2-03 NO 24 UT-45S 1-2-03 R 1-003 25 26 RC-SW-A3 PIPE -ELB LR PT 1-2-03 04.00 0.531 NO 27 UT-45S 1-2-03 R 1-003 28 29 RC-SW-A4 ELB LR -PIPE PT 04.00 0.531 NO 30 UT-45S R 1-003 31 32 RC"SW-AB PIPE -PIPE PT 04.00 0.531 NO 33 UT-455 34 35 RC-SW-A5 PIPE -ELB LR PT 04.00 0.531 NO 36 UT-45S 37 38 RC-SW-A6 ELB LR -PIPE PT 04.00 0.531 NO 39 UT-45S 40 41 RC-76-1-SW-1 PIPE -ELB LR PT 04.00 0.531 NO 42 UT-45S 43 44 RC-FW-332 ELB LR -PIPE PT 04.00 0.531 j NO UT-45S tat tf frff tfIff f ff ff tff f ft tllrtttff tff f t't t t tf t tfst t t'f tf f tf ttff f tftftfft f t f f tf ft tff tftff tf t*tftftf f ft f f tttf f t tt tf 45 46 f tlirt 47 48 49 50 51 52 53 54 I 55 56 57 58 59 60 FOAM 0'113 (02I83)
155 tttttt t'tt et t t t t t t t t t t t t t tet t t tet t t ttt st t t st t t tt t t t tet t tt t tt t t t tt t t t t tft t t t t t t t tttft t tt t t et t t st t ttt tet et t t t t t t t t t tt t tt NUTECH CAROLINA POWER Sr LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING t't t t t t t t t* et t*t et st COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 154 ASME SECTION XI. 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 ttt tt t t 't t! t 't tt tt tt t t t t rt t tt t ttt t t 't t tt tt 't t! t tt
- t
- tt t
- t t t t t t 't t t
- t 't t
- t 't t t t t t t t t t 'l t tt t 't tt t t t t t tt t t t t t t 't t t t DATE rt ll t t t t t tt t t *t t 't t t t 9
10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE )% 4 IN.
12 13 t' t t
- t t t t
- t t t t t t t t t t t t t t t t t t t t t t t tt t t tt t t' t t t t t tt t t tt t t t t t t t t t t t t t t t t t t tt t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 ssaasssseassasssassessss essasssaassessa assess aas ss = sa sss asses eases eessaeea assess ssa assess eaeses assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-027 22 23 RC-SW-C4 ELB LR -PIPE UT-45S 06.00 0.719 24 25 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RH-009 26 27 RC-FW-292 NOZZLE -PIPE PT 1-2-03 12.00 1.125 NO 28 UT-50S 1-2-03 R 1-003 29 30 RC-SW-A3 PIPE -ELB LR PT 1-2-03 12.00 1. 125 NO 31 UT-505 1-2-03 32 33 RC-SW-A4 ELB LR -PIPE PT 1-2-03 12.00 1. 125 NO 34 UT-505 1-2-03 R 1-003 35 36 RC-SW-A5 PIPE -ELB LR PT 1-2-03 12.00 1. 125 NO 37 UT-505 1-2-03 R 1-003 38 39 RC-SW"A6 ELB LR -PIPE PT 1-2-03 12.00 1. 125 40 UT-50S 1-2-03 R 1-003 41 42 RC-FW-291 PIPE "VALVE PT 12.00 1. 125 NO 43 UT-50S R 1-003 44 45 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RH-010 46 47 RC-FW-289 NOZZLE "PIPE PT 1-2-03 12.00 1. 125 48 tet t t t t t tt t tet tt t t tf tt tt tt t t t t t t t t t t t t tt tt tt t a*tet t t t*tt t t t t tet et t t t t tt t t t t t t t et tt t t t t et st t t t t tt et et t tet t t 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
160 ttttttttttttttttttttttttttttttftttt ttttttttttt*ttfttttttttttttttttttta+ttttttttttat tttttttttttttttttttttttttt*ttttttt t NUTECH CAROLINA POWER 8) LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWEP. PLANT - UNIT PLANNING 1
st st t*tt t tt st t t tat
~
5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 159 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t t tt t t tt t t t t t t t ttt t t tt ttt t t t t tt t tt t t t t t tt t t t tt t t t t t t t t' t t t t t t t tt t tt t t' t 1 t 88/01/12
'7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY =
DATE 8 t t' t t t t t t t t 9
10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >s 4 IN.
12 13 tt t t t t t tt t t tt t t tt t t t t t t t tttt *t t t t t t t t t t t t tt t tt t
- t tt t t t t t t t tt ttt t t t' t t t t tt t t tt t tt tt t t tt t t t tt t t t t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssssssssssssassssasss aaasassssassaas sass s aaasssasasssssss sssaa sssaa ======== sassss sas sssass ssaaas sassss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-SI-025 22 23 SI-FW-536 VALVE -PIPE UT-45S 1-1-01 06.00 0.719 NO R 1-003 24 25 RC-SW-J4 PIPE -ELB LR PT 1-1-01 06.00 0.719 26 UT-45S 1-1-01 27 28 RC-SW-J3 ELB LR -PIPE PT 1-1-01 06.00 0.719 29 UT-455 1-1-01 30 31 RC-FW-295 PIPE -NOZZLE PT 1-1-01 06.00 0.719 NO 32 UT-45S 1-1-01 33 34 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-SI-026 35 36 SI-FW-543 VALVE -PIPE PT 06.00 0.719 NO 37 UT-455 R1-003 38 39 RC-SW-A6 PIPE -ELB LR PT 1-2-03 06.00 0.719 40 UT-45S 1-2-03 41 42 RC-SW-A5 ELB LR -PIPE PT 1-2-03 06.00 0.719 NO 43 UT-455 1-2-03 44 )
I 45 RC-SW-A4 PIPE -ELB LR PT 1-2-03 06.00 0.719 NO UT-45S 1-2-03 46 47 tttttttttttttttttttttt'tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 {02I83!
162 t tii t t t t t t tt t t ttt t tt t t t t t t i i t t t i *t i tt tt i t i t t i t i t t t t t t i t t t t tt tt t t tt ! t t t tt i' t t tt t t' t tt tt i tt t t t t t ft t i t t t t i t tt t tt t i t t 2
1 NUTECH CAROLINA POWER Er LIGH1 COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3
4 PLANNING 1
titttttttttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 161 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA. INTERVAL 01 ONLY DATE 88/01/12 t It tt t t t t t t t t t t tt t tt t t t tt t t t t tt t t t t t t t t tt ttt t tf t i t ii t t t t t t t f ii tt t t t t t t tt tt t t t t t t t i t t t t t t t t t t t t i t t tt t i t i t i t t tt tt t t t t t t 9
10 CATEGORY B-1J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9. 11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >s 4 IN.
t t t ir t ttt tt t ttt t tt t t t t t tt ttt t tt t t tt t t t t ttt t t t t t' i t tt t t t t t t t t i t i t t t t ttt i tt t t tt t f i t t t t t t tt t t t t t tt i t i t tt t i tt t t t t 12 13 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULEO INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES
'19 sssssssasesassssssssssss ssasssesssasass assess sssessssssasesas asses asses aassssss === s sss assess assess assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-SI-028 22 23 SI-FW-535 VALVE -P BEND UT-455 06.00 0.719 NO R1-003 24 25 RC-SW-F3 P BEND -ELB LR PT 1-1-01 06.00 0.719 26 UT-455 1-1-01 27 28 RC-SW-F4 ELB LR -PIPE PT 1-1-01 06.00 0.719 NO 29 UT-455 1-1-01 30 31 RC-SW-FS PIPE -ELB LR PT 1-1-01 06.00 0.719 32 UT-455 1-1-01 33 34 RC-SW-F6 ELB LR -PIPE PT 1-1-01 06.00 0.719 NO 35 UT-45S 1-1-01 36 37 RC-FW-296 PIPE -NOZZLE PT 1-1-01 06.00 0.719 NO 38 UT-45S 1-1-01 R 1-003 39 40 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-009 41 42 RH-FW"204 VALVE -PIPE PT 12.00 1.125 NO 43 UT-50S R 1-003 44 45 RH-SW-B3 P BEND -PIPE PT 12.00 1. 125 NO UT-50S 46 47 ii ir t t t i tt t t t t il t tt t t it t t t t ir tt t t *t t i tt t t ir tt t t t t t ttt t tt tt tt t t tt tt t tt t t t tt tt tt t t it t t i t i t i t i t t i tt tt t t tt t tt i tt *
- tt t tt t t i t t ir 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 102I831
163 1 t fr f aft t st t tat tat t'sf at t fr f f t' f t tfft tt t t f fff tft tt tt t f tft f t t t f tft t f ff ft t f t t t t t t t f ff t tt t t t t' t t t E tffr ft t t t fft tt t f f' ftf 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRIS IM SHEARON HARRIS NUCLEAR POWER PLANT UNIT 3
4 PLANNING ffft COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 162 ASME SECTION XI. 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 ttf 'ff'ftffttttttftftttttttttftfftttfttttf sf sf ttftttttftttftftf ttttttttttftt*fff tttfat fttftttfat sf fttfIEff ttf88/01/12 THE SUMMER 1983 ADDENDA. INTERVAL 01 ONLY DATE staff sf f f tt 9
10 CATEGORY B-LJ PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9. 11 CIRCUMFERENTIAL WELOS IN PIPING, NOMINAL PIPE SIZE >s 4 IN.
12 13 t ff *t t t t t t *ftf 'f f t t t t t t t t t f t t tt *t ft t
- ftt t t
- t f t f t t ft ftt t ff t f t f 't t t t t t f f t tftt t t t f t tttt t t tf t f t f ff t ff t t 'f t t t t t 'f t IEI 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM ECHE- CU~TPRIOR DIAN THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 rEErsrssssssssssssssassaa ssasssssassssss ararat sssssrasEEsaaasrr stars rsssr asrrrsr arras sara EEaaEEss assEEss 20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-009 22 23 RH-FW-203 PIPE -ELB LR PT 12.00 1. 125 24 UT-505 25 26 RH-SW-C3 ELB LR -PIPE PT 12.00 1. 125 NO 27 UT-505 28 29 RH-FW-202 PIPE -ELB LR PT 12.00 1. 125 NO 30 UT-505 31 32 RH-SW-D3 ELB LR -P BEND PT 12.00 1. 125 33 UT-505 34 35 RH-SW-D4 P BEND -ELB LR PT 12. 00 1 . 125 36 UT-505 37 38 RH"FW" 199 ELB LR -PIPE PT 12.00 1. 125 NO 39 UT-505
~ 40 41 RH-SW-E3 PIPE -ELB LR PT 12.00 1. 125 42 UT-505 43 44 RH-SW-E4 ELB LR -PIPE PT 12.00 1. 125 NO 45 UT-505 46 t t t t f f tft t t t t t t tt t t tf t t tt t t 'f t f tf t f t ffftt ff t t tt t t f ftt ttt t tt t t t t tf
- tf f f f t f f t t ft tft **t 'f tt tt t t tt ft tt t t t t t f t f t f't t ff t t t t f t f 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
164 t t t t t t t' t tt tt t t t t tt t tt t t t t t t' t t t t t tt t tt tt tttt t' t t ttt t t tt t tt t
- t t t t t tt t t t t t t tt t t t t t t t t t t tt t t t tt t tt t t t t t t t t t tt t t t t t tt t t t NUTECH CAROLINA POWER 8 LIGrl. COMPANY PR I 5 IM
- SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t t t 4 t t t t t t*t 1
PLANNING COMPONENT LISTING ANO ISI 10 YEAR PLAN: 835-01 PAGE 163 ASME SECTION'XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 88/01/12 ttttttttttttttttttttttttttttttttttttttttt*ttttttttttttttttttttttttttttttttttttttttttttttttttttttttt THE SUMMER 1983 ADDENDA> INTERVAL 01 ONLY ttttttttttttttt DATE
~
9 10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ll ITEM NO. B9.11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >$ 4 IN.
12 13 't t t ttt t t tt t 't t t tttt t ttt tt tt t tt t tt t t t t tt t tt t t t t t t t tt t t tt t t t t t t t tttt tt t t t tt t t *tt t t tt tt t tt t tt t t t tt t ttt t tt t t 't t tt t 14 15 DONE 16 OUTAGE THIS DONE COMP NOhl BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 $ $ ~ $ $ $ $ $ $ $ ~ $ $ ~ $ $ $ $ $ $ $ $ $ $$$$ $ $$$~$$$$ $~$$$~ ~$~$$$ $$ ~$$~$$$~ $$~$$ $ $$ $ $$$ $$$$$$ $~$~$$ $$$$$$
20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC. NUMBER: I I-RH-009 22 23 RH-SW-E5 PIPE -ELB LR PT 12.00 1. 125 NO 24 UT-50S 25 26 RH-SW-E6 ELB LR -PIPE PT 12.00 1. 125 27 UT-50S 28 29 RH"FW"200 PIPE -VALVE PT 12.00 1. 125 NO 30 UT-50S R 1-003 31 32 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I -RH-010 33 34 RH-FW-198 VALVE -P BEND PT 12.00 1. 125 NO 35 UT-535 R 1"'003 36 37 RH-SW-B6 P BEND -PIPE PT 12.00 1. 125 NO 38 UT-53S 39 40 RH-FW-197 PIPE -ELB LR PT ~
12.00 1.125 NO 41 UT-50S 42 43 RH"SW-C3 ELB LR -PIPE PT 12.00 1. 125 NO 44 UT-535 45 4e RH-SW-C4 PIPE -PIPE PT 12.00 1. 125 NO 47 t t t t t t t tt t tt t t t t tt t t t t t ttt t t t t t t t t t 't t t t t t t t t t t t t t tt t t t t t t t t t t t t t t t t
- t t tt t t t t ttt tt t t tt tt t t t tt t tt t t t t tt t t t t t t t ttt t tt t t 48 49 50 51 52 53 54 55 58 57 58 59 eo
167 1 1 1 1 '1 1 1 1 1 1 1 t f 1 1 1 f 1 1 1 f 1 1 f tff1 1 t tff 1 tf1 1 1 11 1 1 1 1 1 1 1 1 f t 1 1 1 1 1 1 1 1 1 1 t 1 f t 1 tf1 1 1 1 1 1 1 1 *1 f 1 1 f 1 1 1 1 1 f 1 1 1 1 1 1 1 1 1 1 t1 f1 1 1 1 1 t 1 tft 1 1 1 f 1 t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT UNITrr,1 4 PLANNING 111111111 tf1 1 1 1 1 1' 1 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 166 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 f f1 f1 tff1fftfftf 1tttff1f1 ttttfff11 ttffttfffft*ftfff1 tttttf1tfftfff1 ftff1ff1 11*11 tfffff11 7
9 10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9. 11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >$ 4 IN.
12 13 1 1 1 t)lt 1 1 1 1 1 1 1 1 tr 1 t 1 1 *f1 f 1 t 1 1 1 1 1 1 1 1 f 1 1 1 1 1 f 1 1 1 1 f 1 1 1 f 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
'1 '1 11111111 t1 1 1 1 1 1 1 1 11 1 111 1 1 1 1 1 1 11 1 1111 11 11 1 1 '1 11 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI
.17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $$ $$$$$$$~$$ ~$$$$$$$ $$$$ $$$$ $$$$$$ $$$$$$ $$$~$$$$~$~$$$$$ ~$$$$ $$$$ $ $$ $~$$$$ $$$$$$ ~$$ $$ $$ $ $ $ '$ $ $ $ ~ $
20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: II-SI-021 22 23 SI-SW-C3 ELB LR -PIPE PT 12.00 1. 125 NO 24 UT-455 25 26 SI-FW-548 PIPE -ELB LR PT 12.00 1. 125 NO 27 UT-455 28 29 SI-SW-D3 ELB LR -PIPE PT 12.00 1. 125 NO 30 UT-455 31 32 SI-SW-D4 PIPE -ELB LR PT 12.00 1. 125 NO 33 UT-455 34 35 SI-SW-05 ELB LR -PIPE PT 12. 00 1 . 125 NO 36 UT-455 37 38 SI-FW-549 PIPE -VALVE PT 12.00 1. 125 NO 39 UT"535 R 1-003 40 41 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-022 42 43 SI-FW-551 VALVE -PIPE PT 12.00 1. 125 NO 44 UT-535 R 1-003 45 SI-SW-C3 -ELB 12.00 1. 125 t tfPIPE 46 LR PT 47 1111 1 1 f 1 1 1 tf1 1 1 1 t 1 1 1 1 1 1 1 1 t 1 1 1 ff 1 1 1 1 1 I 1 1 1 1 1 1 1 1 1 1 trt tf 1 1 1 1 1 1 1 f1 1 1 1 1 1 f 1 1 1 1 1 1 1 1 1 tftf t 1 1 1 1 1 tf1 1 1 tt 1 1 1 1 48 49 50 51 52 53 54 55 56 57 58 59 60 FORIVI 0113 (02I83)
171 et tet t f tf sf fr t sf t et et tet et t tt t f t tft t f t ft t f t t f t f et t t t t t tt t t t tet t t t'f t t tt sf et t taft t t et t et t t t t t f f t t t t tet**'tf NUTECH CAROLINA POWER 8 LIGHT COMPANY PRIS IM t f SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING fr t t f t et t t t f t t't t f t t COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 170 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tttfttttfffffet fftaft fet ft tet tet tf tttff et tet tftftf sf tet ttttftttftf et tttttf tfr tftetf fffDATE tf tft 88/01/12 fff tfet f tet 9
10 CATEGORY 8-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE >s 4 IN.
12 13 sf f sf frtet frfrt t tet tet f f tt tet tft f staff sf et t et f t f sf sf frfr et f f tft f et t tt f t fr tt t t et et t f t t t taft et t fr ft off t sf t t ff 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM s
18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 saassassreassasssssaessa ssssssesaasssss sssras sarsssseasassars arras asser eraser e eseasa sas ssaara assess rasa 20 21 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER : II-SI-024 22 23 SI-FW-586 PIPE -ELB LR UT-455 06.00 0.719 NO 24 25 SI-SW-83 ELB LR -PIPE PT 06.00 0.719 26 UT-45S 27 28 SI-SW-B4 PIPE -ELB LR PT 06.00 0.719 NO 29 UT-45S 30 31 SI-SW-85 ELB LR -PIPE PT 06.00 0.719 NO 32 UT-45S 33 34 SI-SW-B12 PIPE -PIPE PT 06.00 0.719 35 UT-45S 36 37 SI-SW-B6 PIPE -ELB LR PT 06.00 0.719 38 UT-455 39 40 SI-SW-87 ELB LR -PIPE PT 06.00 0.719 NO 4'I UT-455 42 43 SI-FW-587 PIPE -VALVE PT 06.00 0.719 NO 44 UT-455 ~ R 1-003 45 48 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-025 47 SI-FW-539 -PIPE 06 . 00 0. 7 19 48 49 t f t et f t fffff f It t t t tl t ttt VALVE PT NO
'f f t f 'f f t t f 'f ft f f t t 'f f f ft f f 'f 'f t f ffft ff 'f f t ft fr It f f ff f t 'f 'f t f tr t t t 'f 'f t 'f fft ft f sf f 'f t t ff f 'f f f t t t f t t ffft f f t III III III 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 102I83)
172 sf tat st t st st st st tt t tt st t t t t t tt t t st t t t tt t tt t t st tt t t tt st t t t tt t t tt st tt tt t tt t t t tt t st tat t't t t t tt t tt tt t t t tt t tt t ttt t t t st t t t t t NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1
ttttttttttt*ttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 171 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL'1. ONLY DATE 88/01/12 tttttttttttttst tttt tatttttttttttttttttttttttttttttttttttttsfttttttttttttttttttttt ttttttttttttstttttttttt ttttt sttttttt 9
10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.11 CIRCUMFERENTIAL WELOS IN PIPING, NOMINAL PIPE SIZE >s 4 IN.
12 13 t tt t rt t t t t t t t t tt t t rt tt t tr t t t t t t t t t t t tt tt t t 't t' t t tt t t t t t t t t t t t t t tt t t t 't 't t t tr t t t t t t t t ttt t t t ttt tt tt t t t t' t t tt tt t t t t tr t t t t t llr 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM DESCRIPTION DULED INT INT (IN) (IN) TIONS NOTES tttttttt 18 NUMBER TYPE ACCESS SELECT IND REOST 19 asaasaasasssassssssassss asssss a ass ' a saasssa sasass sas ssasss ssaasa ssssss 20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: II-SI-025 22 23 SI-FW-539 VALVE -PIPE UT-45S 06.00 0.719 NO R 1-003 24 25 SI "SW-H4 PIPE -ELB LR PT 06.00 0.719 NO 28 UT-455 27 28 SI-SW-H3 ELB LR -PIPE PT 06.00 0.719 NO 29 UT-455 30 SI-FW-538 PIPE -ELB LR PT 06.00 0.719 NO 32 UT-455 33 34 SI-SW-I9 ELB LR -PIPE PT 06.00 0.719 NO 35 ttst UT-45S 38 37 SI-SW-IB PIPE -ELB LR PT <<06.00 0.719 NO 38 UT-455 39 40 SI-SW-I6 ELB LR -PIPE PT 06.00 0.719 NO 41 UT-455 42 43 SI-SW-I7 PIPE -ELB LR PT 06.00 0.719 NO 44 UT-455 45 SI-SW-IS 06.00 0.719 48 47 t tat ttt tt ttt t tt ttsttt"PIPE ELB LR t st t ttt ttt t ttttst tat tat tatttttttt tttttt**ttt t t srtt ttttt PT NO t st t tt t t t t t tt t ttt st tt tt tt t t t st 48 49 50 51 52 53 54 55 58 57 58 59 I50 FORM 0113 102I831
.0
174 It t t t t t tt t t t t tt tt t t f t ttt ftt f 0 t t f tt t tt t tttt t tt t t t tt f t*tOf *Sf t t t f t*tt f t t t t t fft t t tt t t ft t ff f f t t t t t t t t t t t t t t t f t t f t f t t*tt t t t NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 'f SHEARON HARRIS NUCLEAR POWER PLANT UNIT PLANNING f flttttfttt*t*ttttttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 173 ASME SECTION. XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t THE SUMMER 1983 AObENDA, INTERVAL 01 ONLY DATE 88/01/12 f f fff tff f tf f f f tff f tff f ff tftttft f f f tf f tff f f f f ft f ttfff tf ff ttff f ff f ft tt ttff f tf f tf f f tff t ttfffff ff f f ffff f ff f tftff 9
10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.11 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE )s 4 IN.
12 13 ttfIlltftftfttttftfttfttff tffttttftttttttfff fttttttfttttttff tttft'ttttttftf tff ttttttttttff ttftttftfttff tttftftttttttt'ftft 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $$$$$$ S S S' S S Rgg ~ $ $ $ $ $ $ $ $ $ ~ S ~ ~ R'$$ ~ $ $ ~ $ ~ $ ~ $ $ $ $ $ $ $ $ $ $ $ SSRRRS SSS SR 20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-026 22 23 SI-SW-C4 PIPE -ELB LR PT 06.00 0.719 YES 24 UT-45S 25 26 SI-SW-C3 ELB LR -PIPE PT 06.00 0.719 27 UT-455 28 29 SI-FW-545 PIPE -ELB LR PT 06.00 0.719 30 UT-45S 31 32 SI-SW-B5 ELB LR -PIPE PT 06.00 0.719 NO 33 UT-45S 34 35 SI-SW-B4 PIPE -ELB LR PT 06.00 0.719 38 UT-45S 37 38 SI-SW-B3 ELB LR -PIPE PT "06.00 0.719 39 UT-45S 40 41 SI-FW-544 PIPE -VALVE PT 06.00 0.719 NO 42 UT-45S R 1-003 43 44 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-027 45 SI-FW"602 VALVE -P BEND PT 06.00 0.719 f fthm f tft t t fft ft tt t t tff ft t tf 4 f f t tt t ttt tt t ff tfff f t tt tft t t ttf t tt tfft t t tft f t tt t f t t f' f f t t t t f ft tftt t*tt tt t t t tt t tt t t t t tt tt tf 45 47 48 49 50 51 52 53 54 55 se 57 58 59 eo FORM 0113 102I83)
I fI II It f tttIIt tfII tIIIII I I tfI IIII IIIII I Its IItfI I IIIIIIIIIfI tfIIII I t It> ate I tt I tft tftftfIII I tI IIta I tfI t f *II IIt tfI tfIIII 178 NUTECH CAROLINA POWER 8 LIG!!: COMPANY PRISIM SHEARON HARRIS NUCLEAR POWEl! PLANT UNIT II 'I IIII 'I I 'IIIIt IIII 1
III II PLANNING COMPONENT LISTING ANO ISI 10 YEAR PLAN: 83S-01 PAGE 177 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01'NLY DATE 88/01/12 I IIIIIIIII II II ItII I III I tIIII I I t I I I II III I III II I II I II *tII II 'I I I I I t I t IIIIIt II ItI I I t I II I III I I I II I I I I I I II t t II I III I I I t *I I rlr rlr rlr 9
10 CATEGORY B-0 PRESSURE RETAINING WELDS IN PIPING 11 .ITEM NO. B9.11 CIRCUMFERENTIAL WELDS IN PIPING. NOMINAL PIPE SIZE > 4 IN.
12 13 I t*tI I I ttIIt III I I It f I I I t IIItffI I f t II tfIII f IIIII I III tt II tII I IItI I I I I If IIIt t tt*ttfI III III I IIIII III tIII I I III I tt'I I t I I t tfI 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULEO INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sassssssssssss sssssasss assess asses ss ss s s sasaassasssassss asses eases aasssaas assess sas assess assess assess 20 21 SYSTEM: SI SAFETY INL/ECTION ISOMETRIC NUMBER : II-SI-028 22 23 SI-FW-534 PIPE -VALVE PT 06.00 0.719 NO UT-45S 1-003 24 25 fftet ItfI IIIIIIIIIIII IIII IttttttttttftftfIfttfttttfIIttftftttttttt'I'tfttttfItttftfR I IfIIII tttftttttftf 28 27 28 29 30 31 32 33 34 35 38 37 38 39 40 41 42 43 44 45 48 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 !02I83!
rIl
180 t t t t t t tt tt ttt tt t ttt t t t t t t t tt t t t t t t t t tt t t t t t t t t t' t t t t t t t tt tt t t t tt tt t t t t t t ttt t t t t t tt t t t' t t t t tt t t t t t ttt t tt t *t t' t t tt t t NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1
t t hatt t et t et et et t at t 5 t COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 179 6 ASME SECTION XI. 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THEs SUMMER 1983 ADDENDA INTERVAL Oj ONLY DATE 88/01/12 8 tt t t t t t tt t t t t t t t t t t t t t t t t t t t t t t t t' tt t t t t' tt t tt t t t t t t t t t t t t tt t t t t t tt t t t t t tt t ttt t t t tt t t t t tt t t t tt t tt t t t t t t t tt tt t tt t tt tt t 9
10 CATEGORY 8-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.21 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE ( 4 IN.
12 13 ttttttttttttttttttttttttttttt*ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt
~
14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 aaaaaaaa --= estates aaa aaaaaaaaaaaaaaa aaaaaa aaaaaaaaaaeaaaaa asses aaaaa settee a aa aaa aaaaea aaa ae aaaa-20 21 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II"CS-094 22 23 CS-FW-3082 PIPE -VALUE PT 03.00 0.438 NO 24 25 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-097 26 27 CS-FW-3074 VALVE -PIPE PT 03.00 0.438 28 29 CS-FW-3071 VALVE -PIPE PT 03.00 0.438 30 31 CS-SW-E4 PIPE -ELB LR PT 03.00 0.438 32 33 CS-SW-E3 ELB LR -PIPE PT 03.00 0.438 NO 34 35 CS-FW-3072 PIPE -VALVE PT 03.00 0.438 36 37 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER: II-CS-102 38 39 CS-FW-3083 VALVE -PIPE PT '03.00 0.438 NO 40 41 CS-FW-3084 PIPE -VALVE PT 03.00 0.438 NO 42 43 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER: I I-CS-103 44 45 CS-FW-3101 VALVE -P BEND PT 01.50 0.281 46 47 CS-FW-3102 P BEND -VALVE PT 01.50 0.281 NO 48 49 CS-FW-3103 VALVE -PIPE PT 01.50 0.281 NO 50 CS-SW-A7 PIPE -TEE PT 01. 50 '0. 281 NO 51 52 t t ttt t t rt t t t t t t t t t t t t t t t t t t tt tt t ttt t t t t t t t t tt t t tt t t t tt t t ttt 1 t t t t t t t t t t tt t t t t t tt t t t tt t t 't t It t tt t t t tt t t t t t t t t t 53 54 55 56 57 58 59 60 0
183 t t tt t t t tt t tt t t t t t t t t t t t t t ttt t t tt t
- t t t t t tt
- t t t **t t t *t *t ttt t t ttt t t tt t t tt t t ttt t tt t t t t t ttt t t t t t t t t t t t t t t t t tt t ttttt t t t t
- 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t 4 PLANNING t t t t tt tt 't tt t t t t t 't t t COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 182 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t *t t t' 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t t t t tt t t t t t 't t t t t t t t t tt t tt t tt t t t t t t t t t t t t tt t tt t t t t tt tt t t t t t tt t tt t tt t t t t t' tt t t tt t 't t t' t t DATE lit ll!
- t'
- t t *t
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- t t t t t tt t t
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10 CATEGORY B-iJ PRESSURE RETAINING WELDS IN PIPING
~ 11 ITEM NO. 89.21 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE < 4 IN.
12 13 t t t t tt t 't t t t t t t ttt tt t t t t tt t t t t t t t t t 't tt t t t t t t tt ttt t **t t t t t t t tt tt t t t t t t t t t t t tt t t t 't tt t 't t t t t t t t t t tt 't t t t t t t tt t t t t t t t t 't tt t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 eraseeaaasaaaaaaaaamraa armessssmrssess assess esssasmssammaaes mares meara erase a assama saa arrear smears assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-CS-102 22 23 RC-FW-443 PIPE -NOZZLE PT 1-3-06 03.00 0.438 NO 24 25 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-CS-106 26 27 RC-131-1-SW-2 PIPE -PIPE PT 02.00 0.344 NO 28 29 RC-131-1-SW-1 PIPE -ELB LR PT 1-1-01 02.00 0.344 NO 30 31 RC-SW-A4 ELB LR -PIPE PT 02.00 0.344 32 33 RC-FW-346 PIPE -VALVE PT 02.00 0.344 34 35 RC-FW-347 VALVE -PIPE PT .-"02.00 0.344 36 37 RC-FW-348 PIPE -VALVE PT 02.00 0.344 38 39 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-008 40 41 RC-SW-L5 PIPE -TEE PT 02.00 0.344 NO 42 43 RC-SW-L3 TEE -REDUCER PT 02.00 0.344 NO 44 45 RC-SW-L4 TEE -PIPE PT 02.00 0.344 46 47 RC-SW-D3 REDUCER-PIPE PT 03.00 0.438 48 49 RC-FW-302 PIPE -VALVE PT 03.00 0.438 50
-PIPE t t t t t t t tt t tt tt t tt tt t t t t t 03.00 t t t t tt 0.438 RC-FW"303 51 52 t t t 't t t t t t tt t t t t t t t tt ttt tt VALVE t t t tt t t t t t tt t t tt PT NO t t t t t t t t 't tt t tt t *t tt t t tt t t t t t tt t t t t' t t t t t tt t t t t 53 54 55 56 57 58 59 60 FORM 0113 (02/83)
tt et t t t tet t tet t t sf et t t t t t t <<t t t t t t tt t t t t*ttent t et t et t et t t t't t t t ttt t et t t t t 184 t tt t et tet et t t et t tet et t t t - t NUTECH CAROLINA POWER & LIGH>'OMPANY PRI SIM SHEARON HARRIS NUCLEAR POWE': PLANT - UNIT PLANNING ttttttttt 5 COMPONENT .LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 183 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
'7 THE SUMMER 1983 ADDENDA'NTERVAL 01=ONLY DATE 88/01/12 8 t t tt t t t t t t tt tt t t t t t tt t t t t t t t t t t tt tt ttt t t tt ttt t t t t t t t t t tt t tt t t t t t tt t t t t t t t t tt t ttt tt t t t tt t t t t tt t tt tt t *tt tt tt t t ttt t t ttt t 9
10 CATEGORY B"%J PRESSURE RETAINING WELDS IN PIPING ll ITEM NO. 89.21 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE < 4 IN. 12 13 t tt t t tt t t t
- tt t tt tt t t t t t t t t tt ttt t t t t t t t t tt t tt t t t t t t t t t tt t t tt t t t t
- tt t e tt tt t t t t t' t t t t t t' t t t t t' t t tt t t t tt t t t t t t t t tt t tt t t t t 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssssssaassssssssaaasa ssssssssssasass assess a sssasessaesass tease asses ~ ssas as assess sss assess assess assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I "RC "008 22 23 RC-SW-CS PIPE -TEE PT 03.00 0.438 24 25 RC-SW-C4 TEE -PIPE PT 03.00 0.438 NO 26 27 RC-SW-C3 PIPE -REDUCER PT 03.00 0.438 NO 28 29 RC"SW-C6 TEE -PIPE PT 03.00 0.438 30 31 RC-SW-C7 PIPE -ELB LR PT 03.00 0.438 NO 32 33 RC-SW-CB ELB LR -PIPE PT 03.00 0.438 NO 34 35 RC-SW-C9 PIPE -FLG WNO PT 03.00 0.438 NO 36 37 RC-SW-83 FLG WNO-PIPE PT 03.00 0.438 NO 38 39 RC-FW-304 PIPE -VALVE PT 03.00 0.438 40 41 RC-FW-305 VALVE -PIPE PT 03.00 0.438 42 43 RC-SW-AB PIPE -ELB LR PT 03.00 0.438 NO 44 45 RC-SW-A7 ELB LR -PIPE PT 1-3-06 03.00 0.438 NO 46 47 RC-32-4-SW-1 PIPE -PIPE PT 03.00 0.438 NO 48 49 RC-SW-A6 PIPE -ELB LR PT 1-3-06 03.00 0.438 NO 50 51 RC"SW-AS ELB LR -PIPE PT 1-3-06 03.00 0.438 NO 52 53 RC-SW-A4 PIPE -ELB LR PT 1-3-06 03.00 0.438 NO 54 t tt t t tt t tt ttt t t tt t t t t t t tt tt t t t t t t tt tt t t t t tt t t t tt t tt t tt t
- t t t t t t t t t t t t t t tt t t t ttt t t t t tt t t t tr *f t t t t t t t
- t t t
- t t t t t t t t t t t t t t t 55 56 57 58 59 60 FORM 0113 (02I83) e 0
h 185 t f t t t l t t t l t t t t t t t tt f t ft t l t t t
- t t t ft t t l tf t t tt t ftt t f t t l t lt t l tt t tt t f t l t t f l tt l t t t t t tt t l I t l t l' l l l l tt t t t l f t t t t ft l t ft t 't CAROLINA POWER 8 LIGHT COMPANY PRISIM l'UTECH f ft tiltttfff ttlltfl SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 184 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 f t't'ttlfttff ttttttt*ttltttttttiltt*ttttttttlttttttfI ttttflittf*lf*ttt*lltl*l THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tifftttltttftttt tttttltflttlttl DATE 88/01/12 tt fitttlttt 9
10 CATEGORY 8-IJ PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. 89.21 CIRCUMFERENTIAL WELOS IN PIPING. NOMINAL PIPE SIZE < 4 IN. 12 13 ffttltttffittt'lfttttttltttttttttttttttltttf tttltfttttttfttlttftttttttttltttttttttttttftflttttttttttttttt tfftftt 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 $$$ $$$$$$$$$$~$~$~$ $$~$$$~$$~$ ~$~ ~ $~$$$$ $$$$$$$ $ $$$$ ~ $~$$$ $ ~$$$ $ $ $$$$$$ $$$$$$ $$$$$~ 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-008 22 23 RC-SW-A3 ELB LR -PIPE PT 1-3-06 03.00 0.438 NO 24 25 RC-FW-306 PIPE -NOZZLE PT 1-3-06 03.00 0.438 NO 26 27 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-010 28 29 RC-SW-H7 PIPE "TEE PT ,03.00 0.438 NO 30 31 RC-SW-K3 REDUCER"PIPE PT 03.00 0.438 NO 32 33 RC"FW-313 PIPE -VALVE PT 03.00 0.438 NO 34 35 RC-FW-314 VALVE -PIPE PT 1 03.00 0.438 36 37 RC-SW-HB PIPE -TEE PT 03.00 0.438 NO 38 39 RC-SW-H9 REDUCER-PIPE PT 03.00 0.438 NO 40 41 RC-SW-H6 TEE -PIPE PT 03.00 0.438 42 43 RC-SW-H5 PIPE -ELB LR PT 03.00 0.438 NO 44 45 RC-SW-H4 ELB LR -PIPE PT 03.00 0.438 NO 46 47 RC-SW-H3 PIPE -FLG RFW PT 03.00 0.438 NO 48 49 RC-SW-I3 FLG RFW-PIPE PT 03.00 0.438 NO 50 51 RC" FW-315 PIPE -VALVE PT 03.00 0.438 NO 52 RC-FW-316 VALVE -PIPE 03.00 0.438 53 54 tlttftfftttttftttttfttfttttf tftiffttfftfttftfltltttttttttttlttttttttfltttttttttlf PT ttfttttttlftttltltttffNO ttttttftttttlt 55 58 57 58 59 80 FORM 0113 (02/83)
186 t t 1 4 1 1 lf 4 1 4 1 4 4 4 1 III 1 4 4 4 4 4 4 4 4 t 1 'at 4' 444444411444 tt4 t41 4 4444 4444 14 III 14 f 4 1 f4 4 4 t 4
'4 4' 4 4 '4 4 4 1 4 4 4 1 4 4 1 1 f4 4 '4 4 1 4' 4 t 4 4 4 4 4 1 4 4 4 4'4 4 1 1 4 tl 1 4 NUTECH CAROLINA POWER 8t LIGHT COMPANY PR IS IM 4 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3
4 PLANNING 1 tttftttftf 4 ttf'1 fttf 5 COMPONENT LISTING ANO ISI 10 YEAR PLAN: 83S-01 PAGE 185 6 ASME SECTION. XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA; INTERVAL='0) ONLY DATE 88/01/12 t 7 8 1144444 f 4 44 fttf1tttttftttttf 44 ftf fttftf4ttf ttftf 1 4 44rf tttttttttttftttftttttftttttttttttttttf 4 44tttt 9 10 CATEGORY B-Lj PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. B9.21 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE < 4 IN. 12 13 11141 41 ftff f 1 ttt414 1 f 1 ttf*4t4tft44*ttf4tttt41 4 f tf ttt tttt ttf41tt tt 44ttt tttttttf tttttftftftf44 ttttttftf14tt tt tff 4 444441441 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 16 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 assssssasassassasasssasa assssaaaassssaa asasaa aaasssaassssssss stats stats aasssa 4 ssasss sas asasas assssa asssss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RC-010 22 23 RC-SW-Lj8 PIPE -ELB LR PT 03.00 0.438 NO 24 25 RC-SW-LJ7 ELB LR -PIPE PT 03.00 0.438 NO 26 27 RC-SW-Lj6 PIPE -ELB LR PT 1-1-01 03.00 0.438 NO 26 29 RC-SW-LJ5 ELB LR -PIPE PT 1-1-01 03.00 0.438 NO 30 31 RC-SW-d4 PIPE -ELB LR PT 1-1-01 03.00 0.438 NO 32 33 RC-SW-Lj3 ELB LR -PIPE PT 1-1-01 03.00 0.438 NO 34
- 35 RC-FW-317 PIPE -NOZZLE PT 1-1-01 03.00 0.438 NO 36 37 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: II-RC-011 36 39 RC-SW-H3 REDUCER-PIPE PT 03.00 0.438 NO 40 41 RC-SW-H4 PIPE -TEE PT 03.00 0.438 NO 42 4 43 RC"SW-K3 REDUCER-PIPE PT 03.00 0.438 NO 44 45 RC-FW-308 PIPE -VALVE PT 03.00 0.438 46 47 RC-FW-309 VALVE -PIPE PT 03.00 0.438 NO 48 49 RC-SW-H5 PIPE -TEE PT 03.00 0.438 NO 50 51 RC-SW-He TEE -PIPE PT 03.00 0.438 NO 52 53 RC-SW-H7 PIPE -ELB LR PT 03.00 0.438 t t t t 54 1 4 1 1 4 1 1 1 1 4 1 1 4 1 4 1 1 4 4 1 4 4 4 1 1 4 4 4 Lt 1 4 1 1 Lt 4 4 1 1 Lt 4 1 1 4 4 4\ 1 1 Lt 4 1 1 4I 1 1 1 ft 1 4 4I 4 4 1 1 4 1 4 1 1 4 1 4 1 4 1 1 1 4 4 1 4 1 1 1 1 4r 1 1 1 4I 1 4 1 1 1 1 4 4 1 1 1 4 1 4 4 1 1 4 4 1 4 4 *1 55 56 57 56 59 60
187 1 t tt t t tt t t t tt t*t*tt tt tie t tt t tt t t tt*ttt tt tt 4 t tt tt t t t t t*t*tt t t*tt t tt tt t tt t t tt t t tt t t tt tt t tt t t t t t tt tt t t t tt tt t t tt t t tt t t t tt t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRIS IM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 r 4
- PLANNING t t t t t t t t t' tt t t t t t tt COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 186 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 t t t ttttttt tt t tt tt t t t
- t t t t t t t t t t 't t t t t t t t t tt t t t t t t t t t t t t tt t t t t tt t t t t t t t 't t t 't t t tt t t t ttttt t t t t t 't t t t t t t t t' DATE tr tr ill t t t rt t t t t t t t tt 't t 9
10 CATEGORY B-J PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. 89.21 CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE ( 4 IN. 12 13 t t t t ttt t t t t tt t t t t t t 't t t t t t tt t' t t ttt t t t tt t tt t t t tt t tt tt t t t t t t t t tt t t t t t t t t t t t t tt t t' t t t t t t t tt tt tt t t t t t t t t t t t t t t t tt t t t t ttt 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM DESCRIPTION DULED INT INT (IN) (IN) SELECT IND REOST TIONS NOTES 18 19 ttttt'Rtttttt ttttttt ttt t NUMBER
~ t TYPE ttt tt tt ttttt t tlat ACCESS Stt t t ttt tt tttRtt ttttt
~ tt 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RC-011 22 23 RC-SW-H8 ELB LR -PIPE PT 03.00 0.438 NO 24 25 RC-SW-H9 PIPE "FLG WNO PT 03.00 0.438 NO 26 27 RC-SW-I3 FLG WNO-PIPE PT 03.00 0.438 28 29 RC-FW-310 PIPE -VALVE PT 03.00 0.438 NO 30 31 RC-FW-311 VALVE -PIPE PT 03.00 0.438 32 33 RC-SW-J8 PIPE -ELB LR PT 03.00 0.438 NO 34 35 RC-43-4-SW-2 ELB LR -PIPE PT . 03.00 0.438 NO 36 37 RC-SW-J6 PIPE -ELB LR PT 1-2 "03 03.00 0.438 NO 38 39 RC-SW-J5 ELB LR -PIPE PT 1-2-03 03.00 0.438 NO 40 41 RC-SW-J4 PIPE -ELB LR PT 1-2-03 03.00 0.438 NO 42 43 RC-SW-J3 ELB LR -PIPE PT 1-2-03 03.00 0.438 44 45 RC-43-4-SW-1 PIPE -PIPE PT 03.00 0.438 NO 46 47 RC-FW-312 PIPE -NOZZLE PT 1-2-03 03.00 0.438 NO 48 49 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RC-022 50 51 RC-149-3-SW-6 RED TEE-PIPE PT 03.00 0.438 52 53 RC-149-3-SW-9 PIPE -ELB LR PT 03.00 0.438 NO 54 tt tt t t tt t t t t t t tt tt t tt t t t tt t t t t
- t t ttt t t t t t
- t t tt t t tt
- t tt t t t t t t t t t t tt t t tt t t t t t t t tt t t tt t t t t t tt t t t t t t t t tr t t t t t t tt t t 55 se 57 58 59 60 FORM 01'13 (02I83)
195 t t t t t t tt t t t t t t t t t tt t t t t t t t t t t t t t t t t t tt t t t t t t t tt t t t t t t t t t t t tt t t t t t t t tt t t t t t t t t 't 't t t t t t t t t tt t t t t t t t t t t t 't t ttt t t t t t t t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT " UNIT 4 PLANNING t t t t t t t t t t t t t t t t t t 't 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 194 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 7 6 t st tt t tt t tt t tttt t ttt tt t t t tt ttt t ttt THE SUMMER 1983 ADDENDA. INTERVAL 01 ONLY at at tat t t t tat't t ttt tttt t tat t tt tt ttt tt tt tt tat at t tt tt tt tt t at t tat at tt at DATE tt st st't88/01/12 t at at atty 9 10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.32 BRANCH PIPE CONNECTION WELDS, NOMINAL PIPE SIZE < 4 IN. 12 13 t t t t t * 't t t t tt t t ttt t tt t t t tt t 't t t t t t tt t tt t t t t t 't t t t t t t t t t t t 't t tt t t t t t t t t t t t t t t t t 't t t t tt t t tt t t t 't t t t t t t t t t t t t tt tt t t t t t t t t t t t t I\I 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sassasss ssssasaaassssas assasssssasssss ssssss saassassasssaass stats asst saaaasss sssaas sss saasas 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-FMR-03 22 23 RC 19- SW" N6 PIPE -COUPLNG PT 1-3-06 29.00 2.330 NO 24 25 RC-10-19-SW-Nj PIPE -THERMOW PT 1-3-06 29.00 2.330 NO 26 27 RC-10-19-SW-09 PIPE -COUPLNG PT 31.00 2.480 NO 28 29 RC-10-19-SW-010 PIPE -COUPLNG PT 31.00 2.480 NO 30 31 RC-10-19-SW-011 PIPE -COUPLNG PT 31 . 00 2. 480 32 33 RC-10-19-SW-012 PIPE -COUPLNG PT 31 . 00 2. 480 NO 34 35 RC-10-19-SW" P7 PIPE -NOZZLE PT 1-3-06 31.00 2.480 NO 38 37 RC-10-19" SW-P8 PIPE -NOZZLE PT 1"3-06 31.00 2.480 NO 38 39 RC-10-19-SW-02 PIPE -NOZZLE PT 27.50 2.210 NO 40 41 RC" 10" 19-SW-03 PIPE "PIPE PT 27.50 2.210 NO 42 43 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-024 44 45 SI-SW-CB PIPE -SOCKOLT PT 06.00 0.719 46 47 SI"SW"BB PIPE -SOCKOLT PT 06.00 0.719 NO 48 49 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: II-SI-025 50 SI "SW-H5 06.00 0.719 51 52 tt t t t t t t t t PIPE -SOCKOLT PT NO tt t tt t tt t t t tt t t t t t t t t t t t t t tt t t t t t t t tt t t t t t t t t t t t t t t t t t t tt t t t tt t t t t t t t t tt t t tt t tt t t t 't t t t t * 't t t 53 54 55 56 57 58 t'ORM 59 80 0113 <02183)
196 tttt t t t tt tt tt tt t tt t tt tt t tt t t t t t t t t t tt t t t t t t t t ttt t t t t ttt t t t t t t t t t t t t tt t t t tt tt t t t t t ttt tt t tt t tt t t t t t tt tt tt t tt t t tt t tt NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING ttttttttttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 195 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA, INTERVAL'3 ODDLY DATE 88/01/12 8 t t t t t t t t *t t tt t t t t t t t t tt t t t t t t t t, t tt t 't t t t t t t t ttt t t t t t t tr tt t' tt t t t t t t t t t t
- t tt t tt t t t t t t t t t t t t t t tt t t t t t tt tt t t t t t t tr tt t t t 9
10 CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. 89.32 BRANCH PIPE CONNECTION WELOS. NOMINAL PIPE SIZE < 4 IN. t 12 13 t t t ttt t t t t t t t t t t tt tt
- tt t t t t tt tt t tt *t t ttt t tt t tt t t. t t t t t t t t t tt tt t tt t t t t t t t t t t t t t t t t t t t t t tt t t' ttt t tt t t t t t tt t t tt t t tt t tt t tt 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 $$$$$ $ $ $$ $$$ $$$$~$ $~ $$ ~ $$$$ $$$ $ ~$$ $$~$$ ~$ $$$$$ $$$$$$ $$$ $$~$$$ $$$$$$ $~$$$$
20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-025 22 23 SI-SW-I 10 PIPE -SOCKOLT PT 06.00 0.719 NO 24 25 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I "SI-026 26 27 SI-SW-C7 PIPE -SOCKOLT PT 06.00 0.719 NO 28 29 SI-SW-86 PIPE -SOCKOLT PT 06.00 0.719 NO 30 31 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-027 32 33 SI-SW-D6 P BEND -SOCKOLT PT 06.00 0.719 NO 34 35 SI "SW-D7 P BEND "SOCKOLT PT 06.00 0.719 NO 36 37 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-028 38 39 SI-SW-C6 PIPE -SOCKOLT PT 06.00 0.719 NO 40 SI-SW-CB 06.00 0.719 41 42 tttttt*ttttttttftttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt*t PIPE -SOCKOLT PT NO 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 {02I83J
197 t 't tt t t t tt t t t tt t t t t t t tt t t tt t t ttttt t t t tt tt t t t t t t tt t t t t t t t t tt t t t tttttt tt t t tt t t tt t t tt t t t t t t t tt t t tt t t *t t t t t t t t tt t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t tat t t tt t t 1 4 PLANNING at at at at 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 196 rlt ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t t tt rt ttttt t t tt t t t t ttt tt tt t tt tt t t t tt tt t t
- t t tt t t t t *t t t t tt t t t t t t tt t t t t t t t t t t ttt t t t t t t t t t t t t tt t t t t t t t tt t DATE t t tt t 88/01/12 7
tlt tt t t t t t tt t t 9 10 CATEGORY 8-LJ PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. 89.40 PIPE SOCKET WELOS 12 13 t t t t t t t t t t tt tt t t tt t tt t t ttt t t t t tt tt t t t t t t t t t t t t t t tt tt t t t t t t
- t t t t t t t t t t t t t t t t t t t t t t t t t t t tt t t t tt t t t t t t t t tt t t t t t t t t tlr 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM I6 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 ~ aseaaaaaaaaaaaaasaaaass aaasaaseessesss assess sssaassssssssssa asses ===== ===---=- assess saa assess -=---- assess 20 21 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-093 22 23 CS-FW-3075 VALVE -PIPE PT 1-3-06 02.00 0.344 NO 24 25 CS-SW-A3 PIPE -TEE PT 1-3-06 02.00 0.344 NO 26 27 CS-SW-A4 TEE -RED INS PT 02.00 0.344 NO 28 29 CS-482-FW-3074 VALVE -PIPE PT 02.00 0.344 NO 30 3'I CS-SW-AS PIPE -TEE PT 02.00 0.344 NO 32 33 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: II-CS-093 34 35 CS-FW-3076 PIPE -VALVE PT 1-2-03 " 02.00 0.344 36 37 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-CS-097 38 39 RC-FW-342 VALVE -PIPE PT 02.00 0.344 NO 40 !1 RC-FW-341 PIPE -VALVE PT 02 00 0 344 r NO 42 43 RC-FW-344 REDUCER-COUPLNG PT 1-2-03 02.00 0.344 NO 44 45 RC-SW-85 COUPLNG-PIPE PT 1-2-03 02.00 0.344 NO 46 47 RC-SW-84 PIPE -ELB LR PT 02.00 0.344 NO 48 49 RC-SW-83 ELB LR -PIPE PT 02.00 0.344 50 RC-FW-343 -VALVE 02.00 0.344 51 52 t t tt t t t t' tt t
- t tt t tttPIPE PT t t t t t' t t t t t ttt tt t tt
- t t t t tt t *t t tt t t t t t t t t t t t
- t t t t t t t t t t tt t t t ttt t t tt tt t t tt t t t tt tt t t t tt t tt t 't t t 53 54 55 56 57 58 59 60 FORM 0113 102I83)
4 4 44 4 4 4 1 1 4 1 t4 4 4 4f 1 1 4f tf1 at f f 41 44 4 4 1 tf4 1444 tt t tt4t4 1 tat 4'4 4 444 tf11 1 1444 4 tt 1 1 1 1 41 1 1 t 1t tf 1 4 1 4 t t 4 41 tf f 4 t4 t4t 4 4 1 414 4f 4 1 t4' 1 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 4 rlr PLANNING 4444 444444444 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 197 ASME SECTION.XI, 1983 EDITION THROUGH ANQ INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01'NLY 88/01/12 ttat 1441444'1'4 41'1 tt1 4 rlrttttfttf4 4 1 tat f1 4 1 t'tttftfttttttfttf 1 f1 1t4tr41 11 144'ttt tat 1 1trlrt f 4'4144 1114f 4 1 tf44'f 1'4 DATE t 4tf1 t111411 1111 9 10 CATEGORY B- J PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.40 PIPE SOCKET WELDS 12 13 ttttftftttftttf 44 taft tttttfttttttttttttftttftttttttttttftf tttf4 tttf4 tttt4 at 4 ttfttt tf ttttat 4 44444 tftat tttfttf4 4 tttf4 f4 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssssssaaassssssassssa sssssasssssssss ====== ====== = stats assss asass aaasssss asssss ssa sassss asasss sasaaa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-CS-106 22 23 RC-FW-345 PIPE -PIPE PT 1-1-01 02.00 0.344 NO 835-61 24 25 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-008 28 27 RC"FW-364 PIPE -MANIFLD PT 02.00 0;344 28 29 RC-38-1-SW-1 PIPE -PIPE PT 02.00 0.344 NO 30 31 RC-FW-354 NOZZLE -PIPE PT 1-3-06 02.00 .0.344 NO 32 33 RC-SW-U4 ELB LR -PIPE PT 1-3-06 02.00 0.344 34 35 RC-SW-IJ3 PIPE -ELB LR PT 1-3-06 02.00 0.344 NO 38 37 RC"FW-353 PIPE -VALVE PT 1-3-06 02.00 0.344 NO 38 39 RC-FW-352 VALVE -PIPE PT 1-3-06 02.00 0.344 NO 40 41 RC-FW-351 PIPE -VALVE PT 1-3-06 02.00 0.344 NO 42 43 44 RC-FW-350 VALVE -PIPE PT, 1-3-06 02.00 0.344 NO 45 RC-FW-349 PIPE -MANIFLD PT 1-3-06 02.00 0.344 NO 48 47 RC-FW-356 MANIFLD-PIPE PT 1-3-06 02.00 0.344 NO 48 49 RC-SW-M3 PIPE -FLG RFW PT 1-3-06 02.00 0.344 NO 50 51 RC-SW-03 FLG RFW-PIPE PT 02.00 0.344 NO 52 53 54 RC-FW-357 PIPE -VALVE
'1 1 4 4'4 f 4 444 44 4 4 4 4 4tf 4 444 1 1 1 f f 4 4 444444 tt PT tf4 1 1 t444tt 1 14144111 tftf tt4102.00 0.344 1 f 1 t441 11 tt 1 1 111 11 11 NO t f1 4t44114444 414 111 1 1*1 144 111 44 55 58 57 58 59 80 FORM 0113 (02I83)
200 1 t t t tt at tat at t t at t t ¹t f t t t t't t ¹ tt tt t t t ¹t t t t t t t t t t t t tt tt t t t tt t ti ~
~ ~ + et t ¹ t t t t t at t t t t t t t ¹t t t 2 NUTECH CAROLINA POWER & LIGHi'OMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWE. PLANT UNIT 1 4 t PLANNING t t t t t t 't t t t t t t t t t t t t COMPONENT LISTING ANO ISI 10 YEAR PLAN: 83S-01 PAGE 199 ASME SECTION XI, 1983. EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENOA, INTERVAL 0)-ONLY DATE 88/01/12 tttttttttttttttttttttttttttttttttttttttttttttf t*tttttttttttttttttttttttttttttt 9
10 CATEGORY B-%J PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. B9.40 PIPE SOCKET WELDS 12 13 t t t t ttt \ t t t t ¹ t tt t t t t t t t tt t ttt t tt t tt t t t tt tt t t t t t t t. tt tt t t t t t t t t t t t t t t t t tt t t tt t t tt ttt t tt ¹ t tt t t t t t ¹ t t tt t t tt t t t t, t' t t tt t t 14 15 DONE 15 OUTAGE THIS DONE . COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sssssassssassssaassasssa aaaasasasaassas raasas ssssaasaasssassa sass aaaaa aaaasaaa f saasss sss ====== sssass ssassa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-008 22 23 RC-FW-361 VALVE -PIPE PT 02.00 0.344 24 25 RC-FW-362 PIPE -VALVE PT 02.00 0.344 26 27 RC-FW-363 VALVE -PIPE PT 02.00 0.344 28 29 RC"36-3-SW-1 PIPE -ELB LR PT 02.00 0.344 30 31 RC-SW"F4 ELB LR -PIPE PT 02.00 0.344 32 33 RC-SW-F5 PIPE -ELB LR PT 02.00 0.344 34 35 RC-SW-F6 ELB LR -PIPE PT 02.00 0.344 NO 36 37 RC-SW-F7 PIPE -ELB LR PT 02.00 0.344 38 39 RC-SW-FB ELB LR -PIPE - PT 02.00 0.344 40 41 RC-36-3"SW"2 PIPE -PIPE 4 PT 02.00 0.344 42 43 RC-FW-365 MANIFLD-PIPE PT 02.00 0.344 44 45 RC-36-FW-367 PIPE -PIPE PT 02.00 0.344 48 47 RC-FW-366 PIPE -REDUCER PT 02.00 0.344 NO 48 49 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RC-010 50 51 RC-58-3-SW-2 ELB LR -PIPE PT 02.00 0.344 52 RC-60-1-SW-1 -TEE 02.00 0.344 ttttt PIPE PT 53 NO 54 t tt t t tt t t t t t t t t tt t t ttt t t' t tt tt t t t tt t t tt t t't t ttt tt t t t tt t ttt t t t t tt t t t t t t tt t t t tt t t '¹ tt t t 't t t 't t t t t 't 55 58 57 58 59 80 FORM 0113 (02/83)
201 t f ttftf ttff f tt*ttttttttftfttff f ttft tttftftf ttftttttfttt*fttf ttttf St*St tftttftttff tt f'ttttttfStd tftt*ft NUTECH CAROLINA POWER. 8 LIGHT COMPANY PRI SIN SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING t t t t t f 't fft f 'f t f t f 'f t III COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 200 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 t t t t tftt t tttf 'f t *t f *f f ft f lt t t t f 't ft tff f ff f t t f f ft f t t f tft tftt f t t f f ffff t t f ff tt f' lt f f f t t t ftDATE Ill f' f f f t ft t f' t t f t 't f f fff f ft f f fft t f t III 9 10 CATEGORY 8-IJ PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. 89.40 PIPE SOCKET WELDS 12 13 f tf t'ft t f t*t*tttt t t t t f f t ff *tft t fft t tfff f fthm t t t f t t tf tt t ftt tt f ff f f tft f t t t ff t f f t f f f t t t t t t Std ft tff tfff f ft tt t ft t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 S ~ $ $ ~ $ $ '$$ $$$$$$$$$$$$$ $ $ $ '$$ $ $ $ $ $ $ '$$ $ $ $ $ '$$ $ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ '$$ $$$$$ $$$~S S~S~$~$$ $$$$$$ S ~S $$ $$$$ $$$$$$ $$ 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-010 22 23 RC-FW-397 NOZZLE -PIPE PT 1-1-01 02.00 0.344 24 25 RC-SW-A6 PIPE -ELB LR PT 1-1-01 02.00 0.344 NO 26 27 RC-SW-A5 ELB LR -PIPE PT 1-1-01 02.00 0.344 28 29 RC-SW"A4 PIPE -ELB LR PT 1-1-01 02.00 0.344 30 3'I RC-SW-A3 ELB LR -PIPE PT 1-1 "01 02.00 0.344 32 33 RC-FW-398 PIPE -VALVE PT 1-1 "01 02.00 0.344 34 35 RC"FW-399 VALVE -PIPE PT 1-1-01 02.00 0.344 36 37 RC-FW-400 PIPE -VALVE PT 1-1-01 02.00 0.344 38 39 RC-FW-401 VALVE -PIPE PT 1-1 "01 02.00 0.344 NO 40 t c. 41 RC-SW-CS PIPE -TEE PT 1-1-01 02.00 0.344 NO 42 43 RC-SW-C4 TEE -REDUCER PT 1-1-01 02.00 0.344 NO 44 45 RC-SW-C3 TEE "PIPE PT 1-1-01 02.00 0.344 NO 46 47 RC-FW-402 PIPE -MANIFLD PT 02.00 0.344 NO 48 49 RC-FW-404 MANIFLD-PIPE PT 02.00 0.344 50 51 RC-SW-D3 PIPE -FLG RFW PT 02.00 0.344 NO 52 53 RC"SW-F3 FLG RFW-PIPE 02.00 0.344 tt fthm f ttttt ff f tf ttftf t*ttt t tffff f tft t tf f t f f f t St*f4 t t ff f f t t tf f t t t f t t t t tt t t tt t t ftf t t tt t tt ft tt t t tf t'f f tftttft PT NO 54 55 56 57 58 59 60 FORM 0113 102I831
203 tttttttttttttttttttttftttttt'tttttttttttttttttttttttt'ttttttttttttttttttttttttttt NUTECH CAROLINA POWER S LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING t t t at t t t t t t at st 4 tat t COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 202 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 t tttt t t t t tt t t t tt t t t t ttt t tt 't t 't t t t tt t t tt t t t tt tt t' 't tt t t 't tt t t t t t t t t t tt t t t t t t tt t t 't t 't t t t' t t t t t t t t tt t t t t t t tt t t t t t t t t t t t t t t t' 9 10 CATEGORY B-LJ PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.40 PIPE SOCKET WELOS 12 13 t tt t t t t t t t t t tt ttt t t tttttt t t t t tt t t t t t t t t tt tt tt t t t t tt t t tt t t t *t t t t t t t t t t t t t t t tt t t t t t t t t t t t t t t t t t t t t t t tt t tt t t t t t t t tt t t t t
)It 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 saaassassssassaaaaassass saasssaassssssa sassas ssassxasssaasasx stats s a sxasss sassss saa sssass asaaas ssasss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RC-010 22 23 RC-FW-408 PIPE -VALVE PT 02.00 0.344 NO 24 25 RC-FW-409 VALVE -PIPE PT 02.00 0.344 NO 26 27 RC-FW-410 PIPE -VALVE PT 02.00 0.344 NO 28 29 RC-FW-411 VALVE -PIPE PT 02.00 0.344 NO 30 31 RC-58-3-SW-1 PIPE "ELB LR PT 02.00 0.344 32 33 RC-58-3-SW-3 ELB LR -PIPE PT 02.00 0.344 34 35 RC-SW-M5 PIPE -ELB LR PT 02.00 0.344 36 37 RC-SW-MG ELB LR -PIPE PT 02.00 0.344 38 39 RC-SW-M7 PIPE -ELB LR PT 02.00 0.344 NO 40 41 RC-SW-M8 PIPE -PIPE PT 02.00 0.344 NO 42 43 RC-FW-412 PIPE -MANIFLD PT 02.00 0.344 NO 44 45 RC-FW-413 MANIFLD-PIPE PT 02.00 0.344 46 47 RC-FW-414 PIPE -REDUCER PT 02.00 0.344 48 49 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RC-011 50 51 RC-49-FW-391 PIPE -ELB LR PT 02.00 0.344 NO 52 1-2-03 RC-FW-373 SOCKOLT"PIPE t t t t t t 0.344 t t t t t t t t tt tt t tt t t t tt t t t t 02.00 NO 53 54 t t tt t ttt t t t t tt tt PT t t tt t t t t t t t t t t t t t tt t tt t t t t t t t t t tt t t' ttt t t t t t tt 55 56 57 58 59 60 FORM 0113 (02I83)
204 I st't t't mt t t sf t t t t tt t t tt mt'tt t t tt tet t tat't t't't tt t tt t t tt t t t tttt t't t tt t t mt mt t t t t t tt t t t t tt t t tat tt tt t mt hatt t st tt t mt tt tt t t't t t t t t 2 NUTECH CAROLINA POWER 8 LIGli'. COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING t ttt t t t t t ttt t tt t t' t COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 203 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 DATE 88/01/12 tttttttttttttttttttttttttttftttt*ttttt*ttttttttttttttttttttttttttttttttttttttttttttttt THE SUMMER 1983 ADDENDA; INTERNAL 01 ONLY 9 10 CATEGORY B-IJ PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.40 PIPE SOCKET WELDS 12 13 t ttt t t t t tt t t t 't t ttttt t t t ttt t t t t t t t t t t t' t ttt tt t' t t t t t t
