ML20213E734
| ML20213E734 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/10/1986 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20213E713 | List: |
| References | |
| NLS-86-399, PROC-861110, NUDOCS 8611130271 | |
| Download: ML20213E734 (45) | |
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ATTACHMENT 1 TO SERIAL NLS-86-399 BRUNSWICK UNIT NOS.1 AND 2 INTERVAL 2 IN-SERVICE INSPECTION PROGRAM l
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CAROLINA POWER & LIGHT COMPANY'S INSERVICE INSPECTION PROGRAM FOR BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 SECOND INSPECTION INTERVAL i
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REVISION CONTROL SHEET DOCUMENT: INSERVICE INSPECTION PROGRAM BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 CPL-02 EFFECTIVE PAGES REVISION 1-27 o e
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l TABLE OF CONTESTS P_,aL*
1.0 IhTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . , i 2.0 APPLICABLE CODES . . . .................... 1
.s 3.0 PROGRAM DESCRIPTION. .................,... p, 4.'0 PROGRAM TABLES . .....................,, 4 5.0 RELIEF REQUESTS. ....................... 15 6.0 CODE CASES .
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7.0 AUGMENTED INSPECTIONS.
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I CPL-02 11 Rev. 0
1.0 INTRODUCTION
1.1 The program contained in this document outlines the Inservice Inspection Program for the Second Inspection Interval at Carolina Power & Light Company's 3runswick Steam Electric Plant, Units 1 and 2.
1.2 The Second Inspection Interval covers the period from July 10, 1986, through July 10, 1996, pursuant to relief granted by the Commission to begin a common interval for both Brunswick units effective July 10, 1986.
1.3 The inspection period dates are indicated below:
1st inspection period July 10, 1986, to November 10, 1989 2nd inspection period November 11, 1989, to March 10, 1993 3rd inspection period March 11, 1993, to July 10, 1996 As permitted by Section XI, the inspection periods specified above and the inspection interval may be decreased or extended (but not cumulatively) by as much as one year to enable an inspection to coincide with a plant outage.
2.0 APPLICABLE CODE 1
4 2.1 The Inservice Inspection Program for the Second Inspection Interval at Brunswick Steam Electric Plant, Unita 1 and 2, meets the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, 1980 edition through and including the 1981-Winter Addenda. All references in this document to Section XI refer to 3 the 1980 edition through and including the Winter 1981 Addenda unless specifically noted otherwise. Where the requirements of Section XI have been determined to be impractical, specific relief has been requested.
2.2 As permitted by 10 CFR 50.55a(b)(2), the extent of' examination (number of welds to be examined) for Class 1 piping welds will be
, determined by the requirements of Table IWB-2500 and Table i
IWB-2600, Category B-J, of Section XI of the ASME Code in the 1974 Edition and Addenda through the Summer 1975 Addenda.
4 2.3 As indicated in Section 6.0 of this document, the extent of examination for Class 2 piping welds will be determined in i-accordance with the requirements of Code Case N-408.
CPL-02 Rev. 0 1
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BRUNSWICK STEAM ELECTRIC PLANT I
UNITS 1 AND 2 i
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3.0 PROGRAM DESCRIPTION 3.1 The following is included in the tables:
3.1.1 Category and Category Description - The Section XI
' Examination Category and its description as defined in Tables IWB-2500-1, IWC-2500-1, IWD-2500-1, and IWF-2500-1 for Class 1, 2, and 3 components are listed.
3.1.2 Item. Number and Item Number Description - The Item Number and its description as defined in Tables IWB-2500-1, IWC-2500-1, IWD-2500-1, and IWF-2500-2 are provided. All item numbers and applicable item descriptions are listed for each category.
3.1.3 Section XI Exam Required - The examination method or methods required per Section XI have been included. The i
abbreviations used are as follows:
SURF - Surface examination per IWA-2220 '
VOL - Volumetric examination per IWA-2230 VT Visual examination per IWA-2211 VT Visual examination per IWA-2212 VT Visual examination per IWA-2213 VT Visual examination per IWA-2214 3.1.4 Relief Requests - Relief request numbers (RR- ) reference a specific relief request contained in Section 5.0. It should be noted that Section 5.0 contains some generic relief requests that are not specifically referenced in the tables but apply to the ISI Program in general.
3.1.5 Alternate Exam - The examination method (s) that will be performed in lieu of the required Section XI method (s),
when relief has been requested, is included.
3.1.6 Remarks - General clarification remarks have been included where appropriate. N/A indicates not applicable since no components exist that would be included with the subject item number.
