ML19347E175

Forwards Matl Engineering Branch Request for Addl Info Re Compliance of Containment Pressure Boundary Matls W/General Design Criterion 51

ML19347E175
Person / Time
Site:	Grand Gulf
Issue date:	04/09/1981
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Mcgaughy J MISSISSIPPI POWER & LIGHT CO.
References
NUDOCS 8104240182
Download: ML19347E175 (8)

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~~ g UNITED STATES NUCLEAR REGULATORY COMMISSION n

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g Mr. J. P. McGaughy, Jr.

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Assistant Vice President, Nuclear Production

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Mississippi Power and Light Company Eh P. O. Box 1640 Jackson, Mississippi 39205

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - GRAND GULF NUCLEAR STATION, UNITS 1 AND 2 As a result of our review of the information contained in the Final Safety Analysis Report for the Grand Gulf Nuclear Station, Units 1 and 2, we have developed the enclosed reouest for additional information.

Included are questions from the Materials Engineering Branch, regarding compliance of the materials of the containment pressure boundary with the requirements of GDC 51.

We request that you amend your Final Safety Analysis Report to reflect your responses to the enclosed requests as soon as possible and to inform the Project Manager, Joseph A. Martore, of the date by which you intend to respond.

Sincerely, 0TW Robert L. Tedesco, Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional Information ecs w/ enclosure:

See next page 8104240182

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APRg gg, Mr. J. P. McGaughy Assistant Vice President - Nuclear Production Mississippi Power & Light Company P. O. Box 1640 Jackson, Mississippi 39205 cc:

Robert B. McGehee, Esq.

Wise, Carter, Child, Steen & Caraway P. O. Box 651 Jackson, Mississippi 39205 Troy B. Conner, Jr., Esq.

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Conner, Moore & Corber 1747 Pennsylvania Avenue, N. W.

Washington, D. C.

20006 Mr. Adrian Zaccaria, Project Engineer Grand Gulf Nuclear Station Bechtel Power Corporation Gaithersburg, Maryland 20760 Mr. Alan G. Wagner, Resident Inspector Route 2 Box 150 Port Gibson, Mississippi 39150 Mr. N. L. Stampley, Sr. Vice President Engineering, Production & Construction 4

P.O. Box 1640 Jackson, Mississippi 39205 Mr. L. F. Dale Nuclear Project fianager P.O. Box 1640 Jackson, Mississippi 39205 Mr. John Richardson P. O. Box 1640 Jackson, Mississippi 39205

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APR 9 W

ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION GRAND GULF NUCLEAR STATION, UNITS 1 AND 2

_ MATERIALS ENGINEERING BRANCH 252.1 Fracture Prevention of Containment Pressure Boundary We have assessed the ferritic materials in the Grand Gulf Units 1 and 2 containment system that constitute the containment pressure boundary to determine if the material fracture toughness is in compliance with the rquirements of General Design Criterion 51, " Fracture Prevention of Containment Pressure Boundary."

GDC-51 requires that under operating, maintenance, testing and postulated accident conditions, (1) the ferritic materials of the containment pressure boundary behave in a nonbrittle manner, and (2) the probability of rapidly propagating fracture is minimized.

The Grand Gulf orimary containment is a reinfnrced concreto structura with a thin steel liner on the inside surface which serves as a leaktight membrane. The ferritic materials of the containment pressure boundary which were considered in our assessment were those applied in the fabrication of the equipment hatch, personnel airlocks, penetrations and piping system components, including the isolation valves required to isolate the system. These components are the parts of the containment system which are not backed by concrete and must sustain loads.

