ML19340C218

Forwards Responses to NRC Questions Re Application for Amend of License DPR-53 Re Fifth Cycle Operation

ML19340C218
Person / Time
Site:	Calvert Cliffs
Issue date:	11/10/1980
From:	Lundvall A BALTIMORE GAS & ELECTRIC CO.
To:	Clark R Office of Nuclear Reactor Regulation
References
NUDOCS 8011140208
Download: ML19340C218 (4)

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B ALTIMORE G AS AND ELE'CTRIC COMPANY P.O. B O X 1475

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B ALTIM O R E, M A R YL AN D 21203 ARTHun E. LUN DVALL.JR.

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w;cES Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ATTENTION:

Mr. R. A. Clark, Chief Operating Reactors Branch #3 Division of Licensing

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No.1, Docket No. 50-317 Amendment to Operating License DPR-53 Fif th Cycle License Application Responses to NRC Staff Questions Gentlemen:

Enclosed are our reponses to questions posed by NRC staff on the subject application.

Very truly yours, BALTIMORE GAS AND ELE RIC COMP,Y

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e A. E. Lunkall, Jr.

Vice President - Supply AEL/WJL/mit Copy To:

3. A. Biddison, Esquire (w/out Encl.)

G. F. Trowbridge, Esquire (w/out Encl.)

Messrs.

E. L. Conner, Jr., NRC P. W. Kruse, CE

Enclosure:

40 copies i

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4 ENCLOSURE Question 1:

i Section 15.4,7 of the Standard Review Plan for the Review of Safety Analysis Reports (NUREG-75/087) requires an analysis of possible fuel loading errors such as the loading of one or more fuel assemblies into improper locations.

Discuss the analysis for each misloading case (including the worst case) considered and show that either the error is detectable (and thus remedial) or that the error is inconsequential and within the nuclear uncertainty or that the offsite consequences of any core damage due to undetected errors are a small fraction of 10 CFR Part 100 guidelines.

Response

Procedures for insuring that fuel misloadings are not present 1.

Cycle 5 I

remain unchanged fran the approved reference cycle (Cycle 4).

Presently, there are tw6 methods which are used to determine a fuel misloading:

1) Visual Core Loading Verification The visual core loading verification is the primary check to insure 4

proper core loading. This check not only verifies the placement of assemblies in the proper core location but also verifies the proper orientation of each assembly.

2) CEA Symmetry Checks Although the visual verification described above is viewed as i

sufficient to preclude misloading, CEA symmetry checks are per-formed to insure that fuel mislo'adings, which might cause a sufficient deviation from the planned design power distributions to impact the sa#ety analyses, would be properly detected. The CEA symmetry checks were approved as part of the Cycle 4 startup l

program per the Cycle 4_ SER which stated that the NRC staff had

Question 1 Response (Continued):

discussed the CEA symmetry tests and criteria with the licensee and found the program to be acceptable. The Cycle 4 startup symmetry checks discussed above had been incorporated in the upcoming Cycle 5 startup test program.

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Question 2:

A partial list of physics characteristics for Cycles 4 and 5 was presented in the Cycle 5 refueling license amendment.

Provide a list of final Cycle 5 physics characteristics if different from the original submittal (Tables 5-1 through 5-6) including the maximum radial power peaks expected to occur (Fr and Fxy with uncertainties and biases).

Response

The list of physics parameters presented in the original submittal is consistent and complete in terms of information presented for past reload submittals for Calvert Cliffs I.

The effects of the extension of the maximum EOC4 burnup window from 11,600 to 11,800 MWD /T will have no impact on the data presented in the original submittal. This data is considered to be final data and includes best estimate radial peaking data with the water hole bias factor applied.

Since uncertainties are accounted for within the setpoint analysis, the allowable radial pea'.s delineated in the Tech Specs include the uncertainty terms.

Consequently, uncertainties are not applied directly to calculated or measured. radial peaking data.

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