3.2 Pursuant to paragraph IWB-1220(a), the maximum size line break that can be made up by the Reactor Coolant Makeup System has been calculated to be 1.15 inches inside diameter for liquid carrying lines and 2.3 inches for steam carrying lines. ,
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SECTION 4.0 INSERVICE INSPECTION PROGRAM TABLES FOR BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 e
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INSERVICE INSPECTION PROGRAM TABLE 4.0 PO O ISI - CLASS 1, 2, AND 3 COMPONENTS y@ Page 1 of 10 BRUNSWICK STEAM ELEC'RIC PLANT - UtlTS 1 AND 2
- 1 CODE ITEM SECT Xi EXAM RELIEF ALTERNATE oO DATEGORY NUMBER ITEM DESCRIPTION REQUIRED REQUESTS EXAM REMARKS B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL Bl.10 Shell Welds RR-2 81.11 Ci rcumfe rent ia l VOL ONE BELTLINE REClON WELD Bl.12 Longitudinal VOL ONE BELTLINE REC 10N WELD B1.20 Head Welds B1.21 C i rcumfe rent ia l VOL ONE WELD Bl.22 Herid iona l VOL ONE WELD B1.30 Shell-to-Flange Weld VOL B1.40 Head-to-Flange Weld VOL AND SURF B1.50 Repai r Welds VOL N/A B-B PRESSURE RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS N/A B-D FULL PENETRATION WELDS OF NOZZLES IN VESSELS - INSPECTION PROGRAM B Reactor Vessel B3.90 Nozzle-to-Vessel Welds VOL on B3.100 Nozzle inside Radius Section VOL Pressurize r B3.110 Nozzle-to-Vessel Wolds N/A B3.120 Nozzle inside Radius Section N/A Steam Generators ( Prima ry Side)
B3.130 Nozzle-to-Vessel Welds N/A B3.140 Nozzle inside Radius Section N/A Heat Exchangers ( Prima ry Side)
B3.150 Nozzle-to-Vessel Welds N/A B3.160 Nozzle inside Radius Section N/A B-E PRESSURE RETAINING PARTIAL PENETRATION
- WELDS IN VESSELS B4.10 Pa rt ia l Penetration Welds EXTERNAL SURFACES B4.11 Vessel Nozzles VT-2 B4.12 Control Rod Drive Nozzles VT-2 B4.13 Instrumentation Nozzles VT-2 Pressu ri ze r 84.20 Heater Penetration Welds N/A
INSERVICE INSPECTION PROGRAM TABLE 4.0 fQ
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ISI - CLASS 1, 2, AND 3 COMPONENTS BRUNSWICK STEAM ELECTRIC PLANT - UPITS 1 AND 2 Page 2 of 10
- 8 CODE ITEM SECT XI EXAM RELIEF ALTERNATE c) O CATECORY NUMBER ITEM DESCRIPTION REQUIRED REQUESTS EXAM REMARKS B-F PRESSURE RETAINING DISSIMILAR METAL WELDS Reactor Vessel B5.10 Nominal Pipe Size 2 4" Nozzle-to-Safe End Butt Welds VOL AND SURF B5.11 Nominal Pipe Size < 4" ^
Nozzle-to-Safe End Butt Wolds SURF B5.12 Nozzle-to-Safe End Socket Welds N/A Pres su rize r -
B5.20 Nominal Pipe Size 2 4" Nozzle-to-Safe End Butt Welds N/A B5.21 Nominal Pipe Size < 4" Nozzle-to-Safe End Butt Welds N/A .
85.22 Nozzle-to-Safe End Socket Welds N/A Steam Generator B5.30 Nominal Pipe Size 2 4" Nozzle-to-Safe End Butt Welds N/A B5.31 Nominal Pipe Size < 4" Nozzle-to-Safe End Butt Welds N/A B5.32 Nozzle-to-Safe End Socket Welds N/A Heat Exchangers B5.40 Nominal Pipe Size 2 4" C'
Nozzle-to-Safe End Butt Welds N/A B5.41 Nominal Pipe Size < 4" Nozzle-to-Safe End Butt Welds N/A B5.42 Nozzle-to-Safe End rocket Welds N/A Piping B5.50 Nominal Pipe Size 2 4" Dissimila r Meta l Butt Welds VOL AND SURF B5.51 Nominal Pipe Size < 4" Dissimilar Metal Butt Welds SURF B5.52 Dissimilar Metal Socket Welds N/A
! B-G-1 PRESSURE RETAINING BOLTING, GREATER THAN 2" IN DIAMETER Reactor Vessel B6.10 Closure Head Nuts SURF B6.20 Closure Studs, in Place VOL B6.30 Closure Studs, When Removed SURF AND VOL B6.40 Threads in Flange VOL B6.50 Closure Washers, Bushings VT-1 .
Pressu rize r 86.60 Bolts and Studs N/A
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INSERVICE INSPECTION PROGRAM fQ
< r* ISI - CLASS 1, 2, AND 3 COMPONENTS TABLE 4.0 Page 4 of 10 BRUNSWICK STEAM ELECTRIC PLANT - UN TS 1 AND 2 CODE ITEM SECT XI EXAM RELIEF
- c)['$ CATEGORY NUMBER ITEM DESCRIPTION REQUIRED REQUESTS ALTERNATE EXAM REMARKS Piping B7.50 Bolts, Studs, and Nuts VT-1 Pumps B7.60 Bolts, Studs, and Nuts VT-1 Valves 87.70 Bolts, Studs, and Nuts VT-1 CRD Housings B7.80 Bolts, Studs, and Nuts VT-1 WHEN DISASSEMBLED B-H INTEGRAL ATTACHMENTS FOR VESSELS Reactor Vessel B8.10 Integrally Welded Attachments SURF Pressurizer B8.20 integrally Welded Attachments N/A Steam Generator B8.30 Integrally Welded Attachments N/A o3 Heat Exchangers 88.40 Integrally Welded Attachments N/A B-J PRESSURE RETAINING WELDS IN PIPING B9.10 Nominal Pipe Size 2 4" 89.11 Ci rcumfe ren t ia l Welds SURF AND VOL RR-1 B9.12 Longitudinal Welds SURF AND VOL B9.20 Nominal Pipe Size < 4"
, 89.21 Ci rcumferentia l Welds SURF 89.22 Longitudinal Welds SURF B9.30 Branch Pipe Conr ection Welds 89.31 ' Nominal Pipe Size 2 4" SURF AND VOL B9.32 Nominal Pipe Size < 4" , SURF 89.40 Socket Welds SURF B-K-1 INTEGRAL ATTACHMENTS FOR PirlNG,
) PUMPS, AND VALVES Piping B10.10 Integrally Welded Attachments SURF l
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INSERVICE INSPECTION PROCRAM- TABLE 4.0
,n ISI - CLASS 1, 2, AND 3 COMPONENTS Page 5 or 10 mm BRUNSWICK STEAM ELECTRIC PLANT - UNITS 1 AND ?
