ML18019A389: Difference between revisions

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1,12''
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                                                                                                                                                '.
NRR/DE/CEB                                    11r      1r                      1"  NRR/DE/EHEB NRR/DE/EQB                                    13(      21t                      2  NRA/DE/GB                  28          2 NRR/DE/MEB                                    18      1                        1  NRR/DE/MTEB'7                          1      1 NRR/DE/SAB NRR/DHFS/HFEB40,"
NRR/DE/CEB                                    11r      1r                      1"  NRR/DE/EHEB NRR/DE/EQB                                    13(      21t                      2  NRA/DE/GB                  28          2 NRR/DE/MEB                                    18      1                        1  NRR/DE/MTEB'7                          1      1 NRR/DE/SAB NRR/DHFS/HFEB40,"
NRR/OHFS/PSRBi 24      1 1
NRR/OHFS/PSRBi 24      1 1

Latest revision as of 19:21, 3 February 2020

Forwards Rev 2 to Inservice Insp Program ISI-201, ASME Preservice Insp Program Plan (Except Reactor Vessel) & Categorization of Request for Relief Re SER Confirmatory Item 34
ML18019A389
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 09/23/1985
From: Zimmerman S
CAROLINA POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML18019A390 List:
References
NLS-85-327, NUDOCS 8509260082
Download: ML18019A389 (22)


Text

r REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

'AtOEASSION NSR:850926008iOOO,DATE,S5/09/25i NOTQIAjt: NO DOCKET P~

FACIL'50 400 Shearon Har ris. Nucl ear>> Powe'r Plant Uni t' ~ Gar ol ina OS000400 AUTH,NAME<, AUTHOR AFFILIATION ZIMMERMAN~S,R; Carolina: Power>> L Light>> Co.

RECIP,NAMEI RECIPIENTS Of f icei of Nucl ear Reactor>> Regul ati one AFFILIATION'ENTONgH',RE D 'ctor

SUBJECT:

Forwar ds Rev 2'o Inset vice>> Insp>> Program LSI"201'f ASMEI-Preservice Insp Program- Plan r(Except>>Reactor Vessel);,"

L categorization of request- for'relief re SER confirmatory DISTRIBUTION CODE',: B00fD'OPIES" RECEIVED:LTR "ENCL' SIZE':,

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L>>icensing Submitta)0'SAR/FSAR'mdts 8 Related Correspondence

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RECIPIENT'D COPIES RECIPIENTS'D COPIES:

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SNK Carolina Power & Light Company 3'38> SERIAL: NLS-85-327

~P g, Q Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 - DOCKET NO.50-000 PRESERVICE INSPECTION PROGRAM AND CATEGORIZATION OF REQUEST FOR RELIEF

REFERENCE:

Letter dated May 9, 1985 from Mr. S. R. Zimmerman (CPRL) to Mr. Harold R. Denton (NRC).

Dear Mr. Denton:

Carolina Power ttt Light Company (CPRL) hereby submits additional information concerning the Shearon Harris Nuclear Power Plant (SHNPP) Preservice Inspection Program (SER Confirmatory Item No. 30). Revision 2 to the Preservice Inspection Program Plan (Procedure ISI-201) is provided as Attachment 1. The categorization of Request for Relief is provided as Attachment 2.

Revision 2 to the Preservice Inspection Program Plan is provided in response to CPdcL's commitment in the reference letter to perform a volumetric exam of line numbers 2CT8-10 and 2CT8-15. This change and other changes are noted by a sidebar in the right-hand margin.

The categorization of Request for Relief is provided in response to CPRL's commitment in Section 0.0 of the Preservice Inspection Program Plan to provide this information six months prior to fuel load. The Preservice Inspection Program is in progress on piping, vessels, bolting and component supports. This submittal covers known categories where relief is required. Additional categories may be necessary as CPRL completes the Preservice Inspection Program. The specific components that fall into the categories for Request for Relief will be submitted at least three months prior'to fuel load to close the SER conf irma tory t tern.

If you have any questions please contact Mr. Gregg A. Sinders at (919) 836-8168.

