Published 1993 | Version v1
Book

Reactor pressure vessel life cycle management at the Calvert Cliffs Nuclear Power Plant

  • 1. Baltimore Gas and Electric Company (United States)
  • 2. Grove Engineering Incorporated (United States)
  • 3. Electric Power Research Institute (United States)

Description

Life Cycle Management (LCM) seeks to manage the aging process of important systems, structures, and components during licensed operation. The goal of Baltimore Gas and Electric Company's (BG and E) Life Cycle Management Program is to assure attainment of 40 years of operation and to preserve the option of an additional 20 years of operation for the Calvert Cliffs Nuclear Power Plant (CCNPP). Since the reactor pressure vessel (RPV) has been identified as one of the most critical components with regard to long-term operation of a nuclear power plant, BG and E initiated actions to manage life limiting or aging issues for the CCNPP RPVs. To achieve long-term operation, technical RPV issues must be effectively managed. This paper describes methods BG and E uses for managing RPV age-related degradation. (author)

Part of:
Transactions of the 12th international conference on structural mechanics in reactor technology. Volume A: Supplement

Additional details

Publishing Information

Publisher
Elsevier
Imprint Place
Amsterdam (Netherlands)
ISBN
0-444-81515-5
Imprint Title
Transactions of the 12th international conference on structural mechanics in reactor technology. Volume A: Supplement
Imprint Pagination
261 p.
Journal Page Range
p. 87-90

Conference

Title
12. international conference on structural mechanics in reactor technology
Acronym
SMiRT 12
Dates
15-20 Aug 1993
Place
Stuttgart (Germany)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35091138
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGING; CALVERT CLIFFS-1 REACTOR; CALVERT CLIFFS-2 REACTOR; PRESSURE VESSELS; RADIATION EFFECTS; SERVICE LIFE; THERMAL DEGRADATION; THERMAL SHOCK
Descriptors DEC
CONTAINERS; ENRICHED URANIUM REACTORS; LIFETIME; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information