- t t t t
- ttt t t f t ttt t t t t tt tt t t t t t t tt t t t t t t t tt t tt ttttt t t t t 't t 't t t t t t t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 aaasssasassasssaessaasss msssssamsssssas smmams amaaaamsamsaamaa seems s s mamma assama aa m s sasse-20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: II-RC-011 r
22 23 RC-SW-A4 PIPE -ELB LR PT 1-2-03 02.00 0.344 NO 24 25 RC-FW-374 PIPE -VALVE PT 1-2-03 02.00 0.344 26 27 RC-FW-375 VALVE -PIPE PT 1-2-03 02.00 0.344 NO 28 29 RC-FW-376 PIPE "VALVE PT 1-2-03 02.00 0.344 30 31 RC-FW-377 VALVE -PIPE PT 1-2-03 02.00 0.344 32 33 RC-SW-C5 PIPE -TEE PT 1-2-03 02.00 0.344 NO 34 35 RC-SW-C3 TEE -REDUCER PT 1-2-03 02.00 0.344 36 37 RC-SW-C4 TEE -PIPE PT 1-2"03 02.00 0.344 NO 38 1 39 RC-FW-378 PIPE -MANIFLD PT 1-2-03 02.00 0.344 NO 40 41 RC-FW-380 MANIFLD-PIPE PT 1-2-03 02.00 0.344 NO 42 43 RC"SW-03 PIPE -FLG RFW PT 02.00 0.344 44 45 RC-SW-F3 FLG RFW-PIPE PT 02.00 0.344 NO 46 47 RC-FW-381 PIPE -VALVE PT 02.00 0.344 NO 48 49 RC-FW-382 VALVE -PIPE PT 02.00 0.344 NO 50 51 RC"SW-G3 PIPE -ELB LR PT 02.00 0.344 NO 52 53 RC-SW-G4 -PIPE 02.00 0.344 54 tt ttt ttttt tttmt st tet t t t t ELB t tt tt LR PT t ttt tt tt t t tt t t mt tet t t tt t t t mt t tet*st t st t t tttt t t tet et st at mt mt t*tt t tt t t NO mt t t*tt t t t t tfr tt tt tt t 55 56 57 58 59 60 FORM 0 I I3 102I83)
206 1 t t tt t t t t ttt t t t t t t t t ttttt tt t t t tt t t tt tt t t tt t t tt t ttt ttt tt t t t t tt tt tt t tt tt *t t tt t t tt t t t t t t t t t t t ttt t t t t' t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - 3 4 PLANNING UNIT 1 ttttttttttttttttttt COMPONENT. LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 205 t = ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 t t tt t t t tt t t t t t tt t t tt t t tt t tt t t t t t t t t t t t t t t t t t t tt t t t tt t t t t *t t t t ttt tt tt t t t t t tt tt t t t t t t t t' t t tt t t t t tt t t t tt t tt t tt t t t t t t t 9 10 CATEGORY B-LJ PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. B9.40 PIPE SOCKET WELDS 12 13 t t t t t t t t t tt t tt tt t t ttt tt t t t t t t tt t t t t t t t tt t t t t t t *t t t t tt t *t t t t t t t tt t t t t tt t t t I tt t t t t t t tt ttt t t ttt t t t t tt t t t tt tt 14 15 ~ DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 asassasaasassaaaaassasas ssasaasssslssssa assssa sssaasaassassass arras aaaar === -- s sass sss sssass rsssss aaasss 20 2'I SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: II"RC-011 22 23 RC-FW-387 VALVE -PIPE PT 02.00 0.344 NO 24 25 RC-FW-388 PIPE -MANIFLD PT 02.00 0.344 26 27 RC-FW-389 MANIFLO-PIPE PT 02.00 0.344 28 29 RC-47-3-SW-3 PIPE -ELB LR PT 02.00 0.344 30 31 RC"47-3-SW-4 ELB LR -PIPE PT 02.00 0.344 32 33 RC-47-3-SW-5 PIPE -ELB LR PT 02.00 0.344 34 35 RC-47-3-SW-6 ELB LR -PIPE PT 02.00 0.344 38 37 RC-47-3-SW-1 PIPE -ELB LR PT 02.00 0.344 38 39 RC-SW-M4 ELB LR -PIPE PT 02.00 0.344 40 41 RC-SW-M5 PIPE -ELB LR PT 02.00 0.344 42 43 RC-SW"M6 ELB LR -PIPE PT 02.00 0.344 NO 45 RC-47-3-SW-7 PIPE -PIPE PT 02.00 0.344 46 47 RC-47-3-SW-8 PIPE -ELB LR PT 02.00 0.344 48 49 RC-SW-MB ELB LR -PIPE PT 02.00 0.344 50 51 RC-47-3-SW-2 PIPE -PIPE PT 02.00 0.344 52 02.00 0.344 53 54 RC-47-FW-391 -PIPE tttttttttttttttttttttttttttttttttttt1ttttttttttttttttttttttttttttttttttttttttttttttttttttt* PIPE PT
~ ttttttttttttttttttttttttt NO 55 58 57 58 59 60 FORM 0113 (02I83) e
207 tttttttttf1tttttttff1f1 ttftfttftlttftf1 ttltl1tttt tttttttt*tttttftttttllf1 tttltltf111**1tttttttf1 tltttttttftftttttf 1 NUTECH CAROLINA POWER 8t LIGHT COMPANY PRISIM PLANT - UNIT 11111'11Ittf tltlff ttt SHEARON HARRIS NUCLEAR POWER 1 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 206 ASME SECTION XI . 1883 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA'NTERVAL 01 ONLY DATE 88/01/12 1 1 1 1 1 1 11 1 11 1 1 f 1 1 t ~ 1 1 1 tt1 f f t f f 111 1111 1 1 11 1 1 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1 1 1 1 t lit t t*1 1 11 111 tt t t f ft 11'111 1 1 1 1 1 11 1 1 1 1 1 1 1 1 1 1 1 1 11 1 1 1 1 1 1 t1I 9 10 CATEGORY 8-J PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. 89.40 PIPE SOCKET WELDS 12 13 11 1 1 11 111 111111111111111 1111 111 f1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 t 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 '1 1 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ $ $ $ ~ SSSSSCS ~ SSSS $$ S S~ $$ SCS $$~$$~S ~1~$$~$$$ $$$~C $$$$~ $ $ 1 CRS $ $ $ $ $ ~ $ $ 1'$$ $ $ $ SSSSSS $ $ $ $ $ $ 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBFR: I I-RC-017 22 23 RC-FW-335 NOZZLE -PIPE PT 1-2-03 02.00 0.344 NO 24 25 RC"SW"A4 PIPE -ELB LR PT 02.00 0.344 26 27 RC-SW-A3 ELB LR -PIPE PT 02.00 0.344 NO 28 29 RC-FW-336 PIPE -VALVE PT 02.00 0.344 30 31 RC-FW-337 VALVE -PIPE PT 02.00 0.344 32 33 RC-FW-338 PIPE -VALVE PT 02.00 0.344 34 35 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RC-023 38 37 RC-SW-87 REDUCER-PIPE PT 02.00 0.344 38 39 RC-92-3-SW-2 PIPE -COUPLNG PT 01.50 0.281 40 4'I RC-SW-E4 PIPE -COUPLNG PT 1-1-01 01.50 0.281 42 43 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-016 44 45 SI-FW-722 VALVE -PIPE PT 02.00 0.344 NO 46 47 SI-SW-A3 PIPE -ELBOW PT 02.00 0.344 NO 48 49 SI-SW-A4 ELBOW -PIPE PT 1-2-03 02.00 0.344 NO 50 I-F W-723 PIPE 1-2-03 02.00 0.344 f1 f1 f1ttttttftttf tf tttttfl*tttttttttt ttttttttfttftttttt1 ttfttttfttf11 111 t1 f1
-SOCKOLT PT 51 52 S
111 1 tttttttfttttttttttf 1 NO 1 11't f1'tf1 1 53 54 55 56 57 58 59 60 FORM 0113 102I831
208 t tff f st t ah ha t tt t st tt t t st st tt t t f st f tt t t sf t t t t t tf t h t ha t f f ff f h t tt t t t t t f st f tfsf t st f t t t*fh f t st f ff f + f tf f ft ht f st fr f't t t t st t f
~
2 NUTFCH CAROLINA POWER & LIGHr'OMPANY PRISIM f t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t 3 4 PLANNING 1 frtff ttfIff ff tff *t 5 COMPONENT LISTING ANO ISI 10 YEAR PLAN: 835-01 PAGE 207 6 ASME SECTIONXI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t DATE 88/01/12 t f ttftttttttttttttttttttttttfttttttftttht tat ttthf f tsttf f tat tttftftttfttttfttttttttttat thhth't frtt't ah'f f tstt ttttttttttttf THE SUMMER 1983 ADDENDA'," INTERVAL 01 'ONLY 9 10 CATEGORY 8-J PRESSURE RETAINING WELDS IN PIPING ll ITEM NO. 89.40 PIPE SOCKET WELDS 12 13 f tttff f f ff ff ff tff f f tff ff tfrttt staff f tthtf ttttthftffhtff 1 hhtf f thttttfttftfttff ha f rttttftttt tttttttttfhf ff f httttt ttthth 14 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 raa rrarraararaaaaaaaaaa aaaaraaaaarrara ararat aaaaaaarrara raaarr aarara ara ararat aaaaar rara a 20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: II-SI-016 22 23 SI-FW-724 VALVE -PIPE PT 02.00 0.344 NO 24 25 SI-SW-83 PIPE -ELBOW PT 02.00 0.344 NO 26 27 SI-SW-84 ELBOW -PIPE PT 02.00 0.344 28 29 SI-FW-725 PIPE -SOCKOLT PT 02.00 0.344 NO 30 3I SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-017 32 33 SI-FW-898 VALVE -PIPE PT 02.00 0.344 NO 34 35 SI-SW-D19 PIPE -RED TEE PT 02.00 0.344 NO 38 37 SI-SW-018 REO TEE-PIPE PT 02.00 0.344 38 39 SI-SW-D17 PIPE. -ELBOW PT 02.00 0.344 NO 40 41 SI-SW-D14 TEE -PIPE PT 02.00 0.344 NO 42 43 S I F W-903 PIPE -VALVE PT 02.00 0.344 NO 44 45 SI-SW-D16 ELBOW -PIPE PT 02.00 0.344 46 47 SI "SW-D15 PIPE -TEE PT 02.00 0.344 48 49 SI-SW-D13 TEE -PIPE PT 02.00 0.344 50 51 SI-FW-904 PIPE -COUPLNG PT 02.00 0.344 52 SI-SW-C12 COUPLNG-PIPE 02.00 0.344 f sf sf ff f ftff ttttff f f f tftat tf f ttff ttfPT f f f f tfff tff f f tff fff tfsf f sf t f fat f fr htf f tff tff f f ff f ff st ff ff f ff f f tff f fffff tfff f 53 NO 54 55 56 57 58 59 60 FOAM 0113 102I831
,0
2 10. et at at at f f t t t t t f at t ff f t et t f at f t at tt ff ff f tat t t t t f t ft t t tff t t t t t f t et f tt tf f f t t t t f ft ft at t t t fff f t f t a**t t t tf t f ft t t t ft f t t t t t't
- NUTECH
- CAROLINA POWER & LIGHT COMPANY PRI SIN SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING t t t*ft t fff sf fff t sf COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 209 ASME SECTION, XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t tat t t tffftt ff tat t t ff t t fft f t sf t t*ft t at t t t tft tfff t tt tt ff/ f f aft THE SUMMER 1983 ADDENDA.. INTERVAL Oi ONLY D ATE 88 /0 1 2 t t t t tt sf tftt ff tt f t ff t staff tan f f f t f t ft t t f t t t t at f at t't at sf sf 9
10 CATEGORY 8"U PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. 89.40 PIPE SOCKET WELDS 12 13 taft tat sf tat at taft t ff tsf f t tt f at t tfft t t t t t t at ft t ff ft tt t t tt tet tf t t f tat t tet ft t t t sf t f't f f't ft f t*tf sf t t t t at f sf t t tt t t t t f t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND RFOST TIONS NOTES 19 ssssssssssssrsaesssrrass ssrssseasssssas erases ssaseasasssassss asses asses rrrsssss assess sss erases refers assess 20 21 SYSTEM: SI SAFETY INLIECTION ISOMETRIC NUMBER: I I-SI-018 22 23 S I-SW"FS PIPE "ELBOW PT 02.00 0.344 NO 24 25 SI-SW-F4 ELBOW -P BEND PT 02.00 0.344 26 27 SI-SW-F3 P BEND -ELBOW PT 02.00 .0.344 28 29 SI-FW-663 ELBOW -P BEND PT 02.00 0.344 30 31 SI-SW-E6 P BEND -P BEND PT 02.00 0.344 NO 32 33 SI-SW-E3 P BEND -ELBOW PT 02.00 0.344 34 35 SI-FW-662 ELBOW -PIPE PT 02.00 0.344 36 37 SI-SW-D3 PIPE -COUPLNG PT 02.00 0.344 38 39 SI-FW"963 COUPLNG-PIPE PT 02.00 0.344 NO 40 41 SI-SW-C3 PIPE -ELBOW PT 02.00 0.344 NO 42 43 SI- F W-964 ELBOW -PIPE PT 02.00 0.344 44 45 SI-SW-83 P BEND -ELBOW PT 02.00 0.344 NO 46 47 SI-FW-965 ELBOW -PIPE PT 1-1-01 02.00 0.344 48 49 SI-SW-A3 PIPE "ELBOW PT 1-1-01 02.00 0.344 50 51 SI-SW-A4 ELBOW -PIPE PT 1-1-01 02.00 0.344 NO 52 SI-SW-AS PIPE 1-1-01 02.00 0.344 53 54 at f at at at t at at sf t at et sf t at tf t t t tt-ELBOW PT f t at t t fff t at f' NO et t sf t t t*tff 4 f t f sf t tr f t t at sf t t t t'et at 1 t t aft sf tt t sf t t t't tat tt 'f f at t t sf t f t'f t 55 56 57 58 59 60
214 4 tt 4 4 4 t 4 4 44 4*4 t 4 4 tf4 4 4 4 4 4 44'4 44 4 4 tt'4*tf4 4 4 4 4'444 tft*f*4 4 % 444444 t 4 4 4 4 4 4 4 4 tie 4 4 4 t4 4 t 4 4 4 4 4 4 4 4 4 4 4 4 f 4 4 4 4 4 4 4 4 t 4 tt 4 4 4 t 4 tt 4' 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM
- SHEARON HARRIS NUCLEAR POWER >LANT - L'NIT 3
4 PLANLVING 1 tttf 4 tfttttttfttttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01
- PAGE 213 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL Of ONLY DATE 88/01/12 7
8 4tt44 444f 44 44444 tfftftf fttftttftttff4 tt4fttttt*4ttt*tttttftf ft*tfttfttttttfftt44tttff4f44'4 ttt4ttff4tttf tttttf'tttf4444 9 10 CATEGORY B-LJ PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. B9.40 PIPE SOCKET WELDS 12 4 4 4 4 4 4 4 4 44 4 44 4 tttf 4 4 44 4 4 4t 4 44 4 4 4 4t4 f 4t 4 t4 4 4 tt't 4 4 4 4 4 4 fthm t 4 4 4 4 4 4 t 44 4 t 4 4 4 tt 4 4 4 4 t 4 4 4 4 4 4 4 4 4 t tt 4 4 4 4 4 4 t4 4 tt 4 4 4 44 4 4 4 4 t44 4 4 4 4
=T 13 14 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT TO TRV RELIEF EXEMP" PROGRM
~ 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 20 21 SYSTEM: SI SAFETY INLJECTION ISOMETRIC NUMBER: II-SI"029 22 23 SI-248-1-SW-2 RED TEE-PIPE PT 02.00 0.344 NO 24 25 SI-FW-998 VALVE -P BEND PT 02.00 0.344 NO 28 27 SI-SW-B6 PIPE -TEE PT 02.00 0.344 28 29 SI "SW-B7 TEE -PIPE PT 02.00 0.344 NO 30 31 SI-FW-999 PIPE -SOCKOLT PT 02.00 0.344 32 33 SI-SW-B5 TEE -REDUCER PT 02.00 0.344 NO 34 35 SI-FW-939 VALVE -PIPE PT 02.00 0.344 NO 38 37 SI-SW-A6 PIPE -ELBOW PT 02.00 0.344 38 39 SI-SW-A5 ELBOW -PIPE PT 02.00 0.344 NO 40 41 SI-SW-A4 PIPE -ELBOW PT 1-3-06 02.00 0.344 NO 42 43 SI-SW-A3 ELBOW -PIPE PT 1-3-06 02.00 0.344 NO 44 45 SI-FW-940 PIPE -SOCKOLT PT 1-3-06 02.00 0.344 NO 4e 47 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: II-SI-030 48 49 SI-FW-993 VALVE -PIPE PT 02.00 0.344 50 51 SI-SW-A3 PIPE -ELBOW PT 02.00 0.344 52 SI-SW-A4 -PIPE PT 02.00 0.344 NO 53 54 44 4 4 4 tf4 4 44 4 444 4 tt tf4 tfELBOW 4 4 4 4 4 4 4 4 44 4 t4 4 4 444 4 44 44 4 t4'4 f 4 4 f t4 4 4 4 4 4 4 4 4 4 4 tf44 4 4 4 4 4 4 4 4 4 4' 444444 44*4 4 4 4 4 4 4 4 4 4 4 4 4 4 tf tt 4 4 '4 4 '4 '4 4 t 55 58 57 58 59 eo
tttttt ttttttttttttttttttttttt tttttttttttttttttttttt 2 lb 5 6 7 8 9 10 ll t t st t t tet t et st t t tt tet et st t t tt t st t t t t t st t t ft t et hatt t t t t t t t tt t t t tft t t tt st tt t t t t tt t t t et tt t t t tt t*t+tt t tt t t et 4 t*tt t et t et t t NUTECH t et t'ttrtst st t tttttttttst CATEGORY et ITEM NO. 810. 10 8-K-1 t st st CAROLINA POWER 8 LIGIII COMPANY SHEARON HARRIS NUCLEAR POWER PLANT - UNIT COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY INTEGRAL ATTACHMENTS FOR PIPING, PUMPS. PIPING INTEGRALLY WELDED ATTACHMENTS PLANNING ASME SECTION .XI, 1983 EDITION THROUGH ANO INCLUDING tt tet AND VALVES 1 PRISIM ttttttttttttttttttt PAGE REVISION NRCI tt tt t ttt t t*tt tDATE 88/01/12 215 t tt tet't tt st t tet 12 13 tt t t tr t t tt tt tt t t t t t t t t t t t t t t t t' t t t t t t t t t t t tt t t t tt tt t t t tt tt t t t t' tt tt t t t tt t t t t t t t t ttt t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 s asses s sass see asa-sa-s ae-- ee seas-- a-ae s-s e s a ~ sa assess a aa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: II-RC-024 22 23 RC-H-0075I(8) PIPE "LUG, PP PT 1-3-06 4.00 0.750 NO 24 25 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER : II-SI-025 26 27 SI-H-0982I (8) PIPE -LUG, PP PT ~ 1-1-01 06.00 0.075 NO 28 29 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: II-SI-026 30 SI-H-0149 I (8) 1-2-03 6.00 1.000 31 32 t t t t tt t -LUG, tt tt t t t ttt t t tr tt tt t t t t PIPE PP PT NO tt t tt t t tt t t t t t t t t t t tt t t t t t t tt t t t tt tt t t tt t t t t t t t t t tt t t tt t t t t t tt t tt tt tt t t t t t tt t tt t t t t t t 33 34 35 36 37 38 39 40 41 42 43
.44 45 ~
46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FOAM 0113 I02/83I e :
~
217 t sf 't st at tf tftaft at f t ft t*tt at sf at at ft tfhatt f t ft tt ft t t t f f t t t tt tt t t tt f t f t ft t f at t t 44 fthm t t tat t t t t %taft* f t*f *t*tt tat t t t'tt t t f NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT UNIT
'tf ttfttftf ttf'fttf'st 1
PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 216 ASME SECTION XI, 1883 EDITION THROUGH AND INCLUDI¹ REVISION NRC1 THE SUMMER 1883 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 ft f t t t t ft 't t 'f ft f *t f t fft t f t t t t t t t t f t
't t
- tt tt f f 'lt f t t t ft t t t t ft f tt tt t t t f f tt fftt fft t f t t f f f t t ftft
't 't *f t 1 t f f f
- f t t t ft t 't f tt 9
10 CATEGORY 8-L-1 PRESSURE RETAINING WELOS IN PUMP CASINGS ll ITEM NO. 812. 10 PUMP CASING WELDS 12 13 t t t t t tt t t t f t f t t t f t f t t f tftt t f t t t f t f t t t t t tt t t t t t t t t f t t f t t ft f t t f t f tt t f f t ff t f f t t t t' t t t tt
- f t t f f t t t t t t t t f' t t t t t t t t fff
- ft t 14 15 DONE 16 OUTAGE THIS DdNE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED IN1 INT (IN) ( IN) ACCESS SELECT IND REQST TIONS NOTES 19 s saaaasss s sasaaaas saasssaaaaaaass aaasas assassssssasaass aaasa asaaa ssasaaas saasaa aaa aasass asssas aaa s 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RCP-01 22 23 RCPA-CW-01 PUMPCW RT 1-3-06 072.0 NO R 1-058 24 25 RCPB-CW-01 PUMPCW RT 072.0 NO R 1-058 26 27 RCPC-CW-01 072.0 1-058 28 ttfftftftff ttftfttt tat at f at f at ttf at taft tsf PUMPCW RT f ttff tf t sf tftff f ff tf*ftftftffff ttfttff t sf fffffff f t at f ff atttttf ff ttfst ff f tf
~ NO R 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 80 FORM 0113 (02I83)
21jj 1 tttttttfttttt1ttttt*f f1 tttttfttf11 tf tf1*ttttttf1111111'1 fttrr fttttttttfttttff111111$ *11111*1 ttf ttttf11111 1 1 1 1 2 NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 11*1*1 f1tff1tf1 1 1 1 4 PLANNING 11 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 217 6 ASME SECTION XI, 1883 EDITION THROUGH ANO INCLUDING REVISION NRC1 fl THE SUMMER 1983 ADDENDAj INTERVAL 01 ONLY 88/01/12 7 ftttff1ttfttff1111*1 tttttttff1 tff1 ftttftttttttffttftttftff11 f1ffftttttfttttttttttttf tfttfttttf1DATE f1 tttttttf1 11 f1 9 10 CATEGORY B-L-2 PUMP CASINGS 11 ITEM NO. B12.20 PUMP CASING 12 f f 13 1 1 1 1 1 1 1 '1 1 1 1 1 1 1 1 1 1 tr 1 1 1 1 1 1 1 ff t 11 111111111111111111111111 tf 11111 11 f ft t t t t t 1 1 t 1111 11111 t 1 t 1 1 1 1 1 1 1 1 1 f1 1' 1111 f1 1 t t t 1 1 1 1 1 1 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 $ $ $ $ ~ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ ~ $ ~ $ ~ $ $ $ $ ~ $ ~ $ $ $ ~ $ ~ $ ~ $ $ $ $ $ $ $ $ ~ $ ~ $ $ $ ~ $ $ $ $ $ '$$ $ $ $ $ $ $ ~ $ ~ $ $ $ $ $ $ ~ $ $ $ 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RCP-01 22 23 RCPA-CASINT PUMP INT VT-3 1-3-06 NO R 1-058 24 25 RCPB-CASINT PUMP INT VT-3 NO R1-058 26 27 RCPC-CASINT PUMP INT VT-3 NO R1-058 28 111 tt 1 1 t 1 1 1 11111111111111111 f t 1 1 1 t 1 1 f1 1 1 1f 1 1 1 11 1 1 1 1 1 tt 1 1)ltf1 1 1 1 1 1 11 1 1 1 1 1 1 1 1 '1 1 tf 1 1 1 fr 1 1*1 fthm 1 t 1 1 f 1 1 1 1 11 1 1 t 1 1 1 t 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FOAM 0113 rj02I83) 0
Cr 223 1 at st st t st t a*tet t t t t tt t t t t t et t tet t tt t t t tt t t t t t t tt t t t t tt et tet et t tt tt t t st st t t t tet tt t tet tt et tet tt t t tet tt t et tt 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM t 3 t SHEARON HARRIS NUCLEAR POWER PLANT " UNIT t et et et t st tet t t t t tt t 1 4 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 222 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t t tt 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY ttt tt t t tt t tt t t t tt tt t tt t t t tt tt t t t t t t t t t t tt t t tt t t tt t t t t t t *t t t t t t t t t t t t t tt ttDATE t t t t t t ttt t t 9 10 CATEGORY B-M-2 VALVE BODIES 11 ITEM NO. B12.50 VALVE BODY, EXCEEDING 4 IN. NOMINAL PIPE SIZE 12 13 't t t t 't tt t t t t t t t tt tt t t tt t t tt t tr t t t t 't t t t t t t t t tt t tt t t t t t t t t 't 'I tt t 't t t t t tt t t t t t t t t t tt t t t t t t t t t 't t t t t t t t t t t t t t t 't t t tt t t t t t t t t 't
- t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sesssassasassassssssssss asses ssssaess assess sasassssssassasa esses sa sa aaaassaa assess aas a se = a assess 20 21 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: II-SI-027 22 23 1SI-135 INT VAL INT VT-3 1-3-06 NO R1-05A 24 25 1SI-137 INT VAL INT VT-3 1-3-06 NO R 1-05A 26 27 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER : II-SI.-028 28 29 1SI-134 INT VAL INT VT-3 1-1-01 NO R1-05A 30 1SI-136 INT INT VT-3 1-1-01 R1-05A 31 32 t t tt t tt t t ttt tt t t tt t t ttVAL tt t t t t t t tt ttt t t t t t tt t t t t t t t t t t tt t t tt t t t t t tt t t tt t t tt t t tt t t t t t t t t t t t t NO t t t t tt t t t tt t t t t t tt t t t t t 't 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I831
228 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttti <<Ctttttttttttttttttttttttttttttttttttt*ttttttt NUTECH CAROLINA POWER 8 LIGI;I COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING t tt t t t t t t 4 st t tt t t t t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 227 8 ASME SECTION XI, 1983 EDITION THROUGH AND;INCLUDING REVISION NRC1 DATE 88/01/12 7 8 ttttttttttttttttt*ttttttttttttfttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt*t THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 9 10 CATEGORY B-N-3 REMOVABLE CORE SUPPORT STRUCTURES (PWR) 11 ITEM NO. B13.70 RV CORE SUPPORT STRUCTURE (PWR) 12 13 ttttttttttttttttttttttttttttttttttttttt*tttttttttttt*ttttttttttttttt tttttttttttttttt*tttttttttttttttttttttttttttttttt l4 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT ( IN) ( IN) ACCESS SELECT IND REQST TIONS NOTES 19 sasassassaaassaasasassaa sssssaasasssssa saassa ssssasaaasasssas aassa stats -==-==== raa = sa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 CORE BARREL CSS VT-3 1-3-06 NO 24 t fttt t t tt tt t ttt t t t tt 't t t t t t t tt t t t tt t t t t t t t t t t t t tt t t 't t t t t t tt t ttt 't t t 't t tt t t t t t t t t t t t t t t t t tt t t tt t tt 't t t ttt t t tt t tt 't t t t t
- t t t t 25 28 27 28 29 30 3I 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 O.
229 ttt t tt t tt t 't t t t t t tttt t t t ftt t t t t t t tt t t t tt t t tt t t t tt t t t t t t t t t t ttt t tttt t tt t tt tt t t t t t t t t t t tt t t t t t t t t tt tt t t t ttt t t t t tt tt t t' 't NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING tttt*tttttttttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S"01 PAGE 228 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING. REVISION NRC1 tr tr THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t tt t t t t t t tt t tt t*tt 4 tt t t tt tt t*tt t t t tt t t*tt tt tt tt tt 4 tttt 4 tt t tt t*ttt t*tt t t t tt t t 4 t t t t t t t t t t tt ttt t t t DATE t t t t t 88/01/12 t t t tt tt t t t t 9 10 CATEGORY B-O PRESSURE RETAINING WELDS IN CONTROL ROO HOUSING ll ITEM NO. B14. 10 WELDS IN PERIPHERAL CRO HOUSINGS 12 13 't tt t t tt tt tt t t t tttt t t t t tt tt t t t t tt tt tt t tt t tt t t t t t t t t t t t tt t t t tt tt t t t t t t t t t t t tt t t t t t t tt tt t t tt t t t t t t t t t t t tt tt t t tt tt t t t t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULEO INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ '$$ $ $ ~ $ $ $ ~ $ ~ $ $ $ $ $ $ $ $ '$$ $ $ $$$$~$$$~$~$$~$ $$~$~$ $$ $$$$$$$$~$$ $~ ~$ $~$ $~$$ ~ $~$ ~$$$~ $$ ~$$$ $ ~$ $$ $ $$ $$$$$~ $$$$ $ $ 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RV-001 22 23 CRDH-42 CRDHW PT 04.00 0.625 24 25 CROH-43 CROHW PT 04.00 0.625 NO 28 27 CRDH-44 CROHW 'PT 04.00 0.625 NO 28 29 CRDH-45 CRDHW PT 04.00 0.625 30 31 CRDH-46 CRDHW PT 04.00 0.625 NO 32 33 CRDH-47 CROHW PT 04.00 0.625 NO 34 35 CRDH-48 CRDHW PT 04.00 0.625 NO 36 37 CRDH-49 CRDHW PT 04.00 0.625 NO 38 39 CRDH-50 CRDHW PT 04.00 0.625 NO 40 41 CRDH-51 CRDHW PT 04.00 0.625 42 43 CRDH-52 CRDHW PT ~ 04.00 0.625 NO 44 45 CRDH-53 CROHW PT 04.00 0.625 NO 46 47 CRDH-54 CRDHW PT 1-3-06 04.00 0.625 NO 48 49 CRDH-55 CRDHW PT 1-3-06 04.00 0.625 NO 50 51 CRDH-56 CRDHW PT 1-3-06 04.00 0.625 52 53 CRDH-57 PT 04.00 0.625 54 t t t t t t t t ttt t t t *t t tt CRDHW
- t t t tt t tt tt t t t tt
- t tt t t t t t tt tt t t tt t t t tt tt t t tt t tt t tt t t t t t t t t tt tt t t tt t t t t I t t tt t t t tt t t t t t 't t tt t t t t 55 56 57 58 59 60 FORM 0113 (02I83)
230 1 1 tat theft*111111 ttt*ttttt1ttttt 1tsttttthf ttf1th tththtt1 ttttthtthtftt1 1hhttthhttt1ttf ttttt ttttttttfttttt th 111 f 111111th 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PR IS IM 3 4 SHEARON HARRIS NUCLEAR POWE!! PLANT PLANNING UNIT 1 etttf tfttttttttttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 229 0 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING 1 REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 7 8 11111111111111 11 t tf t t t f 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 *1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t tt t 1 t t 1 1 t 1 1 1 1 1 t 1 1 f 1 1 1 1 1 1 1 1 1 t t 9 10 CATEGORY 8"0 PRESSURE RETAINING WELDS IN CONTROL ROD HOUSING 11 ITEM NO. B14.10 WELDS IN PERIPHERAL CRD HOUSINGS fttfftttttttftttttttftttttttttttf1tttttttttttththttttttttttttttttt*th*ttttttttttf 11111th tfhttttftttttftthttttttf11th 12 13 1 14 15 DONE 10 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssaeasaasssssasssssassss ssssaasasssaasa assess aas sees sse asses seats seaaseas assess sss assess = ss s ~ sass 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RV-001 22 23 CROH-58 CRDHW PT 04.00 0.625 24 25 CRDH"59 CRDHW PT 04.00 0.625 20 27 CROH-60 CRDHW PT 04.00 0.62S 28 29 CROH-61 CRDHW PT 04.00 0.625 NO 30 31 CRDH"62 CRDHW PT 04.00 0.62S 32 33 CRDH-63 CRDHW PT 04.00 0.625 NO 34 35 CRDH-64 CRDHW PT 04.00 0.625 30 37 CRDH-65 PT 04.00 0.625 NO ttf tf tt f1 1 1 1 f 1 1 1 I 1 1 1 1 1 et 1 1 1 1 1 t 1 1 1 1 1 1 f 1 1 1 ft 1 1 1 1 1 1'1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 et 1 t 1 t 1 f tf1 1 1 1 1 1 1 1 1 1 1 t 1 CRDHW 38 1 1 1 1 1 1 1 1 1 1 1 fr 1 1 1 1 1 1 1 1 1 1 1 1 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 00
232 t f f t f t st sf t at t at rt t st t't tf sf tt fr t tat tt st t tt t t tt st t t t st sf ftet sf t sf t t f f f t*tt et t t t t sf f t t f tft f f t tft t t t f t t ft t f t*t at f f t t f sf f t f NUTECH CAROLINA POWER & LIG))1'OMPANY PRI SIN f SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1 st tf ttt tat at t st tftt COMPONENT:LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 231 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ()NLY DATE 88/01/12
- f t't f t t t f staff et ft f t st taft tt t t sf t' t t t t sf et t t aft at st t tt ttt t t t t fthm at f f tt st t t f t t t' t st t t t f taft t ft ff tt t ft ttf st f st ttft t t' t st 9
10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15. 11 RV PRESSURE RETAINING BOUNDARY - STATIC 12 13 ttt t t t t f t tttftt ff t tt ft t t t t' t f t t t ft t tt t t *a ftt f t t tt tf t t t t t t t t t t t ft fftt tt tt ft t f' t tft t ft tt t f t t ff ttt t ft t t t tt t f t tt tt t t t' 't t t 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 a aaasessssssssasasaasss sssssaseeesaesa assess aasssssssaaassss asses eas s asssasas assess sss a -- assess assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RV-001 22 23 REACTOR VESSEL REACTOR VT-2ST 1-3-06 24 t ttf f ftf tft tft f tt t t t t t ttt t t t t t tt t t t t t tft t t t t t t t tt t tt t t tt t t tft **t t tt t tt t t t t tt t t t t t t' t t t t t tt t tt tt tt t f t ftt t t t t t t tt t t t
- t' 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60
233 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttt*ttttttttttttttttttttttt'ttttttttttttttt NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM HARRIS NUCLEAR PLANT - UNIT SHEARON PLANNING POWER 1 tttt*tttttttttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 232 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t t tt t 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t t t tttt 't t t t t ttttt t t t t 't tt t t t t tt tt tt tt t t tt *t t ttt t t t t t t tt t t t t t tt t tt t t tt t tt t t t t t t t t t t t t t tt tt t tttttt t t tt t t DATE t tt t t t ttt t t 9 10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. 815.20 PRZ PRESSURE RETAINING BOUNDARY - OPERATIONAL 12 13 t t tt tt t t t t t t t t t tt t tt t t t tt tt t t tt ttt
- tt t tt t t t t t t t t t t t t t t t t t ttt tt t t t
- t tt t t tt t t t t t t tt t t t t t t t tt t t t t t t t t tt t
- t t t t t t t 't t t 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXA61 SCHE- OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT INO REOST TIONS NOTES 19 asasssaasaaasssssssssass assssassa s = ======= === = aaasa stats sassas = ~ aaasss ssassa sssssa 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-PZR-01 22 23 PRESSURIZER VPZR VT-20T 1-3-06 NO 24 VT-20T 1-3-05 25 VT-20T 1-2-03 26 VT-20T 1-2-04 27 VT-20T 1-1-02 1-1-01 28 29 t t t t ttt t t t t t t t tt t t 't t 't t tt tt t tt ttt tt tt t t t t t VT-20T t t ttt
- t t t t t tt t tt t t t t t t tt t t t t t t t t t t t tt t t t t t t t t t t t tt t tt t t t tt t t t tt t t t tt t t 't t 't t 't t 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 48 47 48 49 50 5'I 52 53 54 55 56 57 58 59 60 FORM 0113 102I83)
tttttt aft tttttf'fl'ttff st tt tf sf taft tf tttfttfftf f ttt'tttt art tffLIGHi tat t rr'tttf sf tff tttttftttftfttttttt sf f tf tttfttf'ff ttsf 234 f st NUTECH CAROLINA POWER Er COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING ttt t t t ttt 't t t tff f tf COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 233 ASME SECTION XI. 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 88/01/12 staff tttttttttttff ttftttt*tttff ftttttfttffttttttftt'tttfttttfsttf f tttfttff ttttttftftf tftttttttfttttttt'ttttff f f st THE SUMMER 1983 'ADDENDA, INTERVAL 01 ONLY DATE 9 10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15.21 PRZ PRESSURE RETAINING BOUNDARY - STATIC 12 13 tt f t t t t t tt t t st t t sf t t ft sf *tt tt t t t t t t t t tt t t ft t t t t t t ft t t t t
- f t f t t t t tt t tt t t t ft f t t ft t tt t tt t t tt tt tt f t t t t*tt f 1
14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE 'ULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 sssssssssssassasssssssss sssasssasasaaas aasass ssssssssssssssas ssasa assss ssssassa ~ sasss == sssass ssssas ssssss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I "PZR-01 22 st staffttttsttttttf f tf ttttttttttttfttttttftt tftf tttf st stttttttf tat ttttttttftttt tat taft tttt 23 PRESSURIZER VPZR VT-2ST 1-3-06 NO 24 tat tat tttttf 25 28 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83) 0
236 t 5 f 5 tt t 5 t tt t t t'tf tff f5 5 5 5 f 5 t tfltd t t t't t 5 t f 5 t 5 t f f t fthm t tt 5 tftfft tftt t f t t t' 5 tt 5 t tt t t t tt tf t 5 t t f tf t 5 5 tt tf tt f 5 t tt t t 1 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 t f 5 t ff ttftf t tf5 5 5 f 5 1 4 PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 235 ASME SECTION XI, 1883 )DITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1883 ADDENDA; INTERVAL 0$ ONLY 88/01/12 f tf5 ttttf5 5 5 5 5 f 5 tftftf 5 tf 5 5 5 5 tftftff ttftf 5 5 5 tf 5 tf tttttft tttt ttf5 tftttttf5 ttttf5 ttft t t ttttf*fttf5 5 5 tftf5 7 DATE tf5 t f 555 9 10 CATEGORY 8-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15.30 SG PRESSURE RETAINING BOUNDARY - OPERATIONAL 12 13 f 5 '5 5 5 5 5 5 5 5 5 5 5 5 5 t tt 5 f 5 5 5 5 5 5 t 5 5 5 5 t
- tf *t 5 f t f 5 f 5 5 t t t t 5 5 t t t t t ft t f 5 t t t f t ft 5 t t 5 t 5 t t 5 5 5 5 t t 5 t 5 t tf t 5 t 5 5 5 t 5 5 t f t 5 t t t t 5 5 tft t t t t t t 14
.15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 5555 ~ 55 ~ 555 ~ 55 ~ 555555555 55 ~ 555555 '5 \5 5 5 5 55 5 55 5 5'555 ~ 5555'5 55555555 55 555 555555 555 5 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-SG-001 22 23 STEAM GEN C SGC VT-20T 1-3-06 VT-20T 1-1-02 24 25 tf*tf t tf tf5 5 fittft'tf tf tf 55 5 5 5 55 t t 5 tftf 5 5 5 5 fthmttt fthm tttf tfttf5 tf5 5 5 f t t t t5tt t tft ttttft tt'5 tt tf t t fit*itf5 5 t'5 tt 5 tff ttt t ft 5 5 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60
241 1 at st at at t at t tt *at t t t t t*tt t t t t t tt t t t t t tt at t t t t at t t t at t t t t tat at tt t at t tt st st t*t*tt t t t**ttt t t tt t t t t t t t st t at t t at tt t t 4 2 NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t t t t t t t t 't 1 4 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 240 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRCI THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t tt t t 88/01/12 t t t t tt t t t t tt t t t t t tt t ttt t t tt t t tt tt t t t t t tt tt tt t t t t t t t t t t t tt tt t tt t t t t t t tt t t ttt t t t t t t t t ttt t t t t t t t t. t t tt t t t DATE t t t t t tt t t tt 9 10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B 15. 50 PIPING PRESSURE RETAINING BOUNDARY OPERATIONAL 12 13 tttttttttttttttttttttttttttttttttttttttttttttttt*ttttftttttttttttttttttttttttttt 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT PSIG (F ) ACCESS SELECT INO REOST TIONS NOTES 19 assassssssassasasasaarsa asssssaasrssass srrrss saassassssssssss === = = rara ararat ras srrasa aasaaa sassss 20 21 SYSTEM ISOMETRIC NUMBER: II-CS-106 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-2-04 24 VT-20T 1-3-06 25 VT-20T 1-3-05 26 27 SYSTEM ISOMETRIC NUMBER: I I-CS-107 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 30 VT-20T 1-2-03 31 VT-20T 1-1-02 32 VT-20T 1-3-05 33 VT-20T 1-2-04 34 VT-20T 1-3-06 35 36 SYSTEM ISOMETRIC NUMBER: I I-FMR-01 37 38 PRESSURE TEST PRESSURE TEST VT-20T 1-3-05 39 VT-20T 1-2-03 40 VT-20T 1-2-04 41 VT-20T 1-1-02 42 ttttt t t 1 t tt t t
- t t t t t t tt t tt t tt t t t tt tt t t t t tt tt tt t t t t t t' t t t t t t t ttt tt t t tt t t t tt t t t t t tt t t t t t t t t
- tt t tt t t t t t t t t 't t t t' t ttt t t 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FOAM 0113 I02I83)
247 f f 'tf ttft t tttff t f t f t t t t tft tft tt t t t t tt hatt tt t t ff tf' f t t f t t t't t tt t t t tt t tff fthm t f'ff tf f t t t t tf t t ft f t f tff f f tf f fff t t f t t t t tt f f f t'f 2 NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 f 4 PLANNING ff t t ft t tf f' tt f t t t *'f COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 246 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 DATE 88/01/12 t ttttffttttt*ftf ttff ft*ttfffttttfft ftttttf*tttttf'fttttttff ttff ttttftt ttttttttttftttfffttttttttf fr THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tttff tf'ftf f tt 9 10 CATEGORY B-P ALL PRESSURE RETAINING COMPONFNTS 11 ITEM NO. B15.50 PIPING PRESSURE RETAINING BOUNDARY - OPERATIONAL 12 13 tt t t f t t t ft f f ft ft fff tff ffftff ft tff ff t fff ff ft ff *f4 ft t fff ff ff f t ft f t tt t tt ft ff t ft f t*tt f ff t*ft tf t tifft t ft ft t f tt t ft fff f ft f 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM DULED INT INT PSIG (F ) SELECT IND REQST TIONS NOTES 18 19 fffffffffffffff ff ffff Sfffffff NUMBER DESCRIPTION fS f TYPE
~ f fff'$$ ffff ~ ~~ f ff ffffff ffACCESS~ f fffffff f ~ f ff f 20 21 SYSTEM ISOMETRIC NUMBER : II-RC-025 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-3-05 24 VT-20T 1-1-02 25 VT-20T 1- 1-01 26 27 SYSTEM ISOMETRIC NUMBER: I I-RC-027 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-2-04 30 VT-20T 1-3-06 31 VT-20T 1-3-05 32 VT-20T 1-1-01 33 VT-20T 1-2-03 34 VT-20T 1-1-02 35 36 SYSTEM ISOMETRIC NUMBER : II-RH-009 37 38 PRESSURE TEST PRESSURE TEST VT-20T 1-1-02 39 VT-20T 1-2-03 40 VT-2'-1-01 Rt 41 VT-20T 1-2-04 42 t t ft t t t tt t t f f' t ff t f t llr!IIt t ff !I! III t' !II t f tr!Iftt t lit f t tt tr t f t f t ilr t f 'f f t fr It t f' t f f 'f f t f f t ft t 't f
- fff rlr!IIff t tft t f f ff t t t t t ft f t t t llr!lrt t f f Ill Ilr III ilr Ilr III Ilr ilr llr 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
248 ftttf4tftttttff444444*tttftffttfftftff4ttftftfttttfffftt4ttftttttt ttttttf44444444444444444tflttttfttttt4ttft4lft NUTECH CAROLINA POWER 8r LIGhlF COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 4 44 4 4'4 4 4 4 4 4 4 44 4 4 4 44 5 COMPONENT, LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 247 6 SECTION XI, 1983 EDITION THROUGH AND INCLUDING 'SME REVISION NRC1
'7 THE SUMMER 1983'ADDENDA, INTERVAL"01 ONLY 'DATE 88/01/12 8 4444 44444444 f tftfttttttttttf444444 tf4 tttttttttttttttf 444'f4 tttttttf tf 4 44 4 4444 4 tttttttttfttttt4 4**44'4 tf'tttttf 4 44 4'tf ttt 4
9 10 CATEGORY B-P ALL PRESSURE, RETAINING COMPONENTS 11 ITEM NO. B15.50 PIPING. PRESSURE RETAINING BOUNDARY - OPERATIONAL 12 13 4ttt 4 44 4 4t f 44 44 4 4 4 4 4 4 t4 4 4 4 4 tf4 4 4 tt44 4 4 4 4 4 t f4 4 4 4 4 4tf 4 4 4 f 4 4 4 4 4 4 4 t t 4 4 4 4 4 4 4 4 4 t4 4 4 4 tf 4 44 4 4 4 tf4 4 4 4 4 44 4 4 4 4 44 4 44 4 tt 4 4 f 44 4 4 4 tf 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM;, SCHE- OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE.. DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES
$ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ ~ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ '$$ $ $ $ $ $ $ $ $ ~ $ $ ~ $ $ $ $ ~ $ $ $$~$$ $ $$$ $$~4~4 $$~ $$~$$$ $$$$$$ $$$$$$
19 20 21 SYSTEM ISOMETRIC NUMBER: I I-RH-009 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1"3"06 24 VT-20T 1-3-05 25 26 SYSTEM ISOMETRIC NUMBER: I I-RH-010 27 28 PRESSURE TEST PRESSURE TEST VT-20T 1-3-05 29 VT-20T 1"3-06 30 VT-20T 1-2-03 31 VT-20T 1-2-04 32 VT-20T 1-1-02 33 VT-20T 1-1-01 34 35 SYSTEM ISOMETRIC NUMBER : II-SI-016 36 37 PRESSURE TEST PRESSURE TEST VT-20T 1-2-04 38 VT-20T 1-3-06 39 VT-20T 1-2-03 40 VT-20T 1-3-05 20T 1-1-02 41 42 '4tf 4 tf 444444 44 4444tttf f tt'tttf4 44444444 VT 44444 4 ttttftttf f t*t4f444ttl f4f t4 tttttt4lrtttfttt4t4t f4 tftf44444 ttf ttf ttf 4 4 44 4 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 {02I83) 0
249 1 tt t t tt tt t t t t tt t t t tat at t t t t tt tt hatt at t tt tt tat t*ttt t t tat tat tat t t t t t t t t t t t t t tat t f tat t t t t tt t t tt st at tt t t t t t t at at tat t tt t at tt 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 248 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 ttttttttttttttttItttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt*ttt THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88 /0 1 12 / 9 10 CATEGORY 8-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO, B15.50 PIPING PRESSURE RFTAINING BOUNDARY - OPERATIONAL 12 13 tt t tt t ttt t t t t t t t t t tt t t t t t t tt t t tt tt tt t t tt t tt t f t*tt ttt t t t *tt t t t t t t tt t t t t t tt t t t t t t t t t t t t t tt t t t t t tt t t t t t t t t tt t t tt t t t t t 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE" OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT INO REOST TIONS NOTES 19 ss a sssasssaassssa a s arts assaaa aasasaaa aa astra arras rsssssss s sss ararat arras sass 20 21 SYSTEM ISOMETRIC NUMBER: I I-SI-016 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 24 25 SYSTEM ISOMETRIC NUMBER: I I-SI-017 26 27 PRESSURE TEST PRESSURE TEST VT-20T 1-1-02 28 VT-20T 1-1-01 29 VT-20T 1-2-04 30 VT-20T 1-3-05 31 VT-20T 1-2-03 32 VT-20T 1"3-06 33 34 SYSTEM ISOMETRIC NUMBER: I I-SI-018 35 38 PRESSURE TEST PRESSURE TEST VT-20T 1-3-05 37 VT"20T 1-1 "02 38 VT-20T 1-2-04 39 VT-20T 1-1-01 40 VT-20T 1-2-03 VT-20T 1-3-06 41 42 t1tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 01'13 (02I83)
250 1 *1 1 1 f 1 1 1 tf 1 1 1 1 1 st 1 1 t t 1 1 f 1 1 f 1 1 1 t tf1 1 t 1 1 1 1 t1 t 1 t 1 tftt t 1 1 1 t tft 1 tf1 1 1 1 t+kt 1 t t 1 1 1 1 1 t 1 1 1 1 1 f 1 1 1 1 tf1 1 1 '1 1 t f 1 t 1 1 1 1 1 1 t 1 1 f 1 1 11 2 NUTECH CAROLINA POMER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POMER PLANT - UNIT 3 4 PLANNING 1 11 tf1 1 1 1 f*ttf tfttf1 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01
- PAGE 249 fr'ff ASME SECTION,XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
'1 1 1 '1'1 ttf tf 1 1 1'11 ttf'fftftf THE SUMMER 1983 ADDENDA, INTERVAL 01 OhlLY 111 tt11 1 f1 1'1 1 1 11 fttt*ttttf*f1tftf tf t1f f1 f1 1 1111 1 1 1 1 tffttftf1111 1 fsf 1 1 11111111 1 88/01/12 DATE 111 fftf1 ft'1 9
10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15.50 PIPING PRESSURE RETAINING BOUNDARY - OPERATIONAL tf t 1 t 1 1 1 t 1 1 1 tf tt 1 tf t 1 1 t 1 t 1 tf1 t 1 1 1 1 1 1 tf 1 1 t tf1 t 1 1 t*ttt 1 t t*f 1 1 1 t 1 1 1 1 1 t 1 1 1 1 1 1 1 1 tf 1 1 1 tf 1 1 1 tf tf tt1 1 12 t 13 1 1 1 1 1 1 1 1 1 1 1 tt f1 111111111 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM -SCHE- OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 sssssssaaaaassaasasrsrss sssssassssassss ssasaa saasaaasssasasrs arras s sas starts sss starts ararat 20 21 SYSTEM ISOMETRIC NUMBER: I I-SI-019 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-1-02 24 VT-20T 1-1-01 25 VT-20T 1-3-05 28 VT-20T 1-2-04 27 VT-20T 1-2-03 28 VT-20T 1-3-08 29 30 SYSTEM ISOMETRIC NUMBER: I I-SI-020 31 32 PRESSURE TEST PRESSURE TEST VT-20T 1-3-05 33 VT-20T 1-1-02 34 VT-20T 1-1-01 35 VT"20T 1-2"03 36 VT-20T 1-3-06 37 VT-20T 1-2-04
'9 38 SYSTEM ISOMETRIC NUMBER: I I-SI -021 40 41 PRESSURE TEST ,PRESSURE TEST VT-20T 1-1-02
'1 '1 42 1 1 1 1 1 1 1 tt t t 1 1 1 1 1 1 1 1 1 1 1t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 tt 111 tt 111111 f 1 1 1 t 1 1 1 1 1 1 1 t tt t 1 t1 1 1 1 1 tf 1 1 1 1 1 1 1 tf1 1 1 1 1 1 1 1 1 tf 1 1 1 1 1 1 1 1 1 1 1 1 1 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
253 1 ttfttf tffttttttttfftttttttfsff tfttttf tttfttttttttttftftftfttttfttf f f ftfff fttttttftttttttfttttffttf t*fttftttf sf f fit 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4 PLANNING 1 ttttfftff fttff tffsf COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 252 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t tet 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY ft t sf f f t'f t tfff t t sf ft f 'f t t ft t t t tt f t aft ft taft t f t it t'f ft t ft ft f sf f t t tft f t tt t t t f f at ft t tt tete ft tt t sf f tt t ft ft ttDATE t tet tf t ff 'f t 9 10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15.50 PIPING PRESSURE RETAINING BOUNDARY - OPERATIONAL 12 13 ttftaffeta tetf f f tftff sf tf*tet etf f f f ttff et f t tffthm tiff tf f tf tf sf f f ff tf ff f etf f t*tf t tf t*fff ff tttff f tt f ttfff tttet tf tf 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT INO REQST TIONS NOTES 19 ssassasssassssssasssssss asassasasssssss assess sasssssssssasssa esses ===== sssssass assess ass assess assess assess 20 21 SYSTEM ISOMETRIC NUMBER : II-SI-025 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 24 VT-20T 1-3-06 25 VT-20T 1-2-04 26 27 SYSTEM ISOMETRIC NUMBER: II-SI-026 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 30 VT-20T 1-2-03 31 VT-20T 1-3-05 32 VT-20T 1-1-01 33 VT-20T 1-2-04 34 VT-20T 1- 1-02 35 36 SYSTEM ISOMETRIC NUMBER : II-SI-027 37 38 PRESSURE TEST PRESSURE TEST VT-20T 1-3-05 39 VT-20T 1- "02 1 40 VT-20 . 1-2-04 VT-20T 1-2-03 41 42 ttff fttfstf tttttttttttaft tttttttfttttttttttftfettf ttt f ttttff et f tftet ettttf tttttft taft tttttttttf ttttfettf sf ttftaft tet 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 {02I83)
2'b6 1 t at*at tatted t tat t t et t t et t tf t et t t t et t t tt*tt tt t t t tt t t t t et et t t tt tt t et tt t t +et t t t t t t t t t et t t et t t tat tt t'et t t t et t t t*ttt t t tt t tt 2 NUTECH CAROLINA POWER & LIGhT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 t PLANNING 1
't tt t
- t t t t t t 't t t't t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE , 255 6 ASME SECTION XI, 1983 EDITION THROUGFI AND INCLUDING RFVISION NRC1 DATE 88/01/12 7
8 ttttttttttttttttttttttttttttttttttttttttttttttttttttftttttttttttttttttttttttttttttt*tt THE SUMMER 1883 ADDENDA; INTERVAL 01 ONLY 9 10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15.51 PIPING PRESSURE RETAINING BOUNDARY - STATIC 12 13 t t tt tft t tt tt t t t t
- t t t t t t t t t t t t
- t tt t t t t t tt *t t t tt tt t ttt t t t tt tt t t t tt tt t t tt t t t tt ttt t t t t tt tttt t t tt t t t t t t t t t t t t t t tt tt t t t tt tt 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PS I 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE OULED INT INT PSIG (F ACCESS SELECT IND REQST TIONS NOTES re- arras) reassert 18 19 ssaeeasaasaaeasasssaasss saasasesrsrsass aerate ssssesesaaseesae a rarer = = s rss ~ sersa 20 21 SYSTEM ISOMETRIC NUMBER : II-CS-088 22 23 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 24 25 SYSTEM ISOMETRIC NUMBER : II-CS-093 26 27 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER : II-CS-094 30 31 PRESSURE TEST PRESSURE TEST VT"2ST 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER : II-CS-097 34 35 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 36 37 SYSTEM ISOMETRIC NUMBER : II-CS-102 38 39 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 40 41 SYSTEM ISOMETRIC NUMBER : II-CS-103 42 43 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 44 45 SYSTEM ISOMETRIC NUMBER : II-CS-106 46 VT-2ST 1-3-06 47 PRESSURE 48 TEST PRESSURE TEST ttttttttttttttttttttttttt*tttttttt*tttttttttttttttttttttttttttttttt'tttttttt*ttttt 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0'113 102I831 a
tatattttttttttt tatttttttt tat ttttttttttttttt tat tat tttttttttttttttttttttttttt tt at 1 tttttttt at ttttat tat t st 2 '<< NUTECH CAROLINA POWER 8L LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4
~
PLANNING 1 ttttttttttttttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 261 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA; INTERVAL 01 ONLY 88/01/12 at t t at t t st t tt t t at 1 at t t st t t t tt tt t t t at at tat t at tat at at tt t t t tt tt t t takeit t at at t at at at tt t tt tt tat tat t at at t atDATE t t at t tt t t at t at t 9 10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15.60 PUMP PRESSURE RETAINING BOUNDARY - OPERATIONAL 12 13 tttttttt t tttt t' t t' t t tt t ttt tttt tt t ttt tt t' t t t t tt t tt t t t tt t t t ttttt t t tt t t t ttt t t t t' t t tt ttttt t ttt t tt tt ttt t tt 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 sssasasssssassssssssasss, ssasassasssassa ssssss ssssasaaaaasssss stats sasss aaassa sassss ass sssaas ssssss ssssss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-RCP-01 22 23 RC PUMP A RC PMPA VT-20T 1-1-01 NO 24 VT-20T 1-3-05 25 VT-20T 1-2-04 28 VT-20T 1-3-06 27 VT-20T 1-2-03 28 VT-20T 1-1-02 29 .30 RC PUMP B RC PMPB VT-20T 1-2-03 NO 31 VT-20T 1-3-06 32 VT-20T 1-2"04 33 VT-20T 1-1-02 34 VT"20T '1-1 "01 35 VT-20T 1-3-05 38 37 RC PUMP C RC PMPC VT-20T 1-1-02 38 VT-20T 1-2-04 39 VT-20T 1-3-06 40 VT-20T 1-1-01 41 ttt t tt t t t tt ttt t t t t tt t t t t t tt t tt t tt t t t 't t tttt t tt t t ttt t t t tt t t t t tt t t ttt t t t tt t t t t t t tttt t t *t tt t t t t tt t
- t ttttt t ttt t tt tt ttt tt t t 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 eo FORM 0113 (02/83)
266 4 t tt tt tt t t t t 't t ttt t tt tt tt t tt tt 't t t *tt ttt t t t tt t t t t tt t t t t t t t ttt tt t t tt tt tt t
- tttt t tt t tt t t t tt tt t t t t t ttt t t' tt t t tt t tt t t 't t t tt t t
~
NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1 tttttttttttttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 265 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1963 ADUEHDA, INTERVAL 01 OhfLY DATE 88/01/12 t t t ttttttt t t t t t tttt *t t ttt t t t tt t t tt t tt t t t tt t tt tt t ttt t tt t t t' t t t t ttt t t t t t' t t t' t tt t t t ttt tt ttt t' t t t tt tt tt t t tt tt t tt 9 10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15.70 VALVE PRESSURE RETAINING BOUNDARY " OPERATIONAL 12 13 t t t tt t 't tttt t tt t t ttt t t t tt t t t ttt t tt tt tt tt t tt t t tt t t t t tt t t tt t t t ttt t t t t t t tt t tt t tt tt tt tt t t t tt t tttttt t t t t t t t t t tt t 't t t lit 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 sssasssssssssssasssssssa sssssssssssssss strata ssssssssassrsssa arras rasa s saasra strata sss ararat ararat tartar 20 21 SYSTEM ISOMETRIC NUMBER: I I-CS-094 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 24 VT-20T 1-3"05 25 VT-20T 1-2-04 26 VT-20T 1-2-03 27 VT-20T 1-1-02 28 29 SYSTEM ISOMETRIC NUMBER: I I-CS-097 30 31 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 32 VT-20T 1-3-05 33 VT-20T 1-3-06 34 VT-20T'1-2-04 35 VT-20T 1-2-03 38 VT-20T 1-1-02 37 38 SYSTEM ISOMETRIC NUMBER: I I-CS-102 39 40 PRESSURE TEST PRESSURE TEST VT-20T 1-2-03 VT "20T 1-1-02 41 42
- ttt t tt t ttt ttt t t t t t t t t' t tt t ttt t t tt t tt t t t t t t t t ttt t t s t tt t t t t tt t t t fr t ttt t t t t tr tt t t' t t t tt tt tt t t 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 01'13 (02I83)
.268 1 fr f ttfff tt f ff ttff f fr ttff tfttff fr tffff f tfff at f tf tftttfat f f fff f tat f tat tfat f ttfttttt f tfffff ~ tftff ttft ff ttff ttff tt tttt f ff 2 NUTECH CAROLINA POWER 8 LIGH: COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1-4 PLANNING ff f f at 't f at ff ftfff 'f COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 267 ASME SECTION. XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 88/01/12 ff aft f f tffr f f tttftffr ff ttff ttftfff fff tftftttttfttftttff*tft*tft fr ff ttftat ff tttttfff f tttff tff ttff ttftff f f f f ff ff tf aft f f THE SUMMER 1983-ADOENDAi INTERVAL 0~ Of4L~ DATE
~ 10 CATEGORY B-P ALI PRESSURE RETAINING COMPONENTS 11 ITEN NO. B15.70 VALVE PRESSURE RETAINING BOUNDARY - OPERATIONAL 12 13 ttffft ff f f ff f f fff tfff tftfff ffff tfff ffrftf tfft fft ft f fff f f f at tt f t tttt tat ffff tffft ffff f ft ttfsf tffffffft tfff tfftff ffat 14 15 DONE 15 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 sssassssssssssssssssasss sssssasrssssass sssasr assssrssssassrss arras arras ssrrassr ararat ssa rsr ss ararat sssssa 20 21 SYSTEM ISOMETRIC NUMBER : II-CS"106 22 23 PRESSURE TEST PRESSURE TEST . VT-20T 1-3-05 24 VT-20T 1-2-03 25 VT-20T 1-3"06 28 27 SYSTEN ISOMETRIC NUMBER: I I-CS-107 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-2-04 30 VT-207 1-2-03 31 VT-20T 1"3-06 32 VT-20T 1-3-05 33 VT-20T 1-1-02 34 VT-20T '1-1-01 35 38 SYSTEM ISOMETRIC NUMBER: I I "FMR-01 37 38 PRESSURE TEST PRESSURE TEST VT-20T 1"1-01 39 VT-20T 1-3-05 40 VT"20T 1"3-06 VT-20T 1-2-04 41 42 f f at f f frf f tff taft t sf f ftf ff f tat ft ft tfat f t t t f t ft f ft f fff t f t t tat tfftf t f fff ff fff f f tat f ff f f ff fft t t t ff tff f tt f t't t Iff f t t 43 44 45 48 47 48 49 50 51 52 53 54 55 55 57 58 59 80 FORM 0113 I02I83I
274 t tt ttt t tt t t tt t t t t tat tt t t t t tt t t t st t t t tt t t t tt t st st t tt t tt tt t t t t tt tt tet st t et t st tt t st et t tet t tt t et t t et tt t t t tet st t t t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4 PLANNING 1 ttttttttttttttttttt 5 COMPONENT LISTING ANO ISI 10 YEAR PLAN: 835-01 PAGE 273 6 ASME SECTION,XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
