Published 1987
| Version v1
Book
Quantification of dynamic human errors in the TMI-1 PRA
Creators
- 1. Pickard, Lowe and Garrick, Inc., Newport Beach, CA (USA)
- 2. GPU Nuclear Corp., Parsippany, NJ (USA)
Description
A methodology for quantifying dynamic human error rates, which makes use of the human cognitive reliability (HCR) model, was developed. The objective was to ensure traceability, repeatability, and consistency in the level of analysis for each action. This methodology was then applied in a full-scope, Level 1 probabilistic risk assessment (PRA); i.e., the Three Mile Island Unit 1 (TMI-1) PRA. (orig.)
Additional details
Publishing Information
- Publisher
- Verl. TUEV Rheinland.
- Imprint Place
- Koeln (Germany, F.R.)
- ISBN
- 3-88585-417-1
- Imprint Title
- Probabilistic safety assessment and risk management PSA '87. Vol. 1
- Imprint Pagination
- 424 p.
- Series
- Risk and safety.
- Journal Page Range
- p. 110-115.
Conference
- Title
- International topical conference on probabilistic safety assessment and risk management (PSA '87).
- Dates
- 31 Aug - 4 Sep 1987.
- Place
- Zurich (Switzerland).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 20061161
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HUMAN FACTORS; MAN-MACHINE SYSTEMS; PROBABILISTIC ESTIMATION; PROBABILITY; REACTOR OPERATORS; RELIABILITY; RISK ASSESSMENT; THREE MILE ISLAND-1 REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; PERSONNEL; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS