ML19320A951
| ML19320A951 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 06/30/1980 |
| From: | Borgmann E CINCINNATI GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8007080317 | |
| Download: ML19320A951 (2) | |
Text
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THE CINCINNATI GAS & ELECTRIC COMPANY cy!-
CINCINNATf, OHIO 45201 E. A. OORGM ANN SE N*CR v5CE PRESIDENT Docket No. 50-358 June 30, 1980 EMr. llarold Denton, Director Office of Nuclear Reactor Regulation U.S.-Nuclear Regulatory Commission j
Washington, D.C.
20555 i.
RE:
WM. H.
ZIMMER. NUCLEAR POWER STATION -
L UNIT 1 - MODIFICATIONS TO BOILING WATER REACTOR CONTROL ROD DRIVE SYSTEMS
Dear Mr. Denton:
~
The following comments and position are in response to the March 7, 1980 letter from Mr. John F. Stolz to L
Mr. E./A.1Borgmann and NUREG-0619 (April 1980 - For Comment).
As a result of'our review of these documents, we have concluded that the St'aff. position'regarding-cutting, capping and rerouting the. control rod drive ("CRD") return line is not applicable to'the Zimmer Station.
The concern stated in Sections 7.2 and 8.3 of NUREG-0619 leading _to the Staff position is the very large amount of inspection ltimeJ(and plant personnel radiation exposure) required to verify that intergranular stress corrosion cracking has not occurred ~in a CRD return.line (and nozzle).
The CRD return line-at Zimmer is not stainless steel but is carbon steel and hence'is not' sensitive to.intergranular stress corrosion cracking.
Therefore, the large amount of inspection with
-concomitant' radiation exposure to plant personnel would not be
-required at'Zimmer.
Furthermore, although Zimmer is a 218 inch BWR/5, it'has the same CRD-hydraulic system _as used in a 218 inch BWR/6. - Thus, inasmuch as NUREG-0619 Section 8.l(4) (a) does not require rerouting of the stainless steel return line'for the 218 inch BWR/6, Zimmer should not be required to reroute
/its carbon steel'CRD return'line.
For Zimmer, we would propose to valve out the CIU). return line without rerouting the line.
By valving out, rather than cutting and capping, the ability to use the CRD pumps to' inject-coolant directly into the vessel is
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. retained. ~As pointed out in.Section 7.3 of NUREG-0619, this is a highly desirable feature.
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To:
Mr. Harold =Denton, Director June 30, 1980 lRe:
Wm. H.
Zimmer Nuclear Power Station -
Page #2 Unit 1 --Modifications to' Boiling Water Reactor Control Rod Drive Systems Please inform us promptly whether or not you concur with this position.
Very truly yours, THE CINCINNATI GAS & ELECTRIC COMPANY By gM-+ ----
E. A. BORGMANN Senior Vice President EAB: dew cc:- Charles Bechhoefer Glenn O. Bright Frank F. Hooper Troy B. Conner, Jr.
Janes P. Fenstermaker Steven G. Smith William J. Moran J.
Robert Newlin William ~G.
Porter, Jr.
James D..Flynn W. Peter Heile Leah S. Kosik John D. Woliver Mary Reder David K.: Martin Robert A.' Jones Andrew B. Dennison
,. _ ~
,