< r* CODE ITEM
- SECT XI EXAM RELIEF ALTERNATE o to CATEGORY NUMBER. ITEM DESCRIPTION REQUIRED REQUESTS EXAM REMARKS Pumps B10.20 Integrally. Welded Attachments SURF Valves 810.30 Integra lly Welded Attachments SURF B-L-1, PRESSURE RETAINING WELDS IN PUMP CASINGS D-M-1 AND VALVE BODIES N/A B12.10 Pump Casing Welds ,
N/A -
812.30 Valve Body Welds N/A B-L-2, PUMP CASINGS AND VALVE BODIES B-M-2 B12.20 Pump Casing VT-3 RR-4 WHEN DISASSEMBLED B12.40 Valve Body, Exceeding 4" Nominal Pipe Size VT-3 RR-3 WHEN DISASSEMBLED B-N-1 INTERIOR OF' REACTOR VESSEL Reactor Vessel 8i4.10 Vessel Interior VT-3 ACCESSIBLE AREAS vs Reactor Vessel- (BWR) 813.20 Interior Attachments Within Beltline VT-1 ACCESSIBLE WELDS Region B13.21 Interior Attachments Beyond Beltine VT-3 ACCESSIBLE WELDS Region ,
813.22 Core Support Structure VT-3 ACCESSIBLE SURFACES Reactor Vessel (PWR)
B13.30 Core Support Structure N/A B-0 PRESSURE RETAINING WELDS IN CONTROL ROD HOUSINGS Reactor Vessel 814.10 Welds in CRD Housing SURF B-P ALL PRESSURE RETAINING COMPONENTS Reactor Vessel B15.10 Pressure Retaining Bounda ry VT-2 SYSTEM LEAKAGE PRESSURE TEST B15.11 Pressure Reta ining Bounda ry VT-2 HYDROSTATIC PRESSURE TEST Pressu rize r B15.20 Pressure Reta ining Bounda ry N/A B15.21 Pressure Retaining Bounda ry ,N/A
INSERVICE INSPECTION PROGRAM TABLE 4.0
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ISI - CLASS 1, 2, AND 3 COMPONENTS Page 6 of 10 8
CODE ITEM BRUNSWICK STEAM ELECTRIC PLANT - UNITS 1 AND 2 SECT XI EXAM hELIEF ALTERNATE o k$ CATECORY NUMBER ITEM DESCRIPTION REQUIRED REQUESTS EXAM REMARKS Steam Generators B15.30 Pressure Retaining Bounda ry B15.31 Pressure Retaining Bounda ry N/A N/A Heat Exchangers B15.40 Pressure Retaining Bounda ry B15.41 Pressure Reta ining Bounda ry N/A N/A Piping B15.50 Pressure Retaining Bounda ry VT-2 SYSTEM LEAKAGE B15.51 Pressure Retaining Bounda ry PRESSURE TEST VT-2 . HYDROSTATIC PRESSURE TEST Pumps B15.60 Pressure Retaining Bounda ry VT-2 SYSTEM LEAKAGE B15.61 Pressure Reta ining Bounda ry PRESSURE TEST VT-2 HYDROSTATIC PRESSURE TEST Valves B15.70 Pressure Retaining Bounda ry VT-2 SYSTEM LEAKAGE B15.71 Pressure Reta ining Bounda ry PRESSURE TEST VT-2 ilYDR0 STATIC PRESSURE TEST
__ B-Q STEAM CENERATOR TUBING o N/A C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS C1.10 Shell Circuarerential Welds VOL RHR HEAT EXCHANGER C1.20 Head Ci rcumferentia l Welds VOL RHR HEAT EXCHANGER C1.30 Tubesheet-to-Shell Wold N/A C-B PRESSURE RETAINING N0ZZLE WELDS IN VESSELS C2.10 Nozzles in Vessel < }"
Nominal Thickness N/A C2.20 Nozzles in Vessel > j" Nominal Thickness C2.21 Nozzle-to-Shell Weld VOL AND SURF C2.22 Nozzle inside Radius Saction RilR llEAT EXCilANGER VOL RHR HEAT EXCHANGER C-C INTEGRAL ATTACliMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES
INSERVICE INSPECTION PROGRAM TABLE 4.0 p, n ISI - CLASS 1, 2, AND 3 COMPONENTS Page 7 of 10 u no BRUNSWICK STEAM ELECTRIC PLANT - UN TS 1 AND 2
< r* CODE ITEM
- SECT XI EXAM RELIEF ALTERNATE oN
