ML19351E521

Forwards Addl Info Re Containment Pressure Boundary Fracture Toughness & Cladding Swelling & Rupture Models for LOCA Analysis,In Response to NRC 800910 & 1008 Requests, Respectively

ML19351E521
Person / Time
Site:	Zimmer
Issue date:	12/08/1980
From:	Borgmann E CINCINNATI GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8012100305
Download: ML19351E521 (4)

Text

.

Fr W F W1 NN

" =~~ ~

TlIE CINCINNATI GAS & ELECTRIC COMI%NY en ~

CINCIN N ATI OHIO 4 52o1 em #

E. A. BORG M ANN semos vice par s> DENT Docket No. 50-358 December 8, 1980 Mr. Ilarold Denton, Director Office of Nuclear Reactor Regulation

'I . S . Nuclear Regulatory Commission Washing an, D.C. 20555 FE: WM . II . ZIMMER NUCLEAR POWER STATION -

UNIT 1 - RESPONSE TO NRC LETTERS OF SF9TEMBER 10 AND OCTOBER 8, 1980

Dear Mr. Denton:

By letter of September 10 from Robert L. Tedesco to E. A. Borgmann, the NRC requested supplemental information relative to the containment pressure boundary fracture toughness. Attachment 1 is in response to that information request.

By letter of October 8 from Robert L. Tedesco to E. A. Borgmann, the NRC requested supplemental information relative to the Staff Position on cladding swelling and rupture models for loss of coolant accident analysis. Attachment 2 cgstainsgheres o

nse to that information request.

U Very truly yours,

. .e r ~

La:D [ fr ka c

a TIIE CINCINNATI GAS & ELECTRIC COMPANY

. <r. .

[::~ -

l y t

By

^'

[WW --

p E. A. BORGMAIIN g Senior Vice President EAB: dew Enclosure cc: Charles Bechhoefer State of Ohio )

Glenn O. Bright County of IIamilton) ss Frank F. Iiooper Troy B. Conner, Jr. Sworn to and subscribed before me this James P. Fenstermaker 8 day of December, 1980.

Steven G. Smith William J. Moran J. Robert Newlin William G. Porter, Jr. IefAM a James D. Flynn jotaryPublic F. T. Daniels W. Peter Heile MARGARIT L. HUBER James H. Feldman, Jr. N:tary r n.- a a caa John D. Woliver My ccombsm tip..a !.g. la Iw Mary Reder David K. Martin Robert A. Jones Andrew B. Dennison 8012100307 f

i ATTACHMENT 1 ZPS Question 12/8/80 The Zimmer containment pressure boundary is constructed using materials meeting the requirements of ASME Section III; however, our licensing review did not include evaluation of explicit .

compliance with these codes. Consequently, to complete our final SER for Zimmer, we require the following information:

1.. Identification of the fabrication codes (edition and addenda) and the specific paragraphs in these codes that specify the fracture toughness requirements and acceptance criteria (for weldments and base metals). Codes and code paragraphs should be identified for all materials which constitute part of the containment pressure boundary (e . g . , drywell head, piping penetrations, personnel airlocks, equipment hatch).

2. The materials test data that certify that the fracture tough-ness acceptance standards have been met for each of the identified materials in the containment pressure boundary.

Response -

1. The Zimmer containment pressure retaining components are fabricated under the fracture toughness requirements of ASME Boiler and Pressure Vessel Code,Section III, Subsection NE for Class MC components (Winter 1971 Addenda). The require-ments are specified in Paragraph NE 2320. The following components are covered:

a. Drywell head, support ring and bolts for the drywell head.

b. Drywell equipment access hatch

c. Drywell personnel access airlock, including all penetra-tions and nozzles for airlock.

d. Suppression chamber personnel access hatch.

e. All penetration sleeves and a'ttachments for all penetra-tions.

f. Weldments - by qualification of welding procedures for welding of impact tested materials in the weld, heat affected zone and base material.

