ML20207S511
| ML20207S511 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/12/1987 |
| From: | Mcneil S Office of Nuclear Reactor Regulation |
| To: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8703190586 | |
| Download: ML20207S511 (3) | |
Text
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Docket No. 50-318 JISTRIBlJTLON DFieno QrfRet;i'ej EJordan nnC FUx BGrimes L PDR JPartlow Mr. J. A. Tiernan PBD#8 Rdg NThompson Jice President-Nuclear Energy FMiraglia Gray File
' Baltimore Gas & Electric Company OGC-Beth PKreutzer P. O. Box 1475 ACRS-10 SMcNeil Bal timore.. MD 21203
Dear Mr. Tiernan:
~
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - UNIT 2 CYCLE 8 RELOAD Your letter dated February 6,1987 requested amendment-to Operating License No. DPR-69 for Calvert Cliffs Unit 2 to operate for an eight cycle. The NRC staff has performed an initial review of your supporting safety analysis information and has detennined that additional information is required to complete the review. The request for additional information is enclosed.
As'you are intending-to complete this refueling outage on May 12, 1987 and since the Commission did not receive your amendment request until February 18, 1987, ~ time is therefore very short for completing our review.
In order to
. expedite the completion of our review, please provide the information-as requested within 20 days following your receipt of this letter.
Th'is request for information affects fewer than 10 respondents; therefore, OMB clearance is not required under Pub. L.95-511.
Sincerely, Odginalcigned t;y Scott Alexander McNeil, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B i
Enclosure:
Request for Additional Information t
cc w/ enclosure:
See next page I
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- 8 PBD PBD#8 PBD#8 PKrqutzer SMcNeil;cf AThadani J
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M 8703190586 B70312 DR ADOCK 0500 8
e Mr. J. A. Tiernan Baltimore Gas & Electric Company Calvert Cliffs Nuclear P.ower Plant cc:
Mr. William T. Bowen, President Regional Administrator, Region I Calvert County Board of U.S. Nuclear Regulatory Commission Commissioners Office of Executive Director Prince Frederick, Maryland 20768 for Operations 631 Park Avenue D. A. Brune, Esq.
King of Prussia, Pennys1vania 19406 General Counsel Baltimore Gas and Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Jay E. Silberg Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.W.
Washington, DC 20037 Mr. M. E. Bowman, General Supervisor Technical Services Engineering Calvert Cliffs Nuclear Power Plant MD Rts 2 & 4, P. O. Box 1535 Lusby, Maryland 20657-0073 Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box 437 f
Lusby, Maryland 20657-0073 Bechtel Power Corporation ATTN: Mr. D. E. Stewart Calvert Cliffs Project Engineer 15740 Shady Grove Road Gaithersburg, Maryland 20760 l
Combustion Engineering, Inc.
ATTN: Mr. W. R. Horlacher, III Project Manager P. O. Box 500 1000 Prospect Hill Road Windsor, Cnnnecticut 06095-0500 Department of Natural Resources Energy Administration, Power Plant Siting Program ATTN:
Mr. T. Magette j
Tawes State Office Building l
Annapolis, Maryland 21204 i
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m REQUEST FOR ADDITIONAL INFORMATION BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS, UNIT 2 CYCLE 8 RELOAD 1.
Table 5-2 of the reload submittal presents an analysis of the shutdown margin for the end of cycle 8 based on hot zero power, steam line break requirements.
The licensee states that this analysis provides the most limiting value of the shutdown margin.
However, since shut-down margin requirements are applicable throughout the cycle and for any operating condition, provide a shutdown margin analysis that considers the following factors:
i a.
Hot full power.
i b.
All CEA's inserted worth, c.
All CEA's inserted less worst stuck rod worth [(N-1) worth].
d.
(N-1) worth less 10% for uncertainty.
e.
Reactivity defects worth (should include Doppler, Tavg, and flux redistribution effects).
f.
Rod insertion allowance worth, g.
Total requirements worth (Items e and f).
h.
Shutdown margin (Item d - Item g).
l i.
Required shutdown margin worth.
j.
Margin in excess of Technical Specification Shutdown Margin (Item h - Item i).
1 i
This analysis should be provided for the most limiting time in the cycle-j which may well be at end of cycle 8.
l 2.
For a CEA ejection accident, the staff assumes for dose calculational i
purposes that clad failure occurs for those fuel rods which experience l
DNB (see Section 15.4.8 of the Standard Review Plan). This reload submittal assumes the number of fuel rods experiencing clad. failure are those with radially averaged fuel enthalples greater than 200 cal /ge.
This is a much higher enthalpy criterion than the staff finds acceptable.
Results from fuel failure tests indicate a clad failure threshold no greater than 140 cal /gm for irradiated fuel.
For CEA ejection analyses which do not use clad failure criteria acceptable to the staff, the staff assumes 10% as the aucunt of failed fuel in the dase calculations.
Therefore, confirm that the dose consequences for such CEA ejection i
accidents for Cycle 8 are well within (25%) of the 10 CFR Part 100 exposure guidelines when using 10% for the amount of failed fuel.
Provide the results of these dose calculations.
3.
The fuel loading error event is not discussed in the reload submittal.
Since the fuel management strategy is different than the previous strategy, confirm that either a reference or generic analysis of the fuel loading error event is still applicable to this reload.
t' 4.
The NRC has approved, with comments, the ANS-19.6.1 A-erican National Standard on Reload Startup Physics Tests for Pressurized Water Reactors.
Since there are a number of changes in the startup test program for Cycle 8, confirm that the revised startup test program conforms to ANS-19.6.1.
i
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