Yours very truly,

~

8509260082 850923 Gp>R Annex 05000+00 PDR S.~ R Zim erman ager Nuclear Licensing Section GAS/ccc (1916GAS)

CC: Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. M. R. Hum (NRC) Mr. 3ohn D. Runkle Mr. G. F. Maxwell (NRC-SHNPP) Dr. Richard D. Wilson Dr. 3. Nelson Grace (NRC-Rll) Mr. G. O. Bright (ASLB)

Mr. Travis Payne (KUDZU) Dr. 3. H. Carpenter (ASLB)

Mr. Daniel F. Read (CHANGE/ELP) Mr. 3. L. Kelley (ASLB)

Wake County Public Library util

) I 411 Fayettevilte Street o P. O. Box 1551 o Raleigh, N. C. 27602

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CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1,.

Relief Request No: R1-001 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS ASME XI CODE CODE COMPONENT OR ITEM CODE CLASS CATEGORY ITEM PRESSURE RETAINING PIPING WELDS CLASS 1 B"J B9. ALL

( PRESERVICE/INSERVICE APPLICABLE)

CODE RE UIREME TS:

ASME section XI, Table IWB-2500-1 requires surface and/or volumetric examinations to be performed as applicable on pressure retaining welds.

RELIEF RE VESTED:

Relief's requested from examinations on Class 1 pressure retaining welds due to structural interferences such as: permanent hangers, saddle plates, support structures, or intervening members for other systems.

ALTER ATE EXA INATIO S:

To the maximum extent possible volumetric examinations were performed. Where the weld was identif'ied as being inaccessible to the volumetric examination, surface examinations were used in I ieu of the volumetric examinations. Visual examinations (VT-1) were performed on components which required surface examination, when accessible. Where access precluded or limited the examination, that fact was documented on the Preservice Base l ine Data Sheet.

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CAROL I NA POWER 8c L I GHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R1-002 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS ASME XI CODE CODE COMPONENT OR ITEM CODE CLASS CATEGORY ITEM COMPONENT SNUBBERS CLASS 1 F-C F3. 50

( PRESERVICE/INSERVICE APPLICABLE)

CODE RE UIREMENT Table 1WF-2500-1 defines the testing and inspection criteria for snubbers.

Rel fef is requested from the functional test requirements for snubbers per article 1WF-5000.

ALTERNATE EXAMI ATIO Al I Shearon Harris component support snubbers wi I I be selected, inspected, and functional ly tested per section 3/4.7.8 of the Shearon Harris Technical Specifications.

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CAROl INA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R1-003 PRESERV I CE EXAHINAT ION PROGRAM REQUEST FOR RELIEF FROM ASHE SECTION XI SYSTEHS CODE REQUIREMENTS ASME XI CODE CODE COMPONENT OR ITEM CODE CLASS CATEGORY ITEM PRESSURE RETAINING PIPING WELDS CLASS 1 8-J B9. 10 - B9. 31

( PRESERVICE/INSERVICE APPLICABLE)

CODE RE UIREME TI ASME Section XI, Table IWB-2500-1 requires volumetric and surface examinations on Z 4" nominal pipe size circumferential and longitudinal pressure retaining welds, including branch connections.

RELIEF RE VESTED:

ASME section XI requires essentially 100$ of the weld length be volumetrica I ly examined. Due to piping weld configurat ions

( reducer to tee, pipe to tee, pipe to flange etc.) volumetric examinations of 100$ of the weld length was sometimes not f'easible.

Relief is requested based on weld configurations not being conducive to 100$ volumetric examination (see additional details on Attachment "A" to this relief request).

ALTERNATE EXAMI ATIO Pressure retaining welds were surface examined for essentially 100$ of the weld length where possible. Volumetric examinations were performed to the maximum extent possible based on physical limitations. Where the component configuration or access precluded or limited this examination, that fact and to the extent was documented on the Preservice Baseline Data Sheet.

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Attachment A Page 1 of 2 RELIEF REQUEST NO: Rl-003 EXAMINATIONS Ultrasonic examinations were conducted to inspect as much of the examination zone as was practical, within geometric, metallurgical, and physical limitations. When the required ultrasonic examination volume or area could not be examined 100 percent, the examination was considered to be partial and was so noted on the applicable component Data Sheet. Generally, partial examinations were done at fitting to fitting assemblies (explained under limitations) and in areas where integrally welded supports, lugs, etc.,

preclude access to some part of the examination area.

Ultrasonic examinations that produced indications 50 percent of DAC or greater from geometric or metallurgical origin were recorded. Examples of areas that,

'generally produced such indications are .as follows:

1. Inside diameter weld preparation or root configuration and the outside diameter down overlay or toe.
2. The inside diameter radius of the tube sheet weld of'he steam generators where examined from the tube sheet side.
3. The metallurgical structure of austenitic materials.
4. Signal responses from the thread areas of bolting.

