ML20204G509
| ML20204G509 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/18/1983 |
| From: | Johnston W Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20204G513 | List: |
| References | |
| FOIA-86-569 NUDOCS 8307220090 | |
| Download: ML20204G509 (5) | |
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p JUL 18 1983 Docket Mo. 5D-423 MEM0PANDUM FOR: Thocas M. f'ovak, Assistant Director for Licensing Division of Licensing FROM:
William V. Johnston, Assistant Director l'.aterials, Chemical ?. Environnental Technology Division of Engineering
SUBJECT:
GDC 51 COMPLIA*!CE - MILLST0!!E UNIT THREE Plant Name: Millstone Nuclear Power Station - Unit Three Suppliers: Westinghouse; Stone & Hehster j
Licensing Stage: OL Docket Ho.: 50-423 l
Responsible Branch & Project Manager: LB 1 j E. Doolittle j
Reviewer:
J. Halapatz i
Requested Completion Date: Open Description of Task: SER Pe GDC 51 Compliance Review Status: Awaiting Confirmatory Information t
j The Materials Engineering Branch, Division of Engineering, foint review of' the l
containment pressure boundary materials of fif11 stone, Unit 3, was conducted Q
with the applicant and architect-engineer, Stone & Webster, at Bethesda, Md.
on June 29, 1983.
The review identified the limiting materials of the containment pressure boundary and the limiting environmental temperature placed on these materials under operating, maintenance, testing and postulated accident conditions cited by GDC 51, " Fracture Prevention of Containment Pressure Boundary. "
l Based on the review, the applicant will provide information confirming that the Ifnf ting postulated design temperatures will not violate the Ifmiting temperatures identified by the review.
fA William V. Johnston, Assistant Director Materials, Chemical & Environmental Technology Division of Engineering
Attachment:
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R. Vollmer D. Eisenhut E. Sullivan S. Pawlicki B. D. Liaw B. Youngblood W. Hazelton R. Klecker C. Cheng E. Doolittle J. Halapatz DISTRIBUTION:
DMB - Docket Files MTEB Reading Files
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MTEB RE 1-1 Millstone 3
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lF ATTACHMENT MILLSTONE NUCLEAR POWER STATION UNIT THREE DOCKET NO. 50-423 MATERIALSENGINEERINGBRhNCH MATERIALS APPLICATION SECTION Fracture Prevention of Containment Pressure Boundary Our safety evaluation review assessed the ferritic materials in the Millstone Nuclear Power Station Unit 3 containment system that consti-tute the containment pressure boundary to determine if the material fracture toughness is in compliance with the requirements of General Design Criterion 51, " Fracture Prevention of Containment Pressure Bounda ry. "
GDC 51 requires that under operating, maintenance, testing and postulated accident conditions, (1) the ferritic materials of the containment pres-sure boundary behave in a nonbrittle manner and (2) the probability of rapidly propagating fracture is minimized.
2 The Millstone 3 containment is a reinforced concrete structure, with a thin steel liner on the inside surface, which serves as a lea.ktight membrane.
The ferritic materials of the containment pressure boundary which were considered in our assessment are those which have been applied in the fabrication of the equipment hatch, personnel locks, penetrations and fluid system components including the valves required to isolate the sys tem.
These components are the parts of the containment system which are not backed by concrete and must sustain loads during the performance of the containment function under the conditions cited by GDC 51.
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We have detennined that the' fracture toughness requirements contained in ASME Code editions and addenda typical of those used in the design of the Millstone 3 containment may not ensure compliance with GDC 51 for all areas of the containment pressure boundary.
We have elected to apply in our licensing reviews of ferritic containment pressure boundary materials, the criteria for Class 2 components identified in the Summer 1977 Addenda of Section III of'the ASME Code.
Because the fracture toughness criteria, that have been applied in construction typically differ in Code classifi-cation and Code edition and addenda, we have chosen the criteria in the Summer 1977 Addenda of Section III of the Code to provide a uniform review, consistent with the safety function of the containment pressure boundary mater'ials.
Therefore, we reviewed the materials of the components of the Millstone 3 containment pressure boundary according to the fracture toughness requirements of the Summer 1977 Addenda of Section III for Class 2 components.
Considered in our review were components of the containment system which are load bearing and provide a pressure boundary in the perfonnance of the containment function under operating, maintenance, testing and postulated accident conditions as addressed in GDC 51.
These components are the equipment hatch, personnel airlocks, penetrations and elements of specific containment penetrating systems.
Our assessment is based on the metallurgical characterization of these materials and fracture toughness data presented in NUREG-0577, " Potential for Low Fracture Toughness and Lamellar Tearing on PWR Steam Generator and Reactor Coolant Pump Supports," USNRC, October 1979 and ASME Code Section III, Summer 1977 Addenda, Subsection NC.
The metallurgical characterization of these materials, with respect to their fracture toughness, was developed from a review of how these materials were fabricated and what thennal history they experienced during fabrication.
The metallurgical characterization of these materials, when correlated with the data presented in NUREG-0577 and the Summer 1977 Addenda of the ASME Code Section III, provides the technical basis for our evaluation.of compliance with the Code requirements.
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.: Based on our review of the available fracture toughness data and materials fabrication histories, and the use of correlations between metallurgical characteristics and material fracture toughness, we conclude, contingent on the receipt of confirmatory information, that the ferritic components in the Millstone 3 containment pressure boundary maet the fracture toughness requirements that are specified for Class 2 components by the 1977 Addenda of Section III of the ASME Code.
Compliance with these Code requirements provides reasonable assurance that the Millstone 3 reactor containment pressure boundary will behave in a nonbrittle manner, that the probability of rapidly propagating fracture will be minimized and that the requirements of GDC 51 are satisfied.
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