.7 t THE- SUMMER 1983 ADDENDA/ INTERVAL 01 ONLY DATE 88/01/12 tt tt tttt tt t t t t t t t t t t t tt t t' t t ttt t t ttt t tt t t t tt ttt t tt tt t t tt tt t t ttt tttt t t t t t t t t tt tt t t tt t t t t tt t t t tt t' t 9
10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15.70 VALVE PRESSURE RETAINING BOUNDARY OPERATIONAL 12 13 ttt t t t t t t t tt t t ttt t t t tt tttt t ttt t t t t t t t t t t t t t t tt t 't t t t t tt tt t t t I t t tt t t t t t t t t ttt t t tt t tt 't t ttt t t t ttt t t t t tt t 't t t ttt t t t tt tt t ttt
-14 15 DONE 16 ~ OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND RE@ST TIONS NOTES 19 seers s e ssssssaassssas ssssssassaassss assess ssasssssssssssss arses rarer reassess reseat sss erases seater stress 20 21 SYSTEM ISOMETRIC NUMBER : II"RC"025 22 23 PRESSURE TEST PRESSURE TEST VT"20T 1-1-02 24 VT-20T 1-2-04 25 26 SYSTEM ISOMETRIC NUMBER: I I-RC-027 27 28 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 29 VT"20T 1-2-03 30 VT"20T 1-2-04 31 VT-20T 1-3-05 32 VT"20T 1-3-06 33 VT-20T 1-1-02 34 35 SYSTEM ISOMETRIC NUMBER: I I-RH"009 36 37 PRESSURE TEST PRESSURE TEST VT-20T 1"2-04 38 VT-20T 1-2-03 39 VT-20T 1-3-06 40 VT-20T 1-3-05 41 VT "JOT 1-1-01 42 tttttt t t tttt t tt *t 't t t t tt tt ttt tt tt t t t t t tt ft t t t t t t t ttt tttt t t
- tttt ttt t ttt t t t t ttt tt tt t tt t t tt t t tt t t t t t t t tt t tt t tt t t t t t' t t
- t 't 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83) e
~
276 ft t f t t ttt t fthm t t tt tt f t tft t t tt t tt f t t tft t tt f ttt ttt t t t' t t tt t t tfftf 4 t t t t t t t tt tt t t tt ff tf fft tt tf t tt tf t tttf t t tffft t tf NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1 tttfftfttfttttftttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 275 8 ASME SECTION, XI. 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 0) ONLY DATE 88/01/'l2 tt tt ftfft t t t t tftft fthm f tff tt f'ft t ft f t*ft t t ft tt f tt tt t tft tt t t t t t t f f t t t ttt f t t tt t tttt ftt tt t tt t tt tt f t t t t t tttft t tt t t t ttt tft tt 7 8 9 10 CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15.70 VALVE PRESSURE RETAINING BOUNDARY - OPERATIONAL 12 13 f ffff tfffffff f fff f ft tt t f t f f f tftt tt t t tft t t ff t tfffft t ft t tft t f t t t fft ftt fft t ft t t f t tff ff f tfff f fff f t tt tt tft t tff t tf 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ ~ $ ~ $ $ ~ $ $ ~ $ $ ~ $ $ $ $ $ $ $ $ $ $ ~ $ ISN ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $$$$$$ $$$$$$ 20 21 SYSTEM ISOMETRIC NUMBER: I I-SI-017 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-3-OS 24 VT-20T 1-2-03 25 VT-20T 1-1-01 28 VT-20T 1-3-06 27 VT-20T 1-2-04 28 29 SYSTEM ISOMETRIC NUMBER: I I-SI-018 30 31 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 32 VT-20T 1-2-04 33 VT-20T 1-3-05 34 VT-20T '1-1-02 35 VT-20T 1-2-03 38 VT-20T 1-3-06 37 38 SYSTEM ISOMETRIC NUMBER: II-SI-019 39 40 PRESSURE TEST PRESSURE TEST VT-20T 1-1-02 VT-20T 1-1-01 41 42 f f tft *ttft t ftIt ft t tftt *tt t t fffff tt t t t f t f(ftt f tt f t tt tt t ttt t t ft tt ttt t t t f ft tt tft t t t tt tt tt t t t t 1 t t t t tt t t t t t tt tt t ttt t t t ttt t t 43 44 45 48 47 48 49 50 51 52 53 54 55 SS 57 58 59 80
283 t t t t tt t t tt t t tt t tt ft t t t t tt t t t t t tt t tt t t tt t t t t t t tt t t t t' tt t t t t t t t t t t t t tt t *t t t t t t t t tt tt tt t t t tt t t tt t t t tt tt t tt NUTECH CAROLINA POWER 8t LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT UNIT PLANNING tttt*tttttttttt*ttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 282 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 t THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 t t tt t t t 't t t ttt tt tt t t t t 't tt tt t t tt tt tt tt t tt t t t t t t t ttt t tt t t t t t t *t t t t tt
- t t tt t tt tt t tt t t t t *t t t t tt t t t t t tt tt t tt DATE t t t tt t t t t tt t t ttt 9
10 CATEGORY 8-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. 815.71 VALVE PRESSURE RETAINING BOUNDARY - STATIC 12 13 t t t t t t t t t ttt t t t t tt t t t tt t t t tt t t t tt t tt t t t t t tt t t t t t tt t t t t t t t t t t tt tt t t t t t t tt t t t t t t t 14 t'ONE 15 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 $ $ $ ~ $ $ $ $ ~ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $~$~$$~$$$$$$ $$ $$ $ $ $$$$$$$$$$$ $$$$ ~$$$$$ $~$ $$$$$$ $ $$$$$ $$$$$$ 20 21 SYSTEM ISOMETRIC NUMBER : II-CS-088 22 23 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 24 25 SYSTEM ISOMETRIC NUMSER : II-CS-093 28 27 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER: I I-CS-094 30 31 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER : II-CS-097 34 35 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 38 37 SYSTEM ISOMETRIC NUMBER : II-CS-102 38 39 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 40 L 41 SYSTEM ISOMETRIC NUMBER: I I-CS- 'I03 42 43 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 44 45 SYSTEM ISOMETRIC NUMBER: I I-CS-106 48 VT-2ST 1-3-06 47 PRESSURE 48 tttttttttttttttttttf TEST tttttttttttttttttttttttt PRESSURE TEST tttttttttttfttttttttttttttttttttttttttttttttttttttttttttttttttt 49 50 51 52 53 54 55 58 57 58 59 80 FORM 0'113 {02I83)
288 ttf4444444444444*ttttf tt4tfttttttftfttftttIII f4 t4IIIIIIIIII4444 I ttttttf4444444444444ttttttttttff 44 ttftf444 44 ftfttttfI 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT UNIT 3 4 PLANNING 'Itftff'ffff4ff4fftft 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 287 5 ASME SECTION XI, 1983. EDITION THROUGH AND INCLUDING REVISION NRC1 4 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 tfIt f44 tttttf44f IttfI tf4444 tftttf4444tf ttf4444 ttfItfI It f tf4*444*fttttfttt44ttf IIIIIItfDATE II tttf tfIfIttfI 9 10 CATEGORY 8-P ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. B15.71 VALVE PRESSURE RETAINING BOUNDARY - STATIC 12 13 III t I I I IIt IIII II I t tI IIt I I I IIttI It I I II t fIIII I I III I III II't 4 tIIII I I I I I I III I III I t It 4 I 'I I I IIIIIII 4 4 4 4 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ 4 $ $ $ $ $ $ $ $ $ 4$ $ $ 4
$ $ $ $ $ $ ~ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ '$$ $ 4 CESS ~ $ $ $ $ ~ 4 $ 4 4 ~ $ $ $ $ $ $ $ $ $ $
20 21 SYSTEM ISOMETRIC NUMBER: I I-SI-028 22 23 PRESSURE TEST PRESSURE TEST VT"2ST 1-3"06 24 25 SYSTEM ISOMETRIC NUMBER : II-SI-029 28 27 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER : II-SI-030 30 31 PRESSURE TEST PRESSURE TEST VT'-2ST 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER : II-SI-032 34 35 PRESSURE TEST VT-2ST 1-3-06 4 tf IIII I III I 4 4 tfI ttII t I t 44 tf 44 4 I It It I I IIII I IIII TEST I I It f 44 t IfO'I It PRESSURE IIf *II *II tfII I I II IIIII I I I IIIIItt III ItIIII I II'I 38 I 44 44 44 44 4 4 37 38 39 40 41 42 43 44
.45 4e 47 48 49 50 51 52 53 54 55 55 57 58 59 eo FOAM 0113 102I83) 0'-:
C 291 tff 'tf fff tfft fit t tt t f tft tt t tt t t t tt tf 4 t tftf t f tt t t t tt f t t tt tftff t tt tt tt t f *ttt tttt t ft tff t t t t ff tft tft'f t f t t t tft tt t t tftft t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM f SHEARON HARRIS NUCLEAR POWER PLANT UNIT 3 4 PLANNING 1 tttftff tffff*f COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 290 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 fftff tftft t tfff tft tff ft tfft t t tt t tt tft t t t t'f t t tf t t tt t t t t f tf f tftftft t tt t t t t t t t tt tt t t t t t tt tft tff tt t it t ft t t t t t t 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE ftt f f tftftt 9 10 CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS 11 ITEM NO. C1.10 PRESSURE VESSEL SHELL CIRCUMFERENTIAL WELDS 12 13 tff f*ftftft f t tt tft t t t tt t tt ft tft t t tt tt t ftft t t t tt t t t t t t tt ft f ft f't tt t ffft t t t t tfff tft't tt t f 14 15 DONE 18 OUTAGE THIS DONE VESS FLNG BASIS PSI e 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES tlff ttlfSf ttftfffffffffff f ffftR ~ Sf ~ ttRSf ~ f tffff f ~ ttt f ~ ftf f Sf ~ t f tRt'IRIS f f ~ f ~ fff ~ t f ~ tSf f f ttttlf 18 19 ~ f ~ RmtgSSI1 ~ 20 21 SYSTEM: RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: II-RHR-01 22 23 RHRA-CSW-02A C SHELL UT-45S 1-1-01 039.7 0.750 NO R2-005 24 25 RHRA-CSW-02B C SHELL UT-00 1-2-03 039.7 0.750 NO R2-005 28 UT-455 1-2-03 R2-005 27 28 RHRA-CSW-02C C SHELL UT-00 1-3-06 039.7 0.750 NO R2-005 29 UT-45S 1-3-06 R2-005 30 31 RHRB-CSW-02A C SHELL UT-00 0.750 NO R2-005 32 UT-45S R2-005 33 34 RHRB-CSW-02B C SHELL UT-00 0.750 NO R2-005 35 UT-45S R2-005 36 37 RHRB-CSW-02C C SHELL UT-00 0.750 NO R2"005 38 UT-455 R2-005 39 40 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-ACC"01 41 42 ATA-STHW-01 STHW UT "00 138.0 1.200 NO 83S-CO 43 UT-45S 83S-CO 44 45 ATA-STHW-02 STHW UT-00 138.0 1.200 NO 835 "CO UT-455 83S-CO 46 47 t fff f tff 'tftffftftftff tftft tffff tfttff t tftt tff f f t f*ttttft ttft f tftftft tft t*tt ff tttt f ftff tt tftfttttttff f tt t ttft tftff tfft 48
'49 50 51 52 53 54 55 56 57 58 59 80 FORM 0113 (02I83)
l 299 1 t 44 444 t4 4t44 44t444 44 44 4 4 4 4 4 44 t44 4 44 4 4 44 4 4 4 t4 444 44 4 44 4' 4 4' 444444 t 4 4 4 4
- 4'* 4 4 4 4 4 4 4 4 4 4 4 4 t 4 4 4 4 4 4 4 t 4 4 4 4 4 4 4 4 4 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM r 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING 4444444444444444444 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 298 6 ASME SECTION XI. 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 tt 4 4 4 88/01/12 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 8 t 4 4 4 4 *4 4 4
- 4 4 4 4 4
- 4 4 4 4 t 4r 44 t 4 4 4 4 4 4 4 4 t 4' *4 4 4 4 4 4 4 4 4 t 4 4 4 4 4 4 t 4 4 4 4 4 4 4 4 4 4 t 4 4 4 4 4' 444 t 4 4 4 4 DATE 44 4 4 4 4 4t4 t4 9
10 CATEGORY C-A PRESSURE RETAINING WELOS IN PRESSURE VESSELS 4 11 ITEM NO. C1.30 PRESSURE VESSEL TUBESHEET-TO-SHELL WELD 12 13 444444444444 tt 4 t 4 t 4 4 4 4 4 4 4 4 4 4 4 4 4 t 4 4 t 4 4 4 4 t 4 4 t 4 4 4 4 4 4 4 4 4 4 4 4 4 t 4 4 4 t 4 4 4 4 4 4 t 4 4 4 4 t 4 4 4r 44444444 t 4' 444444 4 t tt 4 4 14 15 DONE 16 OUTAGE THIS DONE VESS FLNG BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULEO INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 ssasssssasaaassssssassss sssssssrasassss cstars saasasssssssasas arras asar ssa 4 ~ ss ararat starts ssasss 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER : II-SG-001 22 23 SGC-TSTSW-09A TSTVW UT-45S 1-1-01 140.0 3.310 NO R2-005 24 UT-605 1-1-01 R2-005 25 26 SGC-TSTSW-09B TSTVW UT-00 1-2-03 140.0 3.310 NO R2-005 27 UT-455 1-2-03 R2-005 28 UT-605 1-2-03 R2-005 29 30 SGC-TSTSW-09C . TSTVW UT-00 1-3-06 140.0 3.310 NO R2-005 31 UT-455 1-3-06 R2-005 32 UT-605 1-3-06 R2-005 33 t t 4 4 4 tl 4 4 4 4 4 rt 4 4 4 4 4 4 rlr 4 4 '4 4 4 rt 4 4 4 4 4 tt 4 4 4 tr 4 4 4 4 4 t4 4 4 t4 4 4 4 4 4 4 4 4 t4 4 4 4 4 t4 4 4 4 4r t 44444 4444444444444 t4 444 444 4 44 4 4 44 4 44 4 4 4 t4 4 rlr 4444 34 35 36 37 38 39 40 41 42 43 44 45 48 47 48 49 50 51 52 53 54 55 se 57 58 59 60 FORM 0113 (02I831
303 f ttfttff f tff ff ttff ffttff fff f tff*ftttffff tf tttfttfttftt tftftttftttttftfff t*tff f tttttttttfttffff tftttt tttff tftftf f f NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARDN HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 302 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 7 8 tftfff fffftttfttt ttfff tttt tff ffff ff tt f ff ttttft t tfff tt t*fff tt f tft ttft t ttttt ttttftfff ff fft*fft tt tft tt t ffDATE tttttf f tt ttfff f 9 10 CATEGORY C-B PRESSURE RETAINING NOZZLE WELDS IN VESSELS 11 ITEM NO. C2.21 NOZZLE-TO-SHELL(OR HEAD) WELD 12 13 fft t tft tftfffttff ff tff f f f ff ff tt tt tff tft tfft f t t it t fft t tffff tttft t tfff f f f t f ffftftt t tt t tff f ft tt t f t t 4* ftt Irk' trlr tf ft fft rlr 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM DESCRIPTION INT INT (IN) (IN) SELECT IND REQST TIONS NOTES 18 19 ~ fffffffff f NUMBER RR I r fff f TYPE f ~ RfR ~ DULEO fmS ff fffff f fff
~ ~ '
ROss ACCESS mffffffs Sfff fff ff ff
~ ~ ~ f ~ f ~ f fffRff 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-SG-001 22 23 SGC-MSNTHW-01 NOZZLE MT 1-2-03 32.06 3.820 NO 24 UT-00 1-2-03 R2-005 25 UT-455 1-2-03 R2-005 26 UT-605 1"2-03 R2-005 27 28 SYSTEM: SI SAFETY INIJECTION ISOMETRIC NUMBER: I I-ACC-01 29 30 ATA-NTHW-03 NOZZLE MT 12.00 1.200 NO 83S-CO 31 UT-00 83S-CO 32 UT-455 83S-CO 33 34 ATB-NTHW-03 NOZZLE MT f 12.00 1.200 NO 83S-CO 35 UT-00 83S-CO 36 UT-45S 83S-CO 37 38 ATC-NTHW-03 NOZZLE MT 12.00 1.200 NO 83S-CO 39 UT-OO, 83S-CO 40 UT"455. 83S-CO 41 42 SYSTEM: SI SAFETY INLJECTION ISOMETRIC NUMBER: I I-BIT-01 43 44 NTHW-03 1-3-06 11.00 2.000 45 ff f ffffff tft ttfft tfffffffNOZZLE PT f f fff ff frffft t f ff f tff f ff f t f tf t tff f tt f tftft ttff f tt tt t t f f tff f ft f tfff tf ff fffffff f *tffff f f t t t ff f 'f NO 46 47 48 49 50 51 52 53 54 55 se 57 58 69 eo FORM 0113 102183)
306 ttttttttttttttttttttttttttttttttttttttttttttttt'sttttttttttttttttttttttttttttttttt*tttttttttt* NUTECH CAROLINA POWER 8 LIGHT COMPANY PRI 5IM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1 ttt t' t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 305 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t tt ttt t t t t t t tt t t tt tt t t t ttt t tt tt t t t tt t t t t t t t t t t t tt t t t t ttt t' t t t t t t t t tt t t t t t t t tt 88/01/12 TfiE SljMMER 1983 ADDENDA, INTERVAL 01 ONLY 7 DATE 8 ttt t tt tt t tt 9 10 CATEGORY C-B PRESSURE RETAINING NOZZLE WELOS IN VESSELS 11 ITEM NO. C2.31 REINFORCING PLATE WELDS TO NOZZLE AND VESSEL t t t tat t tt t t tt ttt et t tt tt tt tt t t t t t st t t t t tt tt t tttt t t t t t t tet tt et t tt t 12 13 at st t t t at *t t st t t st st st 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 assasssssssasssesssssssa raassssssssssss arrear sreseas ~ ssaeesss sears rarer seer ss assess sas assess seater ararat 20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RHR-01 22 23 RHRA-SR-4A SADDLE PT 1-1-01 039.7 0.750 24 25 RHRA-SR-48 SADDLE PT 1-2-03 039.7 0.750 NO 26 27 RHRA-SR-4C SADDLE PT 1-3-06 039.7 0.750 28 29 RHRA-SR-4D SADDLE PT 1-3-06 039.7 0.750 NO 30 31 RHRA-SR-SA SADDLE PT 1-1-01 039.7 0.750 NO 32 33 RHRA"SR"SB SADDLE PT 1-2-03 039.7 0.750 34 35 RHRA-SR"SC SADDLE PT 1-2-03 039.7 0.750 NO 36 37 RHRA-SR-50 SADDLE PT 1-3-06 039.7 0.750 NO 38 39 RHRB-SR-4A SADDLE PT '39.7 0.750 NO 40 41 RHRB-SR-48 SADDLE PT 039.7 0.750 NO 42 43 RHRB-SR-4C SADDLE PT 039.7 0.750 NO 44 45 RHRB-SR-40 SADDLE PT 039.7 0.750 NO 46 47 RHRB-SR-5A SADDLE PT 039.7 0.750 NO 48 49 RHRB-SR-58 SADDLE PT 039.7 0.750 NO 50 51 RHRB-SR-SC SADDLE PT 039.7 0.750 NO 52 RHRB-SR-SD PT 039.7 0.750 NO 53 54 tt tt t tt t tt t t ttt t t ti t t tt t t t SADDLE t t t t tt tttt tt tt t tt t tt t t t t t t t tt tt t t ttt t tt t t t t t t t t tt tt t t t tt t t t t t t t t t t t tt tt t tttttt t t t t t t tt t t t t 't t 55 56 57 58 59 60 FORM 0113 (02183)
308 1 41 41 tf1 441 444 tft 4 41 4 441 4 t 4 1 44 4 1 4 4 4 4 1 4 1441 44 141 4 14*4 4 4 4 1 4 4 44 4 1 1 444 441 4 4 1 4 4 41 4 4 444 4 I 4 4 4 t 1 1 1 4 '44 4 t 4 4 44 4 t 4 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 1 SHEARON HARRIS NUCLEAR POWER PLANT " UNIT 1 4 PLANNING 4'141 1 4 1 1 1 114141444 4 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 307 8 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC 1 THE SUMMER 1983 ADDENDA, INTERVAL 03 ONLY DATE 88/01/12 7 8 4ttttrrttt41414 4 ttt*tf4414 ttttf f 1 1 444444 ftrf ttfttf 4111 4141 4 ttttttftttf 1 ttttt4441411 14 4 141tttf tttf11 ttfttf 4414 ttf4 f1 41 44 9 10 CATEGORY C-B PRESSURE RETAINING NOZZLE WELDS IN VESSELS 11 ITEM NO. C2.33 INSIDE OF VESSEL INACCESSIBLE, NOZZLE-TO-SHELL(OR HEAD) WELD 12 13 t t1 t tf141 14 111 11 4 4t4 44 4 4 t 41 4 1 t t4 tftf4 1 tt 4t 1 tft 4 1 1 14 4 4 1 1 4 4 1 4 t 1 t 1 4 4 141 1 1 1 4 t4 t 4 4 1 4 114 4 41 41 t 4 S '4 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ $ $ $ $ $ $ $ $ ~ SSSSSSSS ~$$$$ $$$$$~$$~4~$$$$ S ~$$~S 1~$$$$$~$$$$$ $$$ S~$$$ $$ $$$ 4 ~$$$$$ $ $$~$$$ $$$ $$$~$$ $$$$$ $$$$$$ 20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RHR-01 22 23 RHRA-NTSW"A NOZZLE VT-2 1-2-03 10.00 0.750 NO 2C232 24 VT-2 1-3-06 25 VT-2 1-1-01 28 27 RHRA-NTSW-8 NOZZLE VT-2 1-2-03 10.00 0.750 NO 2C232 28 VT-2 1-3-06 29 VT-2 1-1-01 30 31 RHRB-NTSW-A NOZZLE VT-2 1-3-06 10.00 0.750 2C232 32 VT"2 1-2-03 33 VT-2 1-1-01 34 35 RHRB-NTSW-8 NOZZLE VT-2 1"3-06 10.00 0.750 2C232 38 VT-2 1-1-01 VT-2 1-2-03 37 tfftft t tf4 4 11 1 1414tt4tf 4 4 4f 1 11 4 441 tf t tt frt 1 ff 4 tft 4 1 1 1 4t t tf*4 4 tf 1 t t4 4 tf4 4 4 4 1 4 4 f fr 1 1 1 14 4 f 1 1 tt 1 1 4 t tf4 4 41 1 f t*1 tt 411 tf1 1 14 39 40 41 42 43 44 45 48 47 48 49 50 51 52 53 54 55 Se 57 58 59 50 FORM 0113 (02I831
~'
311 t t t t t t t t t ttt t t t tt t t t t t t t tt tt t t t t tt t tt tt tt ttt tt t ttt t t tt t t t t t t t t t t ttt t t t t t t t t t t t t t t t t t t t tt t t tt t t ttt *ttt t t t t t ttt t t t t t NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1" PLANNING t 1 t t t t t t t t It 't tr It t tt tt COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 310 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 st t t t t t tt t st t st tat t tat tat t st st t t tt at st st tt tat tt t t t t tat st tt tt 9 10 CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES ll ITEM NO. C3.20 PIPING INTEGRALLY WELDED ATTACHMENTS 12 13 **tt tt t tt t t't st st st t st tat at t ttt t tt t ttrtt st t st at t t tt t at t st t t t hatt t t st t tat t st tat t tt t st tat t t t st tt tat tat t st *a tt st t tt tt tt t t tt 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR. DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssssssssssaasssssrsssaas ssssassssaasssa saa s ss ra s r ss a ss ssasas sss sssarr sss as sa
'20 21 SYSTEM: AF AUXILIARY FEEDWATER ISOMETRIC NUMBER: I I-AF-008 22 23 AF-1-FW-449(5) PEN SHL MT 1-1-01 06.00 0.432 24 25 AF-1-FW-450 5 PEN SHL MT 1-1-01 06.00 0.432 NO 28 27 SYSTEM: AF AUXILIARY FEEDWATER ISOMETRIC NUMBER: I I-AF-009 28 29 AF-3-FW-434 5 PEN SHL MT 1-2-03 06.00 0.432 30 31 AF-3-FW-435(5) PEN SHL MT 1-2-03 06.00 0.432 NO 32 33 SYSTEM: AF AUXILIARY FEEOWATER ISOMETRIC NUMBER: I I-AF-010 34 35 AF"H-0320I(8) PIPE -LUG, PP MT 1-3-06 '-:6.00 0.750 36 37 AF-H"0328I 8 PIPE "LUG, PP MT 1-3-06 6.00 0.750 NO 38 39 AF-2-FW-456(5) PEN SHL MT 1-3-06 06.00 0.432 NO 40 41 AF-2-FW-457 5 PEN SHL MT 1-3-06 06.00 0.432 42 r 43 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER: I I-CS-021 44 45 CS-H-0006I 2 PIPE -LUG, PP PT 1-1-01 08.00 0.322 NO 46 47 CS-H-0011I(4) PIPE -LUG, PP PT . 1-3-06 8.00 0.750 NO R2-001 48 49 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER : II-CT-002 50 51 CT "H-0330I (4 ) 1-1-01 ttt t t t t t ttPTt tt t t t t t t t tt t ttt t t t t t tt 08.00 t tt t t t t -LUG, t tt tt t t t t t t t PIPE t t tt t t t1.500 PP 52 tt
- t t t t t tt t t ttt ttt t t t NO t t t t t t t t tt t 1 t t t t t t t' t t t t 53 54 55 58 57 58 59 60 FOAM 0I13 102183)
312 tttt*tt*ftttttttttftttttfttftttttttfttttttttff tttttttttttftttfttfttttttttttttff tf*tttttt*tttftttttttttttttttt f NUTECH CAROLINA POWER 8 LIGH1 COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t tt tt t tt 1 t tff t tfftt 1 PLANNING !It 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 311
,8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01'ONLY DATE 88/01/12 7
8 fllltrlrtftttf tttfttrltlllrltttttlllfftill!Ittt*tttttt'Irtffttttttftftrlttrlrtf rl'ttttt*t'ttttttt'iltttft'tllltttttttttttt*fttttrll*f 'Irf't*tf ttttrl!ttrlttrlff 9 10 CATEGORY C"C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, ANO VALVES 11 ITEM NO. C3.20 PIPING INTEGRALLY WELDED ATTACHMENTS 12 13 f tf *ff tt f tff tt t t *f tfrf1 tft f 1 ft f f f 1 t tt 1 t t tt t tt f 1 1 t f 1 1 t t t t t tftt ftt tt t t tt t t tt t t t t t t t t t tftttftft tfft ttt 1 1 f 1 t f t tftt tt tt 1 11 1 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 ~ 111 ~ 1 ~ $ 1111111111' 11111 11111 ~ 111111'$$ 1 111111 11$ 111$ 1 ~ $ 11111 1~$ 11111 1$ 1 11111 ~ $ $ 1 ~ $ 11 ~ 1 $ 11111 20 21 SYSTEM: CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I "CT"016 22 23 CT-H-0095 (8 I ) PIPE -LUG, PP PT 1-2-03 8.00 0.750 NO 24 23 SYSTEM : FW FEED WATER ISOMETRIC NUMBER: I I-FMR-01 28 27 F W-H-0106 I (8) PIPE -LUG, PP MT 1-3-06 16.00 1.437 NO 28 29 FW"H"0211I 8 PIPE -LUG, PP MT 1 "3"06 16.00 2.000 NO 30 31 FW-H-0212I (8) PIPE "LUG, PP MT 1-3-06 16.00 1.500 NO R2-001 32 33 SYSTEM : FW FEED WATER ISOMETRIC NUMBER: II-FMR-02 34 35 F W-H-0224 I ( 1 ) PIPE -LUG, PP MT 1-2-03 16.00 0.750 NO 38 37 SYSTEM : FW FEED WATER ISOMETRIC NUMBER: I I-FMR-03 38 39 FW "H-0126 I (8) PIPE -LUG, PP MT 1-1-01 16. 00 1 . 375 40 41 SYSTEM: MS MAIN STEAM ISOMETRIC NUMBER: I I "FMR-01 42 43 MS-H-0005I (4) PIPE -LUG, PP MT 1-3-06 32.00 2.000 NO 44 45 MS-H-0006I 2 PIPE -TRUNNON MT 1-3-06 32.00 1.312 NO 48 47 SYSTEM: MS MAIN STEAM ISOMETRIC NUMBER: I I-FMR-02 48 49 MS-H-0018 I 8 1-2-03 50 f !liftffftffff ttttff tftff tftf PIPE ttfff -LUG, ttttttttf'ttf PP MT ttttttttttttttttftfttf32.00 tftttf2.000tt tttff tf1 t f tttf*ttttttttttttf NO tttf1ftttff rltttt 51 52 53 54 55 58 57 58 59 80
319 ff f tff fffff f t f f t tft ttff st ttf tt f f ff ff t t t ttf'tft t tff'ff ff tff f tttff tftfft tff'tff ff tat t ff f ffff f fff f tf'ffff ff f ff 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t tt tf t llt ft f tf *t tftff 1 4 PLANNING 5 COMPONENT LISTING ANO ISI 10 YEAR PLAN: 835-01 PAGE 318 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 f *a ft f f!itsff f f f t tff fff fff sf f ff at fff f f f t at ff f t fff f fft sf *f f f fff f f ff at tfff f t f at t t tfft fff sf ff sf f fff f tff f sf t at 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 7 8 ft f tff f tat f 9 10 CATEGORY C-D PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER 11 ITEM NO. C4.30 PUMP BOLTS AND STUDS (> 2") 12 13 ff t trit t sf f ftat f t sf t tff at f fff at at st f f ff ft f at f tfff f fftt f ft t t f tat f f t tt t f t ft fat 'sf f f f f ff f f t'f f st fffff sf t aft f llr t sf t tfsf t ff f f f t tlt 14 15 DONE 18 OUTAGE THIS DONE BOLT BOLT BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM LNTH TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND RE@ST TIONS NOTES 19 ssasssasssssssasasssassa ssssssssasasa stars sasrsssaassssssa sssar attar assasssa ararat ass sssrss === ssa 20 21 SYSTEM : REF REFERENCE ISOMETRIC NUMBER : REFERENCE 22 23 NOT APPLICABLE at f f ffftff f at ff ff sf t tff f ff ff at f ft tff f tttfsf f ft f f tf t tft at st f sf tt tt f f f t t tff tff tff ffft t tff tfff f ff tftf at t ff tan tftfff f tf f NO COMPONENTS 24 25 28 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 <02I83)
325 f f f f f f f ff t f f ff fff f f f fff ff tf ffft ff t fthm'f f tftftftfftfff f *ff tft tftf f tfft t tftftf*ft tff t f f f f f ftf *fff f fft f t tftfft t f et f fff f f f NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM f SHEARON HARRIS NUCLEAR POWER PLANT - UNIT f f f f f f tffff tf f f f f fff 1 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 324 f ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tffff et ff tfat ttf f tftat f ttttfftttfttftfff f tf*fff f*aff tff t*tfttff f ff tftf*ff ttet ff tfttfff tet tffff ff at f fDATE fff f f88/01/12 tff ff ftff f t 8 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING
'11 ITEM NO. C5.11 PIPING CIRCUMFERENTIAL WELD <e 1/2" NOMINAL WALL THICKNESS 12 13 'f ff tf'f f t tff f f t t ff tff ttff f tt ffff tt f ff f t ff t ff t ft f fft t ff f t f t f t tftf t t ft f fffft tt tf f t tffff f f f sf f f f t f f tffff tff t t t f f f tft ft tff 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT. COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 saasassss sasessssasases sesesssasaaassa assess asssasssasssssaa asses aa a se ae e eeease aas assess assess asses 20 21 SYSTEM : AF AUXILIARY FEEDWATER ISOMETRIC NUMBER : II-AF-010 22 23 AF-SW"D3 P BEND -P BEND MT 06.00 0.432 NO 24 25 AF-FW-447 P BEND -P BEND MT 06.00 0.432 NO 28 27 AF-SW-E4 PIPE -ELB LR MT 06.00 0.432 NO 28 29 AF-SW-E3 ELB LR -PIPE MT 06.00 0.432 NO 30 3'1 AF-FW-448 PIPE -ELB LR MT 1-3-06 06.00 0.432 NO 32 33 AF-SW-F4 PIPE -PIPE MT 06.00 0.432 NO 34 35 AF-SW-FS PIPE -P BEND MT 1-3-06 06.00 0.432 38 37 AF-SW-F6 P BEND -PIPE MT 06.00. 0.432 38 39 AF-SW"Fj PIPE -P BEND MT 06.00 0.432 NO 40 41 AF-SW-F8 P BEND -PIPE MT 06.00 0.432 NO 42 43 AF-FW-450 VALVE -PIPE MT 06.00 0.432 NO 44 45 AF-SW-G3 PIPE -ELB LR MT 06.00 0.432 NO 48 47 AF-FW-451 PIPE -NOZ1CI MT 06.00 0.432 48 49 AF-FW-449 PIPE -VALVE MT 06.00 0.432 NO 50 51 SYSTEM: AF AUXILIARY FEEDWATER ISOMETRIC NUMBER: I I-FW-002 52 AF-16-2-SW-1 TEE -PIPE 1-1-01 06.00 0.432 ff f!ff tff f ffff fffff at tfffftf NO 53 54 fet ff t t tffft ttfMTfff f et f tff f t t f t tft f f f fffff et f f f f f f ff f f ffff ff tf et et f fff f ff f f f fffffff f f tfff ff 55 55 57 58 59 80 FORM 0113 {02/83/
~ 'vv+ ~ vv ~ v'v~vv ~ tv@ V+'res'.v!v'va vs'vrvv vs vv ~ v ~ V'v Jv, hvar'" v ~ v~ 4K ! e vl
331 11111s t'tII IIIIIIIIII I It f1 I tfI II11 tII tf'II III I*1III I tff I f *I*IfI II I IIII tftfIIIII II II I IIII It tet tet f't It I f1 O'I IIIIII IIIIIII I NUTECH CAROLINA POWER Sr LIGHT COMPANY PRISIM I SHEARON HARRIS NUCLEAR POWER PLANT UNIT PLANNING 1 ttt tet f1fII f1 11 t tet COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 330 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 DATE 88/01/12 f*tttfftttftfttttfttfttttttff1 ttffttftttttftttftttfttfttttftftfII ttfff1I ftftttftffttfIttftfftttttfItfttttf1f THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tttttf tf 1 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. CS. 11 PIPING CIRCUMFERENTIAL WELD (s 1/2" NOMINAL WALL THICKNESS 12 13 II f1 fI 11 O'I I 1111 III 11 'I 1 11 I'111 III IIII I f I IfIIIIItfI III 11 IIII*III I III 11111 IIIII I 111 I I I It IIt tt Its t f 111 11 I tfIII11 IIII I ItI It 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM- SCHE- OUT PRIOR. DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REOST TIONS NOTES
=-
19 s sssaaaaassaasssassassa sasassasaaasssa assess saaasaaaaaasaass asses asses saaaassa assess ~. assess assess 20 21 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER: II-CS-021 22 23 CS-SW-IS PIPE -ELB LR PT 08.00 0.322 NO 24 25 CS-127-FW-223 PIPE -VALVE PT 08.00 0.322 28 27 CS-127-FW-224 VALVE -PIPE PT 08.00 0.322 NO 28 29 CS-FW-109 VALVE -PIPE PT 08.00 0.322 NO 30 31 CS-FW-216 TEE -PIPE PT 08.00 0.322 NO 32 33 CS-SW-D3 PIPE -TEE PT 08.00 0.322 NO 34 35 CS-SW-DS PIPE -TEE PT 08.00 0.322 NO 36 37 CS-SW-07 PIPE -TEE PT 08.00 0.322 NO 38 39 CS-SW-D8 ELB LR -PIPE PT 08.00 0.322 NO 40 t 41 CS-SW-I8 TEE -PIPE PT 1-3-06 08.00 0.322 NO 42 43 CS-SW-I9 PIPE -TEE PT 1-3-06 08.00 0.322 NO 44 45 CS-SW-I7 PIPE -ELB LR PT 08.00 0.322 NO 46 47 CS-SW-I6 ELB LR -PIPE PT 08.00 0.322 NO 48 49 CS-SW-I4 ELB LR -PIPE PT 08.00 0.322 NO 50 51 CS-SW-I3 PIPE -ELB LR PT 08.00 0.322 NO 52 53 54 CS-FW-212 tff 11*11 tfttfItfIIttttff 111ELBIttf ttfttfttt fPTttfI f1tttttttfIIIIttfItf08.00 LR -PIPE 0.322 ttttttttf tttttttet f1*sf tttftfNOttfI tf111 tftttfII Iftf O'I 55 SB 57 58 59 60 FORM 0113 (02I83)
332 l tt t l' lt tt lt llt t t lt t lt t t t t t t tt t tt t t t t ttt tttttt t lll ttt t ttt t t tt l t t t ttt t tt tt t t ltt l t ttt t t t t t ttt t t t l t tt tt t t t 2 NUTECH CAROLINA POWER Sr LIGH1 COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 !t PLANNING la la la la tall stall la 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 331 8 ASME SECTION XI, 1983 EDITION THROUGH AND; INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 7 8 ltt t t t t ltt llt t t lt ll tt t t llt llt t t t t **l t t t t lt t t t tt llt lt ttt ttt l tt lt tt lt tt tt t t t l tt l t lt t ttt t tt ttt t t t tt t lt tttDATE t t t tt t tt t t t t ttt 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.11 PIPING CIRCUMFERENTIAL WELD <a 1/2" NOMINAL WALL THICKNESS 12 13 l ttt t t t tt t t t t tttt t l t l tt t t l t tt t tt t ll tt 'l lt l t tt l t l t t l t l lt t l t l t l*t t t l t t t t l t 14 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sass sss a ssssssssass sssssasaasaassa assacs ss a sssassas ccats salsa sssssssc ssssss ssa ssssas ssssaa ssssss 20 21 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II"CS-021 22 23 CS-FW-209 PIPE -VALVE PT 08.00 0.322 NO 24 25 CS-FW-210 VALVE -PIPE PT 08.00 0.322 NO 28 27 CS-FW-211 PIPE -VALVE PT 08.00 0.322 NO 28 29 CS-SW-D4 TEE -PIPE PT 08.00 0.322 NO 30 31 CS-SW-C6 REDUCER-PIPE PT 08.00 0.322 32 33 CS-SW"C5 PIPE -ELB LR PT 08.00 0.322 34 35 CS-SW-C4 ELB LR -PIPE PT 08.00 0.322 NO 35 37 CS-SW-C3 PIPE -PIPE PT 08.00 0.322 NO 38 39 CS-FW-111 PIPE -ELB LR PT 08.00 0.322 NO 40 41 CS-FW-213 TEE -PIPE PT 1-1-01 06.00 0.280 NO 42 43 CS-SW-J6 PIPE -ELB LR PT ~ 06.00 0.280 NO 44 45 CS-SW-IJS ELB LR -PIPE PT 06.00 0.280 NO 48 47 CS-SW-U4 PIPE "ELB LR PT 06.00 0.280 NO 48 49 CS-SW-d3 ELB LR -PIPE PT 06.00 0.280 50 51 CS-FW-214 PIPE -VALVE PT 06.00 0.280 NO 52 CS-FW-215 -PIPE 06.00 0.280 53 54 t t t tt t VALVE t tr t tt t ttt t t t t t l tt l t t ttt t t l t t l t tt t t t t *l t tt l tt l ll tttt l t ttt t t t l t tt t ll t t' l tt t t 'l t t tt lt l t t t t l t I ll t PT NO 55 Se 57 58 59 50
333 1 tttttttfffttttttttttttttttftttttttt*ttttttftttttttttttttttttttt*t*ttttttttttfttttttttttttftttttttftt*tttttttftttf fttt 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4 PLANNING ttftat ff fsftttff aft 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 332 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 DATE 88/01/12 7 8 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY ttfttfft*tttsftst tat tttftftfattttttf tttattttat f tat at tttttttttf tat tat atttttt at tttat at taft ttf at tttf ff ttttt taft ttttttttf 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5. 11 PIPING CIRCUMFERENTIAL WELD <s 1/2" NOMINAL WALL THICKNESS aft ttfltttrlrttft!IIIIrtttttaft'Ilttttttffff f f f 'ttf fat f tt fff ttfttttttttttttftat ttttttttllrttttftttttftat t'trlrt'ftt'ftttttttllrttft 12 13 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 asaasaasasssssssssassass ssssassssssssss sassss sssassaasasssaas ~ IIssa stats as sssss s sss assass ssasss sa s 20 21 SYSTEM : CS CHEMICAL ANO VOLUME CONTROL ISOMETRIC NUMBER : II-CS-021 22 23 CS-SW-K9 PIPE -ELB LR PT 06.00 0.280 NO 24 25 CS-SW-KB ELB LR -PIPE PT 06.00 0.280 26 27 CS-SW-K7 PIPE -ELB SR PT 06.00 0.280 28 29 CS-129-3-SW-1 ELB SR -PIPE PT 06.00 0.280 NO 30 31 CS-129-3"SW-2 PIPE -TEE PT 06.00 0.280 NO 32 33 CS-SW-K10 TEE -FLG RFW PT 06.00 0.280 34 35 CS-SW-K4 TEE -PIPE PT 06.00 0.280 36 37 CS-129-3-SW-3 PIPE "FLG RFW PT 06.00 0.280 38 39 CS-FW-110 TEE -PIPE PT 06.00 0.280 40 41 CS-SW-E3 PIPE -ELB LR PT 06.00 0.280 42 43 CS-SW-E4 ELB LR -PIPE PT 06.00 0.280 NO 44 45 CS-FW-107 PIPE -VALVE PT 1-3-06 06.00 0.280 NO 48 47 CS-FW-108 VALVE -PIPE PT 06.00 0.280 48 49 CS-SW-F9 PIPE -ELB LR PT 06.00 0.280 50 51 CS-SW-FB ELB LR -PIPE PT 06.00 0.280 NO 52 06.00 0.280 f f ttff tttttsf aft tfttff sf sf aft ttftff tf ttftftttfttfatttttf ttttttttat tat tat ttttfattf ttttftttttttttff tst sf tff tttftttftftt 53 CS-SW-F7 PIPE -ELB SR PT NO 54 55 56 57 58 59 60
'! w ~I wa+w ~ ~
FOAM 0113 (02I83)
~,yt ~ wt ~. Pr 'r ~ ',t ~ 4a'r. vI Ir Sar 'r ~,r, 4 rt,,r l J,AEY, prs vr {rI'rI
~ 'f, ~ r' 0 I ~ r r 4'p6'r ~, rr';, rI '
~ lp t ..'I 4 f . )0 r, ~ '
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337 I *44 4 ttttttttt444444 tftfttftf4 4 4444 444f tf4 4 tftttfetttttf 444 tf4 tff tf4 tttfttttftttttf444 ftffttf4 4 ttttf4 44 4444 444 44 4*tft* 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING 4 44444 4 4 444 4 4 444 4 4 4 COMPONENT LISTING ANO ISI 10 YEAR PLAN: 83S-01 PAGE 336 ASME SECTION XI, 1883 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1883 ADDENDA, INTERVAL 01 ONLY
- 88/01/12 et 4444444 t4 4 4 44 44 4 4 4 4 4 4 44 t tf 4 444 4 4 44 4 f tf 4 44 4 tt 44444444444 444 f tt ff tgf 4 4 etta 4 4 4 4 4 4 444 4 4 4 tf 44tttt tf4 4 frtt DATE4 4 4 4 4 4 4 4 4 4 4 4 4 f4 4 9
10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.11 PIPING CIRCUMFERENTIAL WELD (a 1/2" NOMINAL WALL THICKNESS tttttfttff tfttftftfff ttttf tfttttf ttttttfttft at tttf ff ttfttf4444 44ttttf 4ttttff ttttttf4 4 tftat'4 44444 ttt 12 13 444 tt4444444 4 44 4 4 4 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULEO INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 ssssassssssssassssssaess asssssssrasssrs assess aaaasaassassssrs rarer asses stresses eraser ses assess ssssaa erases 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I -CT-001 22 23 CT-FW-4 PIPE -ELB LR PT 08.00 0.322 24 25 CT-SW-DB ELB LR -PIPE PT 08.00 0.322 NO 26 27 CT-SW-D4 PIPE -ELB LR PT 08.00 0.322 NO 28 29 CT-SW-D3 ELB LR -PIPE PT 08.00 0.322 30 3'I CT-FW-5 PIPE -ELB LR PT 08.00 0.322 NO 32 33 CT-SW-E3 ELB LR -PIPE PT 08.00 0.322 NO 34
~ 35 CT-SW-E4 PIPE -PIPE - PT b8.00 0.322 NO 36 37 CT"FW-6 PIPE -ELB LR PT 08.00 0.322 NO 38 39 CT-SW-F6 ELB LR -PIPE PT 08.00 0.322 NO 40 4 41 CT-SW-FS PIPE "ELB LR PT 08.00 0.322 NO 42 43 CT-SW-F4 ELB LR -PIPE PT 08.00 0.322 NO 44 45 CT-SW-F3 PIPE -ELB LR PT 08.00 0.322 NO 46 47 CT-FW-7 ELB LR -PIPE PT 08.00 0.322 48 49 CT-SW-G4 PIPE -ELB LR PT 08.00 0.322 50 51 CT-SW-G3 ELB LR -PIPE PT 1-3-06 08.00 0.322 NO 52 CT-FW-8 1-3-06 08.00 0.322 53 54 44 444*f44 fttfttttftat PIPE tftfttf-VALVE tfttftttt4PT tff44 44 tet ttf 4 f*44f tf4 444 4 4 4 4 tet tf 4 44 4 4 44 4 ttf4 4 4 4 tf4 4 44 4 4 tf tet 4f ttf4 4 4 44 4 tt NO 55 56 57 58 59 60 FORM 0113 1021831
345 ff f f fff f f f f f ff f f fff f f f f ff f f liltf tf f f f t f t tff tftf f t f ff ff fff f ft tft*tff f tfff *ffff at f tt f f f ffffft tff t f fffff f ff f tftfft NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT f lll f f ill ff f fftf f 1 llt PLANNING llt III COMPONENT LISTING ANO ISI 10 YEAR PLAN: 835-01 PAGE 344 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 fff f f f ffff ffff f fff f ff fr fffffff 't ff f t ff fff f t t't 'f fff f ff t fftt ff f t ff t f t sf ft t t f f 't 't tf f tt ff f f t at tt its 't 't t f tlirt f lll t ff
- f *fff f fffff f f a!
9 10 CATEGORY C-F PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. CS.11 PIPING CIRCUMFERENTIAL WELD <s 1/2" NOMINAL WALL THICKNESS 12 13 f f ff f f f ff f fff f fffffff f f ffftf f f ff ft ft f f ff f f f 't fff f ff f ff f ff ff fft ffff 'f ff f 'f t t f t ft f' fff f f 'f tf ffft f fffff
- f t t t f f t f t ll! fr 1II lit lit a! III lll fr IIr llr 14 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssssasasssaasasaaaas asssasasssasass asssss sssasssasassssss ssaas stats ssssaass sasass ass ~ sass sssssa asssss 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER : II-CT-008 22 23 CT-SW-EB ELB LR -PIPE PT 12.00 0.375 NO 24 25 CT-12-FW-55 PIPE -VALVE PT 12.00 0.375 28 27 CT-FW-45 VALVE -PIPE PT 1-3-06 12.00 0.375 NO 28 29 CT-SW-FB PIPE -TEE PT 1-3-06 12.00 0.375 NO 30 31 CT-SW-F6 TEE "PIPE PT 1" 1-01 12.00 0.375 NO 32 33 CT-SW-F5 PIPE -TEE PT 12.00 0.375 NO 34 35 CT-SW-F7 TEE -T STRNR PT <12.00 0.375 NO 38 37 CT-12-9-SW-2 TEE -PIPE PT 12.00 0.375 NO 38 39 CT- 12-9-SW-3 PIPE -RED ELB PT 12.00 0.375 NO 40 41 CT-FW-51 RED ELB-NOZZLE PT 12.00 0.375 NO 42 43 CT-FW-52A SUMP PL-REDUCER SUR 24.00 0.375 NO R2-004 44 45 CT-SW-I3 REDUCER-PIPE SUR 12.00 0.375 NO R2-004 48 47 CT-FW"46 PIPE -P BEND PT 12.00 0.375 48 49 CT-FW-47 PIPE -VALVE PT 1-2-03 12.00 0.375 NO 50 51 CT-12-FW-48 VALVE -PIPE PT 1-2-03 12.00 0.375 NO 52 C CT-12-FW-48A -FLG 12.00 0.375 53 54 f f fffff tffff t f fPIPE f f ff tff f f ffffBLN *ffPTt tff t f f t ftf tat ffft f f f f f t ff t t tf ff f f ffft f t t sf tft t f t f f t t tf ft ff f f f ffff tf f ftff fff 55 se 57 58 59 80 FORM 0113 rt02I83)
347 1 rlr t tt t t t t t t tft ftt t t t tt t t t f fff ft t t t ft t t t ttt t f t t t t t ft t t' t t t tf f t t f t t fttf fttf ff ft t tt t t t t f t fff f f f fftft f
- t t t t *tt t t ft t f f'lrt tf t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRI SIN
- UNIT 3
4 SHEARON HARRIS NUCLEAR POWER PLANT PLANNING 1 ttftttttt tftft 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-O'I PAGE 346 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 7 8 tllltrlrff tff!lrfttfttf'tfff ff f f llr'ff ffItlf tttff tttff f'f tffttrttfIlrfttftttttft'tff tttfttttff'ft'tttt littf fit tf f f tffff f f tttttlrtf ttttffffff 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.11 PIPING CIRCUMFERENTIAL WELD <$ 1/2" NOMINAL WALL THICKNESS 12 13 ttfttftttttttttftff tff ttttt*tttttftftfff ttfttfttttttttttfttttftftttt ttttftttttttttfttf*tftttt f ttft tftttttfttttt 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 $$$ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ ~ $ $ $ $ ~ $ $ $ $ $ '$$ $ $ $ $ '$$ ~ $ $ $ $ ~ $ ~ $ ~ $ ~ $ ~ $ ~ $ $ $ $ ~ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $$ $$$$$$ 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: II-CT-014 22 23 CT-FW-185 PIPE -VALVE PT 08.00 0.322 NO 24 25 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER : II-CT-016 26 27 CT-M23-PW-1 PP,FHS-INTERNAL SUR 08.00 0.322 IA NO R2-004 28 29 CT-FW-143 FL HEAD-ELB LR PT 1-2-03 08.00 0.322 30 31 CT-SW"A3 ELB LR -PIPE PT 1-2-03 08.00 0.322 NO 32 33 CT-FW-144 PIPE -VALVE PT 08.00 0.322 NO 34 35 CT-FW-145 VALVE -PIPE PT 1-2-03 ()8.00 0.322 36 37 CT-SW-83 PIPE -ELB LR PT OS.OO 0.322 38 39 CT-SW-B4 ELB LR -PIPE PT 08.00 0.322 NO 40 41 CT-SW-86 PIPE ~ -PIPE PT 08.00 0.322 NO 42 43 CT-FW-146 PIPE -P BEND PT 08.00 0.322 NO 44 45 CT-SW-C3 P BEND -PIPE PT 08.00 0.322 NO 46 47 CT-SW-CS PIPE -P BEND PT 08.00 0.322 48 49 CT-FW-148 P BEND -PIPE PT 08.00 0.322 NO 50 51 CT-SW-04 PIPE -RED TEE PT 1-1-01 08.00 0.322 NO 52 CT-SW-05 08.00 0.322 f tttttttfff ttttttt*ttttttttttttftttftttttttttfttttttttftttfttttt ttttttttftftttttttttt TEE-FLG 53 54 tttttttttf REO RFW PT NO 55 56 57 58 59 60 FORM 0113 (021831
348 tt t tt tt 't tt t ttt t t tt t t tt t t t t tt ftt t tt t t t tt t ttt tt t tt t t tt t t t t t t t tt t t' ttt ttt t t t tttt t t tt t t tt ttt tt t t t t t t tt t tt 2 NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM 3 t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 t PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 347 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
'7 THE SUhlMER 1983 ADDEADA, INTERVAL '0310NLY DATE 88/01/12 8 tt tt t tt tt t t t t t t t tt 4 t tt tt t t t t t tt t tt t t tttt t t t tt t tt t tt t tt t tt t t tt t tttt tt t t t tt t tt t tt t tt t tt t tt t tt t t 9
10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. CS.11 PIPING CIRCUMFERENTIAL WELD <$ 1/2" NOMINAL WALL THICKNESS 12 13 t t t t t t *t *t t t tt t t tt t tt t t t t ttttt t' t t t t t t t t t tt t t t t tttt t t tt t t ttt t tttt t ttt tt t t tt t t t ttt **t t t t ttt ttt t t t t t t ttt t t 't t t t 't t tt t t t 't t 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ ~ $ $ $ $ $ ~ $ $ $ ~ $ $ $ ~ $ $ ~ ggg $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ '$$ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-CT-016 22 23 CT-SW-D3 RED TEE-PIPE PT 1-1-01 08.00 0.322 24 25 CT-2-FW-154 PIPE -VALVE PT 08.00 0.322 26 27 SYSTEM : MS MAIN STEAM ISOMETRIC NUMBER: I I-MS-001 28 29 MS-SW-A30 EXTRUD -PIPE MT 1-1-01 08.00 0.500 30 31 MS-SW-B30 EXTRUD -PIPE MT . 1-2-03 08.00 0.500 NO 32 33 MS-SW-B34 EXTRUD -PIPE MT 1-2-03 06.00 0.432 34 35 MS"SW"C30 EXTRUD -PIPE MT 1-3-06 08.00 0.500 36 37 MS-SW-C34 EXTRUD -PIPE MT 1"3-06 06.00 0.432 I~ 38 39 SYSTEM : MS MAIN STEAM ISOMETRIC NUMBER: I I-MS-002 40 41 MS-'FW-693 PIPE -ELB LR MT 1" 1-01 08.00 0.500 NO 42 43 MS-SW-A3 ELB LR -PIPE PT 1" 1 "01 08.00 0.500 44 45 MS-FW-692 PIPE -VALVE PT 1-1-01 08.00 0.500 NO 46 47 MS-FW-691 VALVE -PIPE MT 1-1-01 08.00 0.500 48 49 MS-FW-690 PIPE -VALVE MT 1-1-01 08.00 0.500 NO 50
-ELB LR 1-2-03 "
08.00 0.500 51 MS-FW-565 52 tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt PIPE MT NO 53 54 55 56 57 58 59 60
349 tttttttttttttttttttttttttfttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt*tttttttttt 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT " UNIT t 4 PLANNING ttttt*et 5 t COMPONENT LISTING AND ISI 10 YEAR PLAN: 835"01 PAGE 348 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 t t t t tt t t ttt t ttttttt t tt tt ttttt tt t t THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t' t' t t t t t t t tt tt ttt t t tt ttt t t t tt t tt t t t t t t tt tt t t t t t tt tt t t tt t t t t t ttDATE t t t t tt t 88/01/12 tt t t t' t t t t t 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.11 PIPING CIRCUMFERENTIAL WELD <e 1/2" NOMINAL WALL THICKNESS 12 13 t t ttttt tttt t tt t t t t t t t t ttt t t ttt t' t tt ft t tt t' t t t t' t t t t ttt tt t t tt t t t tt tt t t t t tt t t t tt t tt t tt t t t tt t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 ssrrsssssassssssssasssas aearrssaassssas erases sseaassrasssssar rarer seers stresses erases sss erases assess ararat 20 21 SYSTEM : MS MAIN STEAM ISOMETRIC NUMBER: I I-MS-002 22 23 MS-SW"C3 ELB LR -PIPE PT 1-2-03 08.00 0.500 NO 24 25 MS-FW-566 PIPE -VALVE PT 1-2-03 08.00 0.500 NO 28 27 MS-FW-567 VALVE -PIPE MT 1-2-03 08.00 0.500 NO 28 29 MS-FW-568 PIPE -VALVE MT 1-2-03 08.00 0.500 NO 30 31 MS-FW-680 PIPE "ELB LR PT 1-3-06 08.00 0.500 32 33 MS-SW-E3 ELB LR -PIPE PT 1-3-06 08.00 0.500 34 35 MS-FW-681 PIPE -VALVE PT 1-3-06 08.00 0.500 NO 38 37 MS-FW-682 VALVE -PIPE MT 1"3-06 08.00 0.500 NO 38 39 MS"FW"683 PIPE -VALVE MT 1-3-06 08.00 0.500 NO 40 41 SYSTEM : MS MAIN STEAM ISOMETRIC NUMBER: I I-MS-007 42 43 MS-FW-564 PIPE -ELB LR PT 1-1-01 06.00 0.432 NO 44 45 MS-SW-A3 ELB LR -PIPE PT 1-1-01 06.00 0.432 NO 4e 47 MS-FW-563 PIPE -VALVE PT 1-1-01 06.00 0.432 NO 48 49 MS-FW-679 PIPE -ELB LR MT 1-1-01 06.00 0.432 NO 50 51 MS-SW"83 ELB LR -PIPE PT 1-1-01 06.00 0.432 NO 52 MS-FW-678 PIPE -VALVE 1-1-01 06.00 0.432 53 54 tet tttttttttttttttttttt'ttttttttttttttttttttttttttttttttt PT tetttttttttttttttttttttttttet tttttttttttttttttttttttettttttet NO 55 Se 57 58 59 eo FORM 0113 102/83)
350 11111111 1 t t *1 1 1 1 t 1 t 1 1 t 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 t t 1 t 1 1 t 1 t t 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 t 1 1 1 1 tI rr 1 t 1 t 1 1 1 1 1 1 t 1 1 1 1 t 1 1 1 1 1' t NUTECH CAROLINA POWER & LIGHT COMPANY PR IS IM 1 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 1 PLANNING 1 1 1 1 '1 1 1 1. 1 tt t 1 1 1 1 1 1 1 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 349
-.8 ASME SECTION XI, 1983 EDITION THROUGH AND-INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01" ONLY DATE 88/01/12 7
8 ttttttttttttttttttttttttttttltttttttttttttttttttttttttltltttttttttttttttttttttttttl ~ 9 10 CATEGORY C-F PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. C5. 11 PIPING CIRCUMFERENTIAL MELO <$ 1/2" NOMINAL WALL THICKNESS 12 13 t tttt t 11 t I 11 111 11 1111 1111 t ttt t t t t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1' 1 1 1 1 1 1 It t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t t 1 1 1 t 1 1 t 1 1 t 1 1 1 1 1 1 1 1 1 1 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND RE@ST TIONS NOTES I 19 $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ IS ~ $ $ $ $ $ $ $ $ ~ $ $ $ $ ~ $ $ $ $ $ $ ~ ~ $ $ $ I ~ I $$$$$ SSSSII ~ I III
~ ~ ~ $$$ $$~ ~ II $ $ $ $ $ $ $ $ ~ IS ~
20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-CS-002 22 23 RH-FW-92 NOZ1AO "PIPE PT . 10.00 0.365 NO 24 25 RH-SW-A14 PIPE -ELB LR PT 10.00 0.365 26 27 RH-SW-A13 ELB LR -PIPE PT 10.00 0.365 NO 28 29 RH-SW-A12 PIPE -ELB LR PT 10.00 0.365 30 31 RH-SW-A11 ELB LR -PIPE PT 10.00 0.365 32 33 RH-25-2-SW-3 PIPE -PIPE PT 08.00 0.322 34 35 RH-SW-A10 PIPE -ELB LR PT 10.00 0.365 NO 38 37 RH-SW-A9 ELB LR -PIPE PT 10.00 0.365 38 39 RH-SW"AB PIPE -TEE PT 10.00 0.365 40 41 RH-SW-AS TEE -PIPE PT 10.00 0.365 NO 42 43 RH" 25-1-SW-1 PIPE -PIPE PT 08.00 0.322 NO 4 45 RH-SW-A6 PIPE -REDUCER PT 10.00 0.365 NO 46 47 RH-SW-A4 TEE -PIPE PT 10.00 0.365 48 49 RH-25-2-SW-1 PIPE -PIPE PT 08.00 0.322 NO 50 51 RH-SW-A3 PIPE -FLG RFW PT 10.00 0.365 NO 52 53 RH-SW-84 FLG RFW-PIPE PT 10.00 0.365 NO 54 t t t t t t t t t t tr 1 1 1 1 1 1 1 1 1 1 1 1 1 tr 1 1 1 1 1 1 1 1 1
- 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
- 1 tr 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t t 55 56 57 58 59 60 FORM 0113 {02I83) 4
353 t t t t 't ttttt t t t *tt t t ttt tt t t t t tt t tt ttt tt t tt t t t t t tt t t t t ttt tt t t t ttt t t t t t f t t tt t t t t t t t t t t tt t t tt t t t t tt t t tt t tt tt tt
- t t t tt t t t NUTECH CAROLINA POWER & LIGHT COMPANY PR IS IM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING tt t t tt 't t t t t tt t t t t t t COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 352 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 tt t tt 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY
't t tt t t t ttttt tt tt tt t ttt tt tt t t t t t t t t t tt t tt t t t t t t ttt t t t tt tt t t t tt t t t tt tt t t tt t tt tt t t tt tt t tt tt t t t ll! t t t t t t t DATE t t t tt
- t t t t t 9
10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING I 'I ITEM NO. C5. 11 PIPING CIRCUMFERENTIAL WELD <s 1/2" NOMINAL WALL THICKNESS 12 13 t *t tttttt t ttt t t t tt t tt t tt t t tt t t tt t t tt tt t t t tt tt t t t t t t t t tt t tt t t tt tt t ttt t t t t tt t t tt t t t tf t t t tt t t t ttt t t 14 15 DONE 15 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 sssassssssassssssaaassss ssaassassssssss a sass s ssa ssssasssas sssas ssaas asssssss ssssas sss asssss sssaaa saasss 20 2I SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-CS-002 22 23 RH-SW-88 ELB LR -PIPE PT 08.00 0.322 NO 24 25 RH-SW-87 PIPE -ELB LR PT 08.00 0.322 28 27 RH"SW"86 ELB LR -PIPE PT 08.00 0.322 NO 28 29 RH-SW-85 PIPE -RED TEE PT 08.00 0.322 30 3'I RH-SW-A7 REDUCER-PIPE PT 08.00 0.322 32 33 RH-FW-90 PIPE -VALVE PT 08.00 0.322 34 35 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER : II-CS-021 38 37 RH"FW-83 PIPE -PIPE PT 10.00 0.365 38 39 RH-SW-86 PIPE -ELB LR PT 1-2-03 10.00 0.365 40 41 RH-SW-87 ELB LR -PIPE PT 1-2-03 10.00 0.365 NO 42 43 RH-FW-84 PIPE -ELB LR PT 10.00 0.365 NO 44 45 RH-SW-A3 ELB LR -PIPE PT 10.00 0.365 48 47 RH-SW-A4 PIPE -ELB LR PT 10.00 0.365 NO 48 49 RH-FW-159 ELB LR -PIPE PT 10.00 0.365 50 51 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER : II-RH-001 52 53 RH-2-2-SW-1 -PIPE t t t t t 0.375 t t t tt t t t t t t t t t t tt t t t t t tt t12.00 PIPE 54 t t t t t t t t t ttt tt t tt t t 't tt ttt
't t tt t t t tt t tt t t t PT NO t t t t t t t t tt t t t tt t t t t t t t t t t t t t t t t t t t tt t t t t t t t t t t 55 58 57 58 59 60 FOAM 0113 102I83)
- r. '<<rw Yjr!, rr,<<q ~ AKg% r .S ra ')'. -4! r, <<! wr. /,, ~ r, r ~ << -. w ' ~,<<' w r ~ ! w, - ~, ~ r ..rsr', l, r ~ ~ s
354 fff f fff 4 f f ff 4 ttft t fittff tt ttff 4 f tfttf4 4 ttt tt ttftt tt t tft tftft tt tt t ttftttfttftftttt f ttftff f 4 4 t tftff tf4 ff ttf4 f 4 t 4 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRI SIN 3 4 - UNIT 4 t SHEARON HARRIS NUCLEAR POWER PLANT PLANNING ffffft'ttfffftt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 353
.6 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 '7 THE SUMMER 1983 ADDENDA, INTERVAL'Of ONLY DATE 88/01/12 8 tttttttfff f tf4 ttttftf tftfttttfttftfftfttftttttttttttttttf ttttftftttttttttttttftttttfttt ttttf ttttf 4 4 4 4 4 tttfttttfttttf 9
10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5. 11 PIPING CIRCUMFERENTIAL WELD <4 1/2" NOMINAL WALL THICKNESS 12 13 f 4 4 4 4 4 4 '4 4 t 4 4 t fl t f OII t 4' 4444 t 4 f 4 f 4 4 4 t 4 t 4 t 4 't 4 4 'f 4 tt tt 4 fl ftt tt t 4 tt t t 't 't f 4 f tf t 4 4 4 f 4 t 4 t f 4 t 4 t 4 4 t 4 t 't f t 4 4 f 4 4 t t t 4 4 t 4 'll 4I 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 4$ 444444444 ~ 4 4444444 ~ 44 SSSSSSSS ~ $ 444 ~ 4 $ $ $ 4$ 4 ~ $ 4444 ~ 444 ~ 4444 ~ 4 ~ 4$ 4 4 ~ 44 444444 444444 444 4 ~ 4$ '4 4$ $ ~ 4 ~ ~ 44444 20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-001 22 23 RH-2-5-SW-1 PIPE -PIPE PT 12.00 0.375 24 25 RH-24-1-SW-1 PIPE -PIPE PT 10.00 0.365 26 27 RH-24-1-SW-2 PIPE "PIPE PT 10.00 0.365 NO 28 29 RH-FW"3 FL HEAD-P BEND PT 1-1-01 12.00 0.37S NO 30 31 RH-SW-A4 P BEND -ELB LR PT 1-1-01 12.00 0.375 NO 32 33 RH"SW-A3 ELB LR -PIPE PT 1-1-01 12.00 0.37S NO 34 35 RH-SW-AB PIPE -PIPE PT 12.00 0.375 NO 36 37 RH"FW-4 PIPE -ELB LR PT v 12.00 0.375 NO 38 39 RH-SW-B6 ELB LR -PIPE PT 12.00 0.375 NO 40 RH-SW-B17 PIPE -PIPE 12.00 0.375 v'. 41 PT 42 43 RH-FW-5 PIPE -PIPE PT 12.00 0.375 NO 44 45 RH-SW-CS PIPE -ELB LR PT 12.00 0.375 NO 46 47 RH-FW-6 ELB LR "PIPE PT 12.00 0.375 NO 48 49 RH-SW"D11 PIPE -PIPE PT 12.00 0.375 NO 50 51 RH-SW-D3 PIPE -ELB LR PT 12.00 0.375 NO 52 53 RH-SW-D4 "PIPE 12.00 0.375 tiff f 4 tlf4 f ftf 4 4 f 4 tff 4 4 4 f 4 f 4 f ttftf4 4 4 t ttttt tttftftft*ttttttt 4 f tf 4 f f 4 tttt'4'4 ttt'tttttf 'tf f ffffff ELB LR PT NO 54 f f f tff t ttftf4 ttftffttf4 tf4 4 55 56 57 58 69 60 v.