$ CATECORY NUMBER. ITEM DESCRIPTION REQUIRED REQUESTS EXAM REMARKS Pressure Vessels C3.10 Integrally Welded Attachments SURF RHR HEAT EXCHANGER Piping C3.40 Integra lly Welded Attachments SURF Pumps C3.70 Integrally Welded Attachments N/A Valves C3.100 Integrally Welded Attachments . N/A i C-D PRESSURE RETAINING BOLTING CREATER THAN 2" IN DIAMETER
- Pressure Vessels C4.10 Bolts and Studs N/A Piping
. C4.20 Bolts and Studs N/A 4
Pumps C4.30 Bolts and Studs VOL HPCI PUMP STUDS
>- Valves C4.40 Bolts and Studs N/A C-F-1 PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL OR HICH ALLOY PIPING N/A SEE CODE CASE N-408 C-F-2 PRESSURE RETAINING WELDS IN CARBON OR LOW ALLOY STEEL PIPING SEE CODE CASE N-408 f C5.50 Piping Welds > 3/8" Nominal Wall Thick-l ness for Piping > 4" NPS t
C5.51 . Ci rcumferentia l Weld SURF AND VOL C5.52 Longitudinal Weld SURF AND VOL C5.60 Piping Welds > 1/5" Nominal Wall Thick-ness for Piping > 2" NPS and < 4" NPS C5.61 Ci rcumferential Weld N/A C5.62 Longitudinal Weld N/A C5.70 Socket Welds N/A .
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INSERVICE INSPECTION PROCRAM TABLE 4.0 po n ISI - CLASS 1 2, AND 3 COMPONENTS Page 8 of 10 W Ns BRUNSWICK STEAM ELECTRIC PLANT - UNITS 1 AND 2' 47o CODE CATECORY ITEM NUMBER ITEM DESCRIPTION SECT XI EXAM REQUIRED RELIEF ALTERNATE REQUESTS EFAM REMARKS oN C5.80 Pipe Branch Connections of Branch Piping
> 2" NPS C5.81 Circumferentia l Weld N/A C5.82 Longitudinal Weld N/A C-G PRESSURE RETAINING WELDS IN PUMPS AND N/A' VALVES C-H ALL PRESSURE RETAINING COMPONENTS .
Pressure Vessel C7.10 Pressure Retaining Components VT-2 SYSTEM FUNCTIONAL PRESSURE TEST . '
C7.20 Pressure Retaining Components VT HYDROSTATIC PRESSURE TEST 4
1 Piping C7.30 Prnssure Retaining Components VT-2 SYSTEM FUNCTIONAL ll PRESSURE TEST
] C7.40 Pressure Retaining Components .VT HYDROSTATIC PRESSURE TEST Pumps C7.50 Pressure Retaining Components VT-2 SYSTEM FUNCTIONAL PRESSURE TEST g C7.60 Pressure Reta ining Components VT-2 HYDROSTATIC PRESSURE TEST Valves t C7.70 Pressure Retaining Components VT-2 SYSTEM FUNCTIONAL PRESSURE TEST C7.80 Pressure Reta ining Components VT-2 HYDROSTATIC PRESSURE TEST L
D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION DI.10 Pressure Retaining Components VT-2 SYSTEM FUNCTIONAL PRESSURE TEST l VT-2 HYDROSTATIC PRESSURE TEST DI.20 Integral Attachment
- Component Supports and Restraints VT-3 a
! D1.30 Integra l Attachment 1 - Mechanical and Hydraulic Snubbers VT-3 D1.40 I n teg ra l Attachment
! - Spring-Type Supports VT-3 .
1 D1.50 Integra l Attachment
- Constant Load-Type Supports VT-3 i
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INSERVICE INSPECTION PROCRAM TABLE 4.0 fQ
< ra ISI - CLASS 1, 2, AND 3 COMPONENTS Page 9 of 10
- BRUNSWICK STEAM ELECTRIC PLANT - UMITS 1 AND 2 8
CODE ITEM SECT XI EXAM RELIEF ALTERNATE C)O CATEGORY NUMBER ITEM DESCRIPTION REQUIRED REQUESTS EXAM REMARKS D1.60 I nteg ra l Attachment
- Shock Absorbers VT-3 D-B SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLINC. CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL D2.10 Pressure Retaining Components VT-2 SYSTEM FUNCTIONAL PRESSURE TEST VT-2 HYDROSTATIC PRESSURE TEST D2.20 Integral Attachment .
