ML20216J694
| ML20216J694 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/29/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20216J698 | List: |
| References | |
| NLR-N87117, NUDOCS 8707060268 | |
| Download: ML20216J694 (7) | |
Text
7-1 Pubhc Service Electric and Gas Company Ctrbin A. McNeill, Jr.
Public Service Electric and Gas Company P.O. Box 236,Hancocks Bridge, NJ 08038 609 339-4800 i
Senior Vice President -
Nuclear June 29, 1987 NLR-NB7117.
i United States Nuclear Regulatory Commission
]
Document Control Desk l
Washington, DC 20555 Gentlemen:
INSERVICE INSPECTION PROGRAM REPLY TO NRC REQUEST FOR ADDITIONAL INFORMATION HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Attached please find six (6) copies of the Hope Creek Generating Station (HCGS) Inservice Inspection Program Long Term Plan, herein referred to as the Plan (Enclosure 2).
This information is provided in response to your. Request for_ Additional Information dated March 6, 1987 as amended by a conference call-held on April 22, 1987 between'PSE&G ISI and Licensing and Regulation personnel and Messrs. G. Rivenbark and M. Hum of your staff along with Mr. B. Brown of EG&G Idaho.
In addition to the requested information, the enclosed Plan also
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contains all the information previously submitted to the NRC in
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the original ISI submittal dated October 10, 1986.
As such, the i
enclosed Plan supercedes the initial submittal.
Our responses to the specific items of the RAI are discussed below.
A.
Isometric and/or Component Drawings Inservice Inspection Boundary Diagrams which were previously transmitted on December 8, 1986,.have also been provided in the Plan (Attachment 5-1).
Examination Figures for Nuclear Class 1 and 2 components and piping have been provided and are included in the Plan (Attachment 5-14, Appendices A & B).
A component Support Allocation Table has been provided in the Plan (Attachment 5-12) as agreed upon in lieu of System Isometric Drawings.
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Document Control Desk 2
6-29-87 j
B.
List of Systems and Acronyms i
This information has been provided in the Plan, pages 3 and 4.
C.
List of Exemptions by Code Class This information has been provided in Section 2 of the Plan.
Specific component and piping line exemption criteria are shown in the appropriate boundary tables which are provided in the Plan (Attachments 5-3 and 5-8).
D.
Line Lists for each system Line lists are part of the appropriate boundary tables (Attachments 5-3 and 5-8) of the Plan which contain the requested information.
E.
Exam Tables for each system This information has been provided in the Plan as j
follows:
Class 1 Component Examination Tables - Attachment 5-4.
Class 2 Component Examination Tables - Attachment 5-6.
Class 3 Component Examination Table - Attachment 5-9.
Component Supports Examination Table - Attachment 5-11.
A list of procedures has been provided separately as to this letter.
The procedure titles adequately describe the examinations performed by the various procedures.
F.
Summary Tables This information has been provided in the Plan as f ollowr. :
Class 1 Allocation Tables - Attachment 5-5.
l Class 2 Allocation Tables - Attachment 5-7.
Class 3 Allocation Tables - Attachment 5-11.
The ASME categories are identified in these allocation i
tables.
However, the ASME Item Numbers are not specifically identified for the following reasons:
Document Control Desk 3
6-29-87 i
The item description was used where appropriate in place of ASME Item Number to more clearly describe the
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type of component or weld.
Piping allocations where the percentages applied, were further separated by system and pipe sizes to ensure representative selections among the sizes.
Multiple ASME Item Numbers containing the identical examination requirement, apply to most individual component supports.
Listing of these component supports by unique ASME Item Number would have required listing those supports several times.
G.
List of NDE Procedures As stated above, a list of procedures has been provided separately as Enclosure 1 to this letter.
This list was not included in the Plan (Enclosure 2) because the procedures are subject to revision.
Specific cycle (outage) examination plans will include procedure references in the examination table listing.
H.
List of Calibration Blocks This information has been provided in the Plan, Section 2.5, with the examinations included in the appropriate table, (Attachment 5-4, 5-6 and 5-9).
J.
Appendix J Containment leakage rate testing is outside the scope of the Inservice Inspection Program.
Containment and Isolation Valve leakage testing is performed in accordance with 10 CFR 50, Appendix J, and the Hope Creek Technical Specifications, Section 4.6.1.2.
K.