356 f f ff t tffffft f t Its sf f sf t f ffffft t tt tt t tt t f ft f tt t ff t fft tt t t f f f t t tfftf t t t t t ft t*ft ftt t t t ft t f t ff f t f ft t f f f t ttf fft t t f f tf t ff 1 2 NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM f SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4 tr PLANNING 1 ffftfffffftfffffftf COMPONENT LISTING AND ISI 'IO YEAR PLAN: 83S-01 PAGE 355 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA,= INTERVAL*OGONLY DATE 88/01/12 f fff f *ftat f f tff f tfff f tff tff tff ff tff f tftttft t t t f f f t tftf ft ffffft f at ff t f at *a ff f sf t' f tf sf f tt t f f t f f tff t tft ff at t ft t f f fft tff 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.11 PIPING CIRCUMFERENTIAL WELD (s 1/2 NOMINAL WALL THICKNESS 12 13 f*ff f at tf ttf f f f ttf f f ff tff fffat ttf tat tat tttf tat sf tf f fat f at at tff tf ttf ttftf tat*a tttf tat f fff f f ffat at at tf taft f fttffff ftff t 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssssssassssssaassssss sssssaaasasaasa ssaasa sssasass s ss s stats fasts ssssasss ssssss sss ssssss ssssss ssassa 20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER : II-RH-001 22 23 SI-FW-9 TEE -PIPE PT 14.00 0.438 NO 24 25 RH-SW-E7 PIPE -TEE PT 14.00 0.438 28 27 RH-SW-E6 TEE -PIPE PT 14.00 0.438 NO 28 29 RH-SW-ES PIPE -TEE PT 14.00 0.438 NO 30 31 RH"SW-EB TEE -FLG WNO PT 14.00 0.438 NO 32 33 RH-SW-E4 TEE -PIPE PT 1" 1-01 14.00 0.438 NO 34 35 RH-SW-E3 PIPE -ELB LR PT 14.00 0.438 38 37 RH-FW-8 ELB LR -NOZ1AI PT 1-1-01 14.00 0.438 NO 38 39 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-002 40 41 RH-11-1-SW-1 PIPE -PIPE PT 10.00 0.365 42 43 RH"5-3-SW-1 PIPE -PIPE PT 12.00 0.406 44 45 RH-5-6-SW-1 PIPE -RED TEE PT 14.00 0.375 45 47 RH-FW-16 FL HEAD-P BEND PT 1-3-06 12.00 0.406 48 49 RH-SW-A3 PIPE -ELB LR PT 1-3-06 12.00 0.406 NO 50 51 RH-SW-A4 ELB LR -PIPE PT 12.00 0.406 52 RH-5-2"SW-1 -PIPE 0.406 53 54 PIPE tftff tff tf*tft*ft f iff f tft12.00 f f ff f ff f ff f f t fffPT tt t ft t t f at ft tt t t tff ft art f ff f t f tff f t f ff tff t f tfft tff tf NO 55 58 57 58 59 80 FORM 0113 (02I83)
.0
357 1 t ttft tt t t tff t f tt t tff t t tt tt tft t tt t fft tt f f tt tt f t t tft t t ftt ftf f f t ft f f tt ft t f t**tt tt t tt tt tt tt t ff tft t tt t t tft t t t tt tft tt t t t t 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT UNIT f t*tftff ttttftfttff 1 4 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 356 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 tr THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t tt t 'f t tfft t f t t *i ff t t t tt t tf t t *t t f f t t t t t t t ttt tt t t t tt t tft t t t t f tt tt t t t tfttt t tfft t t t t t t t t tt t fttttt t ttt tt DATE
- f. ft t f t 88/01/12 t t t rt tt t rt t t f 9
10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. CS. 11 PIPING CIRCUMFERENTIAL WELD <$ 1/2'OMINAL WALL THICKNESS 12 13 tt t tt tf tt t tt f ttft t t f ft tt*ttttff tfftttt ft tft t t tft tfft t t tttt t f f t t tff tt t tt t t t t t t tfftt ff ft t t
'f fthm t tt t t tt t f tt tt t t tt tf *tt t tt 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ~ $ $ $ $ ~ $ $ $ ~ $ $ $ ~ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ ~ $ ~ $ $ $ $ $ $ $ ~ $ $ $ ~ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ '$$ $ $ '$$ $$ ~$$$ $~$ $$ $~$$ ~$$$~$ $$$$$$
20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER : II-RH"002 22 23 RH-FW" 17 PIPE -ELB LR PT 12.00 0.406 NO 24 25 RH-SW-85 ELB LR -PIPE PT 12.00 0.406 NO 28 27 RH-FW-18 PIPE -PIPE PT 12.00 0.406 28 29 RH-SW-C19 PIPE -PIPE PT 12.00 0.406 NO 30 31 RH"SW-C6 PIPE -ELB LR PT 12.00 0.406 NO 32 33 RH" FW-19 ELB LR -PIPE PT 12.00 0.406 NO 34 35 RH-SW-D6 PIPE -PIPE PT )2.00 0.406 NO 38 37 RH-SW-D19 PIPE -PIPE PT 12.00 0.406 38 39 RH-SW-D5 PIPE -ELB LR PT 12.00 0.406 40 41 RH-SW-D4 ELB LR -PIPE PT 12.00 0.406 42 43 RH-SW-D3 PIPE -ELB LR PT 12.00 0.406 44 45 RH-FW-20 ELB LR -PIPE PT 12.00 0.406 48 47 RH-SW-EB PIPE "RED TEE PT 12.00 0.406 48 49 RH-FW-63 NOZ180 -REDUCER PT 10.00 0.365 50 51 RH-SW-LS REDUCER-PIPE PT 1-3-06 10.00 0.365 52 RH-SW-L4 -ELB 1-3-06 0.365 ff ft t t tf t f t f f f f f ff t f t t tft t t f tt t t t f' t f f' f t10.00 t t t rf tt t f f f ff *t It
- fl t tr fr f t PIPE 53 LR PT NO 54 lit rlr rlr t tft tfft f t t f tff t t tt t ft t f ft tt f t ftt ft t f f' f t' t t t t fffft 55 58 57 58 59 80 FOAM 0113 (02IS3)
359
**ast tat tet t t t tt'st tet t tt tt tt t'tt't t tt t t et t tet tt tttt tt t tt et t t tt t*tt tt tet t tt tet t t tt 4 t it t t tet t t st st st tet t t t t tet et t testate t NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 PLANNING t t t t t t' t t tt t t t t t tt t 5 t COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 358 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 8 tat et t tent et t tet t at st t at st t tf tt tt t t t t t t t t t t tt t t tt at t t*a et tet tet
- t' t t t et t et t at et et tet tt arts t t et st t t tt t t st et et tt llr*at 9
10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.11 PIPING CIRCUMFERENTIAL WELD (a 1/2" NOMINAL WALL THICKNESS 12 13 t t t t t ttt tt tt t t t t t ttt tt ttttt t t t t t tt t t t tt t t tt t t t t tt t t t tt ttt t t t tt t tt t t t t ttt t tt tt t t tt tt t tt tt t t t tttt t t tt t t t t t t t ttt t tt t t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssasasasassssesssassasss ssaeesessssssss assess sa sasssasaassss asses seats asssasas states sss assess assess sssaa-20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-004 22 23 RH-FW-78 NOZ180 -PIPE PT 10.00 0.365 NO 24 25 RH-SW-A3 PIPE -ELB LR PT 10.00 0.365 26 27 RH-SW"A4 ELB LR -PIPE PT 10.00 0.365 NO 28 29 RH-SW-A5 PIPE -ELB LR PT 10.00 0.365 NO 30 31 RH-SW-A6 ELB LR -PIPE PT 10.00 0.365 NO 32 33 RH-SW-A7 PIPE -ELB LR PT 10.00 0.365 NO 34 4 35 RH-SW-AB ELB LR -PIPE PT 10.00 0.365 NO 36 37 RH-FW-79 PIPE -TEE PT 10.00 0.365 38 39 RH-SW-84 TEE -PIPE PT 10.00 0.365 NO 40 41 RH-SW-83 PIPE -FLG RFW PT 10.00 0.365 NO 42 43 RH-SW-C5 FLG RFW-PIPE PT 10.00 0.365 NO 44 45 RH-SW-C4 PIPE -RED TEE PT 10.00 0.365 NO 46 47 RH-SW-C3 RED TEE-PIPE PT 10.00 0.365 48 49 RH-FW-74 PIPE -ELB LR PT 10.00 0.365 50 51 RH-SW-D3 ELB LR -PIPE PT 10.00 0.365 52 53 RH-SW-D4 -ELB 10.00 0.365 54 ttt t t t tt t t t t tt t tt t t tt t tt PIPE t tt tt t t tt t tt t t tt PT, LR NO rt t t ttt tt ttt t t t t t t tt tt t t t t t t t t t t ttt t t t ttt t t t tt t t tt
- t t t t t tt t t t t t t t t t t t t t tt t t tt 55 56 57 58 59 60 FORM 0113 (02I83)
tet 361 t t t tt 't t ttttttt t t t t tt rt t t t t t 't t t t t t ttt t tt t t t t t t tt ttt tt t t' t t tt tt tt tt t t tt tt t t t t t t tt t t tt t t t tt t t t t t t t tt ttt t tt t tt t t tt t 't tt tt t 't 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 tr SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 PLANNING 1 t tt et t t tet t tt t tt t t t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 360 6 ASME SECTION XI. 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 DATE 88/01/12 7 8 tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt*ttf THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY ttttttttttttttttttttttttt 9 10 CATEGORY C-F PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. C5.11 PIPING CIRCUMFERENTIAL WELD <s 1/2" NOMINAL WALL THICKNESS t tttt tt t t tt t t t 4 at art sf st 12 13 tat t mt t tt tt t t t t et et t tet t et t ~ et t mt t mt tat at t t at tent t t et t t t t t t t t t et tamest t t tet t t at et'at t t mt tat t mt 0 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 ssassssssssssssassssssss ssssassssas s sea se aseasssssssseess asses amass eaasaasa asa a s s assess assama assama ttttttt 20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-004 22 23 RH-SW-H6 PIPE -ELB LR PT 08.00 0.322 NO ~ 24 at 25 RH-SW-H7 ELB LR -PIPE PT 08.00 0.322 NO 26 27 RH-SW-HB PIPE -ELB LR PT 08.00 0.322 NO 28 29 RH-SW-H9 ELB LR -PIPE PT . 08.00 0.322 30 31 RH-FW-75 PIPE -REO TEE PT 1-3-06 08.00 0.322 NO 32 33 RH-SW-87 REDUCER-PIPE PT 1"3-06 08.00 0.322 NO 34 35 RH-FW-80 PIPE -VALVE PT 08.00 0.322 36 37 RH-SW-G5 PIPE -ELB LR PT 10.00 0.365 NO tetttttttttttttttttttttttmt 38 39 RH-SW-G4 ELB LR -PIPE PT 10.00 0.365 NO 40 41 RH-SW-G3 PIPE -ELB LR PT 10.00 0.365 NO 42 43 RH-FW-66 ELB LR -PIPE PT 10.00 0.365 NO 44 45 RH-FW-67 PIPE -VALVE PT 10.00 0.365 46 47 RH-FW-76 VALVE -PIPE PT 10.00 0.365 NO 48 49 RH-SW"E3 PIPE -RED TEE PT 10.00 0:365 50 51 RH-12-1-SW-1 RED TEE-PIPE PT 1-2-03 10.00 0.365 NO 52 RH-FW-77 -NOZ1BI 1-2-03 10.00 0.365 tat tt'tttttttttttttttttttttttttttttttf PIPE PT NO 53 54 ttttttmtt tet ttttttttttttt tat tttttatttet et 55 56 57 58 59 60 FORM 0113 102I83)
364 t 4 4 4t 4 4 4 4 4 4 4 44 tft 4 4 44 4 4 4 t 4 4 4 44 4 44 4 4 t f tf4 4 44 t 444 4 4 4 f4 44 t 4 4 44 4 4 4 4 4 t ' t tt 4 44 4 4 f 4 4 4 t 44 4 t4t4 4 tftf t 44 4 4 4 4 4 4 4 4 44 4 4 t tftt 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT UNIT 3 4 PLANNING tf 44 4 4 444*f444 44 4 tt 5 COMPONENT LISTING QND IS I 10 YEAR PLAN: 835-01 PAGE 363 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 4 THE SUMMER 1983 ADDENDA. INTERVAL 0) ONLY DATE 88/01/12 7 4 44 ttt f t f 4 444 4 4 4 44 4 4 444 4 4 444 444 4 4 4 t4 44 4 44 4'4 4'4 4 4 4 4 4 t t4 4 4 4 4 4 4 4 4 4 tf 4 4 t fthm 4 4 4 4 4 444 4 444 4 4 4 4 4 444 4 4444't 4 4 4 4 t tf 4 4 4' tt tf tf 44 44 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ll ITEM NO. C5.11 PIPING CIRCUMFERENTIAL WELD <4 1/2" NOMINAL WALL THICKNESS 12 13 ttttf tat 44 tf ftftff 4 4 4 44 f f at tan tttft444 tt f 44 ttttt tf tttt4 f4ttttttt ttf44f f t4tttfttf tttttttt4ttf44 4tt4tttttt4 tat tt 44 4 14 15 DONE le OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM le NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 ssssssssssssssssasssaass sssassssssssass ssssss saaassssssaassss ssaas sssas asssssaa ssssss sss ssasss ssasss ssassa 20 21 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-RH-001 22 23 SI "SW-G3 ELB LR -PIPE PT 14.00 0.438 24 25 SI-F W-7 PIPE -VALVE PT 14 . 00 0. 438 NO 26 27 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-RH-002 28 29 SI-2-FW-31 PIPE -PIPE PT 14.00 0.375 ND 30 31 SI-FW-24 VALVE -PIPE PT 14.00 0.375 32 33 SI-FW-23 PIPF -VALVE PT 1-2-03 14.00 0.375 34 35 SI-FW-13A PIPE -SUMP PL SUR 14.00 0.375 NO R2-004 36 37 SI-SW-K3 REDUCER-PIPE SUR 14.00 0.375 NO R2-004 38 39 SI-SW-K5 PIPE -PIPE SUR 3 14.00 0.375 NO R2-004 40 41 SI-FW-14 PIPE -P BEND PT 1-2-03 14.00 0.375 NO 42 43 SI-FW-15 P BEND -VALVE PT 14.00 0.375 NO 44 45 SI-2-FW-16 VALVE -PIPE PT 14.00 0.375 NO 4e 47 S I-2-F W-16A PIPE -FLG BLN PT 14.00 0.375 NO 48 49 SI-FW-18 PIPE -ELB LR PT 14.00 0.375 50 51 SI-SW-G3 ELB LR -PIPE PT 14.00 0.375 NO 52 SI-FW-19 PIPE -VALVE 1-2-03 14.00 0.375 NO 4f 44 4 4 4444 4 4 4 4 4 4 44 444 4 tt 444 t tf4 444 4 4 4 4 4*ft 4 4 4 Ptt 4 4 tat tf4 4 f 4 4 ttt 4 444 4 t f 4 tft4 4 4 4 4 4 44'4 4 4 tt4 4'4 4 4 4 4444'tt 53 PT 54 4 55 se 57 58 59 60
370 ttttttttttttttttttttttttttttttttttt*ttttttttttttttttt*ttttttttttttttttttttttttttttttttttttttttttttttt NUTECH CAROLINA POWER & LIGHT COMPANY PR I 5IM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1 ttttt f ttttttt at attt COMPONENT LISTING ANO ISI 10 YEAR PLAN: 835-01 PAGE 369 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL-.01 ONLY .DATE 88/01/12 tt t t t t ttt t t t t t t ttt tt 't tt t ttt t t t t tt t t ttt t t t t t tt t t t tt t t tt ttt t tt t t t t t t t tt t t ttt t tt tt tt t tt tt t tt t t t ttttt t t t ttt t t t t tt t t t t t t t t w 7 8 I 9 10 CATEGORY C-F PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. C5.11 PIPING CIRCUMFERENTIAL WELD <s 1/2" NOMINAL WALL THICKNESS 12 13 tt t t ttttt t ttt t tttt t tt t t t t ttt t t tt tt t t t *t tt t t t t t t t tt t t t t t tt ttt t t t ttt t t t t tt t t. t, tt tt t t t t tttt t t t tttt t t t ttt ttt t t ttt t t t t tt 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssssssaasasasassasass ssarssssssaasss ararat asssssasssssssss stars sass- sssssrss ssassa sas tartar ararat sassss 20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER II-SI-009 22 23 SI-SW-CB PIP( -PIPE PT 10. 00 0. 365 NO 24 25 SI-FW-277 PIPE -PIPE PT 10.00 0.365 'NO 28 27 SI"94-2-SW-1 PIPE -PIPE PT 10.00 0.365 28 29 SI-SW-87 PIPE -PIPE PT 10.00 0.365 30 31 SI-SW-86 PIPE -ELB LR PT 10.00 0.365 32 33 SI-SW-85 ELB LR -PIPE PT 1-1-01 10.00 0.365 34 35 5 I-F W-278 PIPE -VALVE PT 1-1-01 10.00 0.365 38 37 SI-SW-E6 RED TEE-PIPE PT 1-3-06 08.00 0.322 38 39 SI-SW-E7 PIPE "ELB LR PT 08.00 0.322 NO 40 41 SI-SW-EB ELB LR -PIPE PT 08.00 0.322 NO 42 43 SI-FW-284 PIPE -VALVE PT 08.00 0.322 NO 44 45 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-021 48 47 SI-FW-555 NOZ1AO -PIPE PT 1-1-01 12.00 0.375 NO 48 49 SI-SW-A6 PIPE -ELB LR PT 12.00 0.375 NO 50 51 SI-SW-A5 ELB LR "PIPE PT 12.00 0.375 NO 52 SI-SW-A4 PIPE -ELB LR PT 12.00 0.375 NO 53 54 t t t t t ttttttt t ttt t tttt t t t t t t t t t t t t tt t tt t tt t tt t t t t t t tt t t t ttt t tt t t tttt t tt tt t t tt t t t tt tt tt tt t t ttt ttt t t t tt t tt tt tt t t t t t t t t tt 55 58 57 58 59 80 FORM 0113 (02I83t
372 1 ff f f f tff ff fff ffff f ff tfffff f ttff f f f tfff f f ff ff f fttfff f ttttff tfff f f tftttftftftftfff ff tt fff ff tff f f f tft tff tftftff tfff tt 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3
- SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t 4 PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 371 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
~ =,7 8
THE SUMMER 1983 ADDENDA; -'INTERVAL 01 ONLY tt f tt 88/01/12. tt ft t t t tt t t t t t tt lr t t t ttt ttt tt t tffthm t t tff f t ff tfft t f t*tt tftf ft*tt ft f t t DATE t t t ft tt t t tt 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5. 11 PIPING CIRCUMFERENTIAL WELD <$ 1/2 NOMINAL WALL THICKNESS 12 13 ttlrfttfttttttttftttttttttttttttttfttfttttft f ttftff ft f f f f tttttttfttlrttfirf tttftff f tttttttttttttfttlrttffff f t ttfttttttf 1 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $$$$$$$$$$ ~$$$ $$$$$$$ $ '$ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ '$$ $ $ $ $ $ $ $ $ $ $ $$$ $$$ $$$$$~ ~$~$$$ $$$$$$ 20 21 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: II-SI-023 22 23 SI-170-1-SW-1 ELB LR -PIPE PT 12.00 0.375 24 25 SI-SW-A6 PIPE -ELB LR PT 12.00 0.375 NO 26 27 SI-SW-A7 ELB LR -PIPE PT 12.00 0.375 NO 28 SI-FW-561 12.00 1. 125 29 30 tff tfft t tft f fftffft ft tftfPIPE tftttfff-VALVE PT NO t tff t f ff t tfff f t t f t fftt t f tftf ff tfff f ff f f f f f f f f f t t f fff tt ftf f f f f ff f f t fffft tt f f f ff f f f t f f 31 32 33 34 35 38 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 se 57 58 59 60 FORM 0113 (02I83)
t st st t tt t tt tt t tt tt lrt t t t lrt tat t t tt t t t t t t t tt t t tt tt t t t t at t t t t t st t at tt t tt t tt tt t t t t st t st st to at't tt t't tt tat at st tt t tt t t NUTECH CAROLINA POWER Er LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1 tt t tt t tt t t' tt t tt t t t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 375 6 ASME SECTIONXI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA; INTERVAL 01 'ONLY DATE 88/01/12 7, 8 t t tt t t t ttt t t t tt tt t tttt ttt tt t tt tt t I t lr t t ttt t t t t t t tt t t t t t ttt t tt t t t lr t t tt tt tt ttt t tt tt t ttt tttt t t t tt t t t t t t t tt t t t tt tt t tt t t t 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. CS. 12 PIPING LONGITUDINAL WELD <x 1/2" NOMINAL WALL THICKNESS 12 13 tttttttttt t tt t tt t tt ttttt tt t t t t tt t t t t t' t tt t t t ttt ttt t t t tt t t tt ttt t t tt t t t t t t ttt t t t t tttt tt lr t tt lr t t tt tt tt t t t ttt t ll t tt ttt t t t lll 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 xsassssssasaaasasassaaas ssasassssaasssa ssssas sass ssxssa s sss s sass sasssssa sxaasa sss saaxss ssasss == sss 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER : II"CT-002 22 23 CT-FW-20A LNGSEAM PT 1-3-06 08.00 0.322 NO 24 25 CT"FW-21A LNGSEAM PT 1-3-06 08.00 0.322 NO 26 27 CT-FW-22ALA LNGSEAM PT 08.00 0.322 NO 28 29 CT-SW-A3A LNGSEAM PT 08.00 0.322 NO 30 31 CT-SW-A4A LNGSEAM PT 1-1-01 08.00 0.322 32 33 CT"SW-ASA LNGSEAM PT 1-1-01 08.00 0.322 34 35 CT-SW-B24A LNGSEAM PT 08.00 0.322 NO 36 37 CT-SW-83A LNGSEAM PT 08.00 0.322 38 39 CT-SW-B4A LNGSEAM PT 08.00 0.322 40 41 CT-SW-03A LNGSEAM PT 08.00 0.322 NO 42 43 CT-SW-D4A LNGSEAM PT 08.00 0.322 NO 44 45 CT-SW-D5A LNGSEAM PT 08.00 0.322 NO 46 47 CT-SW-DBA LNGSEAM PT 08.00 0.322 NO 48 49 CT-SW-DBB LNGSEAM PT 08.00 0.322 NO 50 51 CT-SW-F3A LNGSEAM PT 08.00 0.322 NO 52 53 CT-SW"F4A LNGSEAM PT 08.00 0.322 NO 54 ttttt t t t tttt t tt t t tr tt t t t t lr tt t t t t lr t tt tt t t t lr t t t t t tt ttt ttt t ttt t t t tt t t t t tt t t t t tt t lr t t t t ttt t t lr t t tt t tt t tt t tt t tt t t t tt t t t ttt t t t 55 56 57 58 59 60 FORM 0113 (02I83) l
379 1 ftffffff *ff f ftt tfft f t' ff t' ft f f f f f ft t f t ff t t t t f t t ft t t tt tt t t ftt
- t t f tt t t ftt *ttt t t ft ft f tt t t t t t' tf t f ft t' fft t ftt t t ff tf f f f f f t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PR IS IM 'f 3
4 SHEARON HARRIS NUCLEAR POWER PLANT PLANNING UNIT tttfttffftff 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 378 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 ft tIf f sf st f f tf fff f tff tt sf f tf f st f t t tf t ft ftf tfstd tfff f frt tf ft tft tt tf tff tft t ft tft t t tf fft f tft tft t tf 7 8 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5. 12 PIPING LONGITUDINAL WELD <s 1/2% NOMINAL WALL THICKNESS 12 13 tfrfrfrtftttttfttttttttttftttttttttttttttttttttttfff tttttftfttttttftffttftfftftftftfttttttfttftfttttttfrfrsf ttftsf ttf t'ONE 14 15 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sass%sass%sass%sass%sass assr%sass%sass% sass%a asssrsssasssarrr sass% arras sass%sar sara%a sss sass%a %rasa% sass%a 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-CT-007 22 23 CT-SW-E6A LNGSEAM PT 12.00 0.375 24 25 CT-SW-E7A LNGSEAM PT 12.00 0.375 26 27 CT-SW-EBA LNGSEAM PT 12.00 0.375 NO 28 29 CT-SW-F3A LNGSEAM PT 1-2-03 12.00 0.375 NO 30 31 CT-SW-F4A LNGSEAM PT 1-3-06 12.00 0.375 NO 32 33 CT-SW-F5A LNGSEAM PT 12.00 0.375 34 35 CT-SW-FGA LNGSEAM PT -12.00 0.375 NO 36 37 CT-SW-F8A LNGSEAM PT 12.00 0.375 NO 38 39 CT-SW-028A LNGSEAM PT 12.00 0.375 NO 40 41 CT-11-FW-33LA LNGSEAM PT 12.00 0.375 P2-REP NO 42 PT 1-1-01 43 44 CT-11-FW-52A LNGSEAM PT 12.00 0.375 NO 45 46 CT-11-FW-528 LNGSEAM PT 12.00 0.375 NO 47 48 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-CT-008 49 50 CT-FW-38A LNGSEAM PT 12.00 0.375 NO 51 0.375 ff fffff tt f f t'%sf ttlt f tff tt ff f f f sf tfft ffff f12.00 CT-FW-38B PT 52 53 tst fr f litt Ill% ff llrttttffr ff it% tfLNGSEAM it% ff f ff t f f f t t tat t\ ff tits ff f ffff f 'at ll' flirt% f t tt t t f tft sf ff 54 55 56 57 58 59 60 FOAM 0113 <02/83/ I I" ( Iv= ( rl . + vt' vs vs 6'p vr (<w + 'I vl vr lv (=7'v %~ v lv" It v, ov "~ ~ vv ~ vl ( vv, 8% ~ q ~ v ' rf,A v yI'~ .
/ ~ (v + ~ ', ~ +Q ~
380 ttffftft tffff tff ffff t ft f ftftfft tftttttfff f f et tftftffftt tftff et ff ftff f twttt t tff fft f ff ttftffff fttft f ttft tftttt t ffff ffff 2 NUTECH CAROLINA POWER 8 LIGHf COMPANY PR IS IM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4 fr PLANNING 1 f etf f et et tfff st taft 5 f COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 379 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 88/01/12 7 THE SUMMER 1983 ADDENDA; INTERVAL 01 ONLY
*tftttttfftttttttttttttftftttttttttttttttfttttttttftftftttfttfttt ~ ttttttttttttftttt*ttttf*f tt*tttffttttfttttttttttttf DATE 9
10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5. 12 PIPING LONGITUDINAL WELD 1 2 . 00 0. 375 NO 38 37 CT-SW-E4A LNGSEAM PT 12.00 0.375 NO 5'O 38 39 CT-SW-E7A LNGSEAM PT 12.00 0.37S 40 41 CT-SW-E8A LNGSEAM PT 12.00 0.375 42 43 CT"SW-F5A LNGSEAM PT 12.00 0.37S 44 45 CT-SW-F6A LNGSEAM PT 1-1-01 12.00 0.375 NO 48 47 CT-SW-FBA LNGSEAM PT 1-3-06 12.00 0.375 NO 48 49 CT-SW-I/29A LNGSEAM PT 12.00 0.375 NO 50 51 CT-12-FW-SSA LNGSEAM PT 12.00 0.375 NO 52 53 CT-12-5"SW-2A LNGSEAM PT 12.00 0.375 54 *f t lll t ffttt ftff tf t f f t t t fft t ft t t ff ff tfft t f tt f t t t t t t t t f t t t ft tt f t t f f t ttft f ff tt t ft t f f fff f t t fNO ft tf t t *t tt t t tt t f t tt t t f t t 55 56 57 58 59 60 FORM 0113 (02/83)
383 f f *fff ffff t hatt f t tfftftfff tftt ffffft tff et f f t st f t f f f f t tt t t tt t ttft f t ff f fff f t tt t f f f tftff f f ft t f tftftf ff f f ttff f tf tff tt tfff t 2 NUTECH CAROLINA POWER Er LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT= 1 ~, 'l 3
4 PLANNING t ff 'f *tff f f f f f f fff f f COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S "O'I PAGE 382 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 f t f rf f f ff 'f t*a f et tl sf ff fet f t tff t tfff ff t ffffffffff f ft f ff ft f' f fffff f f f fffff ff t fff f fff f f f f f ff ffft t f f' ff f f ft DATE f fft ffff ff ffffff 9
10 CATEGORY C-F PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. C5.12 PIPING LONGITUDINAL WELD (s 1/2" NOMINAL WALL THICKNESS 12 13 ff ff f fff ft f f t f *fftff tf t tf f f ftf 'f ft ttt f tf tf tffff ff t ff f ft f f f f t ff t f fff t f f f f f f 't tt f f ff 'f f fft f f ft f ff f fftf ff 't f f f f f t 't ff 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT . (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sasaasssssssassaas s a sass assess assess esssesaassssssas asses esses asssasss assess sss assess = as ess 20
~ 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER : II-CS-002 22 23 RH-SW-A10A LNGSEAM PT 10.00 0.365 NO 24 25 RH-SW-A11A LNGSEAM PT 10.00 0.365 26 27 RH-SW-A12A LNGSEAM PT 10.00 0.365 NO 28 29 RH" SW-A13A LNGSEAM PT 10.00 0.365 NO 30 31 RH-SW"A 14A LNGSEAM PT 10.00 0.365 32 33 RH-SW-A3A LNGSEAM PT 10.00 0.365 NO 34 35 RH-SW-A4A LNGSEAM PT 30.00 0.365 36 37 RH-SW-A5A LNGSEAM PT 10.00 0.365 38 39 RH-SW-AGA LNGSEAM PT 10.00 0.365 NO 40 41 RH-SW-A8A LNGSEAM PT 10.00 0.365 42 43 RH-SW"ABA LNGSEAM PT 10.00 0.365 NO 44 45 RH-SW-83A LNGSEAM PT 10.00 0.365 NO 46 47 RH-SW-B4A LNGSEAM PT . 10.00 0.365 NO 48 49 RH-SW-C10A LNGSEAM PT 10.00 0.365 NO 50 51 RH-SW-C3A LNGSEAM PT 10.00 0.365 NO 52 0.365 f f f f fff f ff ff f f f f f'fft tff trtt f sf t ttff ttftt f10.00 53 RH-SW-C33A 54 ff f ff tttff f ttff ff f ttff f fffLNGSEAM PT f f tffffff et ff tf f ff fffft f tftff f f tff ff f tfff ffffff ff ff NO 55 56 57 58 59 80 FORM 0113 (02I83)
'L 387 1 ttttftttttftttttttttftttttttttff tfttttfttttff tftff tfffttttttftttttttttttttttttttftttff ttff f tttttff tttfftttt ttftftfftt 2 NUTECH CAROLINA POWER 8 'LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR PLANT - UNIT 4 f PLANNING POWER 1 tttff f tttfttfftff tt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 386 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1883 ADDENDA, INTERVAL 01 ONLY 88/01/12 tttftff f ff f tftff ttff tttttttftfff tfftftff ff f tff off f tftttttff tttllrllrtftttttftDATE tftfttf tttf%lilttf 9
10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. CS. 12 PIPING LONGITUDINAL WELD <% 1/2 NOMINAL WALL THICKNESS 12 13 tff tttttttttttf*ttf f tfttftftttttff tff tff tfIff tff ttttttttfff ttfff fffff ftfftfttfttftffttftffff tftftf 14 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 SR%%' $ %%%$ %$ SSR'$ ~ R%$ $ %%$ %%$ ~ %%$ ~ %%$ ~ $ $ $ $ %% % % ~ SSSRSSS %$ %%% SR%%% %%%'%% % ~ $ $ %%%$ % % %%%% ~ $ $ ~ $ %% ~ 20 21 SYSTEM: RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-001 22 23 RH-SW-E3B ELBSEAM PT 14.00 0.438 NO 24 25 RH-SW-E3C ELBSEAM PT 14.00 0.438 NO 28 27 RH"SW-E34A LNGSEAM PT 12.00 0.378 28 29 RH-SW-E34B LNGSEAM PT 12.00 0.375 NO 30 31 RH-SW-E4A TEESEAM PT ~ 1-1-01 14.00 0.438 NO 32 33 RH-SW-E4B LNGSEAM PT 1-1-01 14.00 0.438 NO 34 35 RH"SW-ESA LNGSEAM PT ~14.00 0.438 NO 38 37 RH-SW-E5B TEESEAM PT 14.00 0.438 NO 38 c 39 RH-SW-EGA TEESEAM PT 14.00 0.438 NO 40 1 41 RH-SW-E6B LNGSEAM PT 14.00 0.438 NO 42 43 RH"SW-E7A LNGSEAM PT 14.00 0.438 NO 45 RH-SW-E7B TEESEAM PT 14.00 0.438 NO 46 47 RH-SW-EBA LNGSEAM PT 12.00 0.375 48 49 RH-SW-L3A LNGSEAM PT 10.00 0.375 NO 50 51 RH-SW-L4A LNGSEAM PT 10.00 0.365 NO 52 53 RH-SW-LSA 10.00 0.365 54 ff ttftt f fff f fr f f ffPTtf t t tff tt f f f f t t f f ffff f f ffff ttt t tfft f ft f ftf fr f t fr fr ff fffLNGSEAM tff ftff f t t t fft ft t tf ffft fNO tt f ff t ff fff t t ft 'f 'f ff t t t ff 55 56 57 58 59 60 FOAM 0113 (02I83) c c $ ,,g, r rr cb! c < H ', ' h, vlcc, i81cccsr vll r,, c, rc m l! c ~~ lc c. c l t ! ~ $ U 1 ~ 4 c C 1 ~
391 ff ft f tftt f tat f t tff tff t tff f tff ff ftat t tfft f ft tft f ftt t ff t tffft tftfff f st f f tff ff tff sf f f f t t t iftft tft t ff f fitf t f t'f f t'f NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1 tfft*ff f ff f ff t f tftt COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 390 ASME SECTION XI, 1983 FDITION THROUGH AND INCLUDING REVISION NRC1 ffff ftfff tft ttff ff fff tf'tttt tft ff t f f t f f f f ftfft tt ft tt tt ft tt tt tff sf f f ff f f f t f t f f'ff f t t tt tfff f fft ff st f aft 88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE f f fft tftt f f 9 10 CATEGORY C-F PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. C5.12 PIPING LONGITUDINAL WELD <s 1)2" NOMINAL WALL THICKNESS 12 13 ff tt sf f ff f tff f ff tft tff tff tff f f t f f f f f t tff t t f sf f ftfff ff f f t f fffft t t t f tftt t tt st tt tff tt f f f f f f t t f f f f f f ffftt f tft t f f tftfff f t 't 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULEO INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssaaassaaasssssassssa s a sss a ssssss sassssssaa s a a a sss saaasass ssssaa ssa aaasss sasass aassss 20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-002 22 23 RH-SW-L3A LNGSEAM PT 10.00 0.365 24 25 RH-SW-L4A LNGSEAM PT 1-3-06 10.00 0.365 NO 28 27 RH-SW-L5A LNGSEAM PT 1-3-06 10.00 0.36S NO 28 29 RH-SW-M4A LNGSEAM PT 10.00 0.365 30 31 RH-SW-M5A LNGSEAM PT 10.00 0.365 NO 32 33 RH-SW-M6A LNGSEAM PT 10.00 0.365 34 35 RH"SW-N3A LNGSEAM PT -10.00 0.365 NO 36 37 RH-SW-N4A LNGSEAM PT 10.00 0.365 NO R2-001 38 39 RH-11-1-SW-1A LNGSEAM PT 10.00 0.365 NO 40 41 RH-5-3-SW-1A LNGSEAM PT 12.00 0.406 NO 42 43 RH-5"3"SW-1B LNGSEAM PT 12.00 0.406 NO 44 45 RH-5-6-SW-1A LNGSEAM PT 14.00 0.375 46 47 RH-5-6-SW-1B TEESEAM PT 14.00 0.375 NO 48 49 SI-FW-21A TEESEAM PT 14 . 00 0. 375 NO 50 51 RH-5"2-SW-1A LNGSEAM PT 12.00 0.406 NO 52 53 RH-5-2-SW-18 LNGSEAM PT 12.00 0.406 NO 54 ff f ffft t f fff t f f ffff ff f ff fft ft t tff f ff f f *'ft ftff f ff f t tf f 't t ft tt t ff 55 56 57 58 59 60 FORhll 0113 (02/83)
393 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt t NUTECH CAROLINA POWER 6 LIGHT COMPANY PRI SIN PLANT - UNIT t SHEARON HARRIS NUCLEAR PLANNING POWER 1 ttt ttattttt tttttttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 392 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 8 t tt t t t tt t t t ttt t tt t tt t ttt t tttf t t t tt tt t tt tt tt t t t t t t t t tt t t t ttt t t t t t t t t tt t tt t t t t t t t *t tt t t t t t tt *tt tt t t t t t t t tt t t t t t t t t t t tr tr tr 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.12 PIPING LONGITUDINAL WELD (a 1/2" NOMINAL WALL THICKNESS 12 13 tt t ttttt t tt t tt t t t t t. t ttt t t t tt tt tt t t t t tt t tt t t tt t t tt tt tt t t t t tt t t t t tt t t tt t t t t t t t tt t
- t tt tt t t t tt tt t t ttt t tt t tt tt 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 ~ sssasssssras ss s s assssr sasssas starts ssssssasrasassss sasss attar aasasaas ssasra ssa ararat ararat tartar 20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-004 22 23 RH-SW-A6A LNGSEAM PT 10.00 0.365 24 25 RH-SW"A7A LNGSEAM PT '0.00 0.365 NO 26 27 RH-SW-A8A LNGSEAM PT 10.00 0.365 28 29 RH-SW-83A LNGSEAM PT 10.00 0.365 NO 30 31 RH-SW-84A LNGSEAM PT 10.00 0.365 NO 32 33 RH-SW-85A LNGSEAM PT 10.00 0.365 NO 34 35 RH-SW-86A LNGSEAM PT 10.00 0.365 NO 36 37 RH-SW-C3A LNGSEAM PT 10.00 0.365 NO 38 39 RH-SW-C4A LNGSEAM PT 10.00 0.36S NO 40 41 RH-SW-CSA LNGSEAM PT 10.00 0.36S 42 43 RH-SW-D14A LNGSEAM PT 10.00 0.365 44 45 RH-SW-D148 LNGSEAM PT 10.00 0.36S NO 48 47 RH-SW-D3A LNGSEAM PT 10.00 0.365 48 49 RH-SW-D4A LNGSEAM PT 10.00 0.365 NO 50 51 RH-SW-D5A LNGSEAM PT 10.00 0.36S NO 52 53 RH-SW-D6A 10.00 0.365 NO t t t t ttt t ttt t t t t t tttt t ttt tt t t tt t tttt tt t tt t t t t tt tt tt t t tt t ttt t t t t t t t t tt t t t t t t t t t t t ttttt t t t t tt ttt t t t tt tt tt tt t t t t t t t t tt LNGSEAM PT 54 55 56 57 58 59 60 FOAM 0113 <02I83)
tttt*tttttttttttttttttttttat 401 ttttttttttttttttttttttttttttttat tt ttttttttttttttttttftttttttttttttttttttttttttttttt tat t'SME 1 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT I t t t st t at tat at t t tt t t
~
4 PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 400 6 SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 8 't ttt t t t t t tt t tt t tt tttt t t t t t t tt *t t ttt t tt tt t t tt tt t tt t t t' t t t t ttt ttt t t t t t tt t t t t t t
- t t t t t t tt t t t t t tt t t t tt tttt t ttt t t t t t ttt t t 9
10 CATEGORY C"F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.12 PIPING LONGITUDINAL WELD <s 1/2" NOMINAL WALL THICKNESS 12 13 t t t t t t t t t t t t tt ttt tt t tt tt *t t t t t t t t t tt t t tt t t t tt t ttt t tt t t t tt t t t t tt tt tt t tt tt t tt t t t t tt t t t t t t t t tt t tt tt tt t t tt t t t t rt t tt tt t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssssaaassassaaasrsraaaaa saassssssrsssrs ssssrs raassrasaasrassa arras arras ssssassa rasasa sss ararat ararat saaaar r 20 21 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER : II-SI-008 22 23 SI-SW"H12A LNGSEAM PT 10.00 0.365 24 25 SI-SW-H20A LNGSEAM PT 10.00 0.365 26 27 SI-SW-H20B LNGSEAM PT 10.00 0.365 NO 26 29 SI-SW-H3A LNGSEAM PT 10.00 0.365 NO 30 31 SI-SW"H4A LNGSEAM PT 10.00 0.365 32 33 SI-SW-HSA LNGSEAM PT 10.00 0.365 NO 34 35 SI-SW-HGA LNGSEAM PT 1-3-06 40.00 0.365 NO 36 37 S I-SW"H7A LNGSEAM PT 10.00 0.365 NO 36 39 SI "SW-H8A LNGSEAM PT 10.00 0.365 40 41 SI-SW-H9A LNGSEAM PT 10.00 0.365 4. NO 42 43 RH"SW"L4A LNGSEAM PT 10.00 0.365 NO 44 45 RH-FW-71A LNGSEAM PT 10.00 0.365 46 47 SI-96-1-SW-1A LNGSEAM PT 10.00 0.344 46 49 SI-96-1-SW-1B LNGSEAM PT 10.00 0.344 50 51 SI-FW-459A LNGSEAM PT 10.00 0.365 NO 52 53 SI "SW-E3B LNGSEAM PT 10.00 0.365 NO 54 tt t ttt t tt tt t t tt t tt tt t ttt t t t t t t tt t t t t tt t t ttt tttt tt tt t t tt t' t ttttt ttt t tt tt t t t t t t tt t t t tt t It t *t t tt tr t tt t tttttt t tt t t tt t t tt 55 se 57 58 59 60 FORM 0113 (02I63)
402 tt t t t t tt t tt t t t t t t t t t t t t t t t tttt t ttt ttt tt t ttt t t t tt tt ttt t t t t t tt t t t t t t t t t t t t t t' t t t tt t t t ttt t tt t t t t tt rt t
- t ttttt ttt t t t t t t t NUTECH CAROLINA POWER Sr LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING t t et et et t et t t t et tet 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 401 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 lt THE SUMMER 1883 ADDENDA; INTERVAL 01 ONLY DATE 88/01/12 8 tt t t tt t t t tt t t t t tttt t ttt t t t ttt t tt t t t tt t tt tr t tttt t tt t *t tttt t t tt t tt tt tt
- t t
- t tttt t ttt t tt t tt t t tt t tt tt tt t t' t t t t ttt rt t t tt tt t 10 CATEGORY C"F PRESSURE RETAINING WELDS IN PIPING ll ITEM NO. C5.12 PIPING LONGITUDINAL WELD <a 1/2" NOMINAL WALL THICKNESS 12 13 t t t t tt t t tt t t t t t rt t t t t ttt t t t t t t t t t
- t t' t t t t tt tt t t t t t t t t t tt t t t tt t ttttt tt t t t t tt t t ttt t t t tttt t t tt t t t ttt t t t t t t tt t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sssaassssss s asses saasssssasssasa sass a = a s sass asses esses assessee assess sss saeses assess assess 20 21 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER : II-SI-009 22 23 SI-FW-281A LNGSEAM PT 1-2-03 10.00 0.365 NO 24 25 SI-FW-282A LNGSEAM PT 10.00 0.365 NO 26 27 SI-FW-283A LNGSEAM PT 10.00 0.365 28 29 SI-FW-447A LNGSEAM - PT 10.00 0.365 30 31 SI-FW-4478 LNGSEAM PT 10.00 0.365 32 33 SI-FW-448A LNGSEAM PT 10.00 0.365 34 35 SI-SW-86A LNGSEAM PT 10.00 0.365 NO 36 37 SI-SW-87A LNGSEAM PT 10.00 0.365 38 39 SI-SW-878 LNGSEAM PT 10.00 0.365 40 41 SI-SW"CBA LNGSEAM PT 10.00 0.365 NO 42 43 SI-SW-C88 LNGSEAM PT 10.00 0.365 NO 44 t 45 SI"SW-C9A LNGSEAM PT 1-2-03 10.00 0.365 NO 48 47 SI-SW-D13A LNGSEAM PT 10.00 0.368 NO 48 r 49 SI-SW" 0138 LNGSEAM PT 10.00 0.365 50 51 SI-SW-D3A LNGSEAM PT 10.00 0.365 52 53 SI-SW-04A LNGSEAM 10.00 0.365 NO 54 rt t t t tt t t t tt t t t t' ttt 't ttt t 't tt t It Il t t tt lt t lt t t PT rl' It tt t tttt t It tt t t t t t
- t t tt t tt 't t t t t tt 't t t t t 't t t t t t t t t t' It tt tt tt t t' ttt tt ttttt t t t t t t' t 55 56 57 58 59 60 FORM 0113 (02I83)
404 tt t tt t t t t t tt t ttt t ttt t t t t 't t t t t t tt tt ttt t t t tt tt t t t tt t t t tt *t *tt tf 4 4 t t tt t t t t tt t t t t tt t t tt t tt t 1 t f 4 t t tt t t t ttt 4 t t tt t t t t r4r 4r 4r 4' 4r 4r NUTECH CAROLINA POWER Er LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 4r t t tttt tt t t tt t tt t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 403 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA; INTERVAL'1 ONLY "DATE 88/01/12 8 t 't t t t t t t t tttttt t tt tt tt t tt t tt t t t t tt t t t t t tt t t t t tt t t t tt t t 4 t t t t t t tttt t t t t t t tt t tt t t t t t t tt tt tt t t 4 4 t tt t tttt tt t 4r 4r 4' 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. CS. 12 PIPING LONGITUDINAL WELD <$ 1/2" NOMINAL WALL THICKNESS 12 13 t t tt t t tt t t t t t t t ttt t t t t t tt tt t t tt t t tttt t t t tt t t tt ttt t ttt t tt t t t tt ttt t t t t t tt tt t t 4 t tt t tt 4
- 4 tt t t tttt t t t t t tt t t
't 4 4r 4' '4 4 4r 4' 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ ~ $ ~ $ $ $ $ $$ $ $$~$$$ $$$$ ~ $$$ $ $$$$$$$$ $ $ $ $ $ ~ $ $ $ ~ $ ~ $ ~ $ $ $ '$$ $ $ $ $ $ $ $
20 21 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-009 22 23 SI-94-2-SW-1B LNGSEAM PT 10.00 0.365 NO 24 25 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-021 28 27 SI-FW-555A LNGSEAM PT 1-1 "01 12.00 0.375 28 29 SI "SW-A4A LNGSEAM PT 12.00 0.375 30 31 SI-SW-ASA LNGSEAM PT 12.00 0.375 NO 32 33 SI-SW-A6A LNGSEAM PT 12.00 0.375 NO 34 35 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-022 36 37 SI-FW"566A LNGSEAM PT 12.00 0.375 NO 38 0.375 SI-SW-A9A PT t t t 12.00 39 LNGSEAM NO 40 t tt tt tt t t t t t ttt 1 tttttt t ttt t t t t t tttt t t tt t t tt t t t t t t 4r 4r 4r 4r 4r 4r 4r 4r 4r 4r 4r tr 4r 4r t tt 4 t t 4 t t t t t t t t t t tt tt t t t t t tt *tt t t 4 tt tt t t t t tt t 4r 4r 4r 4r 4r 4r 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 se 57 58 59 eo
- 0
412 f t 4 Al 4 4 Al 4 4 4 4 4 4 4 4 Al At 4 4 4 4 4 4 '4 4 4 4 4 AI 4 4 O'l Al 4 4 4 4 4 4 4 4 4 t 4' 444 Al 4 4 4 4 4 '4 4 At 4 4 4 AI 4 4 4 O'l 4 4 4 4 <<4 '4 4 4 '4 4 4 4 *4 4 At 4 4 4 4 4 4 4 4 4 4 4 '4 4 4 4 At 4 4 4 4 Al 4 4 4 4 4 4! 4 4 4 4 t 4 NUTECH CAROLINA POWER St LIGHT COMPANY PRI SIN 4 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT tt'tf ttf At PLANNING '4 4 44 4'st'4 tftt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 411 6 ASME SECTION XI, 1)83 EDITION THROUGH AND INCLUDING REVISION NRC1 47 THE SUMMER 1983 ADDENDA, -INTERVAL 03 ONLY 4 DATE 88/01/12 tfst 4t f 4 44 tftaft tf tt tftftt tt tf tf tt tttf tftt f tf tt tt 8 44 4444 4 4 4 4 4 44 4 4 4 4't4 4 t4 4 4 4 4 4t 44 4 4 4 4 4 4 4 4 4 4444 t 4 4 fat 4 4 4 4 4t 44 4 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.21 PIPING CIRCUMFERENTIAL WELD > 1/2" NOMINAL WALL THICKNESS tttttttfrtttArtAtttft4ttttttfAlt ttltft4tttt'44444 444tf At sf tf 4 4 Art f 4ttArftf t Art 4 4 4 fits Art ttttttttttttt ArttttttttAI44ttttArArtttttttftt 12 13 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 16 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssssasssassssassssaasssa assassssssssssa ararat asasssraaaaa ars stars stars rsaasass ararat sss tartar raasss 4 4 20 21 SYSTEM : FW FEED WATER ISOMETRIC NUMBER : II-FMR-03 22 23 FW-SW-L4 ELB LR -PIPE MT 16.00 0.668 NO 24 UT-45S 25 26 FW-SW-LS PIPE -ELB LR MT 16.00 0.668 27 UT-45S 26 29 FW-SW"L6 ELB LR -PIPE MT 16.00 0.668 NO 30 UT-45S 31 32 FW-FW-486 PIPE "ELB LR MT 16.00 0.668 NO 33 UT-45S 34 35 FW-SW-M6 ELB LR -PIPE MT 16.00 0.668 NO 36 UT-45S 37 36 FW"SW"M5 PIPE -ELB LR MT 16.00 0.668 NO 39 UT-455 40 41 FW-SW-M4 ELB LR -PIPE MT 'l6.00 0.668 YES 42 UT-45S 43 44 FW-SW-M3 PIPE -ELB LR MT 16.00 0.668 NO UT-45S 45 46 4 tat tttf4 f ttAt4tt'4 4 4 444 4 Arf4 4 tttArtfttf4 444 ttf4 4 4 4 444444 44 44 st f4 44 ttt*tfttt4 ttfttfttttsf 44444 t st tttttttf ttf 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02IS3i h
413 tt t tt t t t t t t tt tt tt t t t t t hatt t t t t t t t t t t t tt t 4 t t tt t t t t tt tt t tt t t t t tt t t t t 4 t t tt tt t t t t t tt hatt t ttt t t tt tt t t t t t t t t t t t NUTECH CAROLINA POWER Br,LIGHT COMPANY PRI 5IM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING t t t tttttt t tttttt t t t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 412 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 7 8 tt 't t t tttttt t t t t tt t t t t t tt tt t t t tt tt t t t tt t tt tt t tt tt t t t t t tt t t t t t t' t t t ttt tt t tt t t tt tt t' t t t tt t tt t t t *ttt t t t tt t DATE t' t tt t t tt t t tt t tt 9 10 CATEGORY C-F PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. C5.21 PIPING CIRCUMFERENTIAL WELD > 1/2$ NOMINAL WALL THICKNESS 12 13 t t t tttt t 't t t tttt tt t t t tt t t tt t t t tttt t t t t tt t t t tt t t t ttt tt t t t tt t t t t t t t t t t t t t t t t t t tt t' t t tt t tt t t t t lt t tt t tt t t tt t t t ttt t t ttt t t t tt 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ II$ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $$ $$ ' 20 21 SYSTEM : FW FEED WATER ISOMETRIC NUMBER: I-FMR-03 I 22 23 FW-FW-485 ELB LR -N021CI MT 16.00 0.668 NO 24 UT-45S 25 26 SYSTEM : FW - FEED WATER ISOMETRIC NUMBER: I I-FW-001 27 28 FW-FW-509 VALVE -PIPE MT 1-2-03 16.00 1.006 NO 29 UT-45S 1-2-03 30 31 FW-SW-A4 PIPE -SWPOLET MT 1-2"03 16.00 1.006 NO 32 UT-455 1-2-03 33 34 FW-FW-510 PIPE -FL HEAD MT 1-2-03 16.00 1.006 35 UT-455 1-2-03 38 37 FW-FW-501 VALVE -PIPE MT 1-2-03 16 . 00 1 . 006 NO 38 UT-45S 1-2-03 39 40 FW-SW-B4 PIPE -SWPOLET MT 1-2-03 16.00 :.006 NO 41 UT-455 1-2-03 42 43 FW-FW-502 PIPE -TYPEIIB MT 1-2-03 16.00 1.006 NO 44 UT-45S 1-2-03 45 48 FW-FW-505 VALVE -PIPE 1-2-03 16.00 1.006 47 tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttllrtttt'tt MT 48 49 50 51 52 53 54 55 56 57 58 59 80 FORM O'I13 102I83)
416 t ttt t t t tt t ttttt t t t tt t t tt t t tt t t t' t tt ttttt t t t tt tt t t t t tt t t t t ttt t t t t t t t tt t t tt t tt t t t t t ttt t t t t t t tt *t t t t t tttt t t t *t' tt t tt tt t NUTECH CAROLINA POWER & LIGHT COMPANY PRI SIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING st st t t st st tat st t st t 5 t COMPONENT. LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 415 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 *
'rr" 7 t THE'SUMMER 1983 ADDENDA,-INTERVAL 01 ONLY DATE 88/01/12 8 t t tt tt t t tt tt tt tt tt ttt tt t tt tt t tt tt t t t tt t t st t f st hatt tate'st st st st t*t at atty tat t t st t st st tat st tt t t tt tt tt t 9
10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.21 PIPING CIRCUMFERENTIAL WELD > 1/2s NOMINAL WALL THICKNESS ' 12 13 t tttt t tt tt t 't t t tt rt t t' t t t ttt tt tt t t 't tt t t *t *t t't t tt t t t t t t t t t tt t tt t t ttttt t t t tt t tt t t t tt t t t t t tt t tt tt t t tt t tt ttt t 't tt tt t t t t
'lr 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE, DULED INT INT (IN) ( IN) ACCESS SELECT IND REQST TIONS NOTES 19 asssssassssssassasssssss sasassassasasss ssssas ssassassssssaass assss assaa asssssaa ssssaa ass aaaaaa == a sass s 20 21 SYSTEM : MS MAIN STEAM ISOMETRIC NUMBER : II-FMR-01 22 23 MS-SW"E3 ELB LR -PIPE MT 32.00 0.953 NO 24 UT-455 25 28 MS-FW-229 PIPE -FL HEAD MT 32.00 0.953 27 UT-45S R2-001 28 29 MS-M3-PW-1 PP,FHS-INTERNAL SUR 32.00 0.953 IA NO R2-004 30 VOL R2-004 31 32 SYSTEM: MS MAIN STEAM ISOMETRIC NUMBER: I I-FMR-02 33 34 MS-FW-294 NOZ1BO -ELB LR MT 1-3-06 32.00 0.953 NO 35 UT-455 1-3-06 35 37 MS-SW"A3 ELB LR -PIPE MT 32.00 0.953 38 UT-455 39 40 MS-SW-A4 PIPE -ELB LR MT 32.00 0.953 NO 41 UT-455 42 43 MS-FW-295 ELB LR -PIPE MT 32.00 0.953 NO 44 UT-45S 45 4e MS-SW-B3 -PIPE 32.00 0.953 47 PIPE tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt MT NO 48 49 50 51 52 53 54 55 ee 57 58 59 50 FOAM 0113 (02/83) 7 0
417 staffed
*ftaft ttff t taft tttfttttttttf sf tt*tt*ftttttttttttttttff tttttttttt sf tfsf st*tat ttttttttttttfaft ttttttttf' NUTECH CAROLINA POWER 8! LIGHT COMPANY PR IS IM 3 SHEARON HARRIS NUCLEAR POWER PLANT UNIT 4 t PLANNING t t ft t t t t t t t f ft t f t!!I!
