ML20154Q054

Rev 1 to Safstor QA Program

ML20154Q054
Person / Time
Site:	Humboldt Bay
Issue date:	03/31/1986
From:	PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML20154Q047	List: HBL-86-006, Forwards Rev 1 to Safstor QA Program & Description of Rev ML20154Q054
References
NUDOCS 8603210016
Download: ML20154Q054 (3)

Text

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l HUMBOLDT BAY POWER PLANT UNIT 3 -

SAFSTOR QUALITY ASSURANCE PLAN December, 1985 (Revised March 1986) 8603210016 060314 3 PDR ADOCK 0500 P

(Rev. 1)

1.0 INTRODUCTION

1 1.1 Plan Objective The objectives of Pacific Gas and Electric Company's (PGandE)

Quality Assurance Plan (Plan) for Humboldt Bay Power Plant Unit 3 (HBPP-3) during SAFSTOR operation are:

a) To establish and implement a graded program that is based upon the appropriate criteria of 10CFR50, ,

I Appendix B and is commensurate with the limited SAFSTOR activiites and required function of the HBPP-3 components. systems and structures..

b) To meet the regulatory requirements for quality assurance programs as specified in 10CFR71,

" Packaging and Transportation of Radioactive Material", and in U.S. Nuclear Regulatory Commission (USNRC) Regulatory Guide 4.15. " Quality Assurance for Radiological Monitoring Programs (Normal Operations)

- Effluent Streams and the Environment".

c) To assure compliance with the plant Technical Specifications.

1.2 Plan Scope a) This Plan applies to the following HBPP-3 SAFSTOR activities:

• Radiological monitoring of gaseous and liquid effluents and the environment.

• Packaging and transport of radioactive material.

• Implementing plant Technical Specifications.

b) This Plan applies to all personnel involved in the HBPP-3 SAFSTOR activities.

i 1.3 Plan Control The Manager, Quality Assurance shall be responsible to identify, prepare, submit for approval, and issue changes as are necessry to maintain the Plan current and in conformance with applicable regulatory requirements and PGandE commitments to the USNRC. Changes to the conunitments contained herein shall be submitted to the USNRC in accordance with 10CFR50.54.

I j

(Rev. 1)

' (Revised 3/86)

< requirements of Section 3.1 and USNRC Regulatory Guide 4.15 (Revision O, December 1977).

3.3 Radioactive Material Packmaina and Transport Containers used for transport of radioactive materials shall be controlled in accordance with the requirements of Section 3.1 and the NRC-approved DCPP Quality Assurance Program, as contained in Sections 17.1 - 17.18 Diablo Canyon Power Plant (DCPP) Final Safety Analysis Report Update (FSARU), and thereby in compliance with the quality assurance requirements of Subpart H of 10CFR71. Relative to Section 17.1, DCPP FSARU, the plant organization referenced therein shall be the HBPP-3 organization described in the HBPP-3 Technical Specifications.

3.4 Technical Specification Activities The Technical Specification activities shall be controlled in accordance with the requirements of Section 3.1 and the Operating Limits and Requirements and the Administrative Controls as specified in the HBPP-3 Technical Specifications.

i (Rev. 1)

(Revised 3/86)