Relief Requests The requests for relief from code requirements based on examination limitations have been revised to delete those components not selected for this First Ten Year Interval.
The limitations have been revised to include estimated coverage percentages against ISI requirements, revised basis for relief, and to show alternate examinations where applicable.
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Document Control Desk 4
6-29-87 If additional information is required, please do not hesitate to contact us.
Sincerely, b
+b 14 A
awn Enclosure l - List of NDE Procedures expected to be used during the First Ten Year Interval. - Hope Creek Generating Station Inservice Inspection Program Long Term Plan - First Ten Year Interval June 1987, Volumes A, B and C.
C Mr.
G.
W. Rivenbark (w/o enclosure)
USNRC Licensing Project Manager Mr.
R.
W. Borchardt (w/o Enclosures)
USNPC Senior Resident Inspector Mr.
W.
T.
Russell Administrator, USNRC Region I Mr.
D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 i
Mr. Boyd Brown
)
EG&G Idaho j
P. O. Box 1625
)
l
Paca No.
1 ENCLOSURE 1 LIST OF NDE PROCEDURES EXPECTED TO BE USED DURING THE FIRST 10 YEAR INTERVAL PROCEDURE PROCEDURE EXAMINATION NUMBER TITLE METHOD SwRI-NDT-200- 1 Liquid Penetrant Examination, PT Color Contrast Method SwRI-NDT-300- 1 Dry Powder Macnetic Particle MT Examination SwRI-NDT-300- 2 Fluorescent Haanetic Particle MT Examination SwRI-NDT-600- 5 Manual Ultrasonic Examination of UT Nuclear Reactor Pressure Vessel F1ance Ligaments SwRI-NDT-600-11 Manual Ultrasonic Examination of UT Vessel-to-Nozzle Inner Radius Sections j
SwRI-NDT-600-15 Manual Ultrasonic Examination of UT Pressure Vessel Welds SwRI-NDT-600-30 Manual Ultrasonic Examination of UT Pressure-Retaining Welds in Heat Exchancers SwRI-NDT-600-31 Manual Ultrasonic Examination of UT Austenitic Pressure Piping Welds SwRI-NDT-600-41 Manual Ultrasonic Examination of UT Ferritic Fressure Piping Welds SwRI-NDT-700- 6 Mechanized Ultrasonic Examination MECH UT of Ferricic Vessels Greater than 2.0 Inches in Thickness SwRI-NDT-800- 20 Manual Ultrasonic Examination of UT Pressure-Retainina RPV Studs 2 In.
and. Greater in Diameter Containing Access Holes at Hope Creek SwRI-NDT-800- 36 Manual Ultrasonic Examination of UT Austenitic Thin Wall Piping Welds SwRI-NDT-800- 55 Manual Ultrasonic Examination of UT Nozzle Inside Radius Sections from the Vessel Base Material
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2 ENCLOSURE 1 LIST OF NDE PROCEDURES EXPECTED TO BE USED DURING THE FIRST 10 YEAR INTERVAL PROCEDURE PROCEDURE EXAMINATION NUMBER TITLE METHOD SWRI-NDT-800- 97 Manual Ultrasonic Examination of UT Pump Studs with Partially Drilled Heater Holes at Hope Creek SWRI-NDT-800-100 Manual Ultrasonic Examination of UT Corrosion-Resistant Clad Pipina Welds at Hope Creek SwRI-NDT-800-104 Inner Surface Examination of the UT Access Holes in Pressure Retaining Studs 2 Inches and Greater in Diameter SwRI-NDT-800-107 Automated Examination of Pressure UT Pipina Welds M9-IIP"02H Visual Examination of Class 1, 2
VT-3 (M9-IIP-201) and 3 Component and Pipe Supports VT-4 M9-IIP-01H VT-1 Visual Examination of Nuclear VT-1 (M9-IIP-202)
Class 1 and 2 Bolting and Internal Surfaces M9-IIP-03H System Leakace Test Nuclear VT-2 (M9-IIP-203)
Class 1 Components M9-IIP-04H Service Pressure Leak Exam, VT-2 (M9-IIP-203A)
Nuclear Class 2 and 3 Components M9-IMP-01H Inservice Inspection Long Term Plan VT-2 tlater)
Hydrostatic Tests General Procedure Hope Creek Generatina Station VENDOR Visual Examination of Reactor VT-1 (later)
Vessel Accessable Interior Welds, VT-3 Surfaces and Areas I
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