)I!
5 t COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 416 6 t ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 88/01/12 7 8 ftttttttttttttfatttf ttf fttttttttftttttf ttttfttttftttttffttttttfttfftttttfttftttfttttttf taft sf f taft sf DATE THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tttttttf ttttttttt 9 10 CATEGORY C-F PRESSURE RETAINING WELOS IN PIPING 11 ITEM NO. C5.21 PIPING CIRCUMFERENTIAL WELD > 1/2" NOMINAL WALL THICKNESS 12 13 t t!I!t !I!!I!!I!!I!t t!I!!I!t t ftt t t t t ttf t t!I!f t! ft t I' t tft tt f ft ffft tt tfff t t tt ft t t tt t t t 'f t t ft t t ftftt t t t! tt t tf ff ftff f f f tt f t f t t t!I!f tt t
- t tt ft tt
!I!
14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULEO INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 aaaa sass asaaa aa aaa a araa a a asaaaa 20 21 SYSTEM: MS MAIN STEAM ISOMETRIC NUMBER : II-FMR-02 22 23 MS-SW-83 PIPE -PIPE UT-45S 32.00 0.953 24 25 MS-SW-86 PIPE -PIPE MT 32.00 0.953 NO 28 UT-45S 27 28 MS-FW-296 PIPE -ELB LR MT 32.00 0.953 29 UT-45S 30 31 MS-SW-C3 ELB LR -PIPE MT 32.00 0.953 32 UT-45S 33 34 MS-FW-297 PIPE -FL HEAD MT 32.00 0.953 35 UT-455 36 37 MS-M2-PW-1 PP,FHS-INTERNAL SUR 32.00 0.953 IA NO R2-004 38 VOL R2-004 39 40 SYSTEM: MS MAIN STEAM ISOMETRIC NUMBER: I I-FMR "03 41 42 MS-FW-288 NOZ1CO -ELB LR MT 32.00 0.953 NO 43 UT-45S 44 45 MS-SW-A3 ELB LR -PIPE MT 32.00 0.953 NO UT-45S 46 47 tt tf tt ttttttf ttttttt tt f tat t at tt t ttfttffttfst t t st f tffttftffst ft aft sf f ftttt tt t tt t tat tt tttttt'fsttf fftt t t tt ttfft'ftaft t t st 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0'113 <02I83)
t 1 1 1 1 1 1 1 1 1 1 '1 1 1 1 '1 1 1 1 1 1 1 1 1 1 t '1 '1 111 t1 '1 1 1 1111 t1 1 t1 1 1 1 1 1 1 1 1 t1 1 1 1 1 1 1 1 1 t1 1 1 1 t1 1 1 1 t 1 1 t1 1 1 t1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 t 1 1 tt1 1 1 t1 1 1 1 1 1 1 t1 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING tttttttttt 5 COMPONENT. LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 419 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 '8 11 t1 1 1 1 1 1 tt1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1' 11 t 1 1 1 1 I 1 1 t 1 1 1 1 1 1 1 1 1 1 1 t 1 1 t 1 t 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 t 1 1 1 DATE 11t11 11111111111 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.21 PIPING CIRCUMFERENTIAL WELD > 1/2 NOMINAL WALL THICKNESS 12 13 t t tt tt 11 1 1 1 1 1 1 11 1 1*1 t 1 1 1 1 1 11 1*1 t1 1 1 t1 t 1 1 11 1 tttt 1 t 1 t 1 1 1 1 t 1 t 1 t 1 1 1 1 1 1 1 11 t 1 t 1 1 1 1 ttt tt 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 tt 1 t 1 1 1 tt 1 1 t 1 1 1 1 1 1 11 1 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 44444444 ~ 44444444 ~ 4444 ~ 4 ~ 4$ $ 4 ~ 4 ~ 444 ~ 4 ~ $ 444 ~ ' '
$ $ 4 ~ 444$ 4$ $ $ $ 4$ ~ $ $ ~ '$4 444 ~ 4 4 ~ $ 44444 $ $ $ $ ~ 4 ~ 44 ~ 444 ~ 4 ~ 4 ~ 4 ~ 4 4 ~ $ $ $ ~
20 21 SYSTEM : MS MAIN STEAM ISOMETRIC NUMBER: I I -MS-001 22 23 MS-SW-A12 PIPE -NOZ WLD UT-45S 1-1-01 34.00 2.000 NO 24 25 MS-SW-A13 PIPE -NOZ WLD MT 1-1-01 34.00 2.000 NO 28 UT-455 1-1-01 27 28 MS-SW-A 14 PIPE -NOZ WLD MT 1-1-01 34.00 2.000 29 UT-455 1-1-01 30 31 MS-SW-A15 PIPE -NOZ WLD MT 1-1-01 34.00 2.000 32 UT-455 1-1-01 33 34 MS-SW-A34 PIPE "PIPE MT 1-1-01 34.00 2.000 35 UT-455 1-1-01 38 37 MS-SW-A3 PIPE -PIPE MT 1-1-01 34.00 2.000 NO 38 UT-45S 1-1-01 39 40 MS-FW-283 PIPE -VALVE MT 1-1-01 34.00 2.000 NO 41 UT-455 1-1-01 42 43 MS-SW-A4 EXTRUD -PIPE MT . 1" 1-01 12.00 0.562 44 UT-45S 1-1-01 45 48 MS-SW-A5 PIPE -CAP MT 1-1 "01 12.00 0.562 NO t t t t t 47 1 1 1 1* 1 1 1 1 1 1 1' 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t tt t t 11111 11111 11111 11 11 11 11111 t t t t t 1 1 1 1 1 1 1 1 1 t t 1 1 1 1 1 1 1 tt 1 1 1 1 1 *1 1 t 1 t 1 1 t 1 1 1 1 1 48 49 50 51 52 53 54 Ss se 57 58 59 80
428 1 t t st t ttt t t t t tt t t t tt t st t t st st t st t st tt t ttt t tt t st t t t st t t tt tttt t t t tt t ttt t t t t t ttt t t t t tt t t t st st t tt st 4 t t tt t t t t t st tt tt t t tt t tt 2 NUTECH CAROLINA POWER Sr LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4 PLANNING 1 ttttttttttttttttttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 427 5 ASME SECTION,,XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t DATE 88/01/12 7 8 *ttttttttttt*tttttttttttttttttttttttt*ttttttttt*ttttttttttttttttttttttttttttttttttttttt THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ll ITEM NO. C5.21 PIPING CIRCUMFERENTIAL WELD > 1/2'OMINAL WALL THICKNESS 12 13 t t t tt t tt t tt t t ttt t t t t ttt tt t t t t t ttt t t t t t t t t t t t tt tt tt ttttt t *t t tt t t tt t t t tt t t t t tt t t t t tt t t tt t t ttttt t t' t tt t tt t t t t 't t t 14 15 DONE 15 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ~ sssssssasssssssssssssss ssssssasasssasa sassss ssssssssssssssss sssas sasss ssssssss assss4 sss aaasss ssssss ssssas 20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-024 22 23 SI-FW-571 P BEND -ELB LR PT 06.00 0.719 NO 24 UT-455 25 28 SI "SW-D5 ELB LR -PIPE PT 06.00 0.719 NO 27 UT-45S 28 29 SI-SW-D4 PIPE -ELB LR PT 06.00 0.719 NO 30 UT-45S 31 32 SI"SW-D3 ELB LR -P BEND PT 06.00 0.719 NO 33 UT-455 34 35 5 I "213-FW" 573 P BEND -VALVE PT 1-1-01 06.00 0.719 NO 38 UT-45S 1-1-01 R2-003 37 38 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-025 39 40 SI-M13-PW-1 PP FHS-INTERNAL SUR 10.00 1.000 IA NO R2-004 41 VOL R2-004 42 43 S I- F W-576 FL HEAD-PIPE PT 10.00 1.000 44 UT-60S i R2-003 45 45 SI-FW-575 -VALVE 10.00 1.000 t t t t tttttt t t t t t tt t t t PIPE ttt t t t ttt tttt tt t PT NO 47 tt t t tt t t t
- t tt t tt tt tttt t tttt t t tr tt t tt t tt t tt t t tttt t t t tt t t ttt t t t ttttt t t t t t t tt t t t 48 49 50 51 52 53 54 55 58 57 58 59 80
~,
429 1 t f t t tt t t tt t t t f t t t' t t t tttt t t ftt tt t t t t tt ft t t t ft tftt tt tt tft t t t t t t ttt tf f t ft t ft t tttt t ttt t t ft t t t t' t f t t t t t t 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 PLANNING 1 tttftaft t f tff atttt't 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 428 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
. 7 8 tt t tt t staff ft at at f tiffs t t tttt t t THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tsf t t tf t st tt t t t tt t at t tf st at st tf ttt sf tt tat t 4 tat tat t ttt t tt at st t st DATE 88/01/12 t st aft't t tat t tt t tt t't t t 9
10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. CS.21 PIPING CIRCUMFERENTIAL WELD > 1/2" NOMINAL WALL THICKNESS 12 13 t t at t tt t t f at t tat tf at at t at taft t taft sf tt tt t at f t tt t t tt at t t tt t t t t t ft t tt t tt t t t t tt t t t at f t at tat st at sf t at tf t t't at at t t' f at tat st 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 ssssssssssssasssssssssss asssssassasssss asssss ssssssssssasssss fasts stats sssssssa sssass sas sssass sasssa sssass 20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: II-SI"025 ttttttat 22 23 SI-FW-575 PIPE -VALVE UT-60S 10.00 1.000 NO R2-003 24 25 SI-FW-574 VALVE -PIPE PT 10.00 1.000 26 UT-60S R2-003 27 28 SI-SW-B5 PIPE -RED TEE PT 10.00 1.000 NO 29 UT-60S R2-003tat 30 31 SI-SW-B4 RED TEE-PIPE PT 10.00 1.000 NO 32 UT-605 R2-003 33 34 SI-SW-B3 PIPE -FLG RFW PT 10.00 1.000 35 UT-60S R2-003 38 37 SI-SW"A6 FLG RWR-PIPE PT 06.00 0.719 NO 38 UT"455 R2-003 39 40 SI-215-F W-573 ELB LR -P BEND PT 06.00 0.719 41 UT-455 jp 42 43 SI"SW-AS PIPE -ELB LR PT 06.00 0.719 NO 44 UT-45S 45 SI-SW-A4 ELB LR -PIPE 00 0. 7 19 f attf tttttftttttftttttttttttttttttf tat06. t taft f t*tt*ttat tttttttttttttttttttt ttttt 46 PT NO 47 f f taft ttttttftfsf ttf at taft 48 49 50 51 52 53 54 55 58 57 58 59 60 FOAM 0113 (02I83)
"teR 4y'q p~ ', v.wc w'4hy ty ~ . +
\ yt gyr ' ~ y -, <<4 . },,h c 'y' Apy '}v. y~.,a' ~ @ay'~" 4ysg I".-vfi )f. imp 'y-'
~ ~ f aha<<,a-:'% ~
437 1 tff fff tftaft'tt'at frtff tfttff tfat ttt tft'f ttt tttfat ttttttf f tttttttttftftttttttttfttttft ttttfttfttfttttftttftft tttttttttft, 2 NUTECH CAROLINA POWER SI LIGHT COMPANY PR IS IM 3 f SHEARON HARRIS NUCLEAR POWER PLANT - UNIT- 1 4 PLANNING fIft*ff 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 436 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY SS/01/12 f ftftftf't tf'at tftt t tftat tff f t sf t tt f f tat ft tftf tat t ttt f t tt tff atty f tt t tat tet f tftet tat t t at f at t et ff sf at at tfDATE t t *et t tf tt t t t tan 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.21 PIPING CIRCUMFERENTIAL WELD > 1/2" NOMINAL WALL THICKNESS 12 13 f f 'tf tttftaft f tft ff f t tt t f at at t*ff *tat at tf f tf*ft*ttt tt tfffffff at fr f t t*tt t tff tf t tt t tt fft tat ft 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssassasssassssasssssssss ssssssssassssss erases srsaasassaeesae seers ress sesasasa erases saa ssasrr eraser erases 20 21 SYSTEM: SI SAFETY INLJECTION ISOMETRIC NUMBER: I I-SI-028 22 23 SI-SW"A9 PIPE -REDUCER PT 10.00 1.000 NO 24 UT-605 R2-003 25 26 SI-SW-A6 TEE -PIPE PT 10.00 1.000 NO 27 UT-60S R 2-003 28 29 SI-SW-Aj PIPE -REDUCER PT 10.00 1.000 NO 30 UT-60S R2-003 31 32 SI-FW-608 REDUCER-PIPE PT 10.00 1.000 NO 33 UT-60S R2-003 34 35 SI-SW-86 P BEND "P BEND PT. "=06.00 0.719 NO 38 UT-60S 37 38 SI-SW-B3 P BEND -P BEND PT 06.00 0.719 39 UT-45S 40 k. 41 SI-FW-610 P BEND -VALVE PT '<<1 "3-06 06.00 0.719 NO UT-45S 1-3-06 R2-003 42 43 fff f f f f f f t'f ff f 'tf tffftf'tf f tff ttttff tat f*tfff*af t f tff f f t'f ff tat f ffff f tftff tfat f f ttftff tff t tff tat tat f tat'f f t f tfsf tftfttt t t 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
440 1 ff t tQf f t ft f f fr t tff f t f t t I fr f t t ft f t t f t t t tffr f t t f f et fr t f tat et t tft tft frt f f t t fr f at tf "<< f t ttt et t t t tt t et et f t t f t fr 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4 PLANNING 1 tfttfff at frttffr tet 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 439 ASME SECTION,XI, 1983 EDITION THROUGH AND .INCLUDING REVISION NRC1 f t*t*ttttftftttttttttttttttetttff ttttttttaft ttttttttfttfttftfttttttftfat'atttttf tttttttttftet frtttftf88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 8 tet f fr tfttt 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.22 PIPING LONGITUDINAL WELD > 1/2'OMINAL WALL THICKNESS 12 13 f ttftffrf ff ff tfff f tttffr tftfttftet tfttftaft fttt*tttttttaft tttttftftftttttfttttttttttttet tftftet f ttf tffff tftfttttt ttt 1 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssaassssssasasssssssa asasassssssaasa assess ssrsaesssassssar arras sears seafarer sssres sss sasrss assess assess 20 21 SYSTEM : MS MAIN STEAM ISOMETRIC NUMBER : II-FMR-02 22 23 MS-FW-294A ELBSEAM MT 1-3-06 32.00 0.953 NO 24 UT-455 1-3-06 25 26 MS-FW-2948 ELBSEAM MT 1-3-06 32.00 0.953 27, UT-45S 1"3-06 28 29 MS-FW-295A ELBSEAM MT 32.00 O.S53 NO 30 UT-455 31 32 MS-FW-2958 ELBSEAM MT 32.00 0.953 33 UT"455 34 35 MS-FW-2S6A ELBSEAM MT 32.00 0.953 NO 36 UT-45S 37 38 MS-FW-2968 ELBSEAM MT 32.00 0.953 39 UT-45S 40 41 MS-SW.-A3A ELBSEAM MT 32.00 0.953 42 UT-455 43 44 MS-SW-A38 ELBSEAM MT 32.00 0.953 NO UT-455 45 46 f tfttttftttttff f ftftfetttttf f tttftft tatters f*~ *atfttttttftftttftff tttttttttftttttftttttttttttt*ftftfet fr taft tt tet
'tf 47 48 49 50 51 52 53 54 55 58 57 58 59 60 FORM 0113 (02I83)
tat tttfttttttttttftff ttttttttftt f sf ttftff tf tfttttttftfstf ff f f tftf tttff ttftt taft t ttfff st tf tff tf tttfttttf 444 1 2 NUTECH CAROLINA POWER 8 LIGHT COMIPANY PRISIM f f SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4 PLANNING f tf tttttttttff'f'f COMPONENT -LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 443 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 4'j7 THE SU4MER 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 8 f t t t f f tttff t tftat t at t t t fft t ft ftt tt ttt tt ftft t't t at tt f ftffff f tt tfsf f t tf t t sf t tat sf fthm tt t t at at f t t tfsf'taft t tt t 9 10 CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING 11 ITEM NO. C5.22 PIPING LONGITUDINAL WELD > 1/2a NOMINAL WALL THICKNESS 12 13 t t tat at t t tfat t taft tat t t sf t t t tt t f tt t t at tf f st f fft f at tt t tftft f at t f tt tf tf f t ft t ffft t t t t t tt t tt t f sf sf t f t sf f *f*ff t tft f tr 14 15 DONE 15 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 saasssssassassssaassasss sassassasssssas sssaaa ssaasasasassssss ssass ss sa asssasss ssasss sss saasas ssssas ssssss 20 21 SYSTEM : MS MAIN STEAM ISOMETRIC NUMBER : II-MS-001 22 23 MS-SW-B3A LNGSEAM MT 1-2-03 34 . 00 2 . 000 NO 24 UT-455 1-2-03 25 25 MS-SW-C3A LNGSEAM MT 1-3-06 34.00 2.000 NO 27 UT-455 1-3-06 28 29 MS-FW-286A LNGSEAM MT 1-2-03 34.00 2.000 NO UT-455 1-2-03 f ff sf ff sf ft at sf t taft at tt t sf f sf t sf t t at f t t t t tt sf tat at t t tt t at ft f f ttt tf st f f 30 31 ~ t at t sf sf taft at at t tttt tf t fr at at sf t tat f atf t st 32 33 34 35 35 37 38 39 40 41 42 43 44 45 45 47 48 49 50 51 52 53 54 55 55 57 58 59 t 50
450 1 tttf tttftftat tfffftttttftff ttttftttffft taft tttf ttfttttttttttttttttttat tf tttft ttet at fttttttttt$ f tttt tftftftfttftf tttt 4 2 tl NUTECH =CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t 3 4 t PLANNING taft tat tat ttttttfat 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 449 6 ASME SECTION 'XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMPTER. 1983 ADDENDA, INTERVAL 01 ONLY DATE 88/01/12 8 f tt at at sf ff at at sf f ft f t t f at t t*tft t ift tat at f taft at at f sf t t tfttt f t f t tt t t t et tf t f tan f at f'aft f tft f aft taft f ft t ff tat t f t at at f tat 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.10 PRESSURE VESSEL PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 f tt'tttttttttttfatttf f tf ttt*ttttt at atttttttt ttt taft tf et'f tftttttttttttftttftt*tttttatttfat tat't tat f tt tt 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 asssssssssssssssssasssss ssssssssseaeasa assess easseaaassssssas asses asses sssassss assess aas seeass assess assess 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-SG-001 22 23 STEAM GEN A2 SGA VT-20T 1-1-01 24 VT-20T 1-3-06 25 VT-20T 1-2-03 28 27 STEAM GEN B2 SGB VT-20T 1-2-03 NO 28 VT-20T 1-1-01 29 VT-20T 1-3-06 30 31 STEAM GEN C2 SGC VT-20T 1-1-01 32 VT-20T 1-3-06 VT-20T 1-2-03 33 34 f t ttf t ft tf ft tt tt t tt ft tI ttt t tt tt t t t t tt f t t t tt t ttt t t ttt t t fftt t ttft t t t t ftt f t ft ft tff t t t t tt t t tt t t t t ft t f tf t tt t tt f ft f 't tt t 't tft 35 36 37 38 39 40 41 42 43 44 45 48 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
/ ;0
iC 451 et t tt tt tt t t t tet t tt t t tt t ttstetted st t t tt tat st t t st t t tet t tttt t tt tt t t at tt t tt tt t t t t t t t tt t t t tt tat st t t t t t t t t t t t t t t tat t t' t t f st 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 t 4 PLANNING st st st st st st tat t t t t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 450 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 DATE 88/01/12 7 8 sttttt'ttttttt'ttttttttt'tttttttttttttttttttttttttttttttttttttttttttttet ttttttttttttttttttttttet tttttttttt*ttttt THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tat'tttt't 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.20 PRESSURE VESSEL PRESSURE RETAINING COMPONENTS " STATIC
'O 12 13 t t ttttt t t t tt ttt t tt t t t t t t t t t t t t t t t ttt t t tt t t tt t t t t t t t t t tt t t t tt t t tt tt tt tt t t t tt tt t t tt t t t t t tttt t t t t tt 't
- t
- t t 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE" OUT PRIOR PRES TEMP TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES
'19 sasssssassassassaessaasa ssaaasassssassa assess ass a s seas asses ssssssaa assess sas assess assess assess 20 21 SYSTEM ISOMETRIC NUMBER: II-BIT-01 22 23 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 24 25 SYSTEM ISOMETRIC NUMBER: I I-EL-001 28 27 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 28 29 SYSTEM ISOMETRIC NUMBER: II-RHR-01 30 31 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 32 33 SYSTEM ISOMETRIC NUMBER: I I-RHX-01 34 35 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 38 37 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-SG-001 38 39 STEAM GEN A2 SGA VT-2ST "3-06 NO 40 41 STEAM GEN 82 SGB VT-2ST '1-3-06 NO 42 43 STEAM GEN C2 SGC VT-2ST 1-3-06 NO 44 st t t t t t t t tt t at t st t t t tt t t t t t t tst et at tat tat t st t t at at st at attestant st st tat et st tat t st st tet t t st t st st st st t t st t tt t t*t*tt tt t st t ~ 45 48 47 48 49 50 51 52 53 54 55 58 57 58 59 80 FORM 0113 (02I83)
f ff ft f f t f f t t f tft tf ft tftfft tfftt ft ft f f f f t tf f tt t t t t f tf f fft f t t t tf t fthm f t'ftfft t fff tftfff fft t ffft f f 453 1 2 NUTECH CAROLINA POWER 5r LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT f tff f ttfff ff fffffff 3 1 4 PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 452
- 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 88/01/12 7
8 f f tftff ff f ff fffff ffft ff fff tff ff tft ff f t f f f tft f f fffff t ffff t ff f t t ft f tft tf f f f tff t tftff fff fftDATE t tf f tff t f fff *f fr 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
'11 ITEM NO. C7.30 PIPING PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 f frfff f f t ff fff tff t f ttft tt tt tt t f f tfft tf f tff f tt tt t tt tff ttt tttt ftt f tfff t t tt t ff t t ftf t tff tt ttt et t f f f t t f tt f tt ff ft tt ft tf t tff f 14 15 DONE 15 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 $ ~ '$$ $ $ $ $ $ $ ~ $ '$$ $ ~ $ $ ~ $ $ $ $
ggggggggggggggg $$$ g $ ~$$ $$ g $ $$ $ $ $$$ ggggg $ '$$ $ $ $ $ $ $ $ $ $ +, 20 21 SYSTEM ISOMETRIC NUMBER: I I-AF-009 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 NO 24 VT-20T 1-3-06 25 VT-20T 1-2-03 26 27 SYSTEM ISOMETRIC NUMBER: I I-AF-010 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 NO 30 VT-20T 1-3-06 31 VT-20T 1-2-03 32 33 SYSTEM ISOMETRIC NUMBER: I I-BD-001 34 35 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 NO 36 VT-20T 1-3-06 37 VT-20T 1-2-03 38 39 SYSTEM ISOMETRIC NUMBER : II-BD"002 40 41 PRESSURE TEST PRESSURE TEST VT-20T r.'1-1-01 NO 42 VT-20T 1-3-06 VT-20T 1-2-03 43 44 *tt fftt f f ff ff f t f t t tf f f f f tf f f f t*tt*f*tft t f t f tff t f if *fff t*fff tft f *tt t ft f ff tffff ft t tf t'ft t fft f ffft fft t f 45 45 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
460 1 11 11 1 1 tf1 1111 t1 1 1 tf1 1 tftf t 11 1 1 1 t 1 1 1 1 f1 1 11 11 1 tf1 1 1 1 1 t 1 tt 1 1 1 1 1 1 1 tf t 11 1 1 1 11 tt tt 1 11 1 1 1 1 11 1 1 1 1 1 1 1 1 1 tt 1 1 1 1 1 1 t 1 t 1 f 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM f - UNIT 3 4 SHEARON HARRIS NUCLEAR POWER PLANT PLANNING 1 ffttfttt 5 COMPONENT. LISTING ANO ISI 10 YEAR PLAN: 835-01 PAGE 459 8 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1
<<7 THE SUMMER 1983 ADDENDA; %INTERVAL 01 ONLY DATE 88/01/12 8 1 1 11 1 *f111 t tt t 11 11 1 1 11 1 1 11 1 1 *1 1 1 1 1 11 11 11 1 1 1 1 1 1 1 1 1 t1 1 1 1 1 1 t1 1 f1 1 1'1 1 1 11 1 1 tftf t f11 1 1 1 1 at 1 1 1'1 11 1 1 11111 111 1 1 1 1 1 1 t*t1 1
- 1 1 1 11 9
10 CATEGORY C-H ALL PRESSURE, RETAINING COMPONENTS 11 ITEM NO. C7.30 PIPING PRESSURE RETAINING COMPONENTS " OPERATIONAL 1 1 1 1 sf 1 1 1 t 1 1 1 1 11 1 1 f1 1 1 1 1 1 1 tf11 tt 1 1't 1 f tt t 1 1 1 1 t 1 1 1 l t 1 1 1 1*1 1 f 1 1 11 1 tt 1 t 1 1 1 1 f 1 1 f 1 11'1 1 1 1 1 1 1 t 12 13 111 t1 1 t 11111111 11 1111111111111 14 15 DONE 18 OUTAGE THIS DONE . TEST TEST BASIS PSI SCHE- OUT PRIOR PRES TO TRV RELIEF EXEMP- PROGRM
's 17 COMPONENT COMPONENT EXAM TEMP 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 sss sssrss s 1 s s ---- ------ 1 as asssass 1 a as sass aassas ssa saaass asssas 1 20 21 SYSTEM ISOMETRIC NUMBER: I I-CT-007 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-2-03 NO 24 VT-20T 1-1-01 25 VT-20T 1-3-06 28 27 SYSTEM ISOMETRIC NUMBER: I I-CT-OOB 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 30 VT-20T 1-3-06 31 VT-20T 1-2-03 32 33 SYSTEM ISOMETRIC NUMBER: II-CT-014 34 35 PRESSURE TEST PRESSURE TEST VT-20T 1-2-03 NO 38 VT-20T 1-1-01 37 VT-20T 1-3-06 38 39 SYSTEM ISOMETRIC NUMBER: I I-CT-016 40 41 PRESSURE TEST PRESSURE TEST VT-20T 1-3"06 NO 42 VT-20T 1-2-03 VT-20T 1-1-01 43 44 1 111 tttttfaft ttf sf 1 11 111 tf11 tf1111 tttf1fttf11111 f1tftt taft f 1 ttttf11 tf1 tt1 ttttf1 tttttttf1st 111 ttf111111111ttttf tt 1
45 48 47 48 49 50 51 52 53 54 55 58 57 58 59 80 FORM 0113 (02I83)
461 1 tttt t t t t t t ttt t tt t tt t t t tt tt *t tt tttt t t t t t tt t t ttt tt t t t t t t t t tt t t t tt t tt tt t' t t t t t ttt tt t tt t t t t tt t tt t tt tt tt t ttt t t tt t ttt tr tr
.2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING t t tt t t t t tt t tt t 't t t t 5 t COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 460 6 t ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7
8 ttttt'ttttttttttttttt tttttt tttt ttttt ttttttt tttttt ttttttt t ttttt ttt tttttttttttt ttt'tttt ttt t tt ttttttttt tt t ttDATE THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY tttt88/01/12 4 tt t tt*ttt 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.30 PIPING PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 It tt It ttt t t t It t ttt t tt t t tt tt t t tt t t t t t t t t t ttt t tt tt t t t t t t f 't t t tt tt t tt t t t ttt tt t t t t 't t t t t t t t tt tt tt t t tt tt t t tt t t t t tt tt t t t tt t tt t t t 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM DESCRIPTION DULED INT INT PSIG (F ) SELECT IND REOST TIONS NOTES 18 19 ttttttStttt NUMBER
~$$$ ttttSttt4 tSISSRSSSSRRSSS TYPE SRSSSI R'StttRSSttSSRSRR IS ttttttt ttttt ACCESS
~ %$ ~ t ~ tttt t tt t tttt
~
A 20 21 SYSTEM ISOMETRIC NUMBER: II-FMR-01 22 23 PRESSURE-TEST PRESSURE .TEST VT-20T 1-1-01 24 VT-20T 1-3-06 25 VT-20T 1-2-03 26 27 SYSTEM ISOMETRIC NUMBER : II"FMR-02 28 29 PRESSURE-TEST PRESSURE TEST VT-20T 1-1-01 30 VT-20T 1-2-03 31 VT-20T 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER : II-FMR-03 34 35 PRESSURE-TEST PRESSURE TEST VT-20T 1-1-01 38 VT-20T 1-2-03 37 VT-20T 1-3-06 38 39 SYSTEM ISOMETRIC NUMBER: I I-FW-001 40 41 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 NO 42 VT-20T 1-2-03 43 VT-20T 1" 1-01 44 t ttt t tttt 't t t t 't tt t tt t tt ttt t tt t ttt t t t t t tttt t tt t t tr t tt t ttt t t t t t t tt t t t t t t tt t tt t tt t t t t t t tt t t t t tt t t t t t t t t t t t t t t t t t t t t t t tt t tt 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 4 60 FORM 0113 {02I83)
466 t t t t t t t t t t t t tt tt t t t t t tt t t t t tt t t t t t t t t t t t t t tt t t t t t t t t t t t t tt t t t t t t ttt t t t tt t t t tt t t t t tt t t t ttt tt s t tt t ttt t t t tt t t t t t t ttt t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4 PLANNING 1 ttt t' tt t t t t t t t tt tt t COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 465 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1
.7 THE SUMMER 1883 AD6EADA1 INTERVAL 01 ONLY DATE 88/01/12 8 ttt t t t tttttttttt t tttttttt t t tt 't t t t t t t tt t tt t tt t t t tttt tt tt t ttt tt t t t t t tt ttt t t tt t ttt tt t ttt ttt t ttt tt tt tt tt t tt 't tt t 't t t t t t t 't t t 9
10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.30 PIPING PRESSURE RETAINING COMPONENTS - OPERATIONAL tt t t t tttt t t ttt tt tt t t t t t t tt t tt t tt t t' t t t t t t t tt t t t tt t t t' t tt t tt t ttt t t t t tt t t t t tt tt t t t tt t t t t t t ttt t t t t t t t t t *tt tt t tt tt t tt tttt 12 13 14 15 DONE 1e OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 assssssssssasaas sssasss ssssssssaasasaa assssa asassaaassa sass stats sasaa sa aasaa ssssss sss sass s sssirs ssssss 20 21 SYSTEM ISOMETRIC NUMBER: I I-SI "010 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 NO 24 VT-20T 1-1-01 25 VT-20T 1-2-03 25 27 SYSTEM ISOMETRIC NUMBER: I I-SI-011 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 NO 30 VT-20T 1-2-03 31 VT-20T 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER : II-SI-016 34 35 PRESSURE-TEST PRESSURE TEST VT-20T 1-3"06 38 VT-20T 1-2-03 37 VT-20T 1-1-01 38 39 SYSTEM ISOMETRIC NUMBER: I I-SI-017 40 41 PRESSURE-TEST PRESSURE TEST VT-20T 1-2-03 42 VT-20T 1-3-06 VT-20T 1-1-01 43 44 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt* ttttttttttttttttttttttttttttttttttttttttttttttttttttt
~ ~
45 45 47 48 49 50 51 52 53 54 55 se 57 58 59 50
470 1 1111 tt 11 111 1 ttft 1 tf1 11 1 tt t t 1 1f 11 1 t 1 f 11 1 1 tt 1 1 t 1 1 11 11 11 1 fttt 11 11 1 1 tf 1 t 11 1 1 1 1 1 1 1 11 1 1 1 1 1 1 et 1 tttf1 1 t tf111 1 1 1 1 1 1 1 tP 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3 4 PLANNING 1 1 f1ttfkf 1 tf1 ttttf1 1 5 COMPONENT, LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 469 6 ASME SECTION XI, 1983 EDITION-THROUGH AND INCLUDING REVISION NRC1
~17 88/01/12 1 8 f1f tttt1ttff1ttttttfttttf tttttttf tf1tttttttftttfttf1 11 tttttttttfDATE THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 1 1 11 ttftttf ttttf1111 9
10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.30 PIPING PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 1 f1tttttttftttf1 ttttff 11 tt*t*ff1ttf11 tttf1 f tttttf1tttftf1ttttttt f1 tttttttttttttttttf1f1ttttf11 f1ttff tttfttt tf 1 1 1 1t tet 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 rsssssssssssaasrrssrssss ssssassssrsssss assess sssassssesrsssss erase esses assessee assess sss arrear assess ersrss 20 21 SYSTEM ISOMETRIC NUMBER : II-SI-030 22 23 PRESSURE-TEST PRESSURE TEST VT-20T 1-1-01 24 VT;. 20T 1-2-03 25 VT-20T 1-3-06 28 27 SYSTEM ISOMETRIC NUMBER: I I-SI-031 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1"2-03 NO 30 VT-20T 1-1-01 31 VT-20T 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER: II-SI-032 34 35 PRESSURE-TEST PRESSURE TEST VT-20T 1-2-03 3S VT-20T 1-1-01 VT-20T 1-3-06 37 1111 tftttf1 1 111*11111 1111111 1tf tttt11 ~ 1*111 ttttf1ttttff1 tttttttt 1*tf1 1*1 f1 f 1 f1 1ttttttttttttttttftft1111tttf 1
~
39 40 41 42 43 44 45 4e 47 48 49 50 51 52 53 54 55 se 57 58 59 60
477 1 44 tltlttttff 44444*44444 444 ates*4444444'ttttf 4444*f 444I44444444tttf 44444 4 4 ttfet tf*tf4 4444*4 4444 4 44444ttt444ttttf t444 4 4 4'4 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 PLANNING 1 444 44 4 tet tf4444 4 t4 4 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 . PAGE 476 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 ttf44 44444tf88/01/12 EE 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 8 4 4*4'4*44 4 444'444ttf 44 44 tttftsf tftttt4 4 4 4444 4 4 ttftf tftttftf ttf 4 4 44 4ttt et sf 4444 tf 444444 4 44Itf 4'4 4 444*4 tt 8 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.40 PIPING PRESSURE RETAINING COMPONENTS - STATIC 12 13 4 4'f 4 f 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 t 4 4 4 4 4 4 4 4 t 4 4 t 4 4 4 4 4 4 4 4 4 t 4 4 4 4 t 4 4 4 4 t f 4 4 t 4 4 4 4 4 4 4 4 4 4' 4444444 E t 44 4 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 sssssssssssaaassasassass assssasaaassass assess ssssass ssaasass feces asses ssassssa assess sss assess assess assess 20 21 SYSTEM ISOMETRIC NUMBER: I I-FW-004 22 23 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 24 25 SYSTEM ISOMETRIC NUMBER: I I-MS-001 28 27 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 28 29 SYSTEM ISOMETRIC NUMBER: I I-MS-002 30 31 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 32 33 SYSTEM ISOMETRIC NUMBER: I I-MS-007 34 35 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 38 37 SYSTEM ISOMETRIC NUMBER: I I-MS"009 38 39 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 40 41 SYSTEM ISOMETRIC NUMBER: I I-RH-001 42 43 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 44 45 SYSTEM ISOMETRIC NUMBER : II-RH-002 46 VT-2ST 1-3-06 f44 44 4 TEST PRESSURE PRESSURE TEST t44f 4 44 f t4 4 4444 f 444444 444 t4 4 4 44 4 tttf4It*44 4 ttt 44 4 44 4 4 47 NO 48 4 4 st f 4 4 4 444 4 4 4 4 4 4 4 4 4 *Iff 4 4 4 t4 4 4 4 t sf 4 tfttt44444 tf4 4 tf4 4 4 4 4 49 50 51 52 II'E 53 E" 54 I 55 58 57 E 58
.59 ~ 60 FORM 0113 (02I83)
478 1 ff f f sf ff f f tfat fffft t ff art f t t t fff t f f f t t sf t sf f *tft t f fft ff f sf t f tf fffffftft t ft t ft ff fft ff fsf tat ff f frf f ft f tf t fff fr sf t t f f f t fff 2 NUTECH CAROLINA POWER 8r LIGHT COMPANY PR IS IM SHEARON HARRIS NUCLEAR POWER PLANT " UNIT 3 4 PLANNING 1
't fff t tff t fff t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 477 f 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL Of ONLY *. ~ DATE 88/01/12 8 'f t t f 'f 'f t ft f ft f fft t t f f f fffft f ff tt tt f ff fft t f ff f f t t fftft t t ft fft ffft t ft f ttt ttttf f t
- t f t ff f t t f f tt t t **f tfff t t fft t t tr 9
10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.40 PIPING PRESSURE RETAINING COMPONENTS - STATIC 12 13 ffrttt tttfffsf fff staff tttff f tttttttttftftat tat f ttfff ff tttftttfttfttftff f f frttffat f tttttff tttt tttttff at f ttfttfstaff ttt 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMSER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 sasssssssssssssssasarsss srssssassssssss ararat saaarssssassssas arras stars rsssassr ssssss aas ararat ararat sssass 20 21 SYSTEM ISOMETRIC NUMSER : II-RH-004 22 23 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 24 25 SYSTEM ISOMETRIC NUMBER : II-RH-009 28 27 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER : II-RH-010 30 31 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER : II-SI-003
~ 34 35 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 38 37 SYSTEM ISOMETRIC NUMBER: I I-SI "004 38 39 PRESSURE TEST PRESSURE TEST VT-2ST 1"3-06 40 41 SYSTEM ISOMETRIC NUMSER : II-SI"008 42 43 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 44 45 SYSTEM ISOMETRIC NUMBER: I I-SI-009 48 VT-2ST 1-3-06 NO t f f t at f aft f tff fr t tff f tf t f tat f f tfff tfff ff tat f t tftff ff tat sf f tt t sf *a t tf f t f ff tft tf ff f tff tff at f f t t t sf tt ff f ft ff sf f PRESSURE TEST t t t f f ffTEST 47 PRESSURE 48 49 50 51 52 53 54 55 se 57 58 59 80 FORM 0113 (02I83)
481 1 t*ftftfff tftf4 ttftfttttfttfsf f tttff tttttff ttttfttfttttttftftftttfttsf f ttttff t ttttt tat sf tftt'tttff ttttff t 2
- NUTECH CAROLINA POWER 8) LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT f ttttttttttttttftft 3
4 t PLANNING 1 5 t COMPONENT LISTING AND ISI 10 YEAR PLAN: 836-01 PAGE 480 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 8 9 fr fr fr f tfstaff ttfttrtt*tt tttttft ttft t tff ff ttft ttft f sf ffff tt tat*at sf ff tfft sf t sf tffsf ftff sf ftff tffr st THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY at DATE 88/01/12 f tftftft ttttft st t 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.40 PIPING PRESSURE RETAINING COMPONENTS STATIC 12 13 'f f tat'staff tt taft f tf taft art sf tttttttttttttttf ttfttttftftfft tat*frstaff attf ttf tt staff f f f tftttff tff f taft tat tttftff f f ttftt 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 ssasssssassasaassaasssss = asar assssssr sasasr ssrsassrssasssss aasaa arras saaaaaaa ararat sas as))ass s s sssaas 20 21 SYSTEM ISOMETRIC NUMBER: II-SI-028 22 23 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 24 25 SYSTEM ISOMETRIC NUMBER: II-SI-029 26 27 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER: I I-SI-030 30 31 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER: II-SI-031 34 35 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 38 37 SYSTEM ISOMETRIC NUMBER: II-SI-032 38 39 PRESSURE"TEST PRESSURE TEST VT-2ST 1"3-06 40 t t*f'aftt ft tff f ft f f fft ff tff t t f f t sf t tt t ft fr ttfftfffff fft ff frat f f tff t frfft t t t t t t ft f f fr ft f f t ff ff ft t t t f st f 't t fr t tat t t t t f f tr 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
483 1 t t t t t t 't t tt 't tt 't tt tt t ttt t t t t t tt tt t t t t t t t' *t t t t t t t t t t t t tt t tt t tt tt t t' t t t t t t t tt t t t t t t t t t tt tt t t
- t t t t tt t t tt t t 't t tt
- t t t t
- t tt t t 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 -
4 SHEARON HARRIS NUCLEAR POWER PLANT PLANNING UNIT 1 ttttttttttttftt'tttt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 482 6 ASME SECTION XI, 1883 EDITION THROUGH ANO INCLUDING REVISION NRC1 t t tt t 88/01/12 7 THE SUMMER 1883 ADDENDA, INTERVAL 01 ONLY 8 t tt 4 t tt t tt hatt t tt t t tt tttttt t t't tt tt t t tt t 4 t t tt tt tt tt t tt t t tt t*thatt tt t t t tt tt ttt t t tt t t tt DATE tt t t t tt t t t t 9 10 CATEGORY C"H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.60 PUMPS PRESSURE RETAINING COMPONENTS " STATIC 12 13 t t t t tt t t ttt t tt t t t t t tt t t t tt t tt t t t t tt t ttt t t tt t tt t tt t tt t t t t tt tt t t t tt t tt t t t tt t t tt t' t t tt t' t tr t t t tt t t tttt t' t t t tt t t
't 1 14 15 DONE 16 I OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ '$$ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ ~ $ ~ $ ~ $ $ $ $ ~ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $$
20 21 SYSTEM ISOMETRIC NUMBER: II-CSIP-1 22 23 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 24 25 SYSTEM ISOMETRIC NUMBER : II"CTP-01 28 27 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER : II"RHRP-1 30 31 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 32 t t tt tt rt t t t t t tttt t t tt t tt tt t t t tt t t ttt ttt t tt t t t t t t t t t tt t t t t t t ttt t tt t t t tt t t tt t t t t t tt t NO ttt tt t tt t tt t t tt t t tt t t tt t 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
+Jr?r??., ~ r'i ~,r)v tt ?r i . ?'v '?,'- ", ?1 ~ ' "' . ~ ~ ~ I >> - \
484 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4' 4 4 4 4 4Ar 4 4 4 4 4 4 4 *4 t 4 4 4 4 4 4 t 4 4 t tf 4 4
- 4 t 4 4 4 4 4 t 4 4 4 t 4 f4 t 4 4 4 4 4 4 4 4 t 4 4 t 4 4 t. 4 4 4 4 4 4 4 t 4 4 4 4 4 4 4 4 4 NUTECH CAROLINA POWER 8 LIGHT COMPANY PR IS IM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3
4 PLANNING 1 4 ttttt4f4 tft44 4 4 44 4 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 483 8 ASME SECTION XI, 1883 EDITION THROUGH AND INCLUDING REVISION NRC1
'-l' THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 44 4 ~ ttt44*f444 t414444444 44444 ttf 444444 4444 444'44*44 f4f '4444 4 4 ttf4 4 ttftfttf 444'tf tt'4f88/01/12 4
DATE 44 4 t44 tt'4 4 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.70 VALVES PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 4 4 4 4 4 4 4 4 4 4 4 4 4' 44444 tt t 4 4444 tt 4 4 4 4 4 4 4 4 4 4 4 4 44 444 4 4 4t f4 4 4 4 4 44 4 tttt 4 4 4 4 4*44 t 4t
'14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE" OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP" PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES l9 ssssssssssssssssssssssas sssssassssssssa sssssa ssssssasssssssss sasss ssssa ssssassa ssssss aas ssaass asasss sassss 20 21 SYSTEM ISOMETRIC NUMBER : II-AF-005 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 24 VT-20T 1-2-03 25 VT-20T 1-1-01 28 ' I-AF-006 27 SYSTEM ISOMETRIC NUMBER:
28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-2-03 30 VT-20T 1-1-01 31 VT-20T 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER: I I-AF-007 34 35 PRESSURE TEST PRESSURE TEST VT-20T 1-2-03 NO 38 VT-20T 1-1-01 37 VT-20T 1-3-06 38 39 SYSTEM ISOMETRIC NUMBER: I I-AF-008 40 41 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 NO 42 VT-20T 1-2-03 43 VT-20T 1-1-01 t f t f t t 44 4 4 4 4 4 4 4 '4 4 4 '4 4 4 4 4 4 4 4 '4 4 4 4 4 '4 4 4 4 4 4 4 4 4 fr 4 4 4 4 4 4 4 4 4 *4 4 4 4 t t t 4 4 4 t 4 4 4 4 4 4 4 4 t 4 4 4 4 4 t f4 4 4 4 4 4 4 4 4 4 4 t 4 4 4 4 4 4 4 t 4 4 4 f4 4 4 4 f4 4 4 4 t 4 4 4 t 4 4 t
. 45 48 47 48 49 50 51 52 53 54 55 58 57 58 59 50 FORM 0113 (02I83)
487 1 f attf tftfttftaft f staff staff tf ttfat attttttttf tftt ttfttfttttt f tat f tttt f tttft tat aft f tttttf*ttttttat tttf ttftftfttttttf 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 4 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING tttttttftttttttttttf 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 486 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t 88/01/12 7 8 tttfttftttfttttfttff ttttttttttttttttttftttftttftttttttttftfttttttfttffttttttttttttfsfttttftttttfDATE THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY ttttttf f ttfttftt 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.70 VALVES PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 ttttttfttttttat sttttttf tftttt tttttttttttttttfff sf ttfstaff f ttftt t tat f tt tat ttttfat tftff tffttfat atttttttttfftat ttfttft 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI
,17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 ssasssssassassasssasssss saaassaassssass ssasas sssasssssassssss stats ssssa sssaasss sassss ass sasssa sassss == sas 20 21 SYSTEM ISOMETRIC NUMBER : II-BD-010 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 NO 24 VT-20T 1-2-03 25 VT-20T 1-1-01 28 27 SYSTEM ISOMETRIC NUMBER: I I-BD-011 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 30 VT-20T 1-2-03 31 VT-20T 1-1-01 32 33 SYSTEM ISOMETRIC NUMBER: II-BD-012 34 35 PRESSURE TEST PRESSURE TEST VT-20T 1-3"06 NO 38 VT-20T 1-2-03 37 VT-20T 1-1-01 38 39 SYSTEM ISOMETRIC NUMBER: I I-CS-001 40 41 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 42 VT-20T 1-2-03 VT-20T 1-1-01 t f sf t at at t tt t tt tfatty tf aft sf tt t ft t t at f t 4 t f tft t t t at t tt t sf t f t t tt t t t f t ffft tff f f at tt at f at taft t at 1 at f t ifsf tat 43 44 t t tf t at t at f sf 45 4e 47 48 49 50 51 52 53 54 55 58 57 58 59 eo FOAM 0113 (02I831
489 1 tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t t t tt 't t *ttt tt t t t tttt 1 4 PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 488 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 Ill THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY ttt t tt t t t lt tt
- t t tt t tt tt t t t tt t t t t tttt t t t t t t t t tt tt tt t t t t t tt t t tt ttt tt t tt t tt t t t t tt t t t' t t tt t tt t tt t t t t DATE llr tr t t t t t 88/01/12 t t tt t t tt t t t 9
10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ll ITEM NO. C7.70 VALVES PRESSURE RETAINING COMPONENTS " OPERATIONAL 12 13 ttttt t tttt 't t t 't tt tt t t t tt t ttt 't tt t t t t t t t t t t t t t tt t 't t t t ttt t tt t tt t t tt tt t t tt tt t tt tt t tt tt tt 't 't t t t t t t tt t t t t t t tt t t tt t tt t t ttt tt tt 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULEO INT INT PSIG'F ) ACCESS SELECT IND REOST TIONS NOTES 19 aaaaaaaaaaasaaasasassasa sssssassaasa as assess ssssssssaassaass asses esses sssssass assess ass as a s assess 20 21 SYSTEM ISOMETRIC NUMBER : II-CS-021 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1"3-06 NO 24 VT-20T 1-2-03 25 VT-20T 1-1-01 26 27 SYSTEM ISOMETRIC NUMBER: I I-CS-022 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 30 VT"20T 1-3-06 31 VT-20T 1-2-03 32 33 SYSTEM ISOMETRIC NUMBER: II-CS-026 34 35 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 36 VT-20T 1-2-03 37 VT-20T 1-1-01 38 39 SYSTEM ISOMETRIC NUMBER: I I-CS-027 40 41 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 NO 42 VT-20T 1-3-06 43 VT-20T 1-2-03 44 t t tt t tt t tt tt t tt t t tt t tt tt t t tt t tt t t t t t t t tt t t t tt ttttt t t tt tt t tt t t t t t t t 't t tt t tt t t t lt t t 't t 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 80
~ '.,' FORM 0113 I02I83)
' p 't,t>>c. r.' t =
>>a>>. >>t >> ~,- >>>> - s>>, ".-" >>t, "~, ~
492 tttttttttfttttttttttttttfttttttff'tttttttttfftfttttf'fttttt taft ttttftftftttftff tftttttttftttttfttftftftftttttttftftf NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM PLANT - UNIT t f f tttttttftttftf'ttt SHEARON HARRIS NUCLEAR POWER 1 PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 491 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA-, INTERVAL-01 ONLY DATE 88/01/12 ft tttfftfttttfat ttttttfttttttttftttttftftff tftt tttfsf ttftff f f at ttttttftaft ttttft staff ttfttftfttfttat atttt 7 8 9 10 CATEGORY C-H ALL PRESSURE, RETAINING COMPONENTS ll ITEM NO. C7.70 VALVES PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 f fttttttttttttttttttttff f tttfftttttff ttttttftttftttttttttttttttttttf tttttttfttttfttttttftt'ftft 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE =DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 asasssssssssssssssasssss ssasssassasasas assssa ssassssssasassss asass assss ssssssss ssssss sss sssssa ssaass ssasss 20 21 SYSTEM ISOMETRIC NUMBER: I I-CT-007 22 23 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 24 VT-20T 1-2-03 25 VT-20T 1-3-06 26 27 SYSTEM ISOMETRIC NUMBER: I I-CT-008 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-2-03 30 VT-20T 1-3-06 31 VT-20T 1-1-01 32 33 SYSTEM ISOMETRIC NUMBER: I I-CT-014 34 35 PRESSURE TEST PRESSURE TEST VT-20T 1-2-03 NO 36 VT-20T 1-3-06 37 VT-20T 1-1-01 38 39 SYSTEM ISOMETRIC NUMBER: I I-CT"016 40 41 PRESSURE TEST PRESSURE TEST VT-20T 1-2-03 NO 42 VT-20T 1-1-01 VT-20T 1-3-06 t at t t at tt t tt at f t at tat tt ft t sf t tff tftt t at tf f tf ft sf t t at t t tt t tat t ff at tf f at t sf f t t sf tt f t t tt t t t f sf f tt t t t tt tf t 43 44 at t t at at 45 48 47 48 49 50 51 52 53 54 55 se 57 58 59 60
493 1 t ttt t ttt ttt t tt tt t t t t *tt t ttt t t t tt t t t tt t tt t t tt t t t tt t t t t t t t' t t t t t tt t t tt t' tt 't tt tt tt t t tt t 't t t tt tt t t t t t ft t t t' t 2 NUTECH CAROLINA POWER Sl LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING t t tt t t t t t tt t t t t t *tt COMPONENT LISTING ANO ISI 10 YEAR PLAN: 63S-01 PAGE 492 ASME SECTION XI, 1963 EDITION THROUGH AND INCLUDING REVISION NRC1 t t t t t 88/01/12 THE SUMMER 1963 ADDENDA, INTERVAL 01 ONLY t t t t t t t t ttt t t t tt tt tt t tt t t tt t t t t tt t t tt tt t ttt t t t tt t t t t t tt tt tt t t t t t t t*ttt tt t t tt t t t t t t t t tt tt t t t t t tt t t t DATE t t tt t t t tt t t 9 10 CATEGORY C"H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.70 VALVES PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 ftt t t ttt t t tt t t t tt t t t t tt t t t tt t t t t tt t tt t t t t tt ttt t tt t t t t tt tt tt t tt t tt t t t tt t t tt t t tt t t t t t t t tt t t t t t t t t t tt t t tt t t t t t t t 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES .TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ ~ $ $ $ ~$$$$$$$$$$~$~$ $$$~$$ $$$$$$$$~$$$$$~$ $$~$$ $$$$~ $$$$$$$$ $~$$$$ $$$ $$$$$$ $$$$$$ $$$$~$ 20 21 SYSTEM ISOMETRIC NUMBER: I I-FMR-01 22 23 PRESSURE-TEST PRESSURE TEST VT-20T 1-1-01 24 VT-20T 1-3-06 25 VT-20T 1-2-03 28 27 SYSTEM ISOMETRIC NUMBER: I I-FMR-02 28 29 PRESSURE-TEST PRESSURE TEST VT-20T 1-1-01 30 VT-20T 1-2-03 31 VT-20T 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER: I I-FMR-03 34 35 PRESSURE-TEST PRESSURE TEST VT-20T 1-3-06 38 VT-20T 1-1-01 37 VT-20T 1-2-03 38 39 SYSTEM ISOMETRIC NUMBER : II-FW-001 40 C 41 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 5 NO 42 VT-20T 1-2-03 43 VT-20T 1-1-01 44 t t 't tt t t tt tt tt t tt t ttt t t t t tt tt tt tt tt t tt tt t t t t t ttt t tt t tt t tt t t t tt t t t t t t t t t t t t t t t t t t tt t t t tttt t t tt t t t tt t tt t t t t tt t t t 45 46 47 48 49 50 51 52 53 54 55 58 57 58 59 60 FORM 0113 <02I83)
495 ft t*fat at tft hatt f f at ff f t sf tat t t at tat f ft f 4 tat ftf t at t t f ftf f ft tatty t t sf at f tat f t at f at at t t tffft t tft t t f tf sf t't tft t tt f f f f f ft t t NUTECH CAROLINA POWER Br LIGHT COMPANY PRISIM SHEARON HARRIS- NUCLEAR POWER PLANT - UNIT 1, PLANNING *tafttft*t*ff f tttt COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 494 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 f t tt t t tt tt t t t at at f f f f sf f f tfat88/01/12 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE
'sf f tat'at t t tt t tt tf tt tt t tt tt ft tt t t t tf tff tat t sf t tat tt tftt t tf at sf at t at sf t t ftf t sf t at f f f t sf t at t 9
10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.70 VALVES PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 tt f t t ff f t t t t tf ttft tt ttt t t t t tt t f t tft t t tt ft f t f f f f t t tft t fft ttt t t t *t ft t ftt f *ff t t tf t tt f f ft f t t t tft 'f f tf t t tt t f t t *ff t t tf t t f f
'f rlr 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ACCESS SELECT IND REQST TIONS NOTES 19 aassssssssasssssssssssss ssassssssass sa ssasaa ssssasssasssasss stats fasts) assasasa ssasas ass aasaas ssssss ssasss 20 21 SYSTEM ISOMETRIC NUMBER: I I-MS-002 22 23 PRESSURE TEST PRESSURE TEST VT.-20T 1-3-06 NO 24 VT-20T 1-2-03 25 VT-20T 1-1-01 26 27 SYSTEM ISOMETRIC NUMBER : II-MS-007 28 29 PRESSURE TEST PRESSURE TEST VT-20T 1-2-03 NO 30 VT-20T 1-1-01 31 VT-20T 1-3-06 4 32 ~.