INFORMATION ON PENETRATION HTAD FITTINGS A) Main Steam Flued Heads Specification H-2235, P.O. Revision, Dated January 15, 1973 Specification

Reference:

Article 2.04C Applicable Code and Addenda: ASME Section III, 1971 Edition thru and including Summer 1972 Addenda Code

Reference:

Article NB-2300, Paragraph NB-2332.a.2 l

ATTACHMENT 1, PAGE 1

. ~ . _. - . ... . . . .-

i , 9, ,

ATTACHMENT-1 2ps (Cont'd) 12/8/80 E) All .Typc 1 and Type' 2 Penetrations - (except ' Main Steam)

} Specification H-2235, Supplement 2, Dated December 28, 1973 i Specification

Reference:

' Article 3.03.A Applicable Code and Addenda: ASME Section III, 1971 Edition thru and including Winter 1972 i

Addenda Code

Reference:

' Article NB-2300, Paragraph NB-2332.a.2 i C) Type 3 Penetrations-Epecification H-2255, Article 3.04.D.a.7 Drawing: M-125 Sheet 3 Notes 12. and 13.

l Applicable Code and Addenda: ASME Section III, 1971 Edition

thru and including Winter 1972

Addenda Code

Reference:

Article NB-2300, Paragraph NB-2332.a.2

, D) Type-4 Penetrations (except penetration M-29)

Specification H-2255, Articles 4.03, 4.04.F Drawing: M-125 Sheet 3 Notes 12. and 13.

Applicable Code and Addenda: ASME Section III, 1971 Edition thru and including Winter 1972 Addenda Code

References:

Article NB-2300, Paragraph NB-2332.a.2 E) Penetration M-29

. Specification'H-283,2 Article 3.04.D Drawing M-125 Sheet 3 Notes 12. and 13.

Applicable Code and Addenda: ASME Section III, 1971 Edition thru and including Winter 1972 Addenda Code

Reference:

' Article NB-2300, Paragraph NB-2332.a.2 1 2. Certified copies of the_Charpy Impact Test reports for all the materials in the containment pressure boundary which are required to'be-impact tested are filed with the applicant.

The applicant has verified to the best of his ability that the acceptance. standards have been met for each of the 1

identified materials.

?

ATTACHMENT 1, PAGE 2 uy - r. y .- -v- . . -

-w - , . - . - - ,,,e, y

q

. R

.s

.e ATTACHMENT 2 ZPS 12/8/80

-Issue The applicant has not provided information to assure that for the fuel cladding in a~LOCA "the degree of swelling and incidence of rupture are not unt'r-estimated" as. required by Appendix K of 10CFR50.46. The procedures proposed

'in NUREG-0630 introduce additional conservatism and should be-utilized to per-form supplemental calculations to the current ECCS analyses.

Position The current analyses in FSAR Section 6.3.3 conservatively bounds the clad swelling and rupture model concerns of NUREG-0630. Additional analyses would be of little value to the ECCS performance evaluation review. In any case,

.since General Electric has not begun to deselop model changes suggested by-NUREG-0630 it would not be possible to perform such an analysis in the near.

future.

This position is supported by three General Electric letters discussing exist-ing model suitability; a GE letter providing comments to NUREG-0630 and a letter from ACRS to the NRC of September 9, 1980 stating "The ACRS recommends that-impi.ementation of the NUREG-0630 models and other significant changes in the evaluation models be held in abeyance-until a thorough revision of the Appendix K requirements can be undertaken ay the NRC staff." These references are listed below.

Reference

1) GE' letter MFN-268-79 of November 2, 1979 from R. H. Buchholz to Darrel G.

Eisenhut, "ORNL Cladding, Swell and' Rupture Data - BWR Evaluation."

2) GE letter MFN-278-79 of November 16, 1979 from R. H. Buchitolz to Darrel G.

Eisenhut, "GE Cladding Hoop Stress at Perforation."

3) GE letter MFN-066-80 of March 24, 1980 from G. G. Sherwood to Richard P.

Denise.

4) GE letter MFN-294-79 of December 7, 1979 from R. H. Buchholzfto Richard P.

Denise, " Comments on the draft report ' Cladding, Swelling and Rupture Models for LOCA Analyses,' NUREG-0630 dated November 8, 1979."

5) ACRS letter of September 9, 1980 from Milton S. Plesset to William J. Dircks,

" Cladding, Swelling and Rupture Models for LOCA Analysis - NUREG-0630."

l I

i' 6 ATTACEMENT 2, PAGE 1 1

l I