ML20150E425
| ML20150E425 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 12/13/1978 |
| From: | Borgmann E CINCINNATI GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7812190146 | |
| Download: ML20150E425 (3) | |
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]OWM cnCf}h hh TW THE ' CINCINNATI GAS & ELECTRIC COMF%NY iTfD$$r==#ddE3 CINCIN N ATI. OHIO 15 201 -
' C. A. BORG M AN N cet easmsormt.cnoingsa >o Docket No. 50-358 December 13, 1978 i
Mr. Harold Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 RE:
WM. H. ZIMMER NUCLEAR POWER STATION -
UNIT 1 - USE OF AUSTENITIC STAINLESS STEEL IN BWR FACILITIES
Dear Mr. Denton:
This is in reply to the February 28, 1978 NRC Letter to Mr. E. A.
Borgmann from Mr. Jchn F. Stoln. Attached is the applicant's response to I
the NRC Staff Position contained in NUREG 0313, dated July,1977, " Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping." The attachment constitutes our complete response j
to the NRC staff position and addresses each of the subsections in Sections II and III of the staff position.
Very truly yours, THE CINCINNATI GAS & ELECTRIC COMPANY BY E. A. BORGMANN Vice President - Engineering Services and Electric Production EAB: dew Enclosure cc: With Enclosure State of Ohio
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Charles Bechhoefer County of Hamilten)**
Glenn O. Bright Frank F. Hooper S[rntoandsubscribedbeforemethis Troy B. Conner, Jr.
ay o ec d er, lW8.
James P. Fenstermaker
. Peter H. Forster William J. Moran J. Rcbert Newlin y
g William G. Porter, Jr.
ry Public James D. Flynn Thomas A. Luebbers MARGARET L'. HUBER
. Stephen Schumacher un pu.a, g, gf gg John D. Woliver My commission bpas Aug.13,19s3 7.812190196 b
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q WM. H. ZIMMER NUCLEAR POWER STATION - UNIT 1 RESPONSE TO NUREG 0313 j
q The following response addresses each subsection of Sections II and III.
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Section II-I The following pipe lines are the only reactor coolant pressure boundary lines made of austenitic stainless steel material. All have a carbon
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content greater than 0.035%.
Line/ Size Length Material Reactor Water Cleanup 4 in.
200 ft.
304 S.S.
Residual Heat Removal 18 in.
10 ft.
304 S.S.
Reactor Recirculation 20 in.
154 ft.
304 S.S.
Reactor Recirculation 16 in.
73 ft.
304 S.S.
Reactor Recirculation 10 in.
130 ft.
304 S.S.
Reactor Water Cleanup 4 in.
20 ft.
316 S.S.
i All of the abovo piping was furnished in the solution annealed condition. Field welds were not solution annealed. Longitudinal seam welds were solution annealed. All welds were controlled to maintain a'S% minimum ferrite content.
Section III For all Class 1 reactor coolant pressure boundary piping which does not meet the guidelines stated in Sec. II, augmented'in-service inspection and leak detection requirements will be implemented. The weld heat affected zones of those lines listed above in Sec. II do not meet the Sec, II guidelines.
Individual weld heat affected zones will be evaluated based on the.
Stress Rule Index calculations to determine which are service' sensitive and which are not service sensitive.
Non-Service Sensitive: will be inspected in accordance with paragraph III. A. (1) of NUREG-0313.
Service Sensitive: will be inspected in accordance with paragraph III.B. (2) of NUREG-0313.
Leak Detection:
a.
The leak detection system provided inside the primary contain-ment for identifying reactor coolant leakage meets the require-ments of Regulatory Guide 1.45 as described in the FSAR.
FSAR Appendix C, page C-36c documents this conformance.
b.
The technical specifications will incorporate the limits for unidentifiable leakage described in NUREG-0313.
c.
-Unidentifiable leakage will include all leakage other than that leakage described in' NUREG-0313, Subsection III.A. (2).c.
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s 2-RESPONSE TO NUREG 0313 (Cont'd)
I The Zimer Plant has no reactor recirculation bypass lines nor does.it have core spray piping of austenitic stainless steel material.
All in-service inspection methods, standards and examination procedures are in accordance with 10CFR 50, Section 50.55a, paragraph (g).
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