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{{Adams
#REDIRECT [[B13258, Forwards Rev 1 to Reload Safety Evaluation Millstone Unit 3 Cycle 3]]
| number = ML20247N070
| issue date = 05/31/1989
| title = Forwards Rev 1 to Reload Safety Evaluation Millstone Unit 3 Cycle 3
| author name = Mroczka E
| author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000423
| license number =
| contact person =
| document report number = B13258, TAC-71942, NUDOCS 8906050239
| package number = ML20247N072
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 5
| project = TAC:71942
| stage = Other
}}
 
=Text=
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[                                                                                                                                                     :1 May 31. 1989 Docket No. 50-423 B13258 Re:    10CFR50.90 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
 
==References:==
(1)    E. J. Mroczka letter to U.S. Nuclear Regulatory Commis-sion, Proposed Revision to Technical Specifications, dated January 24, 1989.
(2)    E. J. Mroczka letter to U.S. Nuclear Regulatory Commis-sion, Cycle 3, Proposed Revision to Technical Specifica-tions, dated April 12, 1989.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 3 Cycle 3, Proposed Revision to Technical Specifications Reload Safety Evaluation Reoort (TAC No. 71942)
Pursuant to 10CFR50.90, Northeast Nuclear Energy Company (NNECO) submitted a proposed amendment to Facility Operating License NPF-49 (Reference [1]). That                              '
amendment would revise Millstone Unit No. 3 Technical Specification Sec-                                                      i tion 5.3.1 which describes the fuel assemblies and Section 5.3.2 which describes the control rod assemblies. In Reference (2), NNEC0 submitted a reload safety evaluation (RSE) report for Millstone Unit No. 3, Cycle 3.
The purpose of this submittal is to respond to a verbal request from the NRC Staff for additional information regarding the RSE report for Millstone Unit No. 3, Cycle 3.
Page 9 of the RSE describes the results of the evaluation of integral fuel burnable absorbers (IFBA) relative to a large-break loss-of-coolant accident (LOCA). The statement regarding the limiting fuel type is also applicable for the small-break LOCA. On page 19, Table 4, a value of 0.88 percent delta-k is listed for Cycle 3 ejected rod worth. This rod worth remains bounding for Cycle 3 if either an Ag-In-Cd or Hafnium control rod assembly is ejected from the core. Table 3 of the RSE has been expanded and attached herewith to include the end of cycle shutdown requirements and margins for Millstone Unit No. 3, Cycle 2, four-loop and three-loop operation. Also enclosed herewith is a ccpy of the revised RSE for Millstone Unit No. 3, Cycle 3. This revision accounts for early shutdown of Unit No. 3 by expanding the burnup window of Cycle 2.
AM 8906050239 890531 PDR  ADOCK 05000423                                                                                  8 I
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                        -Q      t U.S. Nuclear Regulatory Commission                                              -
B13258/Page 2                                                                    i May 31, 1989 We believe the above information, coupled with the information provided in l                        References (1) and (2), provides a complete basis for approval of the requested amendment.      Of course, should the Staff have any additional ques-l                        tions, NNEC0 will be available to discuss the Staff's concerns.
l                                                                    Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 6
E. J Senir//firoczka or Vice President //
cc:    W. T. Russell, Region I Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit No. 3 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2, and 3 Mr. Kevin McCarthy, Director Radiation Control Unit Department of Environmental Protection Hartford, CT 06116 STATE OF CONNECTICUT)
                                                  ) ss. Berlin COUNTY OF HARTFORD )                                                            ,
Then personally appeared before me, E. J. Mroczka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensees herein, and that the statements contained in said information are true and correct to the best of his knowledge and belief.                                                        j Mata h $$MWY      -
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:                        .,                +:
                                                          -d-    -4 Docket No. 50-423 813258-l l.
1 1
Attachment 1 Millstone Nuclear Power Station, Unit No. 3 End-of-Cycle Shutdown Requirements and Margins for Cycle 2 and Cycle 3 May 1989
 
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    ",,a i: ,                : U.S' Nuclear Regulatory Commission L.                    . B13258/ Attachment 1/Page 1-May 31, 1989 Table 3
. ~
Millstone Nuclear Power Station, Unit No. 3 L                                              End-of-Cycle Shutdown Requirements and Margins for Cycle 2 and Cycle 3 4-Loop            4-Loop                      3-Loop--                                  3-Loop (N)            (N)                            (N-1)                            (N-1)-
Cycle 3            Cycle 2                    Cycle 3                                  Cycle 2 Control' Rod Worth (%Ao)
: All Rods Inserted                        7.61                  7.82                            7.61                              -7.82 All Rods Inserted Less Worst Stuck Rod                              6.48                  6.78                            6.48                              6.78 (1) Less 10%                            5.83                6.10                            5.83                              6.10
                      ' Control Rod Requirements (%Ao)
Reactivity Defects (Combined Doppler, Moderator Tempera-ture, Void)                            3.57                3.64                            2.85                              2.60 Rod Insertion Allowance                0.33                0.44                            0.50                              0.56 (2) Total Requirements                  3.90                4.08                            3.35                              3.16 Shutdown Margin (1)-(2) (%Ap)          1.93                2.02                            2.48                              2.94 Requirement Shutdown Margin
(%Ap)'                                  1.60                1.60                            1.60                              1.60
 
I o                                                                        J Docket No. 50-423 B13_216 I
1 Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Reload Safety Evaluation Report, P vision 1 May 1989
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