LIMITATIONS Some of the arrangements and details of the piping system and components were designed and fabricated before the access and examinations requirements of Section XI of the 1980 Code could be applied; consequently, some examinations are 'limited or not practical due to geometric configuration or accessibility.

Generally these limitations exist at all fitting-to-fitting joints such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface condition preclude ultrasonic coupling or access for the required scan length.

The limitations exist to a lesser degree at pipe to fitting assemblies, particularly where the weld is not ground flush with the pipe O.D. surface.

At these joints examinations can be conduced form the pipe side; however, the fitting again limits or precludes examination from the opposite side.

In most cases, examinations in limited areas were accomplished as a best effort attempt to cover as much of the code required area or volume (generally, the weld and base metal for 1 "T" on each side) as possible.

However, the extent of examination coverage in the base metal of the fitting or component cannot be specifically quantified as being 100 percent. These areas where complete examination of 100 percent of the required volume of area could not be achieved were indicated and noted to the extent on the limiting cause noted.

examiners'ata Sheet and the Attachment 2 to NLS-85-327 Page 4 of 15

Attachment A Page 2 of 2 RELIEF REQUEST NO: Rl"003 LI>jITATIONS The principal basis for partial examinations is to identify the inability to examine 100 percent of the required base metal volume for the 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 de-coupling 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 for 1 "T" on the pipe side can be achieved by scanning from the pipe side of the weld. An indeterminate coverage of the base metal on the fitting or component side may be achieved during this pipe side scan depending on the calibrated sweep length, attenuation, joint configuration, etc. However, the volume on the fitting or component side additionally cannot be scanned completely for transverse indications as required by Code. In either case, 100 percent of this 1 "T".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.

Specific limitations and restrictions for all examinations are as indicated on the specific report Data Sheets.

Attachment 2 to NLS-85-327 Page 5 of 15

CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-004 PRESERVICE EXAHINATION PROGRAM REQUEST FOR RELIEF FROM ASNE SECTION XI SYSTEHS CODE REQUIREMENTS ASME XI CODE CODE CONPONENT OR ITEN CODE CLASS CATEGORY ITEM PRESSURE RETAINING WELDS IN REACTOR VESSEL CLASS 1 8-A 8" 8 81.20'1. 30 PRESSURE RETAINING WELDS IN VESSELS OTHER THAN CLASS 1 82. 10, 82.20 REACTOR VESSEL 82.30'2.40

( PRESERVICE/INSERVICE APPLI,CABLE) 82.50, 82.60 82.70 CODE RE UIR NE T Table IWB-2500-1 defines the volume of material which should be covered during the volumetric examinations.

In instances where component configuration or limited access resulted in the examination of less than 100$ of the code required volume, alternate examination techniques were considered and if, feasible, used.

ALTER ATE EXAM! ATIO The ultrasonic examinations were performed to the maximum extent possible. Where the component configuration or access precludes or limits the examination, the fact was documented on the applicable report, and the volumes of material not fully examined were defined.

CAROLINA POWER IL LIGHT SNEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-005 PRESERVICE EXAMINATION PROGRAM'SHE REQUEST FOR RELIEF FROM SECTION Xl 'SYSTEMS CODE REQUIREHENTS ASHE XI CODE CODE COHPONENT OR ITEM CODE CLASS CATEGORY ITEN PUMP CASINGS CLASS 1 8" L-2 812-20 VALVE BODIES, EXCEEDING 4 IN. NOMINAL PIPE SIZE CLASS 1 B"H-2 812. 50 (PRESERVICE APPLICABLE)

CODE RE U I REHE T ASHE Section XI, Table IWB-2500-1 requi res visual examinations (VT-3) be performed, as part of the Preservice Program, on the internal surfaces of pump casing's and valve bodies, exceeding 4 In. nominal pipe size.

RELIEF RE VESTED:

Relief is requested from the ASHE Section XI requirements for visual examinations (VT-3 ) of internal surfaces of pumps and valves.

Disassembly of these components would not be practical as unnecessary damage may occur from .the disassembly process.

ALTER ATE EXAHI ATIO S:

'I Manufactures records will be utilized as the recorded condition of internal surfaces for Preservice. No relief is requested for the Inserv ice Program.

