ML20091C183

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Forwards Acceptability of Class 1 24-Inch Feedwater Check Valves, Addressing Concerns Raised at GDC 51 Compliance Audit Conducted on 830624.Info Should Assist NRC in Closeout of SER Confirmatory Issue 22
ML20091C183
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 05/25/1984
From: Kemper J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Schwencer A
Office of Nuclear Reactor Regulation
Shared Package
ML20091C186 List:
References
NUDOCS 8405300498
Download: ML20091C183 (3)


Text

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O PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A, PA.19101 MAY 251984

'284'-45o2 mmm.

VfCE PRESIDEPsT EMapMas asMe Amo ness ancM Mr. A. Schwancer, Chief Docket Nos.: 50-352 Licensing aranch No. 2 50-353 Division of Licensing U.

S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Limerick Generating Station, Units 1 & 2 Additional Infcrmation for Materials Engineering Branch (MTEB) Regarding SER Confirmatory Issue #22 - Fracture Toughness of Containment Pressure Boundary

Reference:

General Design Criteria (GDC) 51 Compliance Audit for Limerick Units 1 and 2, conducted on June 24, 1983.

Enclosure:

" Acceptability of 24-Inch Class 1 Feedwater check Valves", Technical Report No.

1183-05EV, Revision 2, May 1984.

Files GOVT 1-1 (NRC)

Dear Mr. Schwencer:

We are pleased to provide the enclosed report in order to address the concerns raised by J. Italapatz (NRC/MTED) at the reference audit regarding the fracture toughness capability of the 24-inch class 1 feedwater check valves (1F074 A and B, 1F010 A and B, 2F074 A and B, 2F010 A and D).

The attached report provides documentation that these valves satisfy the acceptance criteria of GDC 51

(" Fracture Prevention of Containment Pressure Boundary")

in the following three areas:

(1) the check valve castings meet the material toughness requirements of the 1977 Summer Addenda of ASME Section III, (2) the permissible lowest service metal temperature was satinfactorily confirmed by available nil ductility transition temperature data, and h

O Ml

. e (3) brittle fractures are highly unlikely as indicated by a fracture mechanics analysis.

In addition, the material of these valves was demonstrated to be satisfactory by Charpy impact testing and by in-situ metallographic examination of the Unit i valves as described in Appendix A of the attached report.

We trust that this information will assist you in the closecut of SER confirmatory issue #22.

Sincerely, AS/~f JIIA/gra/050984950 cc:

See Attached Service List

g.

s cc: 4.idge Lawrence Brenner (w/o enclosure)

Judge Peter A. Morris (w/o enclosure)

Judge' Richard F. Cole (w/o enclosure)

Troy B. Conner, Jr., Esq.

(w/o enclosure)

Ann P. Hodgdon, Esq.

(w/o enclosure)

Mr. Frank R. Romano (w/o enclosure)

Mr.-Robert L. Anthony (w/o enclosure)

Maureen Mulligan (w/o enclosure)

Charles W. Elliott, Esq.

(w/o enclosure)

Zori G. Ferkin, Esq.

(w/o enclosure)

Mr. Thomas Gerusky (w/o enclosure)

Director, Penna. Emergency (w/o enclosure)

Management Agency Angus Inve, Esq.

(w/o enclosure)

David Wersan, Esq.

(w/o enclosure)

Robert J. Sugarman, Esq.

(w/o enclosure)

Martha W. Bush, Esq.

(w/o enclosure)

Spence W. Perry, Esq.

(w/o enclosure)

Jay M. Gutierrez, Esq.

(w/o enclosure)

Atomic Safety & Licensing Appeal Board (w/o enclosure)

Atomic Safety & Licensing Board Panel (w/o enclosure)

Docket & Service Section (w/o enclosure)

James Wiggins (w/o enclosure)

Timotny R. S. Campbell (w/o enclosure)

..I' l

/ ^

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