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United States Nuclear Regulatory Commission Official Hearing Exhibit In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3) ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 | 05000286 Exhibit #: Identified: Admitted: Withdrawn: Rejected: Stricken: Other: ENT000383-00-BD01 10/15/2012 10/15/2012 ENT000383 Submitted: March 30, 2012 AN AMERICAN NATIONAL STANDARD CODE FOR OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS 5 E0 CODE·2001 (Revision of AS E 0 CODE .. 199B)
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CODE FOR OPERATION OF NUCLEAR POWER PLANTS · nuclear power plant items such as pumps, valves, and dynamic restraints (snubbers). ISTA-1320 Classifications. Optional construction

Apr 19, 2020

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Page 1: CODE FOR OPERATION OF NUCLEAR POWER PLANTS · nuclear power plant items such as pumps, valves, and dynamic restraints (snubbers). ISTA-1320 Classifications. Optional construction

United States Nuclear Regulatory Commission Official Hearing Exhibit

In the Matter of: Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Units 2 and 3)

ASLBP #: 07-858-03-LR-BD01 Docket #: 05000247 | 05000286 Exhibit #: Identified: Admitted: Withdrawn: Rejected: Stricken:

Other:

ENT000383-00-BD01 10/15/201210/15/2012

ENT000383 Submitted: March 30, 2012

AN AMERICAN NATIONAL STANDARD

CODE FOR OPERATION AND MAINTENANCE

OF NUCLEAR POWER PLANTS

5 E 0 CODE·2001 (Revision of AS E 0 CODE .. 199B)

Page 2: CODE FOR OPERATION OF NUCLEAR POWER PLANTS · nuclear power plant items such as pumps, valves, and dynamic restraints (snubbers). ISTA-1320 Classifications. Optional construction

ASME OMa CODE-2002

SUBSECTION ISTA General Requirements

ISTA-l0 0 INTRODUCTION

Section 1ST establishes the requirements for preser­vice and inservice testing and examination of certain components to assess their operational readiness in light-water reactor nuclear power plants. It identifies the components subject to test or examination, re­sponsibilities, methods, intervals, parameters to be measured and evaluated, criteria for evaluating the results, corrective action, personnel qualification, and record keeping. These requirements apply to:

(a) pumps and valves that are required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the conse­quences of an accident;

(b) pressure relief devices that protect systems or portions of systems that perform one or more of these three functions; and

(a) (c) dynamic restraints (snubbers) used in systems that perform one or more of these three functions, or to ensure the integrity of the reactor coolant pressure boundary.

1ST A-1200 Jurisdiction

The jurisdiction of Section 1ST covers individual components that have met all the requirements of the construction code commencing at the time when the construction code requirements have been met, irrespective of the physical location. When portions of systems or plants are completed at different times, the jurisdiction of this Section shall cover only those components on which all construction related to the components has been completed.

ISTA-1300Application

(01) ISTA-1310 Components Subject to Testing and Examination. Components identified in Section 1ST for testing or examination shall be included in the test plan (1ST A-311 0). These components include

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nuclear power plant items such as pumps, valves, and dynamic restraints (snubbers).

ISTA-1320 Classifications. Optional construction (01)

of a component in a system boundary to a classifica- A tion higher than the minimum class established in .. the component Design Specification (either upgrad-ing from Class 2 to Class 1 or Class 3 to Class 2) shall not affect the overall system classification by which the applicable requirements of Section 1ST are determined.

1ST A-1400 Referenced Standards and Specifications

When standards and specifications are referenced in Section 1ST, their revision date or indicator shall be as shown in Table ISTA-1400-1.

ISTA-1S00 Owner's Responsibilities (01)

The responsibilities of the Owner of the nuclear power plant shall include the following:

(a) determination of the appropriate Code Class for each component of the plant, identification of the system boundaries for each class of components subject to test or examination, and the components exempt from testing or examination requirements;

(b) design and arrangement of system components to include allowance for adequate access and clear­ances for conduct of the tests and examinations;

(c) preparation of plans and schedules; (d) preparation of written test and examination

instructions and procedures; (e) qualification of personnel who perform and

evaluate examinations and tests in accordance with the Owner's quality assurance program;

(f) performance of required tests and examina­tions;

(g) recording of required test and examination resu lts that provide a basis for evaluation and facili ­tate comparison wi th the results of subsequent tests or examinations;

(h) evaluation of tests and examination results;