ML20080A876
| ML20080A876 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/21/1983 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20080A866 | List: |
| References | |
| NUDOCS 8402060380 | |
| Download: ML20080A876 (3) | |
Text
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FIGURE 16.1-2 QUALITY STANDARDS 1.
1ASME Boiler and Pressure Vessel i
Code:
Section II -Material Specifications Part A-~
Ferrous Part B Non-Ferrous-Part C Welding Editions as specified in Sections 3.9.3, 5.2.1 of the
-Hope Creek. Generating Station FSAR.
2.
ASME Boiler and Pressure Vessel' Code:
Section III, Nuclear Power Plant Components Editions as specified in Sections 3.9.3, 5.2.1 of the Hope Creek Generating Station FSAR.
3.
ASME Boiler and Pressure Vessel Code:
Section VIII, Pressure Vessels, Division 1 and Division II Editions as specified in Sections 3.9.3, 5.2.1 of the Hope Creek Generating Station FSAR.
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4.
ASME Boiler and Pressure Vessel Code:
Part IX, Welding Qualifications Editions as specified in Sections 3.9.3, 5.2.1 of the Hope Creek Generating Station FSAR.
5.
ASME Boiler and Pressure Vessel Code:
Part XI, Rules for Inservice Inspection of Nuclear Reactor Coolant Systems Editions as specified in Sections 3.9.3, 5.2.1 of the Hope Creek Generating Station FSAR.
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~6.
Draft ASME Code for Pumps and Valves for Nuclear Power, November 1968 HCGS-PSAR FIG. 16.1-2, p.1 of 3 0402060380 831021 PDR ADOCK 05000354 B
PDR i=
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-FIGURE-16.1-2 QUALITY STANDARDS 7.
ANSI Standard No. B31.1 i:
Power Piping 1973 Summer Addenda 1973 8.
- ANSI Standard No. B31.7 Nuclear: Power Piping J
1970 Addenda tc same, ANSI 31.7.13 1971 9.
~ American Society for Non-Destructive Testing, Recommended i
Practice No. SNT-TC-1A
[
_ Supplement A, Radiographic Testing Method 1971 Supplement B, Magnetic Particle Method 1971 Supplement C, Ultrasonic Testing Method 1971 Supplement D, Liquid Penetrant Testing Method 1968 Supplement E, Eddy Current Testing Method 1960 or 1975. edition depending upon the date of contract.
l The following Regulatory Guides were used as guides in structuring PSE&G's QA procedures _and instructions.
Issue 10.-AEC Regulatory Guide No. 1.28 (Formerly Date Safety Guide 28)
QA Program Requirements (Design and 6/7/72 Construction) 7
- 11. AEC Regulatory Guide No. 1.30 (Formerly Safety Guide 30)
QA Requirements for the Installation, 8/11/72 Inspection and Testing of Instrumentation and Electric Equipment
- 12. AEC Regulatory Guide No. 1.37
~
QA Requirements for Cleaning of Fluid 3/16/73 Systems and Associated Components of Water-Cooled Nuclear Power Plants
- 13. AEC Regulatory Guide No. 1.38 QA Requirements for Packaging, Shipping, 3/16/73 Receiving, and Handling of Items for Water-Cooled Reactors HCGS-PSAR FIG. 16.1-2, p.2 of 3
4
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FIGURE 16.1-2 s
QUALITY STANDARDS
- 14. NRC Regulatory Guide No. 1.58,(Rev. 1 Qualification of Nuclear Power Plant Inspection, Examination and Testing Personnel This guide will be followed with the following exception'(Ref:
PSE&G letter to NRC dated August 3, 1981, in reply to Generic Letter 81-03 ) :
Paragraph 6 of Regulatory Guide 1.58 requires for
"... Level I, II and III personnel, the candidate should be a high school graduate or have earned the General Education Development Equivalent of a high school diploma."
Both Public Service Electric and Gas Company and the American National Standard ANSI /ASME N45.2.6-1978, Para. 3.5 have recognized
"... that other factors may provide reasonable assurance that a person can competently perform a particular task."
The other factors which may demonstrate capability in a given job are previous performance or satisfactory completion of testing.
These two far. tors will be cons!dered when evaluating education pnd experience requirements for certifi-cation.
- 15. NRC Regulatory Guide 1.146 Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants This guide was adopted per PSE&G letter to NRR dated August 3, 1981, in response to Generic Letter 81-01.
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HCGS-PSAR FIG. 16-1.2, p.3 of 3 i
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