View source for BECO-86-156, Application for Proposed Change 86-10 to License DPR-35, Adding Figure 3.11-7 to Provide MAPLHGR Vs Average Exposure Curves for Fuel Type BP8DRB300 Used During Reload 7.Fee Paid

{{Adams
| number = ML20210V508
| issue date = 10/02/1986
| title = Application for Proposed Change 86-10 to License DPR-35, Adding Figure 3.11-7 to Provide MAPLHGR Vs Average Exposure Curves for Fuel Type BP8DRB300 Used During Reload 7.Fee Paid
| author name = Lydon J
| author affiliation = BOSTON EDISON CO.
| addressee name = Zwolinski J
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000293
| license number = 
| contact person = 
| document report number = BECO-86-156, NUDOCS 8610100716
| package number = ML20210V512
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 4
| project = 
| stage = Request
}}

=Text=
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w 8057tWED5CW Executive Offices 800 Boylston Street Boston, Massachusetts 02199 October 2, 1986 James M. Lydon                                                              BECo 86-156 Chief Operating Officer Proposed Change 86-10 Mr. John A. Zwolinski, Director BWR Project Directorate #1 Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.           20555 License DPR-35 Docket 50-293 r
Reload #7 Proposed Technical Specification Change (MAPLHGR Curve)

==Dear Sir:==

Pursuant to 10CFR50.90, Boston Edison Company hereby proposes the modifications to Appendix A of Operating License No. DPR-35, which are provided as an attachment to this letter. These proposed modifications are required for our restart from Refueling Outage #7.
The proposed change involves Section 3.ll.A and the figures associated with it. Figure 3.11-7 is added to provide the maximum average planar linear heat generation rate (MAPLHGR) versus planar averagt exposure curves for fuel type BP8DRB300. BP80R8300 is to be used during Reload 7 at Pilgrim in addition to the fuel types currently reflected in curves found in Figures 3.11-1 through 3.11-6. The addition of this fuel to the Pilgrim core requires the addition of this Figure because this fuel type has not been previously licensed to I                 operate at PNPS.
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    ,,    )BOSTONEDISONCOMPANY October 2,219861
       .g  .Page Two-Mr. John A. ' Zwolinski
:Should you have any questions or wish any further.information on this request, please contact us.
Very truly yours, PMK/ pac Attachment 3 signed originals and 37 copies cc: Mr. Robert Hallisey, Director Radiation Control Program Massachusetts Dept. of Public Health 600 Washington Street, Room 770 Boston, MA 02111 Commonwealth of Massachusetts)
County of Suffolk              )
Then personally appeared before me, James M. Lydon,who, being duly sworn, did state that he is Chief Operating Officer of Boston Edison Company and that he '
is duly authorized to execute and file the submittal contained herein in the name and on behalf of