- Component Support and Restraints VT-3 D2.30 Integra l Attachment
- Mechanical and Hydraulic Snubbers VT-3 D2.40 Integ ra l Attachment
- Spring-Type Supports VT-3 D2.50 Integral Attachment
- Constant Load-Type Supports VT-3 D2.60 Integral Attachment w - Shock Absorbers VT-3 D-C SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL D3.10 Pressure Retaining Components VT-2
, SYSTEM FUNCTIONAL PRESSURE TEST VT-2 HYDROSTATIC PRES $URE TEST D3.20 Integra l Attachment
- Component Supports and Restraints VT-3 D3.30 Integra l Attachment
- Mechanical and Hydraulic Snubbers VT-3 D3.40 Integra l Attachment
- Spring-Type Supports VT-3 D3.50 Integ ra l Attachment
- Constant Load-Type Supports VT-3 D3.60 Integral Attachment
- Shock Absorbers VT-3
.. .1 INSERVICE INSPECTION PROGRAM fQ
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ISI - CLASS 1, 2 AND 3 COMPONENTS TABLE 4.0 Page 10 of 10
- BRUNSWICK STEAM ELECTRIC PLANT - UpIlTS 1 AND 2 ow 5 CODE ITEM NUMBER SECT XI EXAM RELIEF ALTERNATE C_ATECORY ITEM DESCRIPTION REQUIRED REQUESTS EXAM REMARKS F-A PLATE AND SHELL TYPE SUPPORTS F1.10 Mechanical Connections to Pressure Retain-ing Components and Building Structure VT-3 F1.20 Weld Connections to Building Structure VT-3 F1.30 Weld and Mechanical Connections at Intermediate Joints in Multiconnected Integral and Nonintegral Supports VT-3 F1.40 Component Displacement Settings of Guides .
and Stops, Misalignment of Supports, Assembly of Support items VT-3 F-B LINEAR-TYPE SUPPORTS F2.10 Mechanical Connections to Pressure Reta in-ing Components and Building Structure VT-3 F2.20 Weld Connections to Building Structure VT-3 F2.30 Weld and Mechanical Connections at intermediate Joints in Multiconnected g I nteg ra l and Nonintegral Supports VT-3 F2.40 Component Displacement Settings of Guides and Stops, Misalignment of Supports, Assembly of Supporg items VT-3 F-C COMPONENT STANDARD SUPPORTS F3.10 Mechanical Connections to Pressure Retain-ing Components and Building Structure VT-3 F3.20 Weld Connections to Building Structure VT-3 F3.30 Weld and Mechanical Connections at intermediate Joints in Multiconnected Integral and Nonintegral Supports VT-3 F3.40 Component Displacement Settings or Guides and Stops, Misalignment of Supports, Assembly of Support items VT-3 F3.50 Spring-Type Supports, Constant Load-Type Supports, Shock Absorbers, Hydraulic and Mechanical-Type Snubbers VT-4
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SECTION 5.0 INSERVICE INSPECTION RELIEF REQUESTS FOR BRUNSWICK STEAM ELECTRIC PIANT UNITS 1 ANT) 2 S
9 CPL-02 15 Rev. O
RELIEF REQUEST NO. RR-1, REV. O I. APPLICABLE COMPONENTS This request is applicable to the circumferential welds within the following Type A penetrations:
X-7A, B, C, D X-8 X-9A, B X-10 X-11 X-12 X-13A, B X-16A, B X-17 II. IMPRACTICAL TEST REQUIREMENT The flued head assembly to process pipe circumferential weld within each of the aforementioned penetrations is subject to a surface and volumetric examination in accordance with Section XI, Category B-J.
III. BASIS FOR RELIEF The design of the Brunswick Plant was finalized before the access requirements of Section XI were published. These penetrations were fabricated such that there is no access to these welds for performance of the required examinations (see attached sketch). The number of welds affected represents only a small number of the total number of Category B-J welds (15 of approximately 470). Adequate assurance of the weld integrity is verified during the VT-2 examination performed on the affected piping systems each refueling outage during system leakage or hydrostatic pressure tests.
IV. ALTERNATE TESTING The first circumferential pressure retaining weld outside containment on each of the subject penetrations will be examined during the inspection interval.
CPL-02 Rev. 0 16
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RELIEF REQUEST NO. RR-2, REV. O I. APPLICABLE COMPONENTS This request is applicable to the RPV circumferential shell welds DC (see attached drawing).
II. IMPRACTICAL TEST REQUIREMENT l
Section XI requires a volumetric examination of essentially 100% of the weld length of a circumferential beltline region weld (Category B-A).
III. BASIS FOR RELIEF The Brunswick plant designed examination accessibility in accordance with !
the requirements of the 1974 Edition through the Summer 1975 Addenda of )
j Section XI by the installation of permanent tracks to be used by automated equipment. This particular edition and addenda of Section XI required examination of 5% of the weld length of circumferential welds and 10% of the weld length of longitudinal seam welds. The new code requirements was designed for. represent a significant change in examination coverage than l
Space limitations between the RPV and the reflective mirror insulation do l not provide the necessary clearance for utilization of trackless '
automated equipment such as magnetic crawlers.
Removal of the reflective mirror insulation and permanent tracks is impractical due to the high radiation fields (5-15 R/hr) between the RPV and biological shield.
Insulation removal (including tracks) would require in excess of 300 man-hours with an estimated 1500-4500 R exposure.
ALTERNATE TESTING Section XI permits this particular examination to be deferred to the end !
of the inspection interval. Carolina Power &' Light'will keep abreast of any technological advancements that could increase the examination coverage. This. examination will be deferred until the last inspection period.
Based upon the technology available at that time, welds will be examined to the extent feasible.