The Grand Gulf containment pressure boundary is comprised of ASf1E Code Class 1, 2 and MC components. In late 1979, we reviewed the fracture toeghness requirements of the ferritic materials of Class MC, Class 2 and Class 1 components which typically constitute the containment

2-pressure boundary. Based on this review we determined that the fracture toughness requirements contained in ASME Code Editions and Addenda typical of those used in the design of the Grand Gulf Units 1 and 2 containment may not ensure compliance with GDC-51 for all areas of the containment pressure boundary. We initiated a program to review fracture toughness requirements for containment pressure boundary materials for the purpose of defining those fracture toughness criteria that most appropriately address the requirements of r,0C-51.,Drior to Completion of this study, we have elected to apply in our licensing reviews the criteria identified in the Summer 1977 Addenda of Section III of the ASME Code for Class 2 components. These criteria were selected to ensure that uniform fracture toughness requirements, consistent with the containment safety function, are applied to all components in the. containment pressure boundary.

Accordingly, we have reviewed the Class 1, 2, and MC components in the Grand Gulf containment pressure boundar.y according to the fracture toughness requirements of the Summer 1977 Addenda of Section III for Class 2 components. However, in order to complete our review, we require additional information because the FSAR does not provide the information necessary to characterize the fracture toughness of the reactor containment pressure boundary within the context of GDC-51. We request, therefore, that the following information be provided by the applicant:

(1)

Lowest Service Metal Temoerature The lowest service metal temperature within the context of the effective NE 2300 and GDC-51.

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. (2)

Penetrations (a) Listing of all containment hot and cold pipe penetrations and related supplemental information which identifies penetration assembly sleeve, process pipe and end closure materials by speci-fication, final heat treat condition, nominal OD and schedule, wall or section thickness.

(b) Full size assembly and detail drawings showing as-built configurations and dimensioning of hot and cold pipe penetrations.

(c) Fracture toughness dita relating to the materials of those parts of penetration assenblies which perform the containment function and provide a preisure boundary under the conditions cited by GDC-51.

(3)

Equipment Hatch and Personnel Access Airlock (a) Full size assembly drawing and detail drawings which identify and dimension those parts which constitute parts of the containment pressure boundary.

(b) Supplemental information related to item 3(a) above which identifies materials of the parts of interest by specification, final heat treat condition and section thickness.

(c) Fracture toughness data relating to the materials of those f

parts which perform the containment function and provide a pressure boundary under the conditions cited by GDC-51.

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(a)

Main Steam - Main Feedwater - Au iliary Feedwater System (a) Full size piping diagrams and related pipeline list, pipe design tables which identify these systems by line designators and pipe size, schedule or wall and material by specification and grade and which identify valves by number, type and valve pressure boundary materials by specification, grade and final heat treat condition.

(b) Fracture toughness data relating to the material of those parts of the main stdam-main feedwater and auxiliary feedwater systems which perform the containment function and provide a pressure boundary under the conditions cited by GDC-51.

(c) Graphic legend information relating to the piping diagrams addressed in item 4(a).

(5)

Should the fracture toughness data requested under items 2(c), 3(c) and 4(b) above be unavailable, the applicant is requested to provide the following information for the materials of interest.

1.

Seamless Pipe (a) Billet heating temperature prior to piercing (b)

In-process reheat temperatures (c) Stock wall thickness prior to final sizing g.

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. (d) Reheat temperature prior to final s'izing (e) Pipa final heat treatment or pipe assembly heat treatment 2.

Seamless Ells (a) Stock heating temperature prior to hot forming (b) In-process reheat temperatures (c) Ell final heat treatment or pipe assembly heat treatment 3.

Melded Pipe (a) Metallurgical heat treat condition of plate stock as entered

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into fabrication (b) Plate stock heating temperature prior to hot forming (c)

In-process reheat temperatures (d) Pipe final heat treatment or p!pe assembly heat treatment 4.

Welded Ells i

(a) Metallurgical heat treat condition of stock as entered into fabrication (b) Stock heating temperature prior to hot forming (c)

In-process reheat temperatures (d)

In-process heat treatments

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. (e) E11 final heat trest:cr.t or pipe assembly heat trettr.cr.ts 5.

Valves (a) Final metallurgical heat treat condition of the material of

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those parts which constitute parts of the pressure boundary.

(b)

In-process postweld repair heat treatments of the material of those parts which constitute parts of the pressure boundary.

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