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CAROLINA POWER 8c LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: Rl-006 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASHE SECTION XI SYSTEMS CODE REQUIREHENTS ASME XI CODE CODE COMPONENT OR ITEM CODE CLASS CATEGORY ITEM FULL PENETRATION WELDS OF NOZZLES IN VESSELS CLASS 1 8-D B3. 90, B3. 110

83. 130 (PRESERVICE/INSERVICE APPLICABLE)

CODE RE UIREHE T Table 1WB-2500-1 defines the volume of material which should be covered during the volumetric examinations.

ln instances where component configuration or limited access resulted in the examination of less than 100$ of the code required volume, alternate examination techniques were considered and, if feasible, used.

ALTERNATE EXAHINATIO The ultrasonic examinations were performed to the maximum extent possible. Where the component configuration or access precludes or limits the examination, the fact was documented on the applicable report, and the volumes of materia I not fully examined were defined.

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CAROLINA POWER Sc LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-001 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEMS CODE REQUIREMENTS ASME XI CODE CODE COMPONENT OR ITEM CODE CLASS CATEGORY ITEM PRESSURE RETAINING PIPING WELDS CLASS 2 C-F C5.ALL

( PRESERVICE/INSERVICE APPLICABLE)

CODE RE UIREME TS:

ASME Section XI, Table IWC-2500-1 requires= surface and/or volumetric examinations to be performed as appl icable on pressure reta inlng welds.

RELIEF RE VESTED:

Relief is requested from examinations on Class 2 pressure retaining welds due to structura I interferences such as: permanent hangers, saddle plates, support structures, or intervening members for other systems.

ALTER ATE EXAMI ATIO S:

To the maximum extent possible volumetric examinations were performed. Where the weld was identified as being inaccessible to the volumetric examination, surface examinations were used in lieu of the volumetric examinations. Visual examinations (VT-1) were performed on components which required surface examination, when accessible. Where access precluded or limited the examination, that fact was documented on the Preservice Baseline Data Sheet.

CAROLINA POWER k LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-002 PRESERVICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI'YSTEMS CODE REQUIREMENTS ASME XI CODE CODE COMPONENT OR ITEM CODE CLASS CATEGORY ITEM COMPONENT SNUBBERS CLASS 2 F-C F3. 50

( PRESERVICE/INSERVICE APPLICABLE)

CODE RE UIREME T Table 1WF-2500-1 defines the testing and inspection criteria for snubbers.

Rel lef is requested from the functional test requirements for snubbers per article 1WF-5000.

ALTER ATE EXAMI ATIO Al I Shearon Harris component support snubbers wll I be selected, inspected, and functional ly tested per section 3/4.7.8 of the f

Shea ron Ha rr I s Techn i ca I- Spec i I ca t i ons.

CAROLINA POWER k LIGHT SNEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-003 PRESERYICE EXAMINATION PROGRAM REQUEST FOR RELIEF FROM ASHE SECTION XI SYSTEMS CODE REQUIREMENTS COMPONENT OR iTEH ASME XI CODE CLASS CATEGORY'ODE CODE ITEM PRESSURE RETAINING PIPING WELDS CLASS 2 C"F C5.20 - C5.22

( PRES ERY I CE/ I NSERY I CE AP PL I CABLE)

CODE R'E UIREHE T:

ASHE section XI, Table IWC-2500-1 requires volumetric and surface examinations on circumferential and longitudinal pressure retaining welds, including branch connections.

RELIEF RE UESTED:

ASME section XI requires essentially 100$ of the weld length be volumetrically examined. Due to piping weld configurations

( reducer to tee, pipe to tee, pipe to flange etc. ) volumetric examinations of 100$ of the weld length was sometimes not feasible.

Relief is requested based on weld configurations not being conducive to 100$ volumetric examination ( see additiona I details on Attachment "A" to this relief request).

ALTERNATE EXAMI ATIO Pressure retaining welds were surface examined for essentially 100$ of the weld length where possible. Volumetric examinations were performed to the maximum extent possible based on physical limitations. Where the component configuration or access precluded

-or limited this examination, that fact and to the extent was documented on the Preservice Baseline Data Sheet.

4 Attachment A Page 1 of 2 RELIEF REQUEST NO: R2-003 EXAMINATIONS Ultrasonic examinations were conducted to inspect as much of the examination zone as was practical, within geometric, metallurgical, and physical limitations. When the required ultrasonic examination volume or area could not be examined 100 percent, the examination was considered to be partial and was so noted on the applicable component Data Sheet. Generally, partial examinations were done at fitting to fitting assemblies (explained under limitations) and in areas where integrally welded supports, lugs, etc.,

preclude access to some part of the examination area.