33 SYSTEM ISOMETRIC NUMBER: I I-MS-009 34 35 PRESSURE TEST PRESSURE TEST VT-20T 1-3-06 36 VT-20T 1-2-03 37 VT-20T 1-1-01 38 39 SYSTEM ISOMETRIC NUMBER: I I-RH-001 40 41 PRESSURE TEST PRESSURE TEST VT-20T 2-03 NO 42 VT-20T 1-1-01 43 VT-20T 1-3-06 1 44 t t t!Ir t rf t t t tt f f t t ttt t t t t t t t 't t t tt tt t ft t t tff t t ffftft ft tf t t f t t t t f ft t tf f t t f t f t tt t t t ft t ttf t tt f f' f t t t t t t **a rlr llr III III rlr rlr III .rr 45 ~ 46 ': 47 48 3 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 C02I83) rt
500 tt t tft t t tt tt t f t t ttt f t f t ttt t t tf t tf f t t t t *t t t t t tttt tfttt t t
- tft t tt f t tt f ttf t t ttt t ttf t t tttt t tt t t t t t f ftt t ft t t t t tt tt t t tt 1
2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT " UNIT 3 4 PLANNING f ttff f ff tftt tf et f tt 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 499 f 8 ASME SECTION',XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983~ADDENDA, INTERVAL 01 ONLY
- DATE 88/01/12 ft tf t sf f et tft tt t f t aft t tf t t t et f tt t et t tt t t t t f t t t tt t t t'tt t t t t tt t tf t t t et f t*tt t t f tet f et et t t fetter ft et t t tt t et et t t et et tet t t t t 7j 8
9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.70 VALVES PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 a* f 4 ff fft t et f ft t*ft tt tet t et et tet et tft t t t fthm et t t t t et sf tt ft t t et et t t f t tet ftt tfft t et'tf %taft tt t t tt et t tfft sf tet t f f t't t 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 asssaasssssssssasssssssa saassssss asses assess asasassssssasssa tasse asses ssassesa assess ssa assess assess assess 20 21 SYSTEM ISOMETRIC NUMBER: II-SI-022 22 23 PRESSURE-TEST PRESSURE TEST VT-20T 1-2-03 24 VT-20T 1-3-06 25 VT-20T 1-1-01 25 27 SYSTEM ISOMETRIC NUMBER: I I-SI-023 28 29 PRESSURE-TEST PRESSURE TEST VT-20T 1-1-01 30 VT-20T 1-2-03 31 VT-20T 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER: I I-SI-024 34 35 PRESSURE-TEST PRESSURE TEST VT-20T 1-1-01 35 VT-20T 1-2-03 37 VT-20T 1-3-06 38 39 SYSTEM ISOMETRIC NUMBER: I I-SI-025 40 41 PRESSURE-TEST PRESSURE TEST VT-20T 1-2-03 42 VT-20T 1-1-01 1 43 VT-20T 1-3-06 44 sf sf tftff tff t t sf tft et ft tftftfet t et tf ted sf tt ff et t t ff t t t tt tt t tfet t t tff et ft f t*tt t t tt f t et tet t sf ttt t tt tf tet et sf et t*t tet tet 45 48 47 48 49 50 51 52 53 54 55 se 57 58 59 eo FORM 0113 (02I83)
- 0
501 f'ff tat f tf ff t fr t ff *a fff tat f t t f t f f tt f tf f ftft t f tft tt t ttfiff f f ft ftt tf t tff t t st f t t t ft t tf tftt tat t t tt tt tf' t t t t'it t t tf't ff 2
- NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 3
PLANNING 1 ttffff ffffff ffftftf 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 500 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 7 8 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY fffff ft tft at f f at at f fff f f f f tff f f f ft t f f tftff tft tttfat f'fsf f t t f t t t f at t f tftfft t f fff f f f ffft fff tft at t't t DATE tt tat 88/01/12 t t tat ft t t f f 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.70 VALVES PRESSURE RETAINING COMPONENTS - OPERATIONAL 12 13 ft f ff t f ff t f ft t f f ft f tff f fff ff ff ft fff ff ft tff f fff ff t ft t f 't t f f t ft st t f t t ffft f ft ftf t t t t ftt f 't t t t ft t f t f f 'f tt fr't t t ff ft f t t ft t f t f t 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 sssasaasassaasssassassss sassssrsssas ss s sssssasssssssara aa a a sas rssssass sssssa aas arrssr ararat ssssss-20 2'I SYSTEM ISOMETRIC NUMBER : II-SI-026 22 23 PRESSURE-TEST PRESSURE TEST VT-20T 1-2-03 24 VT-20T 1-1-01 25 VT-20T 1-3-06 26 27 SYSTEM ISOMETRIC NUMBER: I I-SI-027 28 29 PRESSURE-TEST PRESSURE TEST VT-20T 1-1-01 30 VT-20T 1-2-03 31 VT-20T 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER : II"SI-028 34 35 PRESSURE-TEST PRESSURE TEST VT-20T 1-1-01 36 VT-20T 1-3-06 37 VT-20T 1-2-03 38 39 SYSTEM ISOMETRIC NUMBER : II-SI-029 40 41 PRESSURE-TEST PRESSURE TEST VT-20T 1-1-01 42 VT-20T 1-2-03 43 VT-20T 1-3-06 44 tff ffffttft tff ff ff tff frff at ft tfff fsf ffff tt t sf ff at f f f fff tf t f ft tftff ffff fff tt ft'f f aft ff t tfff fftft t at f 'f f *a 'f f tfftft f f 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 <02/83)
502 flufft ttt tlltt t t f l t t t f fitflitt f l litltd fttt t ttt t tt t ttt fl>> tt t ft t t t t t t t t l t l tt ll't J P NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT UNIT ill t l f l tft l tt l t f t l t 'f 'l t 1 PLANNING 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-,01 PAGE 501 8 ASME SECTION.XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 DATE 88/01/12 f ff ttff*ttfftffttftftttttttttftf ttttftftftftfftttt++4+tttttt*t*+tftfttttftftttttfff THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY 7 8 ttf ttfftttttfff ff 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ll ITEM NO C7,70 VALVES PRESSURE RETAINING COMPONENTS OPERATIONAL 12 13 t tt tttt t tfft t t t lt f t t tt ft t f l t t ll t ft t tt f tf t t t l t l l t l ftf t t t t tt t tt t t l tt t tt t t t ll t l t l t ttt t t t t tt t tt tt t l t tt t ll t l t t t t t t t l t tt t l t 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 $$$$$$$$$$$$~$$$$$$$$$$$ $$$$ ~$$$$ $ $$ $ $$ ' '
$ $ $ $ ~ '$ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $$$$$$ ~$$ ~$~$$$ $~$~$~ ~$~$~$
20 21 SYSTEM ISOMETRIC NUMBER: I I-SI-030 22 23 PRESSURE-TEST PRESSURE TEST VT-20T 1-2-03 24 VT-20T 1-1-01 25 VT-20T 1-3-06 26 27 SYSTEM ISOMETRIC NUMBER: I I-SI-031
"'8 29 PRESSURE TEST PRESSURE TEST VT-20T 1-1-01 30 VT-20T 1-2-03 31 VT-20T 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER: I I-SI-032 34 35 PRESSURE-TEST PRESSURE TEST VT-20T 1-1 "01 36 VT-20T 1"2"03 VT-20T 1-3-06 37 38 tttttfttttftttttffttffttfflitttttffftiffttftifftftfftiffltttltttfittilttttttfftttttttttflttttttlttttllttlf ttttttt 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60
504 tftftaft ttf t tttf f tf tttft ttttt tat ttfttftttftttfttttttftff tftftftt tan tat tfttftt taft tttttftaft t f kttff offaft f tat tat tat tf 4 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING tt t 'f t t t t f' t tt t f ft 't t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 503 8 ASI11E SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 88/01/12 ft f sf staff tff tt t f tft t t tf t t t fft t t tt tftftt f f t t t ttt f'ft f ft tt t tt tt tt t t tf t THE SUMMER 1983 ADDENDA, INTERVAL 0'1 ONLY DATE 8 at sf f f at sf f t tfat tt sf t f fsf tft tfft t tan tat t at t 4 at sf 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.80 VALVES PRESSURE RETAINING COMPONENTS - STATIC staff taft tff ftstaff sf t t f sf f f tff tat tt tf f f t f f t ft t ft tf *ttt t st st t t f t t tt t sf t t tt f tft t st t t t t t t t sf t t t tf t tft at f t t t tat tt f t 12 13 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 assassssssssssasssssasas ssssssssssassss sssssa ssassssassaaaaas stats fasts ssssssaa asssss ass ssssss assssa sssass 20 21 SYSTEM ISOMETRIC NUMBER : II-80-002 22 23 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 24 25 SYSTEM ISOMETRIC NUMBER : II-BD"003 28 27 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER : II-BD-007 30 31 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER : II-80-008 34 35 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 38 37 SYSTEM ISOMETRIC NUMBER : II-BD-009 38 39 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 40 41 SYSTEM ISOMETRIC NUMBER : II-80-010 42 43 PRESSURE. TEST PRESSURE TEST VT-2ST 1-3-06 NO 44 45 SYSTEM ISOMETRIC NUMBER : II-BD-011 48
- 47 PRESSURE TEST TEST VT"2ST 1-3"06 ff at fat t t tft f f t 1 PRESSURE tat t sf tffttttt t tt t tt t t tt tat tt sf aft tt at tt t ftt t f at t t t f t t at f tt t t t t*tt*tt ft tt t tt t t t t at t t tt at*at t NO 48 49 50 51 52 53 54 55 se 57 58 59 80 FORM 0113 {02I83)
506 ftftt frf ettf ff f f f f fffft tet ff t et f ff ttftf tt ff tff f f ff ffft t tfft tft tet fff et f fr tft tftfft tf et ttt t tt t t ttft sf t tt t t tt
't NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t ttttt t tet'*taft et t fr 1
PLANNING COMPONENT LISTING AND ISI 10 YEAR PLAN: 835-01 PAGE 505 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 88/01/12 t frt tt f tt tt tftt tt t THE SUMMER 1983 ADDENbA-, INTERVAL 0$ OblLY tt tt t t tftt tft t tf t ted et*et t t t fr tet t fthm t t t tet t' t tt t ttt t*t t t sf t st f t et sf DATE t t et et fr taft t tet 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.80 VALVES PRESSURE RETAINING COMPONENTS - STATIC 12 13 f tftttftfttftfft tfet tff et sf t tet tftttff tfttttttttttttftet ttttttttttttttet ttttfr ttff et ttff tttfttttttttttaft tttttft tt 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 sssssesssssesss seafarer ssssssarssassra arrear ssasssssasrsssrs rarer seers srssssss errata ssa rsssrs seater assess 20 21 SYSTEM ISOMETRIC NUMBER: I I-CS-022 22 23 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 24 25 SYSTEM ISOMETRIC NUMBER: I I-CS-026 28 27 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER : II-CS-027 30 31 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 32 33 SYSTEM ISOMETRIC NUMBER: I I-CS-033 34 35 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 38 37 SYSTEM ISOMETRIC NUMBER: I I-CS-088 38 39 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 40 41 SYSTEM ISOMETRIC NUMBER : II-CS"089 42 43 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 44 45 SYSTEM ISOMETRIC NUMBER: I I-CS-092 48 VT-2ST 1-3-06 47 48 ttttffrtttf PRESSURE TEST ftfttfttff tftftf PRESSURE TEST tttttsf ttttttttttttttttttttttttttttf tetttt*t**t'etet ttttf ttt tet tttttttttftttttttt*ttttftet t NO 49 50 51 52 53 54 55 55 57 58 59 80 FORM 0113 (02I83)
508 tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt*tttt NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING t t tt t' tt t t t tt t t t t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 507 8 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA; INTERVAL Of ONLY DATE 88/01/12
'?
8 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.80 VALVES PRESSURE RETAINING COMPONENTS - STATIC 12 13 tt t t t t ttt tt t tt tt t tt t tt t tt t t t t tt t t 4 t t t t tt ttt tt tt t t t t t t t t tt tt t t t t tt t t itWatt t*tt t t t*ttt tt t tttt t tt t tt ttt tt tt tt t t 4 14 15 DONE 18 "-OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ ~ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ '$$ $ $ $ ~ $ $ $ ~ $ $ $ $ ~ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $$$$~$ $$~$$$ $$$$~$ 20 21 SYSTEM ISOMETRIC NUMBER: II-CT"016 22 23 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 24 25 SYSTEM ISOMETRIC NUMBER: I I "FMR-01 28 27 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER : II-FMR-02 30 31 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER : II-FMR-03 34 35 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 36 37 SYSTEM ISOMETRIC NUMBER : II-FW-001 38 39 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 40 41 SYSTEM ISOMETRIC NUMBER : II-FW-002 42 43 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 44 45 SYSTEM ISOMETRIC NUMBER: I I-FW-003 46 47 PRESSURE TEST PRESSURE TEST VT-2ST 1"3"06 NO 48 ttt t ttt t ttt t ttt t ttttt ttt t t tt ttt t t t tt t t t tt t tt t t t t t tttt t t tt ttt t ttt tt t t t t t t t t tt tt t t t ttt tt ttt tt ttt tt t t t t t t tt tt t
- t t t t 't t t t t 49 50 51 52 53 54 55 se 57 58 59 60 FORM 0113 (02I83)
509 t t tt t tt t t tt t t t t tt tt t t t t t ttt t t t tt ttt t tt *t tt t t f tt t t t t t tt tt t t t t t t t tt t tt t tt t t t t t t t' t t t tt t tt t t t NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT UNIT PLANNING tt t t tt7. t t t ttt t' t t tt t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 508 8 ASME SECTION XI. 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY t t t t t tt t tt *t t tttttt tt t t t ttt t t t t tt ttt t tt t tt tt tt t t ttt tt t tt t t t t tt tt tt t t t t t t t t t t t t t t t ttt t t t t t t t t t t t t t' DATE tt tt 88/01/12 7 8 't t t t tt t tt t t t t t t 10 CATEGORY C"H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.80 VALVES PRESSURE RETAINING COMPONENTS - STATIC 12 13 14 t t t t t t t tt t tt t t tat at tt t t tt t tat t at tt at t tat tt at t t t at t tt tat t t t tt tat at tt t tt t t t t tt f t at t t tt t tt t ttt t tt t tt at t t at t tt tat t tt t t t 15 'DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REOST TIONS NOTES 19 sssssasssaaasaasssaasaaa asssssssassssss ssasas sasssasassssssss stats s a a a a s as ssssas aaa saasss asaass sssasa 20 21 SYSTEM ISOMETRIC NUMBER.: I I-FW-004 22 23 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 24 25 SYSTEM ISOMETRIC NUMBER : II-MS-001 28 27 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 28 29 SYSTEM ISOMETRIC NUMBER: I I-MS-002 30 31 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 32 33 SYSTEM ISOMETRIC NUMBER: I I-MS-007 34 35 PRESSURE TEST PRESSURE TEST VT"2ST 1-3"06 38 37 SYSTEM ISOMETRIC NUMBER : II-MS-009 38 39 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 40 41 SYSTEM ISOMETRIC NUMBER: I I-RH-001 42 43 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 44 45 SYSTEM ISOMETRIC NUMBER : II-RH-002 48 VT-2ST 1-3-06 48 tttt t t tt t TEST 47 PRESSURE ttttt t tttt t t t t t t PRESSURE TEST NO t t tt tttt tt t t t t t t tt t t' t t t' t t t ttt tt t t t t tt t t tt tt t t t t t t t t t t t I t tt t t ttt t t t t tt t *t t t t t tt t t 1 tt tl t t tr t t t 49 50 5'I 52 53 54 55 55 57 58 59 50 FORM 0113 (02I831
fff tf f sf t tff tff tfat f ft t t f f t t tftt ff f t f f't t t'ff ft t t f f *ft tftf f t tf fff t fff ff f t f t t tff "4 t t tf t t fft t tt ff f tfff t f t '5 12 lll NUTECH CAROLINA POWER 8t LIGHT COMPANY PRISIM lt SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1 f tll!littllttf'4lftttf lifttf* 5 COMPONENT. LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 511 8 ASME SECTION XI, 1983 EDITION THROUGH ANO INCLUDING REVISION NRC1 THE SUMMER 1983 ADDENDAI INTERVAL b1 ONLY f -- DATE 88/01/12 f f f tftftat tf taft tftffff f f ttff tftfffff f f tf tttftff tftftttftttttt tf f f t ttttff fsf stf tttftff tt tf ff tfff f tt ttfffffff f ff 7 8 sf 9 10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.80 VALVES PRESSURE RETAINING COMPONENTS - STATIC 12 13 ffftff tff t ff f f f ft ttfft f f fff fft tt t fffftf tftffft tf f f tt f tff tff t tff tt f f tft f f f ft tt ff t fft f t f tffffft st at 14 15 DONE 18 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT PSIG (F ) ACCESS SELECT IND RE@ST TIONS NOTES 19 sasssassssssasssilssasass ssssssssssssssa asssas ssssssassassssss stats stats ssrssass ssssss ass asssss sassss sssssa 20 21 SYSTEM ISOMETRIC NUMSER : II-SI-021 22 23 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 24 25 SYSTEM ISOMETRIC NUMBER : II-SI-022 28 27 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER: I I-SI-023 30 31 PRESSURE-TEST PRESSURE TEST'T-2ST 1-3-06 32 33 SYSTEM ISOMETRIC NUMSER : II-SI-024 34 35 PRESSURE"TEST PRESSURE TEST .VT-2ST 1-3-06 38 37 SYSTEM ISOMETRIC NUMBER : II-SI-025 38 39 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3"06 40 41 SYSTEM ISOMETRIC NUMBER: II-SI-026 42 43 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 44 45 SYSTEM ISOMETRIC NUMBER : II-SI-027 48 47 PRESSURE-TEST TEST VT-2ST 1-3-06 48 tfffff tt tftftff ffftftftffPRESSURE f tftff tff ff f tff f ff ff ft tf f f f tf f t tf tff ff f tff tf ff ff f tff tfttff tfff f f tfat tffft tft f ff tft tf f f tf f t t
~
49 50 51 52 53 54 55 se 57 58 59 80 FOAM 0113 (02183) 0:
513 1 tr t t t tttt t tttt tt t t ttt tt t t t t t t t t t tt t t t tt tt t t t t t' t t t tt t t t t t t t t tt t t tt t tt tt tt tt t t t t tt t tt t t t t t t t tt t t t t t tt tt t t tt t t ttt t ttt t t t 2 NUTECH CAROLINA POWER S LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 PLANNING t tt t t t stat t t t t 5 COMPONENT LISTING AND ISI 10 YEAR PLAN: 83S-01 PAGE 512 6 ASME SECTION XI, 1983 EDITION THROUGH AND INCLUDING REVISION NRC1 t t t t t t t t tt tt tt t t t t t tt tttt *tt tt tt t t tt tt t t tt t tt t tt tt t tt t t t t tt t t t tt t tt *t t t t t t
- t t tt t t t' t t t t t t t tt 88/01/12 7 THE SUMMER 1983 ADDENDA, INTERVAL 01 ONLY DATE 8 t t t t tt t t tt t 9
10 CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS 11 ITEM NO. C7.80 VALVES PRESSURE RETAINING COMPONENTS - STATIC 12 13 ttt t t t tt t t t t 't t t t t tt tt ttt tt t t ttt t tt t t tt tt t tt ttt t tt t tt t tt t t t t t t t t t t t t t t t t tt t t t tt t t t t t t t t t t t t t tt t tt t t t tt t t t tt t t t t t t t t t t t 14 15 DONE 16 OUTAGE THIS DONE TEST TEST BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE" OUT/ PRIOR PRES TEMP TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT PSIG (F ) ACCESS SELECT IND REQST TIONS NOTES 19 aaraasasasasssssssasssss sasssssss ra ss stars ~ ssssassassaasrss stars arras sssassss ararat sas strata araasr ararat 20 21 SYSTEM ISOMETRIC NUMBER: II-SI-028 22 23 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 24 25 SYSTEM ISOMETRIC NUMBER: I I-SI-029 26 27 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 28 29 SYSTEM ISOMETRIC NUMBER : II-SI-030 30 31 PRESSURE-TEST PRESSURE TEST VT-2ST 1-3-06 32 33 SYSTEM ISOMETRIC NUMBER : II-SI-031 34 35 PRESSURE TEST PRESSURE TEST VT-2ST 1-3-06 NO 36 37 SYSTEM ISOMETRIC NUMBER : II-SI-032 38 PRESSURE-TEST VT-2ST 1-3-06 39 40 PRESSURE tttttttttttttttttttttttt'ttttttttttttttttt'tttttttttttttttt'ttttttttttttttttt*t'tt'tttttttt TEST 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 FORM 0113 {02I83)
I
~
4~
1 1 SELECTION RECORDS 2 3 EXAM S COMPNOEX EXREQ CATEGORY EXREO ITEMNO 4 EXAM EXREO EXSCHD OUTAGE SELECT REQUEST 5 EXAM EXEMPT EXDATE CREDIT NDEPROC CALSTD 8 COMP SYSTEM COMPDES ACCESS 1 ACCESS 2 ACCESS 3 7 COMP ACCESS 4 ACCESS 5 ACCESS 6 TRANSIN TENRMKS 8 COMP NEWCOMNO ORDER COMPDIA NOMTHCK REFDWG 9 COMP OLDCOMNO 10 PICK EXREQ EQS B02"01 11 15 RECORDS HAVE BEEN SELECTED 12 13 14 SELECTED DATA RECORD FORMAT 15 I I I 5 5 ll 5 ll 4 S ~ 8 8 E 5 8 ~ N ~ 8 ~ 5 0 5 S 5 S 16 17 ELEMENT LENGTH STARTING COL. 18 19 COMPNOEX 24 1 20 EXREO 6 25 21 CATEGORY 6 31 22 EXREO 6 37 23 IT EMNO 6 43 24 EXREO 6 49 25 EXSCHD 6 55 26 OUTAGE 6 61 27 SELECT 6 67 28 REQUEST 6 73 29 EXEMPT 6 79 30 EXDATE 8 85 31 CREDIT 1 93 32 NDEPROC 6 94 33 CALSTD 6 100 34 SYSTEM 3 106 35 COMPDES 15 109 38 ACCESS 2 124 37 ACCESS 2 2 126 38 ACCESS 3 2 128 39 ACCESS 4 2 130. 40 ACCESS 5 2 132 41 ACCESS 6 2 134 42 TRANSIN 1 136 43 TENRMKS 6 137 44 NEWCOMNO 24 143 45 ORDER 4 167 48 COMPDIA 5 171 47 NOMTHCK 5 176 48 REFDWG 16 181 49 OLDCOMNO 24 197 50 51 52 53 54 55 58 57 58 59 60 FORM 0113 {02I83)
ff f f f ffff t ff f f f tff ff f tff f frf ff f ffttf f f f fr ffff tt t'tt f f sf tft t f tfat f ft ttff f f ff t't f f't f t f t t st tf t tfsf f ft ff t f f f ff f ft ft t f ttf NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING tfsf ff ftftfttt fff 5 AUGMENTED EXAMINATION COMPONENT LISTING - B02-01 PAGE 1 8 REACTOR COOLANT PUMP. FLYWHEEL INTEGRITY REVISION NRC1 17 PER REGt)LATORY GUIDE 1. 14- INTERVAL 01 ONLY DATE 89/01/12 8 ftt f f t f f f st f ff at ttff f ff f t f fr f f f tff f tff tt ffff ft tff ff tt fft f tt ff f t fff f tf t f f f t f tff t t fr t t ff f't ftt tft tf ff
'f art 9
10 CATEGORY RG1. 14 REACTOR COOLANT PUMP FLYWHEEL INTEGRITY EXAMINATION 11 ITEM NO. BORE REACTOR COOLANT PUMP FLYWHEEL BORE UT ff f fft f f f sf t fr t fr t t ff f t t st t ft t t ttt t fff t f frf at t tfff t ft t t t f f f fff f f tt t t f ttftff t ft tt t fff t' tt tf t t t f ff ft tf t 't ttfft f f t t t at f fr
- 12 13 14 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 asasssssssssssssssssrsss sssssasasssssas srssas saasaaaaa aaaaas = ss rssaa ssraasas ararat ssa ararat sasass ararat 20 21 SYSTEM : RC REACTOR COOLANT ISOMETRIC NUMBER: I I-RCP-02 22 23 RCP-A-FLYWHEEL FLYWHL UT-00 1"2-03 74.99 15.00 NO 24 UT-00 1-1-01 25 UT-00 1-3-06 28 27 RCP-B-FLYWHEEL FLYWHL UT-00 1-1-01 74.99 15.00 NO 28 UT"00 1 "3 29 UT-00 1-2-03 30 31 RCP-C"FLYWHEEL FLYWHL UT-00 1-3-06 74.99 15.00 NO 32 UT-00 1-2-03 UT-00 1-1-01 33 34 f f f tftff sf t f tff fffff f ff tffff tff f f tff ff f f st f f st f ff frf tfffff at fff t f f tff tff fff *ttf tttft tff f f f f f ff tfffft tf t tfff tf t f *a t ff f'5 38 37 38 39 40 41 42 43 44 45 45 47 48 49 50 51 52 53 54 55 55 57
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'59 eo FPRM 0113 It02/83)
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1 SELECTION RECORDS 2 3 EXAM S COMPNOEX EXREQ CATEGORY EXREQ IT EMNO 4 EXAM EXREQ EXSCHO OUTAGE SELECT REQUEST 5 EXAM EXEMPT EXOATE CREDIT NDEPROC CALSTD 6 COMP SYSTEM COMPDES ACCESS 1 ACCESS 2 ACCESS 3 7 COMP 4 ACCESS 4 ACCESS 5 ACCESS 6 TRANSIN TENRMKS 8 COMP NEWCOMNO ORDER COMPDIA NOMTHCK REFDWG 9 COMP
- OLDCOMNO 10 PICK EXREQ EQS 803-01 11 1058 RECORDS HAVE BEEN SELECTED 12 13 14 SELECTED DATA RECORD FORMAT 15 ISSSSSSRRSR ~ S ~ $ $ ~ $ %$ 15 ZS 16 17 ELEMENT LENGTH STARTING COL.
18 19 COMPNOEX 24 20 EXREQ 6 25 21 CATEGORY 6 31 22 EXREQ 6' 37 23 ITEMNO 43 24 EXREQ 6 49 25 EXSCHD 6 55 26 OUTAGE 6 61 27 SELECT 6 67 28 REQUEST 6 73 29 EXEMPT 6 79 30 EXOATE 8 85 31 CREDIT 93 32 NDEPROC 6 94 33 CALSTD 6 100 34 SYSTEM 3 106 35 COMPOES 15 109 38 ACCESS 2 124 37 ACCESS 2 2 126 38 ACCESS 3 2 128 39 ACCESS 4 2 130 40 ACCESS 5 2 132 41 ACCESS 6 2 134 42 TRANSIN 136 43 TENRMKS 6 137 44 NEWCOMNO 24 143 45 ORDER 4 167 46 COMPDIA 5 171 47 NOMTHCK 5 176 48 REFOWG 16 181 49 OLDCOMNO 24 197 50 51 52 53 54 55 56 57 58 59 80 FOAM 01'l3 (02I83)
ttt4f ttf14411 tttttt44144 41 4 41*4 *tf4f 4t 1tf 444 44f 4 14444*f 4 tttftttttttttttt*ttttt4tttfttttttttttttt*tttt4 tf444 4 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 4 3 SHEARON HARRIS NUCLEAR POWER PLANT " UNIT 1 4 4 PLANNING tttttft'tftttt44ftt AUGMENTED EXAMINATION COMPONENT LISTING - B03-01 PAGE 1 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 REPORT QOESTION 250.1- INTERVAL 01 bNLY tttttfttttttttttttf tttftttfttfttttt4441tfrtttftf 44 4 t44ttttf 44 ttttttttttf14ttttttttttfttf tr444 f4ttf4 tf1 ttf4 DATE 88/01/12 f4 ttf4 tttf144 9 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250: 15 SAFETY EVALUATION REPORT, SAFETY'EVIEW QUESTION 45250. 1 12 13 If4 ttttttf4 ttf4 444 ttttftttrttftttttttttt414 44 tttt4441ttttf ttttttfttt14 tff4tftfttftttttttt4tttttt44'4 4ttf ttt4444ttf44tttr 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV.RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION J'YPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ 4&&& ~ &$ 4&& & $ 4 ~ $ $ ~ $ $ $ $ $ $ $ $ ~ &&&' ~ $ $ '& $ 4 $ 4 ~ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ &&&~ $ $ $ $ $ $ $ $ 20 2'1 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-CS-001 22 23 CT-FW-100A LNGSEAM PT 1-1-01 08.00 0.322 NO 24 25 CT-FW-101A LNGSEAM PT 08.00 0.322 26 27 CT-FW-1018 LNGSEAM PT 08.00 0.322 NO 28 29 CT-FW-102A LNGSEAM PT 08.00 0.322 NO 30 31 CT-SW-I11A LNGSEAM PT 08.00 0.322 32 33 Cr T-SW- I 1 18 LNGSEAM PT 08.00 0.322 NO 34 35 36 CT-SW-I3A LNGSEAM PT '8.00 0.322 37 CT-SW-I4A LNGSEAM PT 08.00 0.322 38 39 CT"SW-J3A LNGSEAM PT 08.00 0.322 NO 40 41 CT-16-19-SW-1A LNGSEAM PT 08.00 0.322 NO 42 43 CT-16-19-SW-1B LNGSEAM PT 08.00 0.322 NO 44 45 CT-FW-100 PIPE -ELB LR PT 1-1-01 08.00 0.322 48 47 CT-SW-J3 ELB LR -PIPE PT 08.00 0.322 NO R2-001 48 49 CT-16-19-SW-1 PIPE . -PIPE . PT 08.00 0.322 NO 50 51 CT-F W- 101 PIPE -PIPE PT 08.00 0.322 52 53 CT-SW-I11 -PIPE 54 1 ftftrftttttttftrtt*ttfrttfttt4tttttttt'ttllrfPIPE PT ttrlrtfttf444tttff 444 4 1414tttttf 08.00 0.322 4444 ttttt444 444ttfff4'tt44tt444tf ttttttftf tttttrt NO 55 58 57 58 59 80 FORM 0113 (02I83) r'I";
t t sf t st t t tttt t t tt t t tt t t tt t't t t tt t st t t tt 't tt ttt t tat tt t t t t tt t t t t tt tt tt t t t t st tt t t t t tt t*tt t st t t t tt t t tt t t tt t tt t st t t t t t t t t tat 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t t st tt tt t t tt t t t t tat 1 4
- PLANNING AUGMENTED EXAMINATION COMPONENT LISTING - 803-01 PAGE 3 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 250.$ - t
*tttttttttttttttttttttttttttttttttttttttttttttttt*tf REPORT-OUESTION INTERVAL 01'bNLY ttttttttttttttttttttttttttttttf DATE 88/01/$ 2 tttttttttttttttttttttttttttttttttt 9 '10 tat't CATEGORY SER SAFETY'VALUATION REPORT, SAFETY REVIEW OUESTION 11 ITEM NO. 250. 1S SAFETY EVALUATION REPORT, SAFETY REVIEW OUESTION 1250. 1 12 13 t tate t ttt t t tran ttt t t t t t tat't t t st t tt t t t t tt tt t stat t t t t st** t t t tt t t t st t t t t t st t tran t t t*tttt tt t t tt tt t t tate tt tt t t t t tt tat t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sasssassssssasasssssssss ssasssssssssass ararat sssassrssssssssa arras sasrr sssssrsr as srs arsasa ararat ararat 20 21 SYSTEM : CT CONTAINMENT SPRAY NUMBER: I I-CT-007 22 0.375'SOMETRIC 23 CT"FW-838 ELBSEAM PT 24.00 NO 24 25 CT-FW"83C ELBSEAM PT 24.00 0.375 NO 26 27 CT-FW-84A LNGSEAM PT 24.00 0.37S 28 29 CT-FW-848 ELBSEAM PT 24.00 0.375 30 31 CT-FW-84C ELBSEAM PT 24.00 0.375 32 33 CT-FW-85A LNGSEAM PT 24.00 0.375 NO 34 35 CT-FW"858 ELBSEAM PT 24.00 0.375 NO 36 37 CT-FW-85C ELBSEAM PT 24.00 0.375 38 39 CT-FW-86A LNGSEAM PT 24.00 0.375 NO 40 41 CT-FW-868 LNGSEAM PT 24.00 0.375 NO 42 43 CT-FW-87A LNGSEAM PT 24 00 0.37S F
44 45 CT-FW-878 TEESEAM PT 24.00 0.375 NO 46 47 CT-FW-89A LNGSEAM PT 16.00 0.375 48 49 CT-FW-898 TEESEAM PT 16.00 0.375 NO 50 51 CT-FW-97A LNGSEAM PT 08.00 0.322 NO 52 CT-FW-98A 08.00 0.322 53 54 ttttttttttttttttttttttttttttttttttttttt*tttttttttttttttttttttttttttttttttttttttttttttttttttttttt LNGSEAM PT NO 55 56 57 58 59 60
t t ttttt tt t t tt t ttt tt t t t t t tt t t t ttt t t t t t t tt t 't t t 't t' t t t t t t tt t tt t tt t tt t t t t t t t t t t t t t t t t tttt tt tt t t t t t t tt t t t tt t t tt t t t t t t t t tt t t
- NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 5
PLANNING 1 ttttttttttttttttttt AUGMENTED EXAMINATION COMPONENT LISTING B03-01 PAGE 5 6 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 7 REPORT QUESTION 250.1= INTERVAL 01 ONLY 8 't tt t tttt ttt t tt t tt t t ttt tt t t 'a t t tt t t ttt t tr t t t t t tt t t t t tt t t t' t tt t tt t t t t t ttt tt t tt ttt t t ttt t t t tt t t t t ttt t t tt t t tttt DATE 88/01/12 tt t t t t t t t 9 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1S SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 4250. 1 12 13 ttttt *t tt tt ttttt t t t t t t ttttt t t t t t t t tt tt tt t ttttt t t t t t t tt t t t t t tt t t t tttt t t t t t f ttt t t
- t ttt t t t t tt t ttt t t t t t t t tt tt ttt t 't t t t t t tr 14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 sass NUMBER ssssasssasssssssa DESCRIPTION sassssssssssass TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 aassas asssssssssasasss ss s sssss sssassss sassas sss ssaaaa ssssss ssssas 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-CT-007 22 23 CT-SW-M3B ELBSEAM PT 24.00 0.375 24 25 CT-SW-M3C ELBSEAM PT 24.00 0.375 26 27 CT-SW-M4A LNGSEAM PT 24.00 0.375 28 29 CT-SW-M4B LNGSEAM PT 24.00 0.375 30 31 CT-SW-N19A LNGSEAM PT 24.00 0.375 NO 32 33 CT-SW-N19B LNGSEAM PT 24.00 0.375 NO 34 35 CT-SW-N5A LNGSEAM PT 24.00 0.375 36 37 CT-SW-NSB ELBSEAM PT 24.00 0.375 NO 38 39 CT-SW-NSC ELBSEAM PT 24'.00 0.375 NO 40 41 CT-SW-020A LNGSEAM PT 24.00 0.375 NO 42 43 CT-SW-0205 LNGSEAM PT 24.00 0.375 44 45 CT-SW-025A LNGSEAM PT 24.00 0.375 46 47 CT-SW-025B LNGSEAM PT 24.00 0.375 48 49 CT-SW-06A LNGSEAM PT 24.00 0.375 NO 50 51 CT-SW-06B LNGSEAM PT 24.00 0.375 NO 52 53 CT-SW-07A 24.00 0.375 54 t t t t ttt t *rt tttt tt t tt t tr t t tttLNGSEAM PT rt t t t t t t t tt tt t tt t t tt t t t t ttt t t t tt tt t tt tt t tt t t t t t t
- ttttt t tt ttt t t t t tttt t t tt t t t t t t tt t tt t t t t It t t tt NO 55 56 57 58 59 60 FORM 0113 (02I83)
Ar 1 1 1 Al 1 4 tt 4 4 4 1 1 t 4 1 f 4 4 1 1 1 4 4 4 1 t 4 1 1 1 A 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 44 4 4 4 4 4 4 t 4 4 4 t 4 4 4 t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 *4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 1 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM Al SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 Al PLANNING 1tttf 114441 11111144 5 AI AUGMENTED EXAMINATION COMPONENT LISTING - 803-01 PAGE 7 1 6 AUGMENTEDEXAMINATIONOF PIPING PER SAFETY,EVALUATION lt 8 1 1 Al t t 4 t 1 1 t 1 4 1 4 f1 t Al AI 4 1 Al 1 1 1 1 'Al REPORT 'QUESTION 250."1- INTERVAL'Oil~ONLY t t1 1 1 1 1 1 1 t 4 1 1 t1 1 4 1
- AI 11114411 t1 Al t 1 1 1 4 1 4 1 1 4 1
- Ar 1 1 t Al 1 1111111 tt1 1 t11 111 4 1111 REVISION NRC1
'DATE 88/01/12 tt 1 4 4 1 1 t4 1 t t 1 4 Al AI Ar 41 9
10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 15 SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 1250. 1 12 13 *1 AI 1 1 f Al ~ 1 1 1 1 ff 4 Al 1 4 1 4 Al t 4 tf Al 4 lt Al 1 f 1 1 t 1 1 1 1 1 1 Al 1 1 It 1 1 1 Al f t 1 1 1 4 1 1 1 1 1 4 1 tft 1 1 1 1 4 1 Al 1 t 1 t 1 1 1 1 1 1 1 1 1 1 Al 4 1 1 t 1 4 Al 4 1 t 1 1 1 f 1 1 f 1 1 1 t *1 1 t 4 1 Al 1 1 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 aasssasssssssasasassaa NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 s asaasssssssases assess sssssaseesasssse safes sass ssssssss aaasss 1 4 = assess assess 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-CT-007 22 23 CT"SW-Q38 LNGSEAM PT 16.00 0.375 24 25 CT-SW-R3A LNGSEAM PT 14.00 0.375 28 27 CT"SW-R38 ELBSEAM PT 14.00 0.375 NO 28 29 CT-SW"R3C ELBSEAM PT 14.00 0.375 NO 30 31 CT-SW-S3A LNGSEAM PT 14.00 0.375 32 33 CT-SW-538 ELBSEAM PT 14.00 0.375 NO 34 35 CT-SW-53C ELBSEAM PT 14.00 0.375 36 37 CT-SW-T3A LNGSEAM PT 14.00 0.375 NO 38 39 CT-SW-T38 ELBSEAM- PT 14.00 0.375 NO 40 41 CT-SW-T3C ELBSEAM PT 14.00 0.375 42 43 CT-SW-T4A LNGSEAM PT 14.00 0.375 NO 44 45 CT-SW-T48 ELBSEAM PT 14.00 0.375 48 47 CT-SW-T4C ELBSEAM PT 14.00 0.375 NO 48 49 CT-SW-T5A LNGSEAM PT 14.00 0.375 NO 50 51 CT-SW-TSB ELBSEAM PT 14.00 0.375 NO 52 53 CT-SW-T5C 54 tt tt ttfef f 1 t 1 et Art et 11 ELBSEAM 41 PT 1 1 f t 1 1 tt t 1 t t44 1 1 tft t1t Art hatt 1 1 1 1 t ArfAlt et 11 114.00 0.375 4 4 tet ttftt 1 t tt 1 tttt ft t4t4 t41 t 1 1 tt f 1 1 11 tf4 tf1t4 1 f et f NO 55 58 57 58 59 80
W 1 t t f t ttt t tt t t ttt t t t ft tt t f tt t t t t' t t f t ft t t t t t' t t tt t. t t tt ft t f t t ft tt t tt t tt tt t t tt t t tt t t t tt t t t t' ft t t tt tt t t t t t tt f t' t t t t f t f t tt f F 2 NUTECH CAROI.INA POWER & LIGHT COMPANY PRISIM f 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 'I-f ftftff*ff 1 4 PLANNING staff sf sf 5 AUGMENTED EXAMINATION COMPONENT LISTING - 803-01 6 t AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION PAGE REVISION NRC1 8 7 REPORT QUESTION 250.1- INTERVAL 01 ONLY 8 t t t 't tt t ftt t tt t 't t t t t t t t t t tt ft tt t tt t ft f tt t tt t t t tft t tt t t t tf t t t tt tt t f t t t t ft t f t t t ft f t tt tt *t fft t t t tt ftt tf t t DATE t t t t t 88/01/12 ttttttttttt 9 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250.1S SAFETY EVALUATION REPORT. SAFETY REVIEW QUESTION JY250.1 12 13 ft t t tttt tt ft ff t t t t t t f t t tt tt t tt t t ttt ftt tt t tt t tt t t t t t t t tt t t t f t t ft t tt tt tt t f t ttt t t t tt tfft t t f t t f t t t t t ttftt t t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER sstlsssssssesaasstlsssss DESCRIPTION ssssssesssassss TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 assess s sssasesssssss asses asses sassasss assess sss assess assess assess 20 lF 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER : II-CT-007 22 23 CT-SW-T6A LNGSEAM PT 14.00 0.375 NO 24 25 CT-SW-T68 ELBSEAM PT 14.00 0.375 NO 26 27 CT-SW-T6C ELBSEAM PT 14.00 0.375 NO 28 29 CT-SW-T7A LNGSEAM PT 14.00 0.375 30 31 CT-SW-T78 ELBSEAM PT 14.00 0.375 32 33 CT-SW-T7C ELBSEAM PT 14.00 0.375 34 35 CT-FW-80 N021XO "PIPE PT 1-3-06 24.00 0.375 NO 36 37 CT-SW-J3 PIPE -ELB SR PT 24.00 0.375 NO 38 39 CT-SW-J12 ELB SR -PIPE PT 24.00 0.375 NO 40 41 CT-FW-82 PIPE -PIPE PT 24.00 0.375 NO 42 43 CT-SW-K3 PIPE -ELB LR PT 24.00 0.375 NO 44 45 CT-SW-K4 ELB LR -PIPE PT 24.00 0.375 NO 46 47 CT-FW-83 PIPE -ELB SR PT 24.00 0.375 48 49 CT-SW-L3 ELB SR -PIPE PT 24.00 0.375 NO
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50 I'3 51 CT-FW-84 PIPE -ELB SR PT 24.00 0.375 52 CT-SW-M3 54 f tt fft f tt t t t f t t tt ELBt t t ttSRt tt-PIPE tt t t tt tt t t t f I ttt tt t t tt f t 24.00 t tt t ff ft PT t t tt tt 0.375 t t t ft t t t f t tt t t t t
- tt t t **NO t tt t t t tt t 1 t t t t t t t t tt t t t 55 F.
56 57 58 59 60 FORM 0113 102I83) ~ I F t IIPlt pFP 'FFI 'I h<<g It)Fr t tg PFF IF P' t F P I t FPF tt
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f tt tf 4 t at at at t at f t t tft tff ftt at t tt t t at ttt t tat t t ttt f ff at tt sf at tt tft t t t tf' tf t t t t tt t tft aft tf ft tt t tf at f tt ft tftt t tft* NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1 ttfttttttttttttttft AUGMENTED EXAMINATION COMPONENT LISTING B03-01 PAGE 10 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1
'f REPORT QUESTION 250.1- INTERVAL 01 ONLY atttttt tat*tat*ttf tttttttttft ttttttttfttftttttttftttttftftfttfttttttfDATE ff tat88/01/12 attttf tfft 9
10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1S SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 8250. 1 12 13 ftftffttfttttttffttttttttttttttff ttttff*ttf*tttttttttttttfttttttttf ttf sf ttttttttffttiftttttttttttttt*tf fatt 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 18 NUMBER asssssaaasasssssssasssss DESCRIPTION assaassassaasss TYPE ssssss OULEO INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 aassssassassasss assss assaa asssssss aassss asa sassas sasssa ssssas 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-CT "007 22 23 CT-FW-88A REDSEAM PT 1-3-06 16.00 0.375 NO 24 25 CT-FW-88B LNGSEAM PT 1-3-06 16.00 0.375 NO 26 27 CT-SW-Q12 PIPE -PIPE PT 1-3-06 16.00 0.37S NO 28 29 CT-SW-Q3 PIPE -PIPE PT 16.00 0.375 NO 30 31 CT-SW-Q13 PIPE -PIPE PT 16.00 0.375 32 33 CT-FW-89 PIPE -RED TEE PT 16.00 0.375 34 35 CT-SW-P23 REO TEE-PIPE PT 1-3-06 14.00 0.375 36 37 CT-FW-53 PIPE "PIPE PT 1-3-06 14.00 0.375 NO 38 39 CT-SW-R3 PIPE -ELB LR PT 14.00 0.375 NO 40 tg 41 CT-FW-54 ELB LR -PIPE PT 14.00 0.375 NO 42 43 CT-SW-53 PIPE -ELB LR PT 14.00 0.37S NO 44 45 CT-FW-55 ELB LR -PIPE PT 14.00 0.375
'O 46 47 CT-FW-SSA LNGSEAM PT 14.00 0.375 NO 48 49 CT-FW-55B ELBSEAM PT 14.00 0.375 50 51 CT-FW-55C ELBSEAM PT 14.00 0.375 NO 52 CT-SW-T7 -ELB staff ttftttftttfPIPE 53 PT 14. 00 0. 375 54 tttttttf tat LR ~ tat ttttttf off tttftttttttttttatttfttsf f ttt tat tttttttfttftff ttttattf tattttttsf ttt 55 56 57 58 59 60 FORM 0'113 (02I83)
13 1 sf f f t ffff tftt ft f tft ftft t ttff tat t t f fff t t t t f *tft tt at f tf f f t tt tat t t f ft t t t t t tt t tttft tf ffft t'f t t ff tt fff t t f 4 ft t t f ff 2 NUTECH CAROLINA POWER 8r LIGHT COMPANY PRI SIN SHEARON HARRIS NUCLEAR POWER PLANT - ttfff ff ftfff at fat tft 3 UNIT 1 4 PLANNING AUGMENTED EXAMINATION COMPONENT LISTING 803-01
- PAGE 12 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 REPORT OUESTION 250. 1- INTERVAL 01 ONLY 88/01/12 fftt tff t ff fff t ft f f tfftt fftt tt ft ft t fftft f tft f ttt fff f fft f f t t*tt ft f t ft t f t f tftt f f't t f f t DATE t f t' fft t t t f tf t t f 9
10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW OUESTION 11 ITEM NO. 250. 15 SAFETY EVALUATION REPORT, SAFETY REVIEW OUESTION 8250. 1 12 13 sf t frff ff ff f tftfat f f f f t tftft ttfttff t t t ttfff at fff t tat tff tf f t I tttfff t*ftf t ff at ff tff tt ffst ft tt tf tf *at f f ft t t at f t sf t f f at f ft 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER ssaassaaasssssssssssssas DESCRIPTION ssssssssssssss TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sssssa sasasssssaassass ssssa sass asasssas sassas aas ssssss aassss asssss 20 2I SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-CT-008 22 23 CT-FW-63B ELBSEAM PT 14.00 0.375 NO 24 25 CT-FW"63C ELBSEAM PT 14.00 0.375 NO 26 27 CT-FW-99A LNGSEAM PT 08.00 0.322 NO 28 29 CT-SW-J24A LNGSEAM PT 16.00 0.375 30 31 CT-SW-J24B LNGSEAM PT 16.00 0.375 NO 32 33 CT-SW-J27A LNGSEAM PT 08.00 0.322 NO 34 35 CT"SW-J28A LNGSEAM PT 1-1-01 14.00 0.375 NO 38 37 CT-SW-J3A LNGSEAM PT 16.00 0.375 38 I 39 CT-SW-J38 TEESEAM PT 16.00 0.375 NO 40 41 CT-SW"J4A LNGSEAM PT 1-1-01 16.00 0.37S NO 42 43 CT-SW-J4B TEESEAM PT 1-1-01 16.00 0.375 NO 44 45 CT-SW-J5A LNGSEAM PT 16.00 0.375 46 47 CT-SW-J5B TEESEAM PT 16.00 0.375 48 49 CT-SW-J6A LNGSEAM PT 16.00 0.375 I 50 51 CT-SW-J6B TEESEAM PT 16.00 0.375 52 53 CT-SW-J7A 16.00 0.375 54 f ft ff f t f ttt ft ff fttTEESEAM t t ift f t tft f f f t ftfff PT f f t *f t' f f ff t f tt tt f fftt ff f f t f t*t t t ff f t f f f t tf f t t fftNOf ftt f f ff t tt fft t t **4 f f tf 55 I 58 57 58 59 80 I FORM 0113 [02I83)
ft ft t tff ff ff f tt t ft ttfft t tt f 4 t*ttff tttff tt tt tt tt t t tt t*t *St t*t t tff tftt t It tt t Ir t t tt t t t tt tt tttff ft tt tt t t t t fthm f tf t t t t f *Sf tt I I5 I 2 t NUTECH CAROLINA POWER 8r LIGHT COMPANY PRIS IM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 5 PLANNING AUGMENTED EXAMINATION COMPONENT LISTING - B03-01 ttfttftttttftfff tff 6 f AUGMENTED EXAMINATION OF PIPING PER SAFETYEVALUATION PAGE 17 7 f REPORT QlJESTION 250:1- INTE(IDEAL'-'1 ONt.Y REVISION NRC1 8 f f f tff f f f ff t tfff fttfttfttff f f tttftff tftftfttff tftftf tfttftftt tf ttttftt tf tttttftttftff fffDATE- 88/01/12 tftftt t t ttff tf f 9 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 1I ITEM NO. 250. 1S SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 8250. 1 12 13 t t t t f tt tf t t frtfft t t Stat t t tt ftt t t tt t f tt t t ft tt t t t t tf ttt t f t t t tt t t ftt tt t t tt t tt t tt t t t t tt tt t tt*tt*ttt t t ft tl ft 14 IS DONE 16 OUTAGE THIS DONE COMP 'OM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES
$ $ $ $ ~ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ 55$ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ ~ $ $ $ $ $ $ $ $ $ $ ~ $ ~ $ $ ~ $ ~ S $ $
19 $ SSSSSS $ $ $ $ ~ $ $ $ RSS ~ $ $ $ ~ $ $ $ $ 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-RH-001 22 ' 23 CT-14-4-SW-2 PIPE -PIPE PT 14.00 0.375 NO 24 25 CT-14-4-SW"2A LNGSEAM PT 14 . 00 0. 375 NO 26 27 CT-14-4" SW-2B LNGSEAM PT 14.00 0.375 28 29 CT-14-4-SW" 3 PIPE -PIPE PT 14.00 0.375 30 31 CT-14-4-SW-3A LNGSEAM PT 14.00 0.375 NO 32 33 CT-14-4"SW-3B LNGSEAM PT 14.00 0.375 NO 34 35 CT-SW-QB PIPE -ELB LR PT 14.00 0.375 36 37 CT-SW-Q7 ELB LR -PIPE PT 14.00 0.375 NO 38 , ~ 39 CT-SW-Q6 PIPE -ELB LR PT 14.00 0.375 NO 40 4'I CT-SW-Q5 ELB LR -PIPE PT 14.00 0.375 42 43 CT-SW-Q4 PIPE -ELB LR PT 14.00 0.375 NO 44 45 CT-SW-Q3 ELB LR -PIPE PT 14.00 0.375 46 47 CT-FW-57 PIPE -VALVE PT 1-1-01 14.00 0.375 NO 48 49 SYSTEM: CT CONTAINMENT SPRAY ISOMETRIC NUMBER: II-RH-002 50 51 CT-FW-61A LNGSEAM PT 14.00 0.375 52 CT-FW-61B 53 54 f ttrttfttttftf'ttff ttttttf ELBSEAM f tfttttttttttttttt'tttttttttttf PT tttftftttf 14.00 0.375 tttttttttttttt'*ftttftftttttttttttttttttt NO tttttfttf 55 56 57 58 59 60 FOAM 0113 102I83I
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19 1 1 ff1 1 ftftttf1'ftttttt*tftttftttf1 tf1 1'1 ftttttttttttfttfttt*tftf1 f1 1 ft tt tat tftftf1 tf1 ttt'f1ftftf1 ttftf1 tttf 2 NUTECH CAROLINA POWER 8r LIGHT COMPANY PR IS IM 3 SHEARON HARRIS NUCLEAR POWER PLANT = UNIT off tttftttfst 1 4 rlr PLANNING ttsttt AUGMENTED EXAMINATION COMPONENT LISTING 803-01
- PAGE 18 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 REPORT OUESTION 250. 1" INTERVAL 01 ONLY 11 f st ttftf1 ttf1 1 f tf1tf tf tfttt tf tftf tftt f t tf 11 1 1 11 1111 tftf tf11 t 1 1 1 1 st 1 tt tftf tftf 1 1 1 111 t sf 1 sf 1 1 1 DATE 88/01/12 1 tf1 1 1 ttf1 1 1 1 tf1 9
