ML19224D804
| ML19224D804 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/11/1979 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907170062 | |
| Download: ML19224D804 (3) | |
Text
s B ALTIMOr I G AS AND ELECTR.lC COMPANY P. O. B O X 1475 B A LTIMO R E. MARYLAND 21203 ARTH u n E. Lu N "JVALL, J R.
' 7.'.T.""
July 11, 1979 s
Office of Nuclear Reactor Regulation U. S. Nuclea" Regulatory Commission Washington, D. C.
20555 ATTENTION: Mr. R. W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No.1, Docket No. 50-317 Proposed Finding of No Unreviewed Safety Question on Unit 2, Cycle 3 Reload Core Design
REFERENCES:
a) NRC Letter dated 6/14/79 from R. W. Reid to A. E. Lundvall Calvert Cliffs Unit 1, Cycle 4 Safety Evaluation Report b) BG&E Letter dated 5/29/79 from A. E. Lundvall to R. W. Reid Supplement No. 4 to Unit 1, Cycle 4 Reload Amendment Application Gentlemen:
Calvert Cliffs Unit Number 2 is currently operating in its second cycle with a refueling outage scheduled to commence in mid-October,1979. The purpose of this letter is to advise you of our plans regarding the Unit 2, Cycle 3 reload core design.
The Unit 2, Cycle 3 reload core is designed to perfonn within the current Cycle 2 design parameters, Technical Specifications and related bases, and current setpoints. A total of sixty-four (64) Batch E assemblies will be inserted at the refueling outage. The Batch E assemblies are identical in their mechanical, nuclear and thennal/ hydraulic characteristics to the standard design Batch D assemblies currently operating in Cycle 2.
Those Batch E assemblies which will be located under Control Element Assemblies (CEA's) will have guide t.2be sleeves installed in a manner cnnsister.t with that previously approved by NRC staff in Reference (a).
%t 356 3 /: S s
79073 yn (' g 7
,c
s Office of Nuclear Reactor Regulation July 11, 1979 Page 2 We have conducted a preliminary review of the design and safety analysis effort which is currently being conducted by Combustion Engineering, Inc.
This effort includes an evaluation of all of the postulated incidents considered in the FSAP and all subsequent submittals on both Calvert Cliffs units up to the present.!me.
Our review to date indicates that changes to the Technical Specifications will not be required for the operation of Unit 2, Cycle 3 and that there will be no unreviewed saf> ty questions as defined by 10 CFR 50.59 involved with this reload core des'gn.
Upon completion of the design and safety analysis eiiort now under way at Combustion Engineering, we will conduct a review of the work.
If our findings at that time substantiate our present observations, we will conclude that no application for amendment to the Unit 2 operating license will be required for Cycle 3.
Verification of the reload core design will be c nfirmed by performing a
'tartup test program which will be similar in scope to that defined in Reference (b).
Shoulo this approach not be acceptable to NRC staff, please infora us by August 10, 1979, in order that we may make the appropriate submittal in a timely manner.
Very truly yours, l
A. E. Lundvall, Jr.
Vice President - Supply AEL/WJL/mrc cc:
J. A. Biddison, Escuire G. F. Trowbridge, Esquire Messrs. E. L. Conner, Jr. - NRC P. W. Kruse - CE bbb
? l J:
Office of Nuclear Reactor Regulation July 11, 1979 Page 3 bcc: Messrs. A. E. Lundvall, Jr.
J. B. Bul'ock J. J. Jones R. M. Doug!?ss R. F. Ash / File R. H. Kent L. B. Russell W. J. Lippo,d R. C. L. Olsan
">b j /l,7
'