Supplemental Information

Section XI, "Rules for Inservice Inspection of

Nuclear Power Plant Components."

"Code Cases, Nuclear Components."

ASNT-SNT-TC-lA, "Nondestructive Testing Personnel

Qualification and Certification."

ASTM A370-86, "Test Methods and Definitions for

Mechanical Testing of Steel Products."

ASTM E208-85, "Method for Conducting Drop-Weight

Tests to Determine Nil-Ductility Transition Temperature of Fer-

ritic Steels."

IEEE 338-1987, "IEEE Standard Criteria for the

Periodic Surveillance Testing of Nuclear Power Generating Sta-

tions Class 1E Power and Protection Systems."

IEEE 379-1977, "IEEE Standard Application of the

Single-Failure Criterion to Nuclear Power Generating Station

Class 1E Systems."

(This standard was revised and issued as

ANSI/IEEE 379-1988, "IEEE Standard Application of the Single-

Failure Criterion to Nuclear Power Generating Station Class 1E

Systems.")

5.4.4

Supplemental Information

"Standard Review Plan," June

NUREG-0800, USNRC,

1987.

SRP

5.4.1.1,

"Pump

Flywheel

Integrity,

(PWR)."

SRP

5.4.2.1, "Steam Generator Materials."

"Steam Generator Tube Inservice

SRP

5.4.2.2,

Inspection."

"Reactor Core Isolation Cooling,

SRP

5.4.6,

(BWR)."

SRP

5.4.7,

"Residual Heat Removal (RHR) Sys-

tern."

5.4.8,

SRP

"Reactor Water Cleanup System,

(BWR)."

SRP

5.4.11, "Pressurizer Relief Tank."

5-11