10 CATEGORY SER SAFETY EVALUATION REPORT. SAFETY REVIEW QUESTION 11 ITEM NO. 250. 15 SAFETY EVALUATION REPORT, SAFETY REVIEW OUESTION @250. 1 12 13 11 sf t*tft 1 t tf1 1 1 1 tf t1 1 1 1 1 1 tf t*f 1 '1 1 1 *1 1 1 sf 1 1 t 1 1 1 t 1 1*1 tf 1 1 t f 1 1 1 t*f1 1 11 *1 1 1 1 tf 1 1 tf 1 1 1 1 1 1 1 1 1 1 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT NUMBER'OMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 aasssssa aaasssssassssa DESCRIPTION ssssssssassssas TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 20 sas aa ssssaasasssssasa assss fasts asssasss sassss ssa aaaass -- sassas 21 SYSTEM: CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-RH-002 22 23 CT-FW-61C ELBSEAM PT 14.00 0.375 24 25 CT-FW-62A LNGSEAM PT 1-3-96 14.00 0.375 NO 26 27 CT-SW-P3A LNGSEAM PT 14.00 0.375 NO 28 29 CT-SW-P38 ELBSEAM PT 14.00 0.375 NO 30 31 CT-SW-P3C ELBSEAM PT $ 4.00 0.375 32 33 CT-SW-P4A LNGSEAM PT 14.00 0.375 NO 34 tat 35 CT-SW-P48 ELBSEAM '14.00 0.375 1fftffttftfftfsfftfttt*f1tsf PT NO 36 37 CT-SW-P4C ELBSEAM PT 14.00 0.37S NO 38 39 CT-SW-P5A LNGSEAM PT 14.00 0.375 40 41 CT-SW-PSB .ELBSEAM PT 14.00 0.375 NO 42 43 CT-SW-PSC ELBSEAM PT 14.00 0.375 44 45 CT-SW-P6A LNGSEAM PT 14.00 0.375 NO 46 47 CT-SW-P68 ELBSEAM PT 14.00 0.375 48 49 CT-SW-P6C ELBSEAM PT 14.00 0.375 50 51 CT-SW-P7A LNGSEAM PT 14.00 0.375 NO 52 CT-SW-P78 53 54 ftff ELBSEAM PT 14.00 0.375 ttfttftf sf f1 tttff1ttttfftttttftf ftfffttf ttftf*ff NO ttfftft*fftff tttf staffs 55 56 57 58 59 60 FORM 0113 102I83)
21 at f Srf ff t t t*fSrf f t tftftff at t tat f at tff f tff f t t ff f f t f tf at ft t ttr f f fft t f t I f f fthm t t tt t t f t tf t t tff tt ff ff t f tt NUTECH t't t t et t sf ft t f t CAROLINA POWER 8 LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING tt'tftftttft'fttft 5 AUGMENTED EXAMINATION COMPONENT LISTING - B03-01 PAGE 20 6 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION t REPORT QUESTION 250. 1- INTERVAL 01 ONLY REVISION NRC1 sf fff ft'f 'f t't t t t't f tat f t tft ft tt tt fff tfftff tffffft tf at f f tftff f fff t t f tf f sf at tff f tft t tff f ff ff ft t fff ffff fDATE Srf f 88/01/12 t et t tttf t t tt fff f 9 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 15 SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 1250. 1 12 13 f*frfrat tfrftfSrf f ttff tfSrf rSf f tftftf'attf at sf ff f tttftftfttftttfSrSrtf ttff Srtrf SrtSrf tft*ttttft ff ftftat tSrtf fat tt*tf*ttSrtff at t'Srtf ff 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER aesassssssassssasasssssss DESCRIPTION sssssasasssasse TYPE OULEO INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 assess eases ssaaassas asses asses asaesees e seas ses s s essa assess 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-RH-002 22 23 CT"SW-QGB LNGSEAM PT 14.00 0.375 NO 24 25 CT-SW-Q7A LNGSEAM PT 14.00 0.375 26 27 CT-SW-07B ELBSEAM PT, 14.00 0.375 NO 28 29 CT-SW-07C ELBSEAM PT 14.00 0.375 NO 30 31 CT-SW-Q3 ELB LR -PIPE PT 14.00 0.375 32 33 CT-SW-Q4 PIPE "ELB LR PT 14.00 0.375 34 s: 35 CT-SW-Q5 ELB LR -PIPE PT 1'4.00 0.375 38 37 CT-SW-QG PIPE -PIPE PT 14.00 0.375 NO 38 39 CT-SW-Q22 PIPE -PIPE PT 14.00 0.375 NO 40 41 CT-SW-Q7 PIPE -ELB LR PT 14.00 0.375 NO 42 43 CT-FW-61 ELB LR -PIPE PT 14.00 0.375 NO 44 45 CT-SW-PB PIPE -ELB LR PT 14.00 0.375 48 47 CT-SW"P7 ELB LR -PIPE PT 14.00 0.375 48 49 CT-SW-P6 PIPE -ELB LR PT 14.00 0.375 NO 50 51 CT-SW-P5 ELB LR -PIPE PT 14.00 0.375 52 CT-SW-P4 53 54 tftftftttttttf PIPE tf-ELB f ttftfttff ttfet attf ttftff tfttttttf14.00 LR PT 0.375 tat f tfft tat st ttttttfttttfttttfttt tttttttftff tftff tf NO 55 I 56 57 58 I 59 60 FORM 0113 {02I83) dv lvArvl t" Il
- ef rv r ' 'vvr \ rvv vvl 0 vw vss ~ >> vlvvv . prv . v ~ ~ " S V ~ ~ l l ~ ~ VVV ~ ~ V ~ . ~
44 tttttf 11 ttttf1t'44444ttttf 144ttttttt4tttf t41441 ttttt4444ttf tttttttf4ttttftttt4ttttf1ttttfttttt st ttttttttttttt ttttt14tt 2 NUTECH CAROLINA POWER 5r LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 ~ PLANNING f 14 1 4 4 4 ttf11 f 444f 4 1 5 AUGMENTED EXAMINATION COMPONENT LISTING 803-01 PAGE 21 4 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 REPORT OUESTION 250. 1- INTERVAL 01 ONLY 1 tf1 tttf1 tftttt44444ttt'41 ttt44141 4 411*1 tf4411 4444441 tttttfttt tttttt414441144411t4tf tttftttt114'44411 DATE 88/01/12 11 4 4441 f* 9 10 CATEGORY SER SAFETY EVALUATION 'REPORT. SAFETY REVIEW OUESTION 11 ITEM NO. 250. 15 SAFETY EVALUATION REPORT, SAFETY REVIEW OUESTION 4l250. 1 12 13 411 11f tff 44 141ttf 1 ttt tfrttf4 1 1 1 tff1ttf44*1411tttttt4t4t4414 4 t1ttf 4411441tttttt411ttttf 4 4tf 11 414 1 ttttttttf44 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER sssssssssaassssssssrsss DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 ~ ssssssssssssssa ssrsaa ~ ~ srasrrasss arras ssasr ssrasrrs starts asr saasas sssass sssssr 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER : II-RH-002 22 23 CT-SW-P3 ELB LR -PIPE PT 14.00 0.375 NO 24 25 CT-FW-62 PIPE -VALVE PT 1-3-06 14.00 0.375 NO 28 27 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-SI-009 28 29 CT-FW-95 VALVE -PIPE PT 08.00 0.322 30 31 CT-16-14" SW-1 PIPE -PIPE . PT 8.00 0.322 NO 32 33 CT-SW-H3 PIPE "ELB LR PT 1-2-03 08.00 0.322 NO 34 35 CT"SW-H4 ELB LR -PIPE PT 08.00 0.322 36 37 CT-SW-HS PIPE -ELB LR PT 08.00 0.322 38 39 CT-FW-96 ELB LR -PIPE PT 08.00 0.322 NO R2-001 40 41 CT-SW-I3 PIPE -ELB LR PT 08.00 0.322 42 43 CT-SW-I 3A LNGSEAM PT 08.00 0.322 NO 44 45 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-016 4I6 47 SI-138-4-SW-1 ELBOW -PIPE PT 02.00 0.344 NO 48 49 SI-138-4" SW-2 PIPE "ELBOW PT 02.00 0.344 NO 50 SI -139-2-SW-3 -P 02.00 0.344 51 52 ttf t taft tf 4 4 4 4 444 P BEND tf4 tf4 4ttttfttt4 4 4 tttftf44 4tttf ttftf tttfttttttttttf BEND PT tf4 tttf4 tt 444 ttt f4 4 444444 NO 4 44444444 4 ttttfr4ttf 4444 53 54 55 56 57 58 59 60 FORM 0113 (02I83)
23 1 tffff tf ff ftftt t tfff fffff ftt f ftftff at fffft t ff fff f ff ftftff tfttftff f'fftff t fthm t tat t tt f ft f ft ft f tffrtff tf tf t tft t t t t t ffffff ff 2 NUTECH CAROLINA POWER & LIGHT COMPANY 3 t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PRISIM
~ 4 f
1 ttttftttttffttttttf f'LANNING 5 AUGMENTED EXAMINATION COMPONENT LISTING - 803-01 PAGE 22 6 AUGMENTED EXAMINATION OF PIPING PER,SAFETY EVALUATION REVISION NRC1 7 REPORT QUESTION 250.1" INTERVAL 01 ONLY 8 *ff tft fff fff tftftfff tff f f fffffff f t tttft tff ff f tf tt t t f f'ft tff f ff f tf f f tftt f f f f t tft tff ftff tftf ff t ffff t f ff ftDATE ff *f88/01/12 t f tft ff f ff f 9 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1S SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 1250. 1 12 13 tftfff at tfff fff at at ff tffff tat tfffff tttftfftftfttttff ttfff tfsf ttff f at ftt t sf at tf tf*tfttftttftfff f f ttff tttftftt*tft 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER rsssssssasssssrsssasssss DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sssssssrasssars arssss ssaaasssassassss rafts astra srssssss ssssas sss ararat sssrar srssss 20 21 22 SYSTEM: SI SAFETY INIJECTION ISOMETRIC NUMBER: II"SI-016 23 SI" 139-2-SW-5 PIPE -COUPLNG PT 02.00 0.344 24 25 SI-139-2-SW-6 COUPLNG-PIPE PT 02.00 0.344 28 27 SI-SW-D7 PIPE -COUPLNG PT 02.00 0.344 28 29 S I-F W-397 COUPLNG-P BEND PT 02.00 0.344 NO 30 31 SI-SW-I12 P BEND -ELBOW PT 02.00 0.344 NO 32 33 SI-SW-I 11 ELBOW -PIPE PT 02.00 0.344 NO 34 35 SI-SW-I10 PIPE -ELBOW PT 02.00 0.344 NO 36 37 SI-SW-I9 ELBOW -PIPE PT 02.00 0.344 NO 38 39 SI-FW-398 PIPE -COUPLNG PT 02.00 0.344 NO 40 '! 41 SI-SW-d8 COUPLNG-P BEND PT 02.00 0.344 NO 42 43 S I -F W-399 P BEND -COUPLNG PT 02.00 0.344 NO 44 45 SI-SW"K7 COUPLNG-P BEND PT 02.00 0.344 NO 48 47 SI-FW-400 P BEND -COUPLNG PT 02.00 0.344 NO 48 49 SI-SW" L7 COUPLNG-PIPE PT 02.00 0.344 NO 50 51 SI-SW-L16 PIPE -P BEND PT 02.00 0.344 52 SI-FW-402 53 54 tff f ftfff t tttftfff *ffft tftf tfff ttff t tt ffftf ftff fff at f fft tff ttt f ftf02.00 P BEND -COUPLNG PT f fft f0.344 fthm f tftf ftt t t t tf ff 'at tf ft f fff f f f t t tff ff fff f I tffNO 55 56 57 58 59 60 FORM 0113 (02I83)
. ~ ~ ~ ~ . ' '
24 1 f1 et 414 41 tf4141 tf1 ~ *1 tf4tf 1 1 f tfrf1 4 111 444ttf 1tf 14444 4 1441 44 t et f 1 tftf4t1 44 tf1 tf444141 14 41 1 14 tt 144 411 441 44 tt tf1 1*4 1 f1 1 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 4 PLANNING *1 4 1 4 1' 4441 t4 tt4 1 1
- 5 AUGMENTED EXAMINATION COMPONENT LISTING - 803-01 PAGE 23 6 AUGMENTED EXAMINATION OF PIPING PER SAFETY, EVALUATION REVISION NRC1 7 REPORT QUESTION 250. 1- INTERVAL 01 ONLY 8 ttttttftf4444 tt tat tt tttftf 44 f4 tf4 4 4 tf4 4 4 ttet ttfttf4 4 ttttfet f4 4444 ttftftt tttf44 4 4 tf4444 4 OAfE 88/01/12 tat 4 tttttttttttttt4 9
10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 15 SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 8250. 1 12 13 141 tet 4 t 4 fr t t1 1tf 4 tttt 4 tf1f 1 1 at f 4 1 11 tfrt 4 41 1 44 tt 11 411 1 1 1 11 et 4 tf4 14 1 411 4111 1 11 444 4 4 1 4 1 tf 1414 1 114 frt tt 14 1 1 1 41 1 1 1114 at f41 1 14
'IS DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 assssassassasssasassssas sssssssssssssrs assess ssasssrsaas s r- sears sears sa sees assess aas assess assess arrear ~ 20 21 SYSTEM: SI SAFETY INIJECTION ISOMETRIC NUMBER: II-SI-016 22 23 SI-SW-M6 COUPLNG-P BEND PT 02.00 0.344 24 25 SI-139-2-SW-1 P BEND -P BEND PT 02.00 0.344 26 27 SI-139-2-SW-4 P BEND -P BEND PT 02.00 0.344 NO 28 29 SI-139-2-SW-7 P BEND -ELBOW PT 02.00 0.344 30 31 SI-FW-401 ELBOW -PIPE PT 02.00 0.344 NO 32 33 SI-191-1-SW-1 PIPE -FLG WNO PT 02.00 0.344 NO 34 35 SI-SW-03 FLG WNO-PIPE PT 2.000 0.344 36 37 SI-FW-915 PIPE -VALVE PT 02.00 0.344 NO 38 39 SI-FW-916 VALVE -PIPE PT 02.00 0.344 NO 40 41 SI-FW-917 PIPE -VALVE PT 02.00 0.344 42 43 SI-SW-08 PIPE -COUPLNG PT 02.00 0.344 44 45 SI-FW-403 COUPLNG"P BEND PT 02.00 0.344 46 47 SI-SW-Q7 P BEND -P BEND PT 02.00 0.344 48 49 SI-SW-Q3 P BEND -COUPLNG PT 02.00 0.344 NO 50 I
51 5 -F W-404 COUPLNG-P BEND PT 02.00 0.344 NO 52 53 SI-SW-D9 PIPE -SOCKOLT PT 1-2-03 03.00 0.438 t t t f f f t t NO t 54 1 1 1 4 1 1 1 1 1 4 1 1 1 4 1 1 4 1 1 4 1 1 1 1 1 4 1 4 4 1 4 1 4 4 4 1 1 1 tr 1 1 1 1 4 4 1
- 4 4 1 4 1 1 4 1 1 4 4 1 4 1 4 1 1
- 1 1 4 1 1 1 1 1 4 4 1 1 1, 4' 1 4 1 1 1 1 1 1 1 1 1 4 4 1 1 1 4 4 1 1 1 1 1 1 4 1 1 1 55 56 57 58 59 60 FORM 0113 (02/83I I
35 1 f f f ff tfftttff f ff tff tff tftttfff tttff f tttff t tftf f ttttftttff sf tttttff ff f tttttttftt t*ttff tft f ttt tt ft tttftt ttt f ttttt ttftft 2 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM
*3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING ft ff *tf lll f t ffff ff f 'f 5 AUGMENTED EXAMINATION COMPONENT LISTING - 803"01 PAGE 34 6 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION f REPORT QUESTION 2S0.1- INTERVAL 01 ONLY REVISION NRC1 7
8 tfffffffff ff tff f tfff ff ff f ftfft f tt f tt f ff t t ff f tft t ff f f tftff f f tfftffffff t f t t'ft tt t t f tffff ttf*ff ft t*ff t t ffft DATE 88/01/12 f tt t fffff tat t 9 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 15 SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION JF250. 1 12 13 t ffft f t ffffft t fft t t ft t f fft t tf *ff t ftff I ftt f ff f ffft f ff f fffft tt ft f ft f t tt ftffffft ft tf t ffff f' f f t f f' t t ff f t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 asasasssas NUMBER ssssssassssss DESCRIPTION ssasssasaasasss TYPE DULED INT INT, (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sssass aasssasssssssasa s aas s = ssssssas ssssss sss asssss sss aa ssasss 20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-032 22 23 SI-FW-976 PIPE -ELBOW PT 02.00 0.344 24 25 SI-SW-F7 ELBOW -P BEND PT 02.00 0.344 26 27 SI-SW-F10 P BEND -P BEND PT 02.00 0.344 NO 28 29 SI-SW-F6 P BEND -COUPLNG PT 02.00 0.344 NO 30 31 SI-FW-977 COUPLNG-P BEND PT 02.00 0.344 NO 32 33 SI-SW-ES P BEND -COUPLNG PT 02.00 0.344 NO 34 35 SI-FW-978 COUPLNG-P BEND PT 02.00 0.344 NO 36 37 SI-SW-D3 P BEND -FLG WNO PT 02.00 0.344 38 39 SI-SW-C3 FLG WNO-PIPE PT 02.00 0.344 NO R2-001 40 41 SI-FW-979 PIPE "VALVE PT 02.00 0.344 NO R2-001 42 43 SI-FW"980 VALVE -PIPE PT 02.00 0.344 44 SI-FW-981 -VALVE 1-1-01 f f f f f tff tfPIPE 45 46 f at f t tt f f ffft tff ffPTf tfff fff f f t ffft tff tft t t02.00 0.344 NO at f f f tf t f tft tt t t t f f ff f f f t ft f 4 f tf ft f f sf ft ff t f f f at f tf f 47 48 49 50 51 52 53 54 55 56 57 58 59 80 >9 Jbb4 FORM 0113 {02I83)
~Vr 0 f/'b ar ~ .r h (% b ~ hbbJ hrr'E rbrbb b, t ~ a f 6 V. Cher+ rh rb h r, b ~ h, b' ! b
36 tftf t t ftt ttt t tft t' 't rt tr tt t t t tf rlr rlr t' t ff f tt tt t ft tt t ttft tt t 'f ttt f *t t tt t t t ftt t t t t t t t t tt ttt tt t t t tt t t t t ft f t t ftt t t ttt tf *t t t t t ttt NUTECH CAROLINA POWER & LIGHT COMPANY PR IS IM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT t t PLANNING 1 tfftttfttttfttttttt AUGMENTED EXAMINATION COMPONENT LISTING B03-01 PAGE 35 AUGMENTED EXAMINATION OF, PIPING PER ISAF~ETY.EVALUATION t REPORT OUESTION 250.1-'NTERVAL-'01 bNLY REVISION NRC1
't at fr tat*a t at t f tf tt t t t t t t t t ft f at tftt ft t sf t t t t tt t t t at f t*ft f tt tt t tt ffft t tt t t ff t t f t tt t aft tt t t tt tt t t tf t at DATE tt t tt 88/01/12 t t t t ft ttttt 9
10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW OUESTION 11 ITEM NO. 250.1V SAFETY EVALUATION REPORT, SAFETY REVIEW OUESTION 1250.1 t ft t t t*t*tfat at t at f tf t tat t f'at t f *t tat aft t t tt t t t tt't at 12 13 at t at tt t t t t t f t t t ft tt t f t t*t tat t tf t at at tt t t tft t t t f f *tat t t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) ( IN) ACCESS SELECT IND REQST TIONS NOTES 19 saaasaassasssassssssssss ssssrsrasssasaa ararat sa saasaaaasssss stars arras saasasss strata ssa ararat ararat rsssas 20 21 SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-006 22 23 CS-141-2-SW-2 PIPE -PIPE UT-455 04.00 0.531 24 25 CS-FW-126 PIPE -RED TEE UT-455 03.00 0.438 NO R2-003 26 27 CS-FW-202 VALVE -PIPE UT-455 04.00 0.531 NO R2-003 28 29 CS-SW-F4 PIPE -RED TEE UT-45S 04.00 0.531 NO R2-003 30 31 CS-SW-F3 RED TEE-PIPE UT-45S 04.00 0.531 NO R2-003 32 33 CS-FW-201 PIPE -VALVE UT-45S 04.00 0.531 NO R2-003 34 35 CS-FW-132 VALVE -PIPE UT-455 04.00 0.531 NO R2-003 36 37 CS-FW-131 PIPE -VALVE UT-455 04.00 0.531 NO 38 39 CS-FW-130 VALVE -PIPE UT-45S 04:00 0.531 NO R2-003 40 41 CS-SW"D5 PIPE -REO TEE UT-45S 04.00 0.531 NO R2-003 42 43 CS-SW-D4 RED TEE-PIPE UT-455 04.00 0.531 NO R2-003 44 45 CS-141-2-SW-1 PIPE -ELB LR UT-45S 04.00 0.531 NO 46 47 CS-FW-129 ELB LR -PIPE UT-455 04.00 0.531 48 49 CS-SW-I/6 PIPE -PIPE UT-45S 04.00 0.531 NO 50 51 CS-SW-d3 PIPE -ELB LR UT-455 1-1-01 04.00 0.531 NO 52 <<? CS-FW-128 53 ftt*ttttttttff ttttttft'ttfELB frttfLRrff-PIPEfrttftttfUT-455 1-1-01 04.00 0.531 54 sf ttt tat'ttf tttttttttttIrtttttf tttftttft at ttttttfttt'tfNO f ttrtfattttttttf ttttt tat 1 55 56 57 58 .I 59 60 iI 4,
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38 44 t4 4 4 4t 4444 444 44 t4 4 tf444 4 444 44 t tftf4 tft4 4 4 t 4 tft4 4 4 4 4 4 4 t4 4 4 4 4 t f 4 4 4 4 444'4444 4 4 4 4 tt 4 4 4 4 4 4 4 4 4 t 4 tt 4 4 4 4 4 t f 44 4 t4t4 4 4 NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING 1 ttftttfttf44 4'tf tttt 5 AUGMENTED EXAMINATION COMPONENT LISTING - B03"01 PAGE 37 6 AUGMENTED EXAMINATION OF PIPING PER SAFFT)'.EVALUATION REVISION NRC1 REPORT QUESTION 250. 1- INTERVAL 01 ONLY 8 4 4 4 4 4 44444f Sf'ttttftf 44444 ttttfttf 44tf t ttf 4 tttf tfttftttfSt*f 4 4 44 tt444 tttf 4 4f 44tttf f4tttfDATE 88/01/12 4 4444ttf tf4 4 tf t 9 10 CATEGORY SER SAFETY EVALUATION REPORT. SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1V SAFETY EVALUATION REPORT. SAFETY REVIEW QUESTION 4'250. 1 12 13 444 t t 4 4 f 4 4 tt 4 4 4 t 4 f 4 4 4 4 4 4 4 4 4 4 t 4 4 f 4 4 4 4 4 fr ft 4 4 t t 4 4 4 4 4 t 4 4 t 4 4 4 t t 4 t 4 4 4 4 4 4 4 4 t t 4 4 ft 4 4 4 4 4 4 4 4 4 4 4 4 t 4 4 f 4 4 4 4 4 t 't 4 4 4 4 4 4 t tr 4 4 4 4 4 4 I4 4 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN)
$ $ ~ $ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ ~ 4 $ $ $ $ ~ $ $ $ '$$ ~ $ $ $ $ ~ $ $ $ $ $ 4 ~ $ $ $ $ $ $ $ $ $ ~ $ $ $ ~ $ $ $ $ $ $ $ $ $
ACCESS SELECT IND REQST TIONS NOTES 19 S 4'$$ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ $ ~ 4 ~ '$$ $ $ $ $ 20 21 SYSTEM : CS CHEMICAL ANO VOLUME CONTROL ISOMETRIC NUMBER: I I-CS-006 22 23 CS-FW-103 VALVE -PIPE UT-45S 03.0b 0.438 NO R2"003 24 25 CS-FW-104 PIPE -VALVE UT-455 03.00 0.438 NO R2-003 26 27 CS-FW-105 VALVE -PIPE UT-45S 03.00 0.438 NO R2-003 28 29 CS-146-3-SW-2 PIPE -ELB LR UT"45S 03.00 0.438 NO 30 31 CS-146-3-SW-1 ELB LR -PIPE UT-455 03.00 0.438 32 33 CS-FW-106 PIPE -TEE UT-455 03.00 0.438 NO R2-003 34 35 SYSTEM: CS CHEMICAL ANO VOLUME CONTRQL ISOMETRIC NUMBER : II-CS-007 36 37 CS-SW-A3 FLG RFW"REDUCER UT-45S 03.00 0.438 NO R2-003 38 39 CS-SW-D7 TEE -REDUCER UT-455 04.00 0.531 NO R2-003 40 41 CS-SW-A4 REDUCER"PIPE UT-455 03.00 0.438 NO R2"001 42 43 CS-145-1-SW-1 PIPE -ELB LR UT-455 03.00 0.438 NO 44 45 CS-SW-A6 ELB LR -PIPE UT-455 03.00 0.438 46 47 CS-FW-92 PIPE -VALVE UT-45S 03.00 0.438 NO R2-003 48 49 CS-FW-93 VALVE "PIPE UT-455 03.00 0.438 NO R2-003 50 Sl CS-FW"94 PIPE -VALVE UT-45S 03.00 0.438 NO R2-003 52 53 CS-FW-95 VALVE -PIPE UT-45S 03.00 0.438 R2-003 54 4 4 4 4 4 4 4 4 4 444 444 4 tf 4 4 4 4 4 4 44 4444 444444 tf4 4 4 4 44 4 4 4 4 4 4 4 4 4 4 4 tf4 4444 tf4 444 NO
*4*4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 44 44 4 4 tf4 4 55 56 57 58 59 60 FORM 0113 {02I83)
.0
43 t 1 1 1 *1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 t 1 1 1 1 t 1 1 1 1 1 1 1 t 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 t 1 1 1 1 1 *1 t 1 t 1 t 1' 11111111 t 1 t 1 t 1 1 t 1 t t 1 1 1 *1 1 1 1 1 1 NUTECH CAROLINA POWER & LIGHT COMPANY PR I SIN 1 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING ~ tttftttttttttftttf 1 5 AUGMENTED EXAMINATION COMPONENT LISTING - B03-01 8 t AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION PAGE REVISION NRC1 42 7 REPORT QUESTION 250. 1- INTERVAL 01 ONLY 8 '1 '1 f f 1 111 11 1111111 t f 1 1 1 1 1 t 1 t 1 1 1 1 *1 1 t t 1 t 1 1 1 f t 1 t 1 t 1 t t 1 t 1 1 1 1 1 1 1 tf 1 1 1 1 1 1 1 t 1 t 1 t t 1 1 1 1 1 1 1 t 1 1 1 1 1 1 t 1 1 1 1 1 t 1 1 1 1 f 1 1 1 1 1 88/01/12 At DATE 1 1' t 1 f 1 1 1 1 1 9 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 8250. 1 12 13 1 1 at 1 t1 t fr 1 t tt 1 1 1 1 tt ttt 1 111 t 1 1 t at t t tt 1 tt tt 1 11 1 t 1 1 1 1 1 1 1 11 1 1 1 1 1 1 t 1 t st f 1 1 111 f1 1 1 1 11 1 1 1 1 t 1 1 1 1 1 1 1 1 1 tf 1 1 f1 tt 1 1 1 1 1 1 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER ssaasssssasssssarasssass DESCRIPTION TYPE DULED INT INT (IN) ( IN) ACCESS SELECT IND REQST TIONS NOTES 19 ssaassaasaasass arras ra sass ssssrsa arras saasr rssassas saasaa sss aar aaaars ararat 20 21 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER : II-CT-001 22 23 CT-SW-E4 PIPE "PIPE UT-455 08.00 0.322 24 25 CT-FW-6 PIPE -ELB LR UT-455 08.00 0.322 NO 26 27 CT-SW-F6 ELB LR -PIPE UT-455 08.00 0.322 NO 28 29 CT-SW-FS PIPE -ELB LR UT-455 08.00 0.322 NO 30 31 CT-SW-F4 ELB LR -PIPE UT-455 08.00 0.322 NO" 32 33 CT-SW-F3 PIPE -ELB LR UT-455 08.00 0.322 NO 34 35 CT-FW-7 ELB LR -PIPE UT-45S 08.00 0.322 36 37 CT-SW-G4 PIPE . -ELB LR UT-455 08.00 0.322 NO 38 39 CT-SW-G3 ELB LR "PIPE UT-45S 1-3-06r 08.00 0.322 NO 40 41 CT-FW-8 PIPE -VALVE UT-455 1."3-06 08.00 0.322 NO R2"003 42 43 CT-FW-9 VALVE -PIPE UT-45S 1-3-06 08.00 0.322 NO R2-003 44 45 CT-FW-10 PIPE -FL HEAD UT-455 1-3-06 08.00 0.322 NO 46 47 SYSTEM: CT CONTAINMENT SPRAY ISOMETRIC NUMBER: ~ I I -CT-002 48 49 CT-FW-12A LNGSEAM UT-455 08.00 0.322 NO 50 51 CT-FW-16A LNGSEAM UT"455 08.00 0.322 52 53 CT-FW"20A UT-455 1-3-06 08.00 0.322 54 Atf ttfttfttttftttAtftttf1 aftLNGSEAM tttf1 tff 11 ttttttt f ttf1AtAtttttttt111111111111 t f1 ttt*ttttAttf1 11tf tttttttt st tf st frttttf tttttf NO 1At 55 58 57 58 59 60 FORM 0113 I02I83) trta ivy y.r>>. p tr = 't r . t -
",rrrt rtrt, 'gK %pert t ~. rS ~ rS rr i iw ti't, r ~ 4 \ r*IR 5 r S '",1 t tr- ~ - r,;,'t ~ 4 ~ g t K rr K(tp'.. ~ ". S't .! Pp,tt ', ~
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4b t*f'1111 1 1 1 11 tt1 1 1 1 tt 1 1 1 1 1 t 1 1 t*f1 t f1 1 1 1 1 11 1 t t1 1 1 1 f 1 1 1 1 1 f 1 1 1111 1 1 1 f 11 1 1 1 tf1 t 1 1 1 1 11 1'tf 1 1 1 1 1 1 1 f 1 11 f1 1 t 1*1 1 1 1 1 t 1 1 1 1 1 11 1*t1 2 t NUTECH CAROLINA POWER & LIGHT COMPANY PRI SIN 1 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 1 PLANNING t 1 '1
- 1 1 1 '1 1 1 1 1 1 tt '1 1 1 '1 5 AUGMENTED EXAMINATION COMPONENT LISTING B03-01 PAGE 45 AUGMENTED EXAMINATION OF PIPING, f?ER SAFETY., EVALUATION REVISION NRC1 7
ttf1 REPORT QUESTION 250. 1- IATERVAt. tf1 tttff1tf1 ff tftftttf ttttfttttf tf ff tttf1 ttft ttf tff ttttf 01'ILY 9 1111 11 111 11 1'1 1 f ttftfkftf ttttf1tftttttftfDATE 1 1 tttf88/01/12 1 tf1 f1 tf1 1 t 10 CATEGORY SER SAFETY EVALUATION REPORT. SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 1250. 1 12 13 1 ttttftf1 ttfftttf1111 11 tftf1tf1 ttttftttttttftf tttttttftf 1 1tf tttf tttttf1 111 tttf 111 1tfttttfttfttft*ftttfttftt f1 f1 1 1 1 1 1 1 1 14 15
'6 OUTAGE DONE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ '$ ~ $ $ $ $ $ $ ~ $ $ $ $ $ $ $ ~ $ $ ~ $ $ $ $ ~ $ $ $ ~ $ $ $ $ $ $ $ $$$ $$$~$~ $$$$$$ $$$$$$
20 21 SYSTEM : CT 22 CONTAINMENT SPRAY ISOMETRIC NUMBER: I-CT-002 I 23 CT-FW-22A VENTURI-PIPE UT-455 08.00 0.322 NO 24 25 CT-SW-B24 PIPE -PIPE UT-45S 08.00 0.322 26 27 CT-SW-B5 PIPE -ELB LR UT-455 08.00 0.322 28 29 CT-SW-84 ELB LR -PIPE UT-455 08.00 0.322 NO 30 31 CT-SW-B3 PIPE -ELB LR UT-455 08.00 0.322 32 33 CT-FW-14 ~ ELB LR -PIPE UT-455 08.00 0.322 NO 34 35 CT-1-3 "SW-1 PIPE -PIPE UT-45S 08.00 0.322 38 37 CT-SW-C3 PIPE -PIPE UT-455 08.00 0.322 NO 38 39 CT-SW-C4 PIPE -RED TEE UT-45S 08;00 0.322 NO 40 41 CT-SW-CS RED TEE-PIPE UT-45S 08.00 0.322 NO 42 43 CT-FW"15 PIPE -ELB LR UT-455 08.00 0.322 NO 44 45 CT-SW-D5 ELB LR -PIPE UT-455 08.00 0.322 46 47 CT-SW"DB PIPE -PIPE UT-45S 08.00 0.322 NO 48 49 CT-SW-D4 PIPE -ELB LR UT-45S 08.00 0.322 50 51 CT-SW-D3 ELB LR -PIPE UT-455 08.00 0.322 52 CT-FW-16 -ELB t f1 1 t f1 11 1 1 1 1 1t1 1 1 t f1 PIPEt 11 f 1tf 1 tt 1 11LRt tfUT-455 tfftf1 1 1 1 1 1 1 1 11 1 1 1 1 t 1 tf 1 f08.00 53 0.322 NO 54 1 1 1 1 f 1 1 1 1 111 tt 1 11 f 1 t 1 1 t 1 1 1 1 1 tft f1 1 f 1 tt 1 t 1 1 1 tf1 1 1 1 1 11 1 55 56 57 58 59 60 FOAM 0113 1021831
- ~
48 f sf f tat tf*tftfstaff t t t sf fr ffft tff fr t t sf t f t sf t f ft t t f t fr tat t t fr t at t t t f ffff ttff t'f t t 4 tf f tt tat f tff tf f t sf t tt f tat'f ft t tf 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY 3 f SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PRISIM f f tttff tff 1 4 PLANNING AUGMENTED EXAMINATION COMPONENT LISTING - B03-01 PAGE 47 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 REPORT QUESTION 250. i- 'iNIEROAL"01'NLY 9 t t ttt t t ft tt tt t ft ft t fft t t t t tt t t t t ft f t t fttt f ft fft t fttt t f f tft tf t tt t f t t ttt tt t t ftf t t tt ff ttbATE t f t ft88/01/12 t ttt t. f t fff 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION >1250. 1 12 13 ttttttf*ttftttttttt*ttttfst sf fttftat ttffrtttfaft ft\ttffrsf f t ttttftat f taft f f ttttttfttfttftat f f ff f f t fr ff f ttftttttt
~
14 15 DONE 16 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER ararat ssassssssssssss DESCRIPTION asssssssrssssss TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 s ssssaa ssssassssssssssa arras stars sasssras ararat ass ararat ass ss ararat 20 21 SYSTEM: CT CONTAINMENT SPRAY ISOMETRIC NUMBER: I I-CT"014 22 23 CT-SW-A3 ELB LR -PIPE UT-45S 08.00 0.322 24 25 CT-FW-175 PIPE -VALVE UT-455 1-2-03 08.00 0.322 NO R2-003 26 27 CT-FW-176 VALVE -PIPE . UT"45S 08.00 0.322 NO R2-003 28 29 CT-SW-B3 PIPE -ELB LR UT-45S 1-2"03 08.00 0.322 NO 30 31 CT-SW-84 ELB LR -PIPE UT-45S 1-2-03 08.00 0.322 32 33 CT-FW-178 PIPE -P BEND UT-45S 08.00 0.322 34 35 CT-SW-C3 P BEND -P BEND UT-45S 08.00 0.322 36 37 CT-FW-179 P BEND -PIPE UT"455 08.00 0.322 NO 38 39 CT-SW-D4 PIPE -RED TEE UT-45S 08.00 0.322 40 41 CT-SW-D3. RED TEE-PIPE UT-455 08.00 0.322 NO R2-003 42 43 CT-FW"185 PIPE -VALVE UT-45S 08.00 0.322 NO R2-003 44 45 SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER : II-CT"016
. 46 47 CT-F W- 143 FL HEAD-ELB LR UT-45S 08.00 0.322 NO R2-003 48 49 CT-SW"A3 ELB LR -PIPE UT-45S 08.00 0.322 NO R2-001 50 51 CT-FW-144 PIPE -VALVE UT"45S 08.00 0.322 NO R2-003 52 CT-FW-145 VALVE -PIPE 1-2-03 53 54 ff tat sf t at sf at t sf f f tat t tttt tttffr tat tft fttUT-45S t fr t f fr ft t f t t t ft ft f f f fr08.00 f ff t ttf0.322 NO R2-003 t f f f t 1 t tt t ft sf t t ff f fr ft t t t tf t tt tt tf t t t f'ttaft 55 56 57 58 59 60
49 t sf t fr f sf tf t tf tt tt f at f ft t tt tff f fft tart st t ff t tt f at fthm tft tftt fft t tff tf t t t st f tt f st t t tt t f tt t t f t at t t t tat ttt st f t t t tt at t f tf t f f NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR POWER PLANT UNIT 5
- PLANNING tftftft tfft t f 't fftft AUGMENTED EXAMINATION COMPONENT LISTING 803-01 PAGE 48 6 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 7 REPORT QUESTION 250.1- INTERVAL 01 ONLY t t tat f 'f f sf ff f sf f st t sf tt sf tfst t tat ff f t tffff f f tfft t t tf tff t*tft*ff t tff f f sf fr t st f at tft t f *tf ffat fftftfst t stDATE 88/01/12 f f t sf 'tat sf sf f ff 9
10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION lF250. 1 12 13 sf f f Iffr ff rttff f rlrtffr ttfff f f trlrff art tttttttfrlrf ff trlrtft'ttf ttttttttftttff rlrffat tat t tat ttftat tat*sf ffttfffttftfffft'f ttttf'lrfff 14 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 16 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 rassaassassaasassssassr rssasasaasassss starts sassssilaa ~ ssr stars asaas ssssasss saaarr asa sass -== ararat 20 2'I SYSTEM : CT CONTAINMENT SPRAY ISOMETRIC NUMBER : II-CT-016 22 23 CT-SW-83 PIPE -ELB LR UT-455 08.00 0.322 24 25 CT-SW-84 ELB LR -PIPE UT-45S 08.00 0.322 26 27 CT-SW-86 PIPE -PIPE UT-455 08.00 0.322 NO 28 29 CT-FW-146 PIPE -P BEND UT-455 08.00 0.322 30 31 CT-SW-C3 P BEND -PIPE UT-455 08.00 0.322 NO 32 33 CT-SW-CB PIPE -P BEND UT-45S 08.00 0.322 34 35 CT-FW-148 P BEND -PIPE UT-455 08.00 0.322 NO 36 37 CT-SW-04 PIPE -REO TEE UT-455 1-2-03 08.00 0.322 NO 38 39 CT-SW-D3 RED TEE"PIPE UT-455 1-2-03 08.00 0.322 NO 40 41 CT-2-FW-154 PIPE -VALVE UT-455 08.00 0.322 NO R2-003 42 43 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER : II-RH-001 44 45 RH-FW-3A LNGSEAM UT-455 1-1-01 12.00 0.375 46 47 RH-FW-4A LNGSEAM UT-455 12.00 0.375 NO 48 49 RH-FW-5A LNGSEAM UT-455 12.00 0.375 50 51 RH-FW-58 LNGSEAM UT-455 12.00 0.375 52 53 RH-FW"6A UT-455 12.00 0.375 54 tffffff tfff tffat tf tfftsf tfLNGSEAM tff tff f tt ttftfttf t ttftfttftftf t tttff tff ff stf tt tt f t at t tat tt tf at f tff ttNOf tttftt fr ttf tttftffftft 55 58 57 58 59 60 FORM 01 13 <0 2 I83)
54 11 1ttf f1tttt'1 tt141ttt tf1ttf 1 1ttf tt tf4 ttft4 1 1 411 41*1 tf414 ttf111114'4 tft1tt*ttttttt ttttt tf1 ttttttftftft4ttttff1 NUTECH CAROLINA POWER 8r LIGHT COMPANY PRISIM 4 SHEARON HARRIS NUCLEAR POWER PLANT UNIT f tftttttttft41 1 PLANNING 5 AUGMENTED EXAMINATION COMPONENT LISTING - B03-01 PAGE 53 6 AUGMENTED.EXAMINATION OF PIPING PER. SAFETY=.EVALUATION REVISION NRC1 7 REPORT QUESTION 250. 1- INTERVAL 01 ONLY 8 44tttttf ttt4tttf414 41t4tf 1 f tf4ttf ttttttttff 4ttttf ttfttff tttftttf ttttt14444tttttttf tftftttttff tt4ttf1 4 4 DATE 88/01/12 14 4 111411 f 1 f tt 9 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION ll ITEM NO. 250. 1V SAFETY EVALUATION REPORT. SAFETY REVIEW QUESTION /250. 1 12 13 44411 t tt 11111 1 11 fthm 1 4 1 tt t t f1 tf tftf411 1 11 1 tt tf11 111 1 t tf4 1 1f 44 1 14 t 1 1 1 4f tt t t 4 t f1 tt4 1 1 t1 11 1 t 1 1 t 111 14 1 4t f 1 1 1 1 1 1 1 4 1'1 tt1 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION 19 $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $ ~ $ $ $ $ $ $ $ $ $ $ ~ $ ~ SISS TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 1~$~$~ $$~$$$$$~4 ~$$$~1 $$$ $ $$$$$ $$~4~$$$ $$~$~$ $$$ ~$$$$~ 4 ~$$$$ $$~$$~ 20 21 SYSTEM: RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-002 22 23 RH-FW-17A LNGSEAM UT-455 12.00 0.406 NO 24 25 RH-FW-18A LNGSEAM UT-455 12.00 0.406 NO 26 27 RH-F W-188 LNGSEAM UT-45S 12.00 0.406 NO 28 29 RH-F W-19A LNGSEAM UT-455 12.00 0.406 NO 30 31 RH-FW-20A LNGSEAM UT-455 12.00 0.406 NO 32 33 RH-FW-21A ELBSEAM UT-455 1-3-06 14.00 0.375 NO 34 35 RH-FW-218 ELBSEAM UT-455 1-3-06 14.00 0.375 36 37 RH-SW-A3A LNGSEAM UT-455 1-3-06 12.00 0.406 NO 38 39 RH-SW-A4A LNGSEAM UT-455 12.00 0.406 NO 40 41 RH-SW-BSA LNGSEAM UT-455 12.00 0.406 42 43 RH-SW-C19A LNGSEAM UT-455 12.00 0.406 44 45 RH-SW-C19B LNGSEAM UT-455 12.00 0.406 NO 46 47 RH-SW-C6A LNGSEAM UT"455 12.00 0.406 48 49 RH-SW-D19A LNGSEAM UT-455 12.00 0.406 50 51 RH-SW-D19B LNGSEAM UT-455 12.00 0.406 NO 52 53 RH-SW-D3A 54 44ttt4tttt114ttttf tf1 ttt4'tf ttttttt4tt1ttfUT-455 LNGSEAM 12.00 0.406 ttftttf114*11144ttttf t1 ~ tf ttt44t*f1ttttttttfft'tt411111 NO 1 1 1 1 1 tf 1141*11 t*tff 1 1 1 55 56 57 58 59 60
55 1 0 t f f t ff fft atf tftftt ftff tff f ff tft fthm tate tff f tff sf ft t at f tff t tfat f at f f t tfat tfft tt t t t tt f t sf t'f t t f t f t t*tt sf t ftttt tat f f ft tftf 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 t PLANNING f tfff f tfttttt*ff at f 5 t ~ AUGMENTED EXAMINATION COMPONENT LISTING " 803-01 PAGE 54 6 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 7 REPORT QUESTION 250. 1- INTERVAL 01 ONLY.
'tf tfff *ftf f sf f sf ff f sf f f f ff tft tf fthm tt t ft t tt ff t t f fffft ft ft tt f tat at at sf tff t tf t at t sf t f f tt 88/01/12 tt t t f t tt t t ff *ft't f tt t t DATE f t tt t tt t tff 9
10 CATEGORY SER SAFETY EVALUATION REPORT. SAFETY REVIEW QUESTION II ITEM NO. 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION /250. 1 12 13 t*tf f f 'f f f ffff tff f tat tfff ff f tat tt t t f f f f at sf ft tff tft sf t t'tt t f t t tt t tff f f at tff at tff t tff f sf t f t tt tf t ff t sf f t f 't t'f at sf ff f at tff f 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 sssssssssssss NUMBER DESCRIPTION TYPE DULED INT INT ( IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 ~ s ~ s ~ as ~ sss sss s sssssssss ~ sss ~ a sssss ~ ssssss s s s sss sssssss ~ s ~ asst sss s s s'as ssssss 20 21 SYSTEM: RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-002 22 23 RH-SW-D4A LNGSEAM UT-455 12.00 0.406 24 r5 RH-SW-D5A LNGSEAM UT-455 12.00 0.406 NO 28 27 RH-SW"DGA LNGSEAM UT"455 'I 2 . 00 0. 406 28 29 RH-SW"D68 LNGSEAM UT-455 12.00 0.406 NO 30 3I RH-SW-E3A LNGSEAM UT-455 14.00 0.375 NO 32 33 RH-SW"E38 ELBSEAM UT-455 14.00 0.375 NO 34 35 kH-SW-E3C ELBSEAM UT"455 14.00 0.375 36 37 RH"SW-E4A TEESEAM UT-455 14.00 0.375 38 39 RH-SW-E48 LNGSEAM UT-455 14.00 0.375 NO 40 41 RH-SW-EBA LNGSEAM UT-455 12.00 0.406 NO 42 43 RH-5-3-SW"1 PIPE -PIPE UT-455 12.00 0.406 44 45 RH-5-3-SW-1A LNGSEAM UT-455 12.00 0.406 48 47 RH-5-3-SW-18 LNGSEAM UT-455 12.00 0.406 NO 48 49 RH-5-6-SW-1 PIPE -RED TEE UT-45S 14.00 0.375 NO R2-003 50 51 hH-5"6-SW-1A LNGSEAM UT-455 14.00 0.375 NO 52 RH-5-6-SW-18 tat f fffftfff f tff tttff ff ttfTEESEAM f ffttff f f f f f tttfUT-455 14.00 0.375 53 f ff f tfff f tftftfsf tfff tt tf at f f t tttt tttt at tff tftf f tff ff tttffff tftff ff tff f tff f NO 54 55 56 57 58 59 60 FORM 0113 102183)
57 ff 't t t tt t t tttt t f tt t ttt t t tt f tf tft t ft tt tftt ft tf ttt f tt t tt f tf t t t t ttt tt tt t *tt t t t fft t t t t tftt t t t t tt tt ft t t t tft tt tt t t t t t t t ttt t t NUTECH CAROLINA POWER & LIGHT COMPANY PRIS IM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 5 PLANNING = 1
*ttttttttttf AUGMENTED EXAMINATION COMPONENT LISTING B03-01 PAGE 56 6 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 REPORT QUESTION 250. 1- INTERVAL 01 ONLY 8 fttttt*ttfttttfttttttttttttftttftttttttff tttttfff ttttttttttttttttttttttttttt*tf ftttttttttttttttftaffetaDATE 88/01/12 ttttttttt'tf tet 9
10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION JY250. 1 12 13 t t tf t t t tt ft f t t t ttt t tt t f t ft t tt t t ttt t tttt t tt t tt t t ttt tt t t t t ft tt t t tt tt t t t t t t t t ttf t t t t t t tf t t t t t t t' t' ft t t t ft tt t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 18 NUMBER assaseaassssesssaasaasss DESCRIPTION ssessasssssssss TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 -=sass ssssssasssssssss asses eases ssesaess reseat sss assess assess assess 20 21 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER : II-RH-002 22 23 RH-SW-D4 ELB LR -PIPE UT-45S 12.00 0.406 24 25 RH-SW-D3 PIPE -ELB LR UT-455 12.00 0.406 26 27 RH-FW-20 ELB LR -PIPE UT-455 12.00 0.406 NO 28 29 RH-SW-EB PIPE -REO TEE UT-45S 12.00 0.406 NO R2-003 30 31 SI-FW-21 TEE -PIPE UT-45S 1-2-03 14.00 0.375 NO R2-003 32 33 RH-S-6-SW-2 RED TEE-PIPE UT-4SS 14.00 0.375 NO R2-003 34 35 RH-5-6"SW-2A TEESEAM UT-45S 14.00 0.375 NO 38 37 RH-5-6-SW-26 LNGSEAM UT-45S 14.00 0.375 38 39 RH-SW-ES TEE -T STRNR UT-455 14.00 0.375 NO R2-003 40 41 RH-5-6-SW-3 PIPE -TEE UT-45S 14.00 0.375 NO 42 43 RH-5-6-SW-3A TEESEAM UT-45S 14.00 0.375 44 45 RH-5-6-SW-3B ~ LNGSEAM UT-455 14.00 0.375 NO 46 47 RH-SW-E4 TEE -PIPE UT-45S 14.00 0.375 NO 48 49 RH-SW-E3 PIPE -ELB LR UT-455 14.00 0.375 50 Sl RH-FW-21 ELB LR -N021BI UT-455 1-3-06 14.00 0.375 NO R2-003 52 53 SYSTEM : RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER : II-RH-009 54 55 RH-FW"15A UT-45S 1-2-03 56 et at 57 t f t f t t t ttfft f at t tfftetf t t at t tff t t tftfet sf LNGSEAM et ttt et 0.406 f et t tt t sf t tt f et t tet12.00 NO ft t et f t t et tet et f tt tt tt ft f f tet sf et et t t t t tet sf ft 58 59 60 FORM 0113 <02I83)
1 f 4 tftf4 f tfftttf4 f 4 tft*f'4tf t t t f t 4 tft tft 4 t t t fI t f 4 t tttt tff tf4 4 f*4fttf4 f 4 tff 4 t tff f f ff 4 t fthm 4 tf4 tf f tf4 4 4 t f f t'4 tft t 2 NUTECH CAROLINA POWER 6 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER. PLANT UNIT 4 f PLANNING tfttttfttttfttftftf 5 AUGMENTED EXAMINATION COMPONENT LISTING B03-01 PAGE 57 6 AUGMENTED EXAMINATION OF PIPING PER,SAFETY EVALUATION REVISION NRC1 7 REPORT QUESTION 250. 1- INTER(/AL d1 bhlLY
- 8 tf4 trf tt 4 4 4 tf4 4 tft4 f4 t tf4 tft tft t t t 44444 44 4 tft t444444 tt t f f t f t tftt tt t t t t f f ft f 4 t t f 4 t t f4 4 4 f4 DATE 444 4 44 4 4 f 4 4 t tfBB/01/12 tft t tf4 4 4 4 9
10 CATEGORY SER SAFETY EVALUATION REPORT. SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION /250. 1 12 13 4 tfftf f 4 4 tf4 t'4 tt 4 4 4 f 4 t f4 4 4 t rt 444 t tf4 tftf4 tf 4 4 4 f tff4 t tt t t 4 4 f 4 fttt t 4 f 4 4 tf4 4 t 4 tf f4 \ t t t t t t tttt f 4 tf4 4 tffr f4 4 t 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 g$ 444444$ 4444 444'444444 4444 ~ 4 ~ 4 ~ $ 4444 ~ $ $ $ ~ $ $ $ $ $ $ $ $ $ $ 4$ ~ 4 ~ 4 ~ 4 $ $ $ ~ 4 '44 4'444 $ 4$ $ $ $ $ 4 ~ 4 ~ 444 ~ 4$ ~ $ $ 20 21 SYSTEM: RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-OOS 22 23 RH-SW-F3A LNGSEAM UT"455 12.00 0.406 24 25 RH-FW-14 VALVE -PIPE UT-505 1-2-03 12.00 0.406 NO R2-003 26 27 RH-FW-15 PIPE -FL HEAD UT-455 1-2-03 12.00 0.406 NO R2-003 28 29 RH"SW-F3 PIPE -PIPE UT-455 12.00 0.406 30 31 SYSTEM: RH RESIDUAL HEAT REMOVAL ISOMETRIC NUMBER: I I-RH-010 32 33 RH-FW-2A LNGSEAM UT-45S 1-2-03 12.00 0.375 34 35 RH-SW-F3A LNGSEAM UT-45S 12.00 0.375 NO 36 37 RH-FW-1S3 VALVE -PIPE UT-505 1-2-03 12.00 1. 125 NO R2-003 38 39 RH-SW-F3 PIPE "PIPE UT-45S 12~00 0.375 NO 40 41 RH-FW-2 PIPE -FL HEAD UT"455 1-2-03 12. 00 0. 3 /5 NO R2-003 42 43 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER : II-CS-007 44 45 SI-FW-25 TEE -PIPE UT-455 1-1-01 04.00 0.531 NO R2-003 46 47 SI-SW-F3 PIPE -PIPE UT-455 04.00 0.531 48 49 SI-13-1-SW-4 PIPE -ELB LR UT-455 04.00 0.531 NO 50 SI-SW-FS ELB LR -PIPE 51 52 4 ttf4 tttfttfttf tttftttfttfUT-455 4 4 tttf ttf f4 f4tttttftf tttff4 4 4 04.00 0.531 44 tf f ttftf4 f tf f ttttf ttttff tttftf ttttttfttft 4 4 4 NO 4 53 54 55 se 57 58 59 60 FOAM 0113 {02/83)
tt tt f t t t fttt t t t t' t t f t t t f ft t t tt t t tt t t ft t t t' tt t tt t f fftt t t ftt f tt t ttt t t t t t f t t t t t t t tt t tt t t tt t t t tt tt ttt t t t t t t ft tf t t t tt 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY 3 t SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PR IS IM 4
- PLANNING t t t t t t f 't tt t t t t t t tt t 5 AUGMENTED EXAMINATION COMPONENT LISTING B03-01 PAGE 61 8 AUGMENTED EXAMINATION OF PIPING PER SAFETY, EVALUATION REVISION NRC1 ttff tfttttttfttftttfttttttttttttttttftfttttttf REPORT QUESTION 250.)- fNl'CRVAL 01 ONLY 88/01/12 7t 8
9 tttttttttttttttttttttttfttttttftttttttttttttfDATE tt ttttttf tttttt 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION JY250. 1 12 13 f t t f t t tt ff t t f t f ttt tf t t t t ttt tt tt t t t ttttt f t t t tt tt t t t tft t t t tttt tt t t t t ttt t t ttt t tt t t t t t tt t t t ttt t t t t' t t t t tttt t t t t t t' t t t t
- t. f. 't 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ ~ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ $$$$$$ $~$$$$$$$$~$$~$ $$$$$$ $$$$$$$$$$~$$~$$ ~$$$~ $$ $ $ $$$ $$$$$$ $$~ ~$$$$$ $$~$$$ $$$$$$
20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-004 22 23 SI-FW-32 P BEND -VALVE UT-455 03.00 0.438 NO R2-003 24 25 SI-FW-33 VALVE -PIPE UT-455 03.00 0.438 NO R2-003 26 27 SI-FW-34 PIPE -FL HEAD UT-455 1-2-03 03.00 0.438 28 29 SI-FW-39 VALVE -PIPE UT-455 03.00 0.438 NO R2-003 30 31 SI-SW-A12 PIPE -TEE UT-455 03.00 0.438 NO R2-003 32 33 SI-SW-D6 PIPE -PIPE ~ UT-455 03.00 0.438 NO 34 'O 35 SI-SW-D3 PIPE -ELB LR UT-455 1-2-03 03.00 0.438 36 37 SI"FW-28 ELB LR "PIPE UT-455 1-2-03 03.00 0.438 NO 38 39 SI "SW-C3 PIPE "TEE UT-455 03.00 0.438 NO 40 41 SI "SW-CS TEE -PIPE UT-455 03.00 0.438 NO 42 43 SI-FW-37 PIPE -TEE UT-455 03.00 0.438 NO R2-003 44 45 SI-SW-88 TEE -PIPE UT-455 03.00 0.438 NO R2-003 46 47 SI-SW-89 PIPE -ELB LR UT-455 03.00 0.438 NO 48 49 SI-SW-810 ELB LR -PIPE UT-455 03.00 0.438 50 51 SI "SW-B11 PIPE -ELB LR UT"455 03.00 0.438 52 SI-FW-38 UT-45S 53 54 tfttftftt ttt tftftttftt ttfELB tttfLR tt*tt-VALVE tft t tfttt ttt tft tt'tt t ttt tftt ttt03.00 4 tt ttttt0.438 tttt t t t tttt ttff t ttt t ttf NO R2-003 tf't*t tttttttttt f t ftftt 55 56 57 58 59 60
'av f1 11 1 1 1 11 1 t tft1 1 1 1 1 11 1 1 1 1 1 t1 sf fr11 tf1 1 t 1 1 1 st tf tftt tt t1f 1 frf 1 1 f 1 st 1 1 1 11 1 1 1 1 t t 1 1 t t t*t1 1 t 1tt tt tff 1 1 t 1 f 1 t 1 tt t t 1 tft st fr 1 1 tf NUT ECH CAROLINA POWER & LIGHT COMPANY PRISIM f SHEARON HARRIS NUCLEAR POWER PLANT " UNIT PLANNING ttsttttttf ttttf 11 AUGMENTED EXAMINATION COMPONENT LISTING - 803"01 PAGE 63 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION t REPORT QUESTION 250.'-- INTER'ltAL 01'ONLY REVISION NRC1 ttt 1111 tt 11 1 1 1 1 1 1 11 1 t tt 1 f1 t 1 1 1 1 tt t t t f tt tt tt tt f1 11 1 1 1 1 1 1 1 1 1 t 1 t 1 1 1 f1 11 1 st t 1 1 1 1 1 1 1 1 1 1 1 1 1 t tf ff 1 1 1 f tft t 1 DATE 1 fr 1 1 1 88/01/12 f1 1 t 1 f 1 1 1 1 1t 1 9 10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO. 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION rY250. 1 ttf ttttttt st ttttf1 f 1 ttttttttftttfttf1st sf 11 ttff1tf t f 1 f 1st tf1111111 tttftf1tf tttttfttfrff 12 13 1 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 . COMPONENT. COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM Ie NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES 19 sraaaaaasssassssssssaras assrsrassssssss tartar ssssssssssssssss arras rasas rssssras strata sss srssrs ~ sssrr ararat >> 20 21 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-004 22 t. 23 SI-SW-A11 RED ELB-PIPE UT-455 06.00 0.719 24 25 SI "FW-42 PIPE -VNOZ1XI UT-455 06 . 00 0. 7 19 NO 28 27 SI-SW-A3 REDUCER-TEE UT-45S 03.00 0.438 NO R2-003 28 >> SI-SW-A4 -PIPE UT "45S r'I
~
29 TEE 03.00 0.438 NO R2-003 30 I-3'I SI-SW-AS PIPE -TEE UT-455 03.00 0.438 NO R2-003 32 33 SI-SW-F3 ELB LR -PIPE UT-45S 04.00 0.531 NO 34 35 SI-SW-F4 PIPE -ELB LR UT-45S 04.00 0.531 NO 38 37 SI-SW-FS ELB LR -PIPE UT-455 04.00 0.531 NO 38 39 SI-SW-F6 PIPE -FLG RFW UT-455 04.00 0.531 NO R2-003 4.