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RELIEF REQUEST NO. RR-3, REV. O I. APPLICABLE COMPONENTS This request is applicable to the following Class 1 valves which are greater than four-inch nominal pipe size:
B32-F023A B21-F013K E21-F006A B32-F023B B21-F013L E21-F006B B32-F031A B21-F022A E21-F007A B32-F031B B21-F022B E21-F007B B32-F043A B21-F022C E11-F008 B32-F043B B21-F022D Ell-F009 -
B21-F010A B21-F028A E11-F015A B21-F010B B21-F028B Ell-F015B B21-F011A B21-F028C Ell-F017A B21-F0llB B21-F028D Ell-F017B B21-F013A B21-F032A Ell-F050A B21-F013B B21-F0328 E11-F050B B21-F013C E41-F002 Ell-F060A B21-F013D E41-F003 Ell-F060B B21-F013E E41-F006 Ell-F067 B21-F013F E21-F004A C31-F001 B21-F0130 E21-F004B C31-F004 B21-F013H E21-F005A C31-F027 B21-F013J E21-F005B II. IMPRACTICAL TEST REQUIREMENT Section XI requires a visual examination of the valve internal surfaces of one valve in each group of valves of the same constructional design and manufacturing method which perform similar functions in the system (Category B-M-2).
III. BASIS FOR RELIEF The requirement to disassemble primary system valves for the sole purpose of performing a visual examination of the internal pressure boundary surfaces has only a very small potential of increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure.
Performing these visual examinations, such adverse conditions as high dose rates (10 R/hr) and poor as-cast surface conditions, realistically provide little additional information about the valve casing integrity.
For approximately 20 percent of these valves, the reactor vessel core must be completely unloaded and the vessel drained to permit disassembly for examination.
CPL-02 Rev. O _ _ _ _ _
20 _
- o. '
A more practical approach that would essentially provide an equivalent sampling program and significantly reduced radiation exposure to plant personnel is to inspect the internal pressure boundary of only those valves that require disassembly for maintenance purposes. This would still provide a reasonable sampling of primary system valves and give adequate assurance that the integrity of these components is being maintained.
ALTERNATE TESTING An examination of the internal pressure boundary surfaces will be performed, to the extent practical, each time a valve is disassembled for maintenance purposes (once per interval).
' CPL-02 Rev. 0 21 ;
RELIEF REQUEST NO. RR-4, REV. 0 I. APPLICABLE COMPONENT (S)
Brunswick Units 1 and 2 each have two ISI Class 1 recirculation pumps in the Reactor Recirculation System. These pumps provide forced recirculation through the reactor core during normal reactor operation.
II. IMPRACTICAL TEST REQUIREMENT Section XI requires that a visual examination be performed on one pump internal pressure boundary surface each interval (Category B-L-2).
III. BASIS FOR RELIEF The basis for this relief request is predicated on the following two A.
To complete the subject examination, large expenditures of man-hours and man-rem are required with essentially no compensating increase in plant safety, and B.
The structural integrity afforded by the pump casing material utilized will not significantly degrade over the lifetime of the pump.
Based on data compiled from an actual recirculation pump disassembly, it
' is expected that approximately 1000 man-hours and 50 man-rem exposure would be required to disassemble, inspect, and reassemble one pump.
Performing this visual examinction under adverse conditions such as high dose rate (30-40 R/hr) and poor as-cast surface condition, realistically, provides little additional information as to the pump casing integrity.
The recirculation pump casing material, cast stainless steel (ASTM A351-CF-8), is widely used in the nuclear industry and has performed extremely well.
The presence of some delta ferrite (typically 5% or more) imparts substantially increased resistance to intergranular stress corrosion cracking. The delta ferrite also results in improved pitting corrosion resistance in chloride containing environments.
In addition, the Reactor Recirculation System is subjected to a VT-2 examination anytime the drywell is deinerted in accordance with Generic Letter 84-11.
IV. ALTERNATE TESTING Whenever a recirculation pump is disassembled for maintenance, an examination of the internal pressure boundary surfaces will be performed.
l CPL-02 22 y _ _ _ _ -_------ -- -- -
RELIEF REQUEST NO RR-5, REV. O I. APPLICABLE COMPONENTS This request is applicable to all component supports on all Service Water Piping greater than four inches an all four Diesel Fuel Storage Chambers.
II. IMPRACTICAL TEST REQUIREMENT These supports are subject to a VT-3 examination once per interval.
III. BASIS FOR RELIEF The component supports on these lines are covered by fire retardant Pyrocrete 102 as mandated per 10 CFR 50, Appendix R, " Fire Protection Program for Nuclear Power Facilities prior to January 1, 1979," and Branch Technical Position APCSB 9.5-1, Appendix A, " Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976."
This material has been applied to cover the entire support from the component to the ceiling / wall for all component supports.
A. Pyrocrete 102 is an extremely hard, rigid material. When applied, it is considered a permanent feature of the system and expected to endure through the life span of the facility. To remove this material from the supports and components would require chipping the material from the support / component. This could harm the supports and components.
B. These supports represent approximately 5 percent of the total Service Water component supports and thus, do not encompass a large percentage of the supports on the Service Water System.
C. With the exception of the two component supports at the south end of each header line (lines 2-SW-235-18-157 and 1-SW-217-18-157),
all supports are basic U-bolt type supports. These supports have no moving parts, thereby eliminating problems associated with supports that have moving parts. The remaining two supports are rigid, strut-type supports.