Ultrasonic examinations. that produced indications 50 percent of DAC or greater from geometric or metallurgical origin were recorded. Examples of areas that generally produced such indications are as follows:

1. Inside diameter weld preparation or root configuration and the outside diameter down overlay or toe.
2. The inside diameter radius of the tube sheet weld of the steam generators where examined from the tube sheet side.
3. The metallurgical structure of austenitic materials.
4. Signal responses from the thread areas of bolting.

LIMITATIONS Some of the arrangements and details of the piping system and components were designed and fabricated before the access and examinations requirements of Section XI of the 1980 Code could be applied; consequently, some examinations are limited or not practical due to geometric configuration or accessibility.

Generally these limitations exist at all fitting-to-fitting joints such as elbow to tee, elbow to valve, reducer to valve, etc., where geometry and sometimes surface condition preclude ultrasonic coupling or access for the required scan length.

The limitations exist to a lesser degree at pipe to fitting assemblies, particularly where the weld is not ground flush with the pipe O.D. surface.

At these joints examinations can be conduced form the pipe side; however, the fitting again limits or precludes examination from the opposite side.

In most cases, examinations in limited areas were accomplished as a best effort attempt to cover as much of the code"T"required area or volume (generally, the weld and base metal for 1 on each side) as possible.

However, the extent of examination coverage in the base metal of the fitting or component cannot be specifically quantified as being 100 percent. These areas where complete. examination of 100 percent of the required volume of area could not be achieved were indicated and noted to the extent on the examiners'ata Sheet and the limiting cause noted.

Attachment 2 to NLS-85-327 Page 12 of 15

Attachment A Page 2 of 2 RELIEF REQUEST NO: R2-003 LIHITATIONS The principal basis for partial examinations is to identify the inability to examine 100 percent of the required base metal volume for the 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 de-coupling 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 for 1 "T" on the pipe side can be achieved by scanning from the pipe side of the weld. An indeterminate coverage of the base metal on the fitting or component side may be achieved during. this pipe side scan depending on the calibrated sweep length, attenuation, joint configuration, etc. However, the volume on the fitting or component side additionally cannot be scanned completely for transverse indications as required by Code. In either case, 100 percent of this 1 "T" volume cannot be assured, thus a par'tial examination is required as a disclaimer to having satisfied code requirements, albeit the intent is.

satisfied to the extent practical.

Specific limitations and restrictions for all examinations are as indicated on the specific report Data Sheets.

Attachment 2 to NLS-85-327 Page 13 of 15

CAROLINA POWER IL LIGHT SNEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R2-004 PRESERV ICE EXAHINAT ION PROGRAM REQUEST FOR RELIEF FROM ASME SECTION XI SYSTEHS CODE REQUIREMENTS ASHE XI CODE CODE COMPONENT OR ITEH CODE CLASS CATEGORY ITEN PRESSURE RETAINING WELDS LOCATED INSIDE OF CLASS 2 C-F C5. 10, C5.20 CONTAINMENT PENETRATIONS (PRESERVICE/INSERVICE APPLICABLE)

CODE RE U EHE ASHE section XI Table IWC-2500-1 requires surface and/or volumetric examination on circumferential and long i tud ina I piping welds.

ELIEF E UES ED:

Relief is requested from ASHE Section XI requi rements as these welds are located inside of conta inment penetrations and are not physically accessible for examination.

ALTER AT EXAM ATIO None. Hydrostatic tests will be performed as required by ASHE Section XI requirements.

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CAROLINA POWER Ec LIGHT SHEARON HARRIS NUCLEAR POWER PLANT UNIT 1 Relief Request No: R3-001 PRESERV ICE EXAHI NAT ION PROGRAH REQUEST FOR RELIEF FROH ASHE SECTION XI SYSTEHS CODE REQUIREHENTS ASHE XI CODE CODE COHPONENT OR ITEH CODE CLASS CATEGORY ITEN COHPONENT SNUBBERS CLASS 3 F-C F3 ~ 50 (PRESERVICE/INSERVICE APPLICABLE)

CODE RE UIREHE T Table 1WF-2500-1 defines the testing and inspection criteria for snubbers.

Relief is requested from the functional test requirements for snubbers per article 1WF-5000.

AL ER ATE EXAHI ATIO All Shearon Shee ron Harris component support snubbers Harris Techni ca I Spec i f i cat i ons.

vill be selected, inspected, and functionally tested per section 3/4.7.8 of the rt 0 rt 0o rt