>>C 40 4'I SI-SW-E3 FLG RFW-PIPE UT-45S 04.00 0.531 NO R2-003 4 42 43 SI-SW-E4 PIPE -REO ELB UT-45S 1-2-03 04.00 0.531 0 44 C>>
45 SYSTEM: SI SAFETY INJECTION ISOMETR C NUMBER: I I-SI-010 f,' 4e 47 SI-SW-A5 PIPE -ELB LR UT-455 04.00 0.531 48 49 SI-SW-A4 ELB LR -PIPE UT-455 04.00 0.531 NO 50 r 51 SI-SW-A3 PIPE -FLG WNO .UT-455 04.00 0.531 NO R2-003 52 53 SI-FW-276 -PIPE UT-455 54 1 st f tf 11 tttf tfirtttf ttfTEEftfsttttf 11 11 1 1 tttttttf ttftf*1111 ttttf 11 tttttf 1 04.00 0.531 st ttf 1tttttfttttsf tftttttttt'ttttttttf f 1 1 NO R2-003 1 1 111 ttf 55 ee Pg 57 58 59 7 ~ 80 FORM 0113 (02183)
44 4 44 4 4tttf 4444 4444tttf ttt tt t f4 tftt4tf444 f tf 4 4444t tt ttt tf tf4 4 tt44 4 4 f tf 4 4t ttf4 4 4 ttttttttt*tf4 4 tfttf44 t tt tt t f4 4 44 4 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM IC SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING tft*tf44ttttttttttt AUGMENTED EXAMINATION COMPONENT LISTING - B03-01 PAGE 65 AUGMENTED EXAMINATION OF PIPING PER, SAFETY EVALUATION REVISION NRC1 REPORT QUESTION 250. 1" I4TEAVAL 01'OILY 4 4 4 44 4 ttft f4 t tttft f ttftt f 4 44444 tf 44 tt4 f tf 4 4 4 4 4 4t f4 4 4 4 4 4 4 4 tftf 444 4 tff t t 4 4 4f 4 4 4 4 444 tt4 4 444 4 tt 4 tt tt t 4 4 88/01/12
'DATE 4 4 4 tf'4 tt 4 4 4 9
10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION 11 ITEM NO 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW QUESTION JY250. 1 12 13 444 44 ttfttf f4tf4 44 44 f4 f4 tf tttt tttfttfttf4 tf tftf 4 44 4 44 4444 ttff4 ttff4t f4tf4 tfttttttftf4tttf4tttf4 tttf4 f4tttftf 4 4444 14 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) ( IN) ACCESS SELECT IND REQST TIONS NOTES
$$$$$$~$~$$$$$$$~$$$$$ ~$$$$$$$$$$$$$$ $$$$~4 $$$ $$$~$$~4~4~$ $$$$~ $$$$$ $$$$$ $$$ ~$$$$$ 4~4 ~$$$$$ $$$$$$ $$$$$$
19 ' 20 21 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-010 22 23 SI-SW-C3 ELB LR -PIPE UT-455 03.00 0.438 NO 24 25 SI-99-FW-270 PIPE -VALVE UT-455 03.00 0.438 NO R2-003 28 27 SI-89-FW-271 VALVE -PIPE UT-455 03.00 0.438 NO R2-003 28 29 SI-99-FW-272 PIPE -FL HEAD UT-455 1-2-03 03.00 0.438 NO 30 31 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-011 32 33 SI-SW-A12 PIPE -P BEND UT-45S 03.00 0.438 NO 34 35 SI-SW-A13 P BEND -P BEND UT-45S 03.00 0.438 36 37 SI-FW-274 P BEND -PIPE UT-45S 03.00 0.438 NO 38 39 SI-SW"B5 PIPE -PIPE UT-455 03.00 NO 40 0.438'3.00 41 SI-FW-470 PIPE -PIPE UT-455 0.438 42 43 SI-SW-C6 PIPE -ELB LR UT-455 03.00 0.438 NO 44 45 SI-SW-C7 ELB LR -PIPE UT-455 03.00 0.438 NO 46 47 SI-FW-471 PIPE -ELB LR UT-455 03.00 0.438 48 49 SI-SW-D3 ELB LR -PIPE UT-455 03.00 0.438 50 51 SI-SW-DS PIPE -PIPE UT"455 03.00 0.438 NO 52 53 SI-FW-472 -ELB LR UT"455 03.00 0.438 54 4 4 fttttttt4tf1*tf 444 rttf4 PIPE 4 44 ftf4tttttttfttf4 tt4ttf t4444 ttftf44444 ttftttff4 444 ttftf44444 444444 44444 ttt4ttttf tf tt4f tf NO 4 4'4 55 58 57 58 59 80
69 I 4 t*f4 4tf tf4 4 4 4 4 4t 4 4 4t4 4 f4 4 4 4 4 f 4 4 4 tttftf44 4 tf444*4 tff 4 *4 4 4 4 4 4 f 4 4t tf4 4 4 444 4 4 tt 4 444444 4444 t 4ft4 4 4 tf 4 4 4 4 4 4 4 4 4 4 4 4 4 4 tf4 4 4 4 2 t NUTECH CAROLINA POWER & LIGHT COMPANY Sr PRI SIN 3 4 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT Sl 4 PLANNING *4 4 4 4 4 4 4 4 S 4 t 4 4 4 44 4 4 5 AUGMENTED EXAMINATION COMPONENT LISTING - 803-01
- PAGE 68 6 AUGMENTED EXAMINATION OF PIPING PER SAFETY EVALUATION REVISION NRC1 7 4 REPORT OUESTION 250.1- INTERVAL 01 ONLY 8 4 4 4 44 ttf44 tttkttttf4 4 4ttf tt'4t tf4 ttftf4 Srf 4 f4tf44 4 4 44t tfttt t tttftf4 f 4 4 4 4 Srtf 4 f4 ff 4 4 4 t tt tt4 4 4 4 4t4 4 tf444 tfDATE 4 88/01/12 Srf 4 4 *4 tf 4 4'4 4 tf 4 9
10 CATEGORY SER SAFETY EVALUATION REPORT, SAFETY REVIEW OUESTION 11 ITEM NO. 250. 1V SAFETY EVALUATION REPORT, SAFETY REVIEW OUESTION IF250. 1 12 13 4 '4tttttf4 f 4 ttttf4 tf'4 tttfttf4ttttttfSrttf 444 tfttf4444 f4 tttttfttfttttttttttttttftir444tttt4ttf4 4 tfSrf 44 4 t4ttf tff 4 4 4 4 ttf4 4 t 14 IS DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER tffff4 444R4444444 ~ 44 DESCRIPTION I TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 4SI ~ ~4 44 44444 444 ~ 4 ~ ~ 44444444 ~ 444444 41444 $ 4 ~ 44 I 444444 ISIS 444444 SI44444 444444 20 21 SYSTEM: SI SAFETY INJECTION ISOMETRIC NUMBER: I I-SI-027 22 23 SI-SW-K3 P BEND -TEE UT-60S 03.00 0.438 NO R2-003 24 25 SI-SW-K5 TEE -PIPE UT-455 03.00 0.438 NO R2-003 26 27 SI-SW-K4 PIPE - -REDUCER UT-455 03.00 0.438 28 29 SI-SW-K6 TEE -PIPE UT-455 03.00 0.438 NO R2-003 30 31 SI-SW-K7 PIPE -ELB LR UT-455 03.00 0.438 NO 32 33 SI-FW-567 ELB LR "PIPE UT-455 03.00 0.438 NO 34 35 SI-SW-J3 PIPE -ELB LR UT"455 03.00 0.438 NO 36 37 SI-SW- J4 ELB LR -PIPE UT-455 03.00 0.438 NO 38 39 SI-SW-JB PIPE "P BEND UT-455 " 03.00 0.438 40 41 SI-SW-J5 P BEND -REDUCER UT-455 1-3-06 03.00 0.438 42 43 SYSTEM : SI SAFETY INJECTION ISOMETRIC NUMBER : II-SI-029 44 45 SI-FW-601 FL HEAD-PIPE U1-605 03.00 0.438 NO 48 47 SI-SW-C14 PIPE -TEE UT-455 1-1-01 03.00 0.438 NO R2-003 48 49 SI-SW-C9 TEE -PIPE UT-455 03.00 0.438 NO R2-003 50 51 SI-SW-C10 PIPE -TEE UT-455 03.00 0.438 NO R2-003 52 53 SI-SW-C11 -REDUCER UT-455 t t t t t 4 t 4 f 4 4 4 4 t 4 4 4 ft 03.00 0.438 TEE NO R2-003 t f t 54 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 1 Sr 4
- 4 4 4 4 4 4 4 4 4 4 4 4 Sr 4
- 4 4 4 4 4 tt 4 4 4 4 t 4 t 4 t 4 4 t 4 4 t 4 t 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 t S Sr Sr Sr 44 55 56
'r 57 58 59 60 FOAM 01'I3 102I831 S
SELECTION RECORDS 2 ~ 3 EXAM S COMPNOEX EXREQ CATEGORY EXREQ ITEMNO 4 EXAM $ EXREQ EXSCHD OUTAGE SELECT REQUEST 5 EXAM EXEMPT EXOATE CREDIT NDEPROC CALSTD COMP SYSTEM COMPDES ACCESS 1 ACCESS 2 ACCESS 3 7 COMP ACCESS 4 ACCESS 5 ACCESS 6 TRANSIN TENRMKS 8 COMP NEWCOMNO ORDER COMPDIA NOMTHCK REFOWG 9 COMP $ OLDCOMNO 10 PICK EXREQ EQS B04-01 II 62 RECORDS HAVE BEEN SELECTED 12 13 14 SELECTED DATA RECORD FORMAT 15 $$$$~$$$$$~$$$~$$~$~$$$$$$$ 18 17 ELEMENT LENGTH STARTING COL. IS 19 COMPNOEX 24 1 20 EXREQ 6 25 21 CATEGORY 6 31 22 EXREQ 6 37 23 ITEMNO 6 43 24 EXREQ 6 49 25 EXSCHD 6 55 26 OUTAGE 6 61 27 SELECT 6 67 28 REQUEST 6 73 29 EXEMPT 6 79 30 EXDATE 8 85 31 CREDIT 93 32 NDEPROC 6 94 33 CALSTD 6 100 34 SYSTEM 3 106 35 COMPDES 15 109 36 ACCESS 1 2 124 4 37 ACCESS 2 2 126 38 ACCESS 3 2 128 39 ACCESS 4 2 130 40 ACCESS 5 2 132 $ 41 ACCESS 6 2 134 'I 42 TRANSIN 136 1 43 TENRMKS 6 137 44 NEWCOMNO 24 143 45 ORDER 4 167 48 COMPDIA 5 171 47 NOMTHCK 5 176 48 REFOWG 16 181 49 OLOCOMNO 24 197 50 51 52 t
~F 53 54 C
55 56 57 58 59 80 FORM 0113 {02183I
1 SELECTION RECORDS ~ ',>> 2 3 4 EXAM EXAM S COMPNOEX EXREQ EXREQ CATEGORY EXREQ I TENNO EXSCHD OUTAGE SELECT REQUEST 5 EXAM EXEMPT EXDATE CREDIT NOEPROC CALSTD 8 COMP SYSTEM COMPDES ACCESS 1 ACCESS 2 ACCESS 3 7 COMP ACCESS 4 ACCESS 5 ACCESS 6 TRANSIN TENRMKS 8 COMP NEWCOMNO ORDER COMPDIA NOMTHCK REFOWG * '>> 9 COMP a OLOCOMNO 10 PICK EXREQ EQS 805"01 11 156 RECORDS HAVE BEEN SELECTED 12 13 14 SELECTEO DATA RECORD FORMAT 15 sssaasssassassassssssaaaaas 18 17 ELEMENT LENGTH STARTING COL. i 18 19 COMPNOEX 24 >> 20 EXREQ 6 25 21 CATEGORY 6 31 22 EXREQ 6 37 23 ITEMNO 6 43 24 EXREQ 6 49 25 EXSCHO 6 55 r 28 OUTAGE 6 61 >> 27 SELECT 6 67 28 REQUEST 6 73 29 EXEMPT 6 79 30 EXOATE 8 85 31 CREDIT 93 32 NDEPROC 6 94 33 CALSTD 6 100 34 SYSTEM 3 106 35 COMPDES 15 109 38 ACCESS 2 124 37 ACCESS 2 2 126 38 ACCESS 3 2 128 39 ACCESS 4 2 130 40 ACCESS 5 2 132 tk '>> 41 ACCESS 6 2 134 42 TRANSIN 136 43 TENRMKS 6 137 44 NEWCOMNO 24 143 45 ORDER 4 167 48 COMPDIA 5 171 7 47 .NOMTHCK 5 176 48 REFDWG 16 181 L 49 OLDCOMNO 24 197 50 51 7 52 53 A 54 55 58 57 58 59 80 FORM 0 I 13 (02I83) 7 'vs>>'a 7>>>>>>.v t>>Jh 'r>> 7 >> " a " ' ~ .a a 7 ~ '7r>>
2 444 t 4 4 4 4* 4 4 1 1 4 4 4 4 t 4 1 4 4 1 1 4 4 4 t 4 1 t tt 4 1 4 4 4 1 4 4 4 4 4 4 4 4 4 t 14 1 t 1 4 4 1 4 4 1 4 4 1 1 4 4 4 4 t 4 4 4 t 4 4 1 4 t 4 4 4 4 4 1 4 4 4 1 1 1 1 t 1 4 4 4 4 1 *4 t 1 4 1 t t 1 4 4 4 4 t 4 *t 4 t NUTECH CAROLINA POWER 5 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING 44444ttttttttttt4tt AUGMENTED EXAMINATION COMPONENT LISTING - B05-01 PAGE 1 EXAMINATION OF MAIN STEAQ AND F~EEDWAQER PIPING IN THE BREAK REVISION NRC1 EXCLUSION REGION PER FSAR SECTI'ON 6.6;8. - INTERVAL 01 ONLY t4 1 4 4 4 1 t4 4 4 1 4 4 4 4 4 4 4 4 4 4 4 4 1 4 1 1 4 1 '4 1 4 4 1 4 4 1 4 4 4 4 4 4 1 4 4 1 4 4 1 1 4 4 4 4 4 4 1 4 4 4 4' 1 4 *4 4 1 4 4 4 4 4 4 4 1 4 4 4 4 4 1 4 4 4 4 1 4 4 1 4 4 88/01/12 DATE 4' t t t t t t t t t t t 4 4444 4411 t 9 10 CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8. 11 ITEM NO. 6.6.8C AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR 12 t t t 13 4 1 4 4 4 1 1 4 4 4 4 1 1 4 4 4 4 1 4 1 1 4 1 4 4 1 4 1 4 4 4 4 4 4 t t t 4 4 4 4 4 4 1 4 4 4 4 4 4 1 1 1 1 4 t 1 t 4 4 1 4 t 4 1 4 t 4 t 1 4 1 1 1 t 1 1 t 4 4 tt 1 1 t 4 4 4 t 4 tt t 4 4 1 1 1 t 4 1 1414 tt 4 4 41144 14 15 DONE 16 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ $ ~ $ $ ~ $ $ $ $ ~ $ $ $ $ $ $ $ $ $ '$$ $ $ '$$ $ $ $ $ $ ~ $ ~ $ $ $ $$$$$$ $$$$$$$~$$$$$$$$ $$$$ $ $$ $$$$$ $$$ $$$$$$ $$$ ~$$~$$ $~$ ~$$ $$$$$$ 20 21 SYSTEM : FW FEED WATER ISOMETRIC NUMBER: I I-FW-001 22 23 FW-FW-469 PIPE -VALVE UT-45S 1-2-03 16.00 1.006 NO 24 25 FW-FW-470 PIPE -PIPE UT-455 1-2-03 16.00 1.006 NO 26 27 FW"FW-473 PIPE -VALVE UT-455 1-2-03 16.00 1.006 NO 28 29 FW-FW-476 PIPE -VALVE UT"455 1-2-03 16 . 00 1 . 006 NO 30 31 FW"SW-K3 PIPE -PIPE UT-455 1-2-03 16 . 00 1 . 006 NO 32 33 FW-SW-KB P BEND -PIPE UT-45S 1-2-03 16.00 1.006 34 35 FW-32-3-SW"1 SWPOLET-PIPE UT-45S 1-2-03 16.00 1.006 NO 36 37 FW-32-4-SW-1 FLG UNK-PIPE UT-45S 1-2-03 16.00 1.006 NO R2-003 ~ 38 39 FW-32-5-SW-5 PIPE -FLG UNK UT-455 1-2-03 16.00 1.006 NO R2-003 40 41 FW-36-1-SW-2 FLG UNK-PIPE UT-45S 1-2"03 16 . 00 1 . 006 NO 42 43 FW-36-2-SW"1 PIPE -FLG UNK UT-45S 1-2"03 16.00 1.006 44 45 FW-36-2-SW-6 PIPE -PIPE UT-455 1-2-03 16.00 1.006 NO 46 47 FW-36-2-SW-7 SWPOLET-PIPE UT-45S 1-2-03 16.00 1.006 48 49 FW-39-3-SW-1 FLG UNK-PIPE UT-455 1-2-03 16.00 1.006 NO 50 51 FW"39-4-SW-1 PIPE -FLG UNK UT-455 1-2-03 16.00 1.006 52 FW-39-4-SW-6 UT-455 1-2-03 53 54 14441414ttttttt 4 t1 4 4ttttt 1 tttttttttt SWPOLET-PIPE 141 trt1t4 1 1 1 4 1 t1 14't1 ~ 111441 4444414 16.00 1.006 4 ttttt ttt 144144tt 441444 144444 NO 4 t14t4414 14144 4 4 4 4 4 55 58 57 58 59 60 F08M 0113 102I83)
3 1 4 1411 t1 I f 11 It f t I 4**14*11 44 4f I Iftt ItIII tf I tfI 14 I I IIIfI 1111 I III 14 tt 4t4 III IIItf I ItI tt 41 I tttt ttf41 II ItIt I Itt I 41 tt tt I III I 4 2 I NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 PLANNING 1 tfftttttf tttttt4441 t AUGMENTED EXAMINATION COMPONENT LISTING B05-01 PAGE EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK REVISION NRC1 I tfI ttf11 ttt41 41141 44t414f 144t444 ttttf4441 4tt4411414114 EXCLUSION REGION PER FSAR SECTION ttft1 1tttttf6.6.8. INTERVAL 01 ONLY DATE 88/01/12 11**1111144 tf*4t14ttt111 14tttf trtffrtt14ff1fI ttt1441 9 10 CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8, 11 ITEM NO. 6.6.8C AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR 12 13 I f I It I II t I I 4 f 4 I t I 1 It 1 I III IIt I t t 4 It 4 4 I I 1 tIII 1 II
- I tI t I 1 II t I IIIIt I f I I I ItI 4 I 4 t I t II I II tt II I 4 4 tt ItI I f It t I ItII I II I It 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER sssssesssssassssassassse DESCRIPTION ssssssssesasess
'YPE assess DULED INT sssssssessesasss INT (IN) (IN) asses esses ACCESS assssssa SELECT INO REOST TIONS NOTES assess sss assess assess 19 assess 20 21 SYSTEM : FW FEED WATER ISOMETRIC NUMBER: I I-FW-001 22 23 FW-FW-500 PIPE -VALVE UT-455'"2-03 16.00 1.006 NO 24 25 FW-FW-499 VALVE -PIPE UT-455 1-2-03 16.00 1.006 28 f7 FW-SW-D4 PIPE -TEE UT-45S 1-2-03 16.00 1.006 NO R2-003 28 29 FW-SW"03 TEE -PIPE UT-45S 1-2-03 16.00 1.006 NO 30 31 FW-FW-509 VALVE -PIPE UT-455 1-2-03 16.00 1.006 NO 32 33 FW-SW-A4 PIPE -SWPOLET UT-455 1-2-03 16 . 00 1 . 006 NO 34 35 FW-FW-510 PIPE -FL HEAD UT-45S 1-2-03 16;00 1.006 NO 38 37 FW-FW-507 VALVE -PIPE- UT-455 1-2-03 16.00 1.006 NO 38 39 FW-SW-E4 PIPE -TEE UT-455 1-2-03 16.00 1.006 NO 40 41 FW-SW-E3 TEE -PIPE UT-455 1 2"03 16.00 1.006 NO 42 43 FW-FW-508 PIPE -VALVE UT-455 1-2-03 16.00 1.006 NO 44 45 FW-FW-501 VALVE -PIPE UT-45S 1-2-03 16.00 1.006 4e 47 FW-SW-B4 PIPE -SWPOLET UT-455 1-2-03 16.00 1.006 48 49 FW-FW-502 PIPE -TYPEIIB UT-45S 1-2-03 16.00 1.006 50 51 FW-FW-503 VALVE -PIPE UT-45S 1-2-03 16.00 1.006 52 53 FW-SW-F4 PIPE -TEE UT-45S 1-2-03 54 ttfIttt1ttf II tfIt4f441444ttf f 114141 ttf11114tt4**4 441 1141tt4tf If1416.00 1
1.006 ttttft4f t tff4 tf II IfIft44 1tf I 1111111 11414 tttt ttttf4 NO
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55 Se 57 58 59 80 FOAM 0113 102I831
1 4444 t 4 4 t 4 4 4 f t 4 t 4 4 t 4 t 4 4 t 4 4 4 t 4 t *4 4 4 t t 4 t ff4 4 t 4 4 ft 4 4 t 4 4 f 4 ft 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 f 4 4 4 4 4 t 4 4 t 4 t 4 4 t 4 4 4 4 t 4 4 t 4 4 *f 4 t t 4 t f 4 ft 4 4 4 t 4 4 ft 4 4' 2 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 3 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 4 PLANNING 4 ttttfttf4tt 5 AUGMENTED EXAMINATION COMPONENT LISTING - 805-01 PAGE 3 t I 5 EXAMINATION OF MAIN STEAM )ND, FbEDWA/Eff PIPING IN THE BREAK PEVJSION NRC1 07 EXCLUSION REGION PER FSAR SECTION 6.6'.8. - INTERVAL 01 ONLY 8 fttf444444444'4f 4444tf 44 44 4444ttttf ttfftttf44ttf ttf4tf tttttftt4 tf f4 tt*44 44444 4 ttftttf44tf 4t f4444 4 ttttfDATE 4ttf 4 88/01/12 ttf4 tfttt tt FF 9 h 10 CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8. 11 ITEM NO. 6.6.8C AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR l2 13 tf t f 44 t f t4 4*4 t4 4 44 44 4444 4 4 4t4 t 44 tt tf4 4 4 tf4 tt 4 4 f t f4 4 4 4 t 4 4 4 4 4 tt t 4tf 4 t 44 4 4 tft t tt tt t f4 4 4 ttf 4 4 4 t4 4 tf4 444 4 4 444 4 4 t4 tf 4 4 4 t tt 4 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM 18 NUMBER 1$ $ $ $ 1$ 'SSSSSS ~ $ 1111 ~ $ $ DESCRIPTION TYPE DULED INT INT ( IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 $ $ ~ $ $ $ $ $ $ $ $ $ $ $ $ $ $ ~ $ 1 ~ $ 1111 ~ 1 1 1 1 1 $ 111' $ 11 1 ~ ~ 1 ~ S'1 1 1$ '1$ $ $ $ $ $ $ $ $ 1 ~ 1 ~ SSSS ~ 1 1 ~ 1 ~ 1' 20 F 21 SYSTEM: FW FEED WATER ISOMETRIC NUMBER: II-FW-001 22 23 FW-SW-F3 TEE -PIPE UT-455 1-2-03 16.00 1.006 NO F'5 24 ) FW-FW-504 PIPE -VALVE UT"45S 1-2-03 16.00 1.006 NO 28 27 FW-FM-505 VALVE -PIPE UT-45S 1-2-03 16.00 1.006 28 29 FW-SW-C4 PIPE -SWPOLET UT-45S 1-2-03 16.00 1.006 NO 30 31 FW-FW-506 PIPE -TYPEIIB UT-455 1-2-03 16.00 1.006 32 33 SYSTEM : FW FEED WATER ISOMETRIC NUMBER: I I-FW-002 ~ . 34 35 FW-FW-576 TEE -REDUCER UT-455 1-1-01 06.00 0.562 NO 35 37 SYSTEM : FW FEED MATER ISOMETRIC NUMBER: I I-FW-003 38 39 FW-FW-578 TEE -REDUCER UT-45S 1-1-01 06.00 0.562 NO 40 41 SYSTEM : FW FEED WATER ISOMETRIC NUMBER: I I-FW-004 42 43 FW-FW-574 TEE -REDUCER UT-455 1-1-01 06.00 0.562 NO 44 C'5 SYSTEM: MS MAIN STEAM ISOMETRIC NUMBER: I I-MS-001 45 47 MS-FM-283A LNGSEAM UT-455 1-1-01 34.00 2.000 48 MS-FW-302A 1-3-06 34.00 2.000 49 50 tttftf44f 4 4 444444 tt*tttttttfttf LNGSEAM 44 ttftftftfUT-4554 44444 tf ttttttf4 tf tf 44 f tftf 4444444 444tttf ttt 4ttf f 4ttf 444 tff 444 tftttt 4 4 4 4 4 NO 44 51 52 53 ~ ~ 54 55 58 57 'I 58 V 59 4 50 FORM 0113 102183I re
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rr 1 1 4*44 4 4 444 4 444 4 1 t tt 1 4 4 4 1 t4 1 4 1 4 4 4 1 1 4 4 1 41 ~ 4 1 1 4 4 4 14t t 4 t tt tt 4 1 4 4*1 t ttttt4 4444 4 1 t t 4 1 4 1 t 1 1 t t 1 11 1 4 4141 1 1 4 t1 t 4 1 4 4 4 4 4'4**14 t st NUTECH CAROLINA POWER & LIGHT COMPANY PRISIM SHEARON HARRIS NUCLEAR POWER PLANT - UNIT PLANNING t 14 1 1t tt 4 1' 1 4 4 t tt 41 AUGMENTED EXAMINATION COMPONENT LISTING " 805-01 PAGE 8 t EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK 1 REVISION NRC1 EXCLUSION REGION PER FSAR SECTION 6.6.8. - INTERVAL 01 ONLY 4 DATE 88/01/12 t t t t t t t 4 1 4 4 4 4 1 4 1 4 1 4 1 1 4 4 1 1 4 4 4 4 4 4 4 1 1 1 4 4 4 4 4 1 4 1 1 1 1 4 4 1 4 4 4 1 1 4 1 1 4 4 4 1 4 1 1 1 1 4 4 4 4 1 4 4 4 1 1 1 1 1 1 1 4 1 4 4 1 4 4 4 4 4 1 1 4 1 1 4 1 4 1 1 4 1 1 1 1 4 1 tr 1 4 4 4 1 4 4 4 9 10 CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8, ll ITEM NO. 6.6.8C AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR 12 13
'4 '1 1144444 t 4 t 4 1 4 1 1 t 1 4 't t 4 1 4 4 1 4 1 1 4 4 4 1 4 1 1 t 4 4 1 t 4 4 t 4 t 4 4 1 1 4 t 4 4 4 1 1 1 t 1 4 4 1 4 4 1' 1 1 4 tr 4 1 1 4 1 1 1 1 1 t 1 1 1 1 4 t 1 1 1 1 1 1 4 1 4 4 **4 4 4 t *4 4 1 1 1 1 1 1 4 4 4 '4 14 15 DONE 18 OUTAGE THIS DONE COMP NOM BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER DESCRIPTION'YPE DULED INT INT (IN) (IN) ACCESS SELECT IND REOST TIONS NOTES 19 sssssassrsssssssarersrss aassssassssssrs assess ssssaasssssssrss rarer ss sa asssaasr arrear aaa ssa sr ssasaa assess 20 21 SYSTEM : MS MAIN STEAM ISOMETRIC NUMBER: I I "MS-001 22 23 MS-FW-263 ELB LR -PIPE UT-455 1-3-06 32.00 0.953 NO 24 25 MS-FW"263A LNGSEAM UT-455 1-3-06 32.00 0.953 NO 28 27 MS-FW-263B LNGSEAM UT-455 1-3-06 32.00 0.953 NO 28 29 MS-SW-El PIPE "PIPE UT-455 1-3-06 32.00 0.953 30 31 MS-FW-262 PIPE -PIPE UT-455 1-3-06 32.00 0.953 NO 32 33 MS-FW-287 VALVE -PIPE UT-455 1-3-06 32.00 0.953 34 35 MS-SW" F 1 PIPE -ELB LR UT-45S 1-3-06 32.00 0.953 NO 38 37 MS-SW"F1A LNGSEAM UT-455 1-3-06 32.00 0.953 38 39 MS-SW-F18 LNGSEAM UT-45S 1"3-06 32.00 0.953 NO 40 41 MS-FW-260 ELB LR -PIPE UT"455 1 3-06 32.00 0.953 NO 42 43 MS-FW-260A LNGSEAM UT-455 1-3-06 32.00 0.953 NO 44 45 MS-FW-2608 LNGSEAM UT-455 1-3-06 32.00 0.953 ND 4e 47 MS-SW-G2 PIPE -PIPE UT-455 1-3-06 32.00 0.953 NO 48 49 MS-SW-G1 PIPE -PIPE UT-455 1-3-06 32.00 0.953 NO 50 51 MS-FW-261 PIPE -PIPE UT-455 1-3-06 32.00 0.9S3 NO 52 53 MS-FW-259 -PIPE UT-455 1-3-06 44.00 1.447 54 4 tt t t 1444 1 44 4111141 4 t t 1 t t PIPE 4 NO 1 4 4 4 t 4 t 4 4 4 1 1 1 t 4 tt 4 4 t 4 4 t t 1 t 4 4 t 1 4 4 1 1 4 4 t 1 1 t 1 4 4 1 1 4 4 1 4 4 4 4 4 t 1 t 4 1 t 1 t t t 4 4 4 t 4 4 1 1 4 1 t 4 4 4 4 1 1 1 4 t 4 1 '1 '4 1111 55 58 57 58 59 eo FORM 01'13 102I83)
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tsr 11 ttf ttf4 44 tfttftfttft4 ttttt f4 tt4 ttttttff4 tftttttftf ttt tttt ttttttttftffttft*tttttftt ttttttttftfttf 4 tf4 tttt4tf4 tt 44 444 4 4 2 NUTECH CAROLINA POWER 8r LIGHT COMPANY PR IS IM 3 4 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1= =s1 4 4 4 PLANNING 1 ttf tttfttttttttt
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RFVISION NRC1 7 EXCLUSION REGION PER FSAR SECTION 6.6.8. - INTERVAL 01 ONLY 4 DATE 88/01/12 4444 44 tsf tf 44 44444444444 4444444 4 444 444444 4 44 ttttt4 t 4tf 4 4 4 4 4 4 4 f4 f4 4 4 4 t4 f4 444 t4tf tt 44 4 4 444 4 4 4 4 4444 4 44 444444444 444 4 444 9 10 CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8, 11 ITEM NO. 6.6.8C AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR 12 13 ttttf tttff ttttttttftttt*tttttttttf4444 tfttftttttfttt4tttf tttttf'4 tttf tttttt ttttt*tftttf 44 4 4 1 44 1 f 4 4 4 ttf'1144141 4 1 11 4 ttf4 14 15 DONE 18 OUTAGE THIS DONE COMP NOM. BASIS PSI 17 COMPONENT COMPONENT EXAM SCHE- OUT PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM 18 NUMBER sasasasssssasssssraasssa DESCRIPTION ssssasaassssrss TYPE DULEO INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES 19 sassss ssarsasssaasssss arras ssaar araraass 4 assr sas sasass sassas ssssss 20 2'1 SYSTEM : MS MAIN STEAM ISOMETRIC NUMBER: I I "MS-002 22 23 MS-FW-692 PIPE -VALVE UT-455 1-1-01 08.00 0.500 NO R2-003 24 25 MS"FW"691 VALVE "PIPE UT-455 1-1 "01 08.00 0.500 NO R2-003 28 27 MS"FW-690 PIPE -VALVE UT"455 1-1-01 OS.OO 0.500 NO R2-003 28 29 MS-FW-565 PIPE -ELB LR UT-455 1-2-03 08.00 0.500 NO 30 31 MS-SW"C3 ELB LR -PIPE UT-455 1-2-03 08.00 0.500 NO 32 33 MS-FW-566 PIPE -VALVE UT-455 1-2-03 08.00 0.500 NO R2-003 34 35 MS-FW-567 VALVE -PIPE UT-455 1-2-03 08'.00 0. 500 NO R2-003 38 37 MS"FW-568 PIPE -VALVE UT-45S 1-2-03 08.00 0.500 NO R2-003 38 39 MS-FW-680 PIPE -ELB LR UT-45S 1-,3-06 08.00 0.500 NO 40 Z~ 41 MS-SW-E3 ELB LR -PIPE UT-455 1"3-06 08.00 0.500 NO 42 43 MS-FW-681 PIPE -VALVE UT-455 1-3-06 08.00 0.500 NO 44 45 MS-FW-682 VALVE -PIPE UT-455 1-3-06 08.00 0.500 48 47 MS-FW-683 PIPE -VALVE UT-455 1-3-06 08.00 0.500 NO 48 49 SYSTEM: MS MAIN STEAM ISOMETRIC NUMBER: I I-MS-007 50 51 MS"FW-S64 PIPE -ELB LR UT-45S 1-1 "01 06.00 0.432 NO 52 53 MS-SW-A3 ELB LR -PIPE UT-455 1" 1-01 06.00 0.432 54 441111 tt441 tfst tf 4 14441 14411 411 tf 4 t4ttttt taft ttf1 fr 1111 11 4111 1 1fttf1 1441111111*1 tf 1*f14 1 f1f f 41 1 41 1141 4 tat ttf 1411 11*1 t NO 55 58 57 58 59 80 p s ~ prosy ~ ~ 's ~ I , FORM 0113 {02I83)
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INTERVAL 01 ONLY DATE 88/01/21 t CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8, t ITEM NO. 6.6.8D AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR t tt ~ t ~ tttt ~ ttt ~ ttttttttttttttttt~ tttttttt ~ ltttt ttt tttttttt ttttttttt ttttttttt tttt ttttttttttttttttttt ttttttttttt
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DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT =- ( IN) ( IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : FW FEED WATER ISOMETRIC NUMBER : II-FW-001 FW-SW-A3 SWPOLET-PIPE MT 1"2-03 03.00 0.438 NO FW-SW-83 SWPOLET-PIPE MT 1-2-03 03.00 0.438 NO FW-SW-C3 SWPOLET-PIPE MT 1-2-03 03.00 0.438 SYSTEM : FW FEED WATER ISOMETRIC NUMBER : II-FW-002 FW-FW-577 PIPE -VALVE MT 1-1-01 03.00 0.438 NO FW-FW-58 1 PIPE -VALVE MT 1-1-0'I 02.00 0.218 NO FW-25-2A-SW-1 REDUCER-PIPE MT 1" 1-01 03.00 0.438 NO FW-25-2A-SW-10 ELBOW -PIPE MT 1-1-01 02.00 0.218 NO FW-25-2A-SW-2 PIPE -ELB LR MT 1-1-01 03".00 0.438 NO FW-25-2A-SW-3 ELB LR -PIPE MT 1-1-01 03.00 0.438 NO FW-25-2A-SW-4 PIPE -ELB LR MT 1-1-0'I 03.00 0.438 NO FW-25-2A-SW-5 ELB LR -PIPE MT 1- -0 'I 03.00 0.438 NO FW-25-2A-SW-6 PIPE -TEE MT 1-1-01 03.00 0.438 NO FW-25-2A-SW-7 PBCC,T-PC,PIPE MT 1-1-01 03.00 0.438 NO FW-25-2A-SW-8 PBCC,T"PC.RED MT 1-1-01 03.00 0.438 NO FW-25-2A-SW-9 REDUCER-ELBOW tttt ~ ~ ~ ttttttttttt ~ ttttttttttttttttttttt MT
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00000000000404000t0000000000000000000SS4004000000S440t000000S04004000t0SS0S400000444000404040 ~ 00000040000040000000000 0 NUTECH CAROLINA 'POWER 8 LIGHT COMPANY PRI SIM 0 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT I 0 0 PLANNING 0400404t00044040000 AUGMENTED, EXAMINATION COMPOVENTI LISTING - 806-01 PAGE- 2 EXAMINATION OF MAIN STEAM AND 'FEEDWATER PIPING IN THE BREAK REVISION NRCI EXCLUSION REGION PER FSAR SECTION 6.6.8 - INTERVAL O'I ONLY DATE 88/01/21 00040000400400000t0000400440 ~ 40000400004000ttttttt4404444044444444404444t44444400044404044444 0400400004000 ~ ttt000000 4 CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8, 0 0 ITEM NO. 6.6.8D AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR 0004000000000000440000000t000000 ~ 000000t4040404400040404t0444440440tttttttt044440040444000000 00040000000 ~ 440t40000ttt DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP" PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : FW FEED WATER ISOMETRIC NUMBER: I I-FW-002 FW-FW-561 VALVE -PIPE MT 1-1-01 03.00 0.438 NO FW-SW-C3 PIPE -ELB LR MT 1-1-01 03.00 0.438 NO FW-SW-CS PIPE -ELB LR MT 1-1-01 03.00 0.438 NO FW-SW-C6 ELB LR -PIPE MT 1-1-01 03.00 0.438 NO FW-SW-C7 PIPE -ELB LR MT 1-1-01 03.00 0.438 FW-SW-CB ELB LR -PIPE MT 1-1-01 03.00 0.438 NO FW-16-4-SW-2 ELB L'R -PIPE MT 1-1-01 03.00 0.438 NO FW-16-4-SW-I PIPE -ELB LR MT 1-1-01 03.00 0.438 NO FW-FW-562 ELB LR -PIPE MT 1-1-01 03700 0.438 NO FW-FW"559 VALVE -PIPE MT 1-1-01 03.00 0.438 NO FW-16-2-SW-I PIPE -PIPE MT 1-1-01 03.00 0..438 NO FW-SW-E3 PIPE -FLG WNO MT I - r-01 03.00 0.438 NO FW-SW-D3 FLG WNO-PIPE MT 1-1-01 03.00 0.438 NO FW-FW-560 PIPE -VALVE MT 1-1-01 03.00 0.438 NO SYSTEM : FW FEED WATER ISOMETRIC NUMBER': II-FW-003
- FW-FW-579 PIPE -VALVE MT - I-'I-01 03.00 0.438 00000000 ~~ ~~ 0'0000 ~ 00 F 000 't0000004tttttt ~ 00 ~ ~ SttttStd 00000040404000 at 0040 ~ ~ 00 ~ ttttttttttttttttNO~ 0000000tttt ~ 00 ~ ~ 00 ~ 00
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INTERVAL 01 ONLY DATE 88/01/21 CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8, ITEM NO. 6.6.8D AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR t t ~ tttttttttttttttttttttttttttttttttttt~ tttttttttttttt ~ tttttttttttttttttttttttttt~ tttt ~ t ttttttttttttttttttttttttttttttt DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) ( IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : FW FEED WATER ISOMETRIC NUMBER : II-FW-003 FW-FW-582 PIPE -VALVE MT 1-1-01 02.00 0.218 NO FW-25-3A-SW-'I REDUCER-PIPE . MT 1- '1-01 03.00 0.438 NO FW-25-3A-SW-10 ELBOW -PIPE MT 1- 'I -01 02.00 0.218 NO FW-25-3A-SW-2 PIPE -ELB LR MT 1-1 "01 '03.00 0.438 NO FW-25-3A-SW-3 ELB LR -PIPE MT 1-1-01 03.00 0.438 NO FW"25-3A-SW-4 PIPE -ELB LR MT ~ 1-1-01 03.00 0.438 NO FW-25-3A-SW-5 ELB LR -PIPE MT 1-1-01 03.00 0.438 NO FW-25-3A-SW-6 PIPE -TEE . MT 1-1-01 03.00 0.438 NO FW-25-3A-SW-7 TEE -PIPE MT 1-1-01 03,00 0.438 NO FW-25-3A-SW-8 TEE -REDUCER MT 1-1-01 03.00 0.438 NO FW-25-3A-SW-9 REDUCER-ELBOW MT 1-1-01 02.00 0.218 NO FW-FW-567 VALVE -PIPE MT I ~l-01 03.00 0.438 NO FW-SW-C3 PIPE ~ -ELB LR MT 1-1-01 03.00 0.438 NO FW-SW-C4 ELB LR -PIPE MT 1-1-01 03.00 0.438 NO FW-SW-C5 PIPE -ELB LR 'T 1-1-0'I 03.00 0.438 NO FW-SW-C6 -PIPE '1-1-0'I 03.00 0.438 ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt ELB LR MT
~ ttttttttttttttttttttttttttttttttt NO
000000000 ~ ttt0440ttt 0000004000000000000000000000000004000000000040444400000000040404000040000000000000000000000000000 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRI SIN 0 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT I 0 PLANNING 0 00 00044441 1 1 000 1 04 0 AUGMENTED EXAMINATION COMPONENT> LISTING - 806-OI PAGE 4 0 0 EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK 0 REVISION NRCl 0 EXCLUSION REGION PER FSAR SECTION 6.6.8 - INTERVAL 01 ONLY DATE 88/01/21 0000 10 1 000 00000000 0 000040004000000000000t401000000410000tttttttttttt4400 ~ 0104401041000000000014ttttttttt ~ 000100000 0 CA TEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8, 0 ITEM NO. 6;6.8D AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR 1 0000000000000004400 00010000000000t0000004ttttttt00040040000000000040440 ~ 00004400000t0010040000000000110404004440404 DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE 'ULEO INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : FW FEED WATER ISOMETRIC NUMBER: I I-FW-003 FW-SW"C7 PIPE -ELB LR MT 1-1-01 03.00 0.438 NO FW-SW-CB ELB LR -PIPE MT I-'I-01 03.00 0.438 NO FW-SW-C9 PIPE "ELB LR MT 1-1-01 03.00 0.438 NO FW-FW-568 ELB LR -PIPE MT 1-1-0 I 03.00 0.438 NO FW-FW-565 VALVE -PIPE MT 1-1-01 03.00 0.438 NO FW-17-2-SW-2 PIPE -PIPE MT 1-1-01 03.00 0.438 NO FW-SW-E3 PIPE -FLG WNO MT 1-1-01 03.00 0.438 NO FW-SW-03 FLG WNO-PIPE MT 1-1-0 I 03.00 0.438 NO FW-FW-566 PIPE -VALVE MT 1-1-01 03.'00 0.438 NO SYSTEM : FW FEED WATER ISOMETRIC NUMBER: II-FW-004 FW-FW-575 PIPE -VALVE MT 'I-1-01 03.00 0.438 NO FW-FW-580 PIPE -VALVE MT I- )-01 02.00 0.218 NO FW-25-IA-SW-I REDUCER-PIPE MT 1-1-01 03.00 0.438 NO FW-25-1A-SW-10 ELBOW -PIPE MT 1-1-01 02.00 0.218 NO FW-25-IA-SW-2 PIPE -ELB LR MT I- I-01 03.00 0.438 NO FW-25-IA-SW-3 ELB LR -PIPE MT 1-1-01 03.00 0.438 NO 0 ~ 00400 ~ 10000004011004014000 ~ ~ 44 ~0~ 000104104140 ~~ 114111144 ~1~~1~~ 01 ~~ 000 ~~ 0111010 ~ 10 4 1 404 1 400 004 00 000 1 0 00 1 0 00 04 040 10
000404 ~j440444044044440000400040400 ~ 044040444f4444f44t414040 ~ Offkt44f440444444444004t 000040t0444440404040444 4 TECH CAROLINA POWER 8 L GHT COMPANY PRISIM 0 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 0 PLANNING 400404044000400f404 AUGMENTED EXAMINATION COMPONENT LISTING - 806-01 PAGE 5 EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK REVISION NRCl 4 EXCLUSION REGION PER FSAR SECTION 6.6.8 - INTERVAL 01 ONLY DATE 88/01/21 Ot ~ Ot4 ~ 0 ~ Oit000004440440 ~ 044404000 ~ f4440 ~ 40010f44404f44404l ~ 04440t040 ~ 44t4 ~ i4040f44t4044 ~ 44401 40144040000404 ~ 4004004t 4 4 CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8, ITEM NO. 6.6.8D AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR 4 0004 ~ 0400000000004004044t4440 ~ 0000 ~ 44444400444044044404444t444400440444040440404000044e04400 44004040tOtOOt440440444 DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE OULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : FW FEED WATER ISOMETRIC NUMBER: II-FW-004 FW-25-1A-SW-4 PIPE -ELB LR MT 1-1-01 03.00 0.438 NO FW-25-1A-SW-5 ELB LR -PIPE MT 1-1-01 03.00 0.438 NO FW-25-1A-SW-6 PIPE -TEE MT '1-1-01 03.00 0.438 NO FW-25-IA-SW-7 TEE -PIPE MT 1-1-01 03.00 0.438 NO FW"25-1A-SW-8 TEE -REDUCER MT 1-1-01 03.00 0.438 NO FW IA-SW-9 REDUCER-ELBOW MT 1-1-01 02.00 0.218 NO FW-SW-D3 FLG RFW-PIPE MT, 1-1-01 03.00 0.438 NO FW-FW-571 PIPE -VALVE MT 1-1-01 03.'00 0.438 NO FW-FW-572 VALVE -PIPE MT 1-1-01 03;00 0.438 NO FW-SW-C3 PIPE -ELB LR MT 1-1-01 03.00 0.438 NO FW-SW-C4 ELB LR -PIPE MT 1-1-01 03.00 0.438 NO FW-SW-CS PIPE -ELB LR MT 1-'1-01 03.00 0.438 NO FW-SW-C6 ELB LR -PIPE 1-1-01 03.00 0.438 NO FW"SW-C7 PIPE -ELB LR MT 1-1-01 03.00 0.438 NO FW-18-4-SW-1 ELB LR -PIPE MT 1-1-01 03.00 0.438 NO FW-SW-C9 PIPE -ELB LR MT 1-1-01 03.00 0.438 0000004040000400004444044tt400000t444004004tbf00044044400400004 0~ ti ~0 NO OOft4440440044404400440404t400404444444
tttttt tttttttttttttttttttttttttttttttttttttttttttt~ ttttt jbtttttt i
~ ttttttttttttttttttttttttttttttttttttttt ufECH CAROLINA POWER 8 LIIJHT COMPANY PRI SIM t SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 t 'UGMENTED PLANNING EXAMINATION COMPONENT LISTING 806-0'1 ttttttttttttttt PAGE 7 EXAMINATION OF MAIN STEAM AND FEEDWATER PIPING IN THE BREAK REVISION NRCl EXCLUSION REGION PER FSAR SECTION 6,.6.8 INTERVAL 01 ONLY DATE 88/0 1/2'I tttttttttttttttt~ tttt~ tttttttttt t t tt t t t t t tt t t t t t t t t t t t t ttttttttttttttttttt t t t ~ t t t 't t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8, ITEM NO. 6.6.8D AUGMENTED PIPING WELD VOLUMETRIC EXAMINATION PER FSAR tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt ~ ~ ttttttttttttt hattt ~ t ~ t ~ tttt ttttttttttttttttttt DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM: MS MAIN STEAM ISOMETRIC NUMBER: II-MS-009 MS-44-2-SW-3 ELB LR -PIPE 1-2-03 03.00 0.300 NO MS-FW-586 PIPE -VALVE MT 1-2-03 03.00 0.300 NO MS-FW-588 PIPE -ELB LR MT 1-3"06 03.00 0.300 NO MS-45-1-SW-1 ELB LR -PIPE MT 1-3-06 03.00 0.300 NO MS-45-1-SW-2 PIPE -ELB LR MT 1-3-06 03.00 0.300 NO MS-45-1-SW-3 ELB LR -PIPE MT 1-3-06 03.00 0.300 NO MS-FW-589 PIPE VALVE MT 1-3-06 03.00 0.300 NO MS-FW-582 PIPE -ELB LR MT 1-1-01 03.00 0.300 NO MS-44-'I-SW-1 ELB LR -PIPE MT 1-1-01 03.00 0.300 NO MS-44-1-SW-2 PIPE -ELB LR MT 1-1-01 03.00 0.300 NO MS 1-SW-3 ELB LR -PIPE 1-1-01 03.00 0.300 NO MS-FW-583 ttttttttttttttttttttttt PIPE
~
-VALVE ttttttttttttttttttttttMT 1-.1-01 03.00 0.300 t'tttttttttttttttttt ~ ttttttttttttttttttttttttttttttttttttttttt NO
P E
0 ffffff ~ f 1000 0000 0 Of f Of 000 00 00 0 0 ~ 0 0 t 0 0 ~ 0 00 t t 00 0 0 t 0 0 t 0 0 0 f 0 f 0 0 0 0 00000t tf 0 t f 00 0 0 0 0 00 0 0 0 0 0 0 t 0 ft f 0 0 0 0 0 0 tf f 0 t f Oft 0 IECH CAROLINA POWER 8, LIGHT COMPANY PRISIM 0 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 PLANNING 0 0000000000 ~ 0 0 0000 0 AUGMENTED EXAMINATION COMPONENT LISTING - 807-01 PAGE 1 EXAMINATION OF PIPING BETWEEN ISOLATION VALVES THROUGH REVISION NRCl PENETRATIONS PER FSAR SECTION 6.6.8. - INTERVAL 1 ONLY DATE 88/01/21 000000 0 00 0 0 0 tf 00 f 000 0 000 000000000 0 0000000000000000000000000000000000000000000000 ~ 000 ~ fffffftt0000000000000000000 F 0000 0 CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8 0 ITEM NO. 6.6.BE AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR Offfffftffffff0000000000000000000
~ 0000 ~ Ot Oft ttf 0~ 000 ~ ttf 0 f 0 f tf tf 0000 tf Of 00 00 tf tf ff 0000 0 ~ 00 0 0 0 0000 f 000 000 Of 0 Of Of tf 0 DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DUL.EO INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES SYSTEM : BD BLOWOOWN ISOMETRIC NUMBER : II-80-001 BD-FW-1 FL HEAD-P BEND MT 1-3-06 04.00 0.237 NO BD-SW-AB P BEND -P BEND MT 1-3-06 04.00 0.237 NO BD-FW-2 P BEND -VALVE MT 1-3-06 04.00 0.237 NO SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER: I I-BD-002 BO-FW-4 FL HEAD-P BEND MT 1"3-06 04.00 0.237 NO 80-SW-A3 P BEND -P BEND MT 1-3-06 04.00 0.237 NO 80-FW-5 P BEND -VALVE MT 1-3-06 04.00 0.237 NO SYSTEM : BD BLOWOOWN ISOMETRIC NUMBER : II-BD-003 80-FW-7 FL HEAD-P BEND MT 1-3-06 04.00 0.237 NO BD-SW-AB P BEND -P BEND MT 1-3-06 04.00 0.237 NO BD-46-1-SW-1 PIPE . -PIPE MT 1-3-06 04.00 0.237 NO BD-FW-8 P BEND -VALVE MT 1-3-06 04.00 0.237 NO SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER : II-BD-007 BD-FW-312 ELB LR -PIPE MT 1-2-03 04.00 0.237 NO BD-FW-313 -FL 1-2-03 t ~ ~ 000 00 ~ 00000 0 000 ~ 000 000 0 ~ Of ~ 00 0 tf 00 ~ f 0 ~ 0 0 ~ 0 ~ 00 00 0 0 0 0 0 tf 0 04.00 0.237 P BEND HEAD MT NO 0 ~ ~ ~ 00 ~ 00 00 0 0 ~ ~ 00000 0 ~ ff tf 0 000 0 0000 ~ 0 00 0 0 00 0 f 00 0 0tf 0 ~ 0 ~ ~ 0 0 0
~ l Pr\ 14, 1 ~ '\'1, 11 ~ h 'h ~ rl 4P 0'ill )llhl'1 1( w t h "' " P, ,'i '.' .. ha ~ r . ~ f, h 1 .rh ". r hrh r ~ "r,pv 0 ~ sr rhl 'i' ~ *~ .';. 'll s,' p ~
004000 ~ 40000000000000 ~ 00000000 ~ 0000000004000044tt ~ 0040440404t0400000000000000000004400444040 ~ 000400004000004000044 F 04 0 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 0 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT I 0 PLANNING 04040.04000040000040 AUGMENTED EXAMINATION COMPONENT LISTING 807-0 1 . PAGE 2 EXAMINATION OF PIPING BETWEEN ISOLATION VALVES THROUGH REVISION NRC1 PENETRATIONS'PER FSAR SECTION 6.6.8. - INTERVAL 1 ONLY 88/01/21 0000000000000000000tt 000000000000400 t 0 0 0 0 0 4 4 0 4 4 0 0 4 0 0 4 0 4 0 0 0 0 4 4 0 0 t 0 0 0 t 0 0 4 4 0 0 0 4 0 0 4 0 4 4 4 0 4 4 t 4 0 4 0 t 0 0 0 0 4 0 0 0 0 DATE 000 000000 00000~ 01 0 0 CAT EGORY FSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8 ITEM NO. 6.6.8E AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR 0000 ~ 00040ttttttt ~ 000 tttt400000000000000000t04tttttttt0004000000400004404040000404000 ~ 004400000000004004000000004040 ~ DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT INO REQST TIONS NOTES SYSTEM : 80 BLOWDOWN ISOMETRIC NUMBER : II-BD"007 BD-M53"PW- I PP,FHS-INTERNAL SUR 04.00 0.337 IA NO R2-004 BD-SW-A3 PIPE -ELB LR MT 1-2-03 04.00 0.237 NO 80-SW-A6 PIPE -ELB LR MT 1-2-03 04.00 0.237 NO BD-SW-83 PIPE -PIPE MT 1-2-03 04.00 0.237 NO BD-SW-84 PIPE -PIPE MT 1-2-03 04.00 0.237 NO BD-61-1-SW-1 ELB LR -PIPE MT 1-2-03 04.00 0.237 NO SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER: I I-.80-008 BO-FW-319 PIPE -ELB LR MT 1-2-03 04.00 0.237 NO BD-FW-320 P BEND -FL HEAD MT 1-2-03 04100 0.237 NO BD-M52-PW-I PP,FHS-INTERNAL SUR 04.00 0.337 IA NO R2-004 BD-SW-A3 PIPE -ELB LR MT 1-2-03 04.00 0.237 NO 80-SW-A4 ELB LR -P BEND MT 1-2-03 04.00 0.237 NO BD-SW-AS PIPE -ELB LR MT 1-2-03 04.00 0.237 NO BD-SW-A6 ELB LR -PIPE MT 1-2-03 04.00 0.237 NO BD-SW-A9 P BEND -PIPE MT 1-2-03 04.00 0.237 NO BD-SW-83 ELB LR -P BEND MT 1-2-03 04.00 0.237 NO 0 ~ 000000000 ~ ttt000000 ~ ttt00000000000 ~ 00004040000044 ~ 0044 ~ 0400040000000000000000400000t ~~ ~ t000000400t04000'tttttt ~ 00000
ttt tttttttttttttttttttttttttttttttttttttttttttttttttttttt tttttttttttttttttttttttttttt tttttttttttttttttt JTECH
~
CAROLINA POWER 6 LIGHT COMPANY PRISIM t SHEARON HARRIS NUCLEAR PLANT - UNIT t t t AUGMENTED EXAMINATION PLANNING COMPONENT POWER LISTING - 807-0'I 1 ttttttttttttttttt ~ t t PAGE 3 EXAMINATION OF PIPING BETWEEN ISOLATION VALVES THROUGH REVISION NRC1 PENETRATIONS PER FSAR SECTION 6.6.8. - t DATE 88/O'I/21 tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt INTERVAL 1 ONLY
~ tttttttttttttttttttttttttttttttttttttt CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8 ITEM NO. 6.6.8E AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR t tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt tttttttttttttttttttttt DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER: II-80-008 BD-SW-84 P BEND -ELB LR MT 1-2-03 04.00 0.237 NO BD-SW-85 ELB LR -P BEND MT '1-2-03 04.00 0.237 NO SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER : II-80-009 BD-FW-305 P BEND -ELB LR MT 'I 03 04.00 0.237 NO BO-FW-306 P BEND -FL HEAD MT 1-2-03 04.00 0.237 NO BD-SW-A3 PIPE -ELB LR MT 1-2-03 04.00 0.237 NO BD-SW-A5 P BEND -P BEND MT 1-2-03 04.00 0.237 NO BO-SW-83 ELB LR -PIPE MT 1-2-03 04.00 0.237 NO BD-SW-84 PIPE -ELB LR MT '1-2-03 043)0 0.237 NO BD-SW-85 ELB LR -P BEND MT 1-2-03 04.00 0.237 NO BD-'56-1-SW-1 ELB LR -P BEND MT '1-2-03 04.00 0.237 NO SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER: II-BO-010 BD-FW-206 VALVE -PIPE MT '1-1-01 02.00 0.218 NO BD-FW-310 REDUCER-ELB LR MT 1-1-01 04.00 0.237 NO BD-FW-31'1 -PIPE 1-1-01 t t t t tt t t t t t t t tt t t t tt t t ~ t t t t t t t t t t t tt t t t t t t t t t t t ~ t t t t t ~ t t tt t t t t t t t 04.00 0.237 TEE MT NO t tt t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t t tt t t t tt t tt t t t t t t 't
~
004040004000000 040404040000400004000000044004444 00444044044000000040040400440t 4044044440 00000000000ttt ~ ~ 004000040 0 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRISIM 0 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT I 0 PLANNING 400400t44000 ~ tt0044 AUGMENTED EXAMINATION COMPONENT LISTING - 807-01 PAGE 4 4 EXAMINATION OF PIPING BETWEEN'ISOLATION VALVES THROUGH REVISION NRCI PENETRATIONS PER FSAR SECTION 6.6.8. - INTERVAL I ONLY DATE 88/01/21 ~ 440004004000400040 440004004000000400040404444t0444404400404040t4t000004444t4400tt40 ~~ 00404t 0~ 044 ~ t00040040 ~ 00040040t CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8 0 ITEM NO. 6.6.8E AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR 4 0040t0040400t000400 4t040444040400040444404444 ~ 4444404404 ~ 4044 ~ 0404044 ~ 0044404444444 ~ 4404444 40 ~ t0004400ttttt004004 ~ tt DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER: I I-BD-010 BD-F5SN-MW-1 VALVE -REDUCER MT 1-1-01 03.00 NO BD-SW-A3 ELB LR -P BEND MT 1-1-01 04.00 0.237 NO BD-SW-A4 P BEND -TEE MT I-'1-01 04.00 0.237 NO BD-SW-A5 RED ELB-TEE MT 1-1-01 04.DO 0.237 NO BD-SW-A6 PIPE -RED ELB MT 1-1-01 02.00 0.218 NO SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER: II-80-011 BD-FW-231 VALVE -PIPE MT 1-1-01 02.00 0.218 NO BD-FW-304. REDUCER-ELB LR MT 1-1-01 04.00 0.237 NO BD-FW-305 TEE -PIPE MT 1-1-01 04'00 0.237 NO 80-F6SN-MW-1 VALVE -REDUCER MT 1-1-01 03.00 NO BD-SW-A3 PIPE -RED ELB MT 1-1-01 02.00 0.218 NO BD-SW-A4 RED ELB-TEE MT I-)-01 04.00 0.237 NO 80-SW-A5 P BEND -TEE MT 'I 0 I 04.00 0.237 NO BD-SW-A6 ELB LR -P BEND MT 1-1-01 04.00 0.237 NO SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER: II-BD-012
-PIPE 1-1-01 0.218 t 4 4 4 4 4 4 4 4 4 4 0 4 4 4 4 0 0 0 0 02.00 BD-FW-190 VALVE MT NO 4 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 0 0 0 0 0 0 0 00 0 0 0 0 0 0 0 0 0 0 0 4 0 0 0 4 4 0 0 0 0 0 0 4 0 4 0 0 0 0 0 ~ 0 4 4 4 0 0 0 ~ 0 tt 4 4 0 0 4 0 0 4 4 4 0 0 0 0 0 0 0 0 0 0 4 0 0 0 0 ~ 0
hatt t t ttt ~ttttttttttttt ~ ttt ~ ttt ~ tttt ~ ttttttt ~ ~ t ~ tt tt
~ ~ tttttttttt ttttttttttttttttttttttttttttttttttttttttttttt t
iECH CAROLINA POWER 8 LIGHT COMPANY
- PRI SIM t SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 t
t PLANNING AUGMENTED EXAMINATION COMPONENT LISTING - 807-01 tttttttttttttttttttt t EXAMINATION OF PIPING BETWEEN ISOLATION VALVES THROUGH PAGE REVISION NRC1 5 t PENETRATIONS PER FSAR SECTION 6.6.8. INTERVAL I ONLY tttt t tttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt DATE 88/01/21 ttttttttttttttttttt t t CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT SECTION 6.6.8 t ITEM NO. 6.6.8E AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR tttt tttttttttttttttttttt tt ttttttttttt ttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttttt tt tttttttt
~ ~ ~ ~ ~ ~
DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER: II-BD"012 BD-FW-317 REDUCER-ELB LR MT 1-1-0'I 04.00 0.237 NO BD-FW-318 TEE -PIPE MT 1-1-01 04.00 0.237 NO BD-F4SN-MW-1 VALVE -REDUCER MT 1-1-01 03.00 NO BD-SW-A3 PIPE -RED ELB MT 1-1-01 02.00 0.218 NO BD-SW-A4 RED ELB-TEE MT 1-1-01 04.00 0.237 NO BD-SW-A5 P BEND -TEE MT 1-1-01 04.00 0.237 NO BD-SW-A6 ELB LR -P BEND MT 1-1-01 04.00 0.237 NO SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-004 CS-FW-97 FL HEAD-PIPE PT '1-3-06 03.00 0.216 NO CS-FW-98 PIPE -VALVE PT 1-3-06 03. 00 0. 216 NO SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-026 CS-FW-1 'I 3 VALVE -PIPE PT '1-3-06 01.50 0.281 NO CS-FW-1 12 PIPE -TYPEIIB PT 1-3-06 01.50 0.281 NO SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-027 CS-FW-1420 -PIPE 1-3-06 01.50 0.281 t ~ tttttttttt~ ttttttttttttttttttttttttttttttttt VALVE PT tt ~ ttttttttttttttt~ ttt ~ ttttttttt NO tttttttttt ~ ttttttttt ~ ttt ~ ~ ~ tt ~ ttttttt ~ ~
C 000400 ~ 040t000000044t0t400004400400004000400004444444t04t400404t00t4t00000440t0040400t44tttttt 00400400000440440400004 0 NUTECH CAROLINA POWER 8 LIGHT COMPANY PR IS IM 0 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT I 0 PLANNING 0040004004444444440 AUGMENTED EXAMINATION COMPONENT LISTING - 807-01 PAGE 6 EXAMINATION OF PIPING BETWEEN ISOLATION VALVES THROUGH REVISION NRCI ttttttttttt tttttttttt4000000 0 PENETRATIONS PER FSAR SECTION 6.6.8. - INTERVAL I ONLY DATE 88/01/21 )
~ ~ t000400000044004tttttttttt00044000404040444044040400044t04000000 0000000004000000444444t rCC CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8 C ITEM NO. 6.6.8E AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR ttttttttttttt tttt
~ ~ ttt000040000000000000400ttttttttttttttttt ~ 4004 'tt4404004400444004000400040 0400000004000004 ~~ ttttt DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-027 CS-FW-1421 PIPE -TYPEIIB PT 1-3-06 01.50 0.281 NO SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-033 CS-FW-1437 VALVE -PIPE PT 1-3-06 01.50 0.281 NO )
t CS-FW-1438 PIPE -TYPEI IB PT 1-3-06 01.50 0.281 NO
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SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-088 CS-M9-PW-1 PP,FHS-INTERNAL SUR 01.50 0.281 IA NO R2-004 CS-FW-1467 TYPEI IB-PIPE PT 1-1-01 01.50 0.281 NO CS-FW-1468 PIPE -VALVE PT 1-1-01 01.50 0.281 NO SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER: I I-CS-089 CS-FW-1998 VALVE -PIPE PT 1-3-06 02.00 0.154 NO CS-FW-1999 PIPE -RED ELB PT 1-3-06 02. 00 0. 154 NO CS-FW-1992 VALVE -PIPE PT 1-3'-06 02.00 0.154 NO CS-FW-1993 PIPE -SOCKOLT PT 1-3-06 02.00 0.154 NO CS-SW-86 RED ELB-PIPE PT 1-3-06 03.00 0.216 NO CS-SW-89 PIPE I"3-06 03.00 0.216 000 ~ 000044000ttttt ~ 0400000 ~ ttttttttt
-SOCKOLT PT
~ 000000'400040ttttttttttttttt ~ ~ ~ t40000000000 ~ ~ tttttttttttttt tttttttttttt 04001000 NO
~ ~
0000000 300000t0400 ~ 040000000000400000004400004404400040440044 ~ 0040004t444000000000 000 ~ 0000040000004000000000 0 IECH CAROLINA POWER P LIGHT COMPANY 4 PRISIM 0 SHEARON HARRIS NUCLEAR POWER PLANT UNIT I 0 0 ~ PLANNING 4000000000004000ttt AUGMENTED EXAMINATION COMPONENT LISTING - 807-01 PAGE .- . 7 0 EXAMINATION OF PIPING BETWEEN ISOLATION VALVES THROUGH REVISION NRCI 0 PENETRATIONS PER FSAR SECTION 6.6.8. INTERVAL I ONLY DATE 88/01/21 0000000000000000t400040000400000000000000400400000040t000t4t4J0t0t0400tt0t0040000000000000 0000000 ~ 000000040000000ttt F, l CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8 ITEM NO. 6.6.8E AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR d 0 000000000000000tt400000000400000000000000444400440tttttt ~ 0040404ttt000040040040040004000ttt 40004t40000040440000004000 DONE ~3 lw'I 3 OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER: I I-CS-089 i CS-SW-88 PIPE -SOCKOLT PT 1-3"06 03.00 0.216 NO CS-SW-85 PIPE -TEE PT I-3-06 03.00 0.216 NO CS-SW-87 TEE, -PIPE PT 1-3-06 03.00 0.216 NO "4 CS-FW- I 771 PIPE -ELB LR PT 1-3-06 03.00 0.216 NO d CS-SW-A3 ELB LR -PIPE PT 'I 06 03.00 0.216 NO CS-FW-3027 PIPE -FL HEAD PT I-3-06 03.00 0.216 NO CS-M7-PW-I PPeFHS INTERNAL SUR 03.00 0.216 IA NO R2-004 3 CS-FW-'I986 VALVE -PIPE PT 1-3-06 02.00 0. 154 NO 3 l., CS-FW-1987 PIPE -RED ELB PT I-3-06 02.00 0. 154 NO CS-SW-83 RED ELB-PIPE PT 1-3-06 02.00 0.154 NO CS-SW-84 PIPE -TEE PT I"3-06 02.00 0. 154 r, d SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-103 CS-M I 0-PW- 'I PP,FHS-INTERNAL SUR 01.50 0.281 IA NO R2-004 C CS-FW-2097 TYPEIIB-PIPE PT 1-2-03 01.50 0.281 NO CS-496-I-SW-2 PIPE -RED TEE PT 1-2-03 01.50 0. 281 NO CS-496-I-SW-I RED TEE-PIPE PT 1-2-03 01. 50 0. 281 NO 00000004000000000000000000000400'00440400044040004t044000400040400044440 4000044440000000000000000044000000400t00000000
00400 ~ tt00400040040000040 ttttt0040400000400440400404400t0440t ~ 00004000400040004t000000000004t000000000004000000 ~ tt440 NUTECH CAROLINA POWER 8 LIGHT COMPANY PRI SIM 0 SHEARON HARRIS NUCLEAR POWER PLANT - UNIT 1 4 PLANNING 400000044 ~ 000004440 0 AUGMENTED EXAMINATION COMPONENT LISTING - 807-01 PAGE 8 0 EXAMINATION OF PIPING BETWEEN ISOLATION VALVES THROUGH REVISION NRCI PENETRATIONS PER FSAR SECTION 6.6.8. - INTERVAL I ONLY DATE 88/01/21 0400 ~ 00004000000404404t 400t40444000400044t4044440040000004000444400044400404444044004004040440040044t04004t400440tt CATEGOR Y FSAR FINAL SAFETY ANALYSIS REPORT . SECTION 6.6.8 ITEM N 0. 6.6.8E AUGMENTED PIPING WELD SURFACE EXAMINATION PER FSAR 0 000000ttttttttt40000ttttt 0000040000000400040404404040040400040400 ~ 00404000 ~ ~ 40400404400004t000400404tt4000000ttt00400 DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER : II-CS-'103 CS-FW-2098 PIPE -VALVE PT 1-2-03 01.50 0.281 NO SYSTEM : CS CHEMICAL AND VOLUME CONTROL ISOMETRIC NUMBER: II-CS-107 CS-Ml I-PW- I PP,FHS-INTERNAL SUR 01.50 0.281 IA NO R2-004 CS-FW-2071 TYPEI I 8-PIPE PT 1-1-01 01.50 0.281 NO CS-SW-C4 PIPE -RED TEE PT 1-1-01 01.50 0.281 NO CS-539-1-SW-1 RED TEE-PIPE PT 1-1-01 01.50 0.281 NO CS-Fd-2072 PIPE -VALVE PT 1-1-01 01.50 0.281 NO 00000000000ttt ~ 040004000000000400000040004404 ~ 004400000000004004040000404404440444000000 F 00400 ~ 044000400444tttttttttt
00 ~ 0000 00000000000000000000000000000000000000000000000000000 c~eeeeeeete F 000000000000 0000000000000000000tete iECH CAROLINA POWER 8 L HT COMPANY PRISIM 0 SHEARON HARRIS NUCLEAR POWER PLANT UNIT I 0 PLANNING 0000 ~ 00000000000000 0 AUGMENTED EXAMINATION COMPONENt LISTING 807-01 0 PAGE 9 EXAMINATION OF PIPING BETWEEN ISOLATION VALVES THROIJGH REVISION NRCI 0 PENETRATIONS PER FSAR SECTION 6.6.8. - INTERVAL 1 ONLY DATE 88/01/21 000000000e000000000t0000ee00t000t000000e0e0000e000e0000000ee0ee000ee00000000t000t000000000tee 00000000000000teeeeeteee 0 CATEGORY FSAR FINAL SAFETY ANALYSIS REPORT - SECTION 6.6.8 0 ITEM NO. 6.6.8F AUGMENTED WELDED ATTACHMENT SURFACE EXAMINATION PER FSAR 000 't000000000000000000t0000000000000t0000ee000t000000000tt0t000000t0ee0000000000000eteeeeee eeeeeetteteeeeeeetetttet DONE OUTAGE THIS DONE COMP NOM. BASIS PSI COMPONENT COMPONENT EXAM SCHE- OUT/ PRIOR DIAM THCK TO TRV RELIEF EXEMP- PROGRM NUMBER DESCRIPTION TYPE DULED INT INT (IN) (IN) ACCESS SELECT IND REQST TIONS NOTES SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER : II-BD-007 BD-H-0015 I (8) PIPE -LUG, PP MT 1-2-03 04.00 0.500 NO SYSTFM : BD SLOWDOWN ISOMETRIC NUMBER : II-BD-009 BD-H-0031I(2) PIPE -TRUNNON MT 1-2-03 04.00 0. 154 NO SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER: II-BD-010 BD-H-409I(2) PIPE -TRUNNON MT 1-1-01 04.00 NO SYSTEM : BD BLOWDOWN ISOMETRIC NUMBER: II-BD"O'II BD-H-0513 I (4) PIPE -LUG, PP MT 1-1-01 04.00 NO 0000000000000000000000 '0000000 ~ eeeeteeeeeeeeeeteteee ~ 00000000000teteeteeee ~ eeeeteteeeeetttt ~ 00000 '0000000 '00000000 4 4 4 W- ~ i@4 4 W 44 4 4 W V 4 W 4 4 ' 4 = 44( 4 V+
SELECTION RECORDS EXAM S COMPNOEX EXREO CATEGORY EXREQ ITEMNO EXAM EXREO EXSCHD OUTAGE SELECT REOUEST EXAM EXEMPT EXOATE CREDIT NOEPROC CALSTO COMP SYSTEM COMPDES ACCESS 1 ACCESS 2 ACCESS 3 COMP
- ACCESS 4 ACCESS 5 ACCESS 6 TRANSIN TENRMKS COMP NEWCOMNO ORDER COMPDIA NOMTHCK REFDWG 9 Collp OLOCOMNO 10 PICK EXREQ EQS S01-01 11 6 RECORDS HAVE BEEN SELECTED 12 13 l4 SELECTEO DATA RECORD FORMAT 15 CIIRSOO'Sl'Z RC '
CSZSS SRRl!$ $ $ 18 17 ELEMENT LENGTH STARTING COL. 18 19 COMPNOEX 24 1 20 EXREO 6 25 21 CATEGORY 6 31 22 EXREO 6 37 23 ITEMNO 6 43 24 EXREO 6 49 25 EXSCHD 6 55 28 OUTAGE 6 61 27 SELECT 6 67 28 REOUEST 6 73 29 EXEMPT 6 79 30 EXOATE 8 85 31 CREDIT 93 32 NDEPROC ,.6 94 33 CALSTD 6 100 34 SYSTEM 3 106 35 COMPOES 15 109 38 ACCESS 2 124 37 ACCESS 2 2 126 38 ACCESS 3 2 128 39 ACCESS 4 2 130 40 ACCESS 5 2 132 4I ACCESS 6 2 134 42 TRANSIN 1 136 43 TENRMKS 6 137 44 NEWCOMNO 24 143 45 ORDER 4 167 48 COMPDIA 5 171 47 NOMTHCK 5 176 48 REFOWG 16 181 49 OLOCOMNO 24 197 50 51 52 53 54 55 58 57 58 59 80 FOAM 0113 {02I83)}}