IV. ALTERNATE TESTING Visually inspect these supports once each interval with the fire retardant Pyrocrete 102 remaining on the supports, examining for any condition which might indicate that the support has been structurally degraded (i.e., severely cracked or missing Pyrocrete, support entirely detached from the component, etc.).
CPL-02 Rev. 0 23
O SECTION 6.0 INSERVICE INSPECTION CODE CASES FOR BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 Y
CPL-02 24 Rev. O
6.0 CODE CASES .
The following code cases as endorsed by revision 5 to Regulatory Guide 1.147 will be used at Brunswick Steam Electric Plant:
N-308 Documentation of Repairs and Replacements of Components in Nuclear Power Plants,Section XI, Division 1 N-343 Alternate Scope of Examination of Attachment Welds for Examination Categories B-H, B-K-1, and C-C,Section XI, Division 1 N-355 Calibration Block for Angle Beam Ultrasonic Examination of Large Fittings in Accordance With Appendix 111-3410, Sec-tion XI, Division 1 N-389 Alternate Rules for Repairs, Replacements, or Modifications,Section XI, Division 1 N-408 Alternate Rules for Examination of Class 2 Piping,Section XI, Division 1 l
N-416 ' Alternate Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping,Section XI, Division 1 N-424 Qualification of Visual Examination Personnel,Section XI, Division 1 N-426 Extent of VT-1 Examinations, Category B-G-2 of Table IWB-2500-1,Section XI, Division 1 i
CPL-02 25
.Rev. O
e =
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SECTION 7.0 AUGMENTED INSPECTIONS FOR BRUNSWICK STEAM ELECTRIC PIANT i
UNITS 1 AND 2 k
CPL-02 w ____ _________-.
26
7.0 AUGMENTED INSPECTIONS In addition to the requirements as specified in ASME,Section XI, Carolina Power & Light has committed to meet the inspection requirements contained in the following documents:
A.
NUREG-0313, revision 1, Material Selection and Processing Guidelines for BWR Boundary Piping Coolant Pressure B.
NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking C. IEB 80-08, Cracking in Core Spray Spargers e
CPL-02 27 Rev. O
.e 4
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ATTACHMENT 2 i
! TO SERIAL NLS-86-399 BRUNSWICK UNIT NOS.1 AND 2 1
INTERVAL 1 IN-SERVICE INSPECTION PROGRAM i EXCEPTIONS I
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Code Exception Number VR-2
- 1. COMPONENTS: All component supports on all Service Water piping greater than four inches in all four Diesel Fuel Storage Chambers.
- 2. FUNCTION: Safety-related equipment cooling.
- 3. CLASS: 3
- 4. TEST REQUIREMENTS: A VT-3/VT-4 examination to be performed on the supports every 40 months.
- 5. BASIS FOR EXCEPTIONS: The component supports on these lines are covered by fire retardant Pyrocrete 102 as mandated per 10 CFR 50, Appendix R, " Fire Protection Program for Nuclear Power Facilities Prior to January 1, 1979," and Branch Technical Position APCSB 9.5-1, Appendix A, " Guidelines for Fire Protection for Nuclear Power Plants Docketed Prior to July 1, 1976." This material has been applied to cover the entire support from the component to the ceiling / wall for all component supports.
- a. Pyrocrete 102 is an extremely hard, rigid material. When applied, it is considered a permanent feature of the system and expected to endure through the life span of the facility. To remove this material from these supports and components would require chipping the material from the support / component. This could harm the supports and components.
- b. These supports represent approximately five percent of the total Service Water component supports, and thus, do not encompass a large percentage of the supports on the Service Water System.
- c. With the exception of the two component supports at the south end of each header line (Lines 2-SW-235-18-157 and 1-SW-217-18-157),
all supports are basic U-bolt type supports. These supports have no moving parts, thereby eliminating problems associated with supports that have moving parts. The remaining two supports are rigid strut type supports.
- 6. ALTERNATE TESTING: Visually inspect these supports once each interval with the fire retardant Pyrocrete 102 remaining on the supports, examining for any condition which might indicate that the support has been structurally degraded (i.e., severely cracked or missing pyrocrete, support entirely detached from the component).
(1143NEL)
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Code Exception Number PR-1
- 1. SPECIFIC RELIEF REQUEST: The system pressure test required by IWD-5223(a) at the pressure specified in IWD-5223(a).
' APPLICABLE TO: The ten-year hydrostatic test of the Class 3 high 2.
pressure portion of HPCI (approximately a two-foot section of pipe between F035 and F059).
- 3. JUSTIFICATION: The piping between E41-F059 and E41-PCV-F035 (line number 11-2-605) has a design rating of 460 psig whereas the piping downstream of E41-PCV-F035 has a design pressure rating of 150 psig.
The.E41-PCV-F035 valve is a pressure control valve providing a pressure drop across the valve, preventing overpressurization of the low pressure portion of the system. Since this valve is designed with holes in the valve disc, it cannot be used as a boundary valve for the hydrostatic pressure test, thus making the hydrostatic test requirement impractical.
- 4. ALTERNATE EXAMINATIONS: A VT-2 examination during the system hydrostatic pressure test of the low pressure side of the system.
Include line number 11-2-605 as part of the quarterly VT-2 examinations performed on the system.
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Code Exception Number PR-3
- 1. SPECIFIC RELIEF REQUEST: The system pressure test required by IWC-5222(a) at the pressure specified in IWC-5222(a).
- 2. APPLICABLE TO: The 10-year pneumatic test on the Class 2 CRD nitrogen accumulators.
- 3. JUSTIFICATION: The CRD nitrogen accumulators are designed at 1750 psig. To perform a pneumatic test of these accumulators, a pressure of 2187.5 psig would be required to satisfy IWC-5222(a).
These accumulators are-equipped with rupture disks that can withstand a pressure between approximately 1900 and 2100 psig only, therefore, the test could result in damage to plant equipment.
- 4. ALTERNATE EXAMINATIONS: Perform a VT-2 examination of the CRD nitrogen accumulators at operating pressure once every 10 years.
(1143NEL)
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Code Exception Number PR-4 -
- 1. SPECIFIC RELIEF REQUEST: The system pressure test required by IWC-5222(a) at the pressure specified in IWC-5222(a). ,
- 2. -APPLICABLE TO: The 10-year hydrostatic test of the Class 2 Main Steam System piping.
- 3. JUSTIFICATION: The MSIVs, which are the only isolation valves between the Class 1 and Class 2 piping, are unidirectional type valves designed to close on flow from the Reactor Vessel. The hydrostatic test would require a pressure of 1105 psig to.be placed against the valve seat from the outboard side. These valves are designed to withstand approximately 25 psig from the opposite side.
An imposed pressure of 1105 psig on these valves when they are gagged could cause damage to the stem and force open the valves resulting in water entering the reactor vessel at approximately 1105 psig.
- 4. ALTERNATE EXAMINATIONS: Perform a VT-2 examination during a system hydrostatic test of the Reactor Pressure Vessel and associated Reactor Coolant System piping at a pressure of approximately 1088 psig by including the Class 2 Main Steam piping within the test boundary.
(1143NEL)
Code Exception Number PR-7
- 1. SPECIFIC RELIEF REQUEST: The system pressure test required by IWC-5210(a)(2) at the pressure specified in IWC-5222(a) .
- 2. APPLICABLE TO: Weld numbers 2-E11-140 and 2-E11-FW138A upstream of RHR Heat Exchanger 2A and welds 2-E11-FW82A and 2-E11-400 upstream of RHR Heat Exchanger 2B, installed under Plant Modification 85-056.
- 3. JUSTIFICATION: In order to pressure test the subject welds, the tube side of the RHR heat exchangers would be pressurized to 1400 psig, which ceuld damage the component. (RHR heat exchangers have a maximum design rating of 415 psig.)
- 4. ALTERNATE EXAMINATIONS: Perform a VT-2 examination during a system functional test (IWC-5221) and a 100 percent surface examination for pre-service.
(1143NEL)
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Code Exception Number PR-8
- 1. SPECIFIC RELIEF REQUEST: The system pressure test required by IWD-5210(a)(3) at the pressure specified in IWD-5223(a).
- 2. APPLICABLE TO: Service Water Lube Water System piping.
- 3. JUSTIFICATION: The piping involved in this test supplies lubricating water to the bearings of all five Service Water Pumps. This common piping precludes running of these pumps during the hydrostatic pressure test as the pumps can only be run a very short period of time without damage to the bearings. Based on the four-hour hold time for the hydrostatic pressure test, this test is impractical.
NOTE: This piping system is scheduled to be deactivated in late 1987 by plant modification which will install a new bearing design.
- 4. ALTERNATE EXAMINATIONS: Perform a VT-2 examination during a system inservice test per IWD-5210(a)(1) until the system is deactivated.
(1143NEL)
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Code Exception Number PR-9
- 1. SPECIFIC RELIEF REQUEST: The system hydrostatic pressure test required IWC-5210(a)(2) at the pressure specified in IWC-5222(a) .
- 2. APPLICABLE TO: Unit No. 2 Main Steam Class System piping and components.
- 3. JUSTIFICATION: In order to pressurize the subject piping system and components, the turbine stop valves would need to be used as test isolation valves. These valves (MS-SV-1, MS-SV-2, MS-SV-3, MS-SV-4) are designed to reduce turbine speed (with no load on the turbine) approximately one third. During performance of the Unit No. 2 hydrostatic test, which was attempted on April 22, 1986, it was determined through temperature indication on both sides of these stop valves, along with RTGB pressure indications for the turbine that the stop valves were leaking by the seats considerably.
Cycling the valves during the performance of the test to try and seat them was not practical due to the potential of inducing large volumes of water to the turbine. These valves are non-safety related; they provide no containment isolation function, and have no specific requirements for maximum leakage (reference FSAR Section 15.6.3).
These valves are worked on a five-year maintenance schedule controlled by a plant maintenance instruction (M1-10-526). They are not acheduled to be worked for Unit No. 2 until late 1987 (MS-SV-3 and MS-SV-4) and 1990 (MS-SV-1 and MS-SV-2) .
- 4. ALTERNATE EXAMINATIONS: Perform a VT-2 examination during a system function test (IWC-5210(a)(1)) utilizing a four-hour minimum hold time. This type of test would be at a pressure of 950 psig which is 140 psig lower than that which would be imposed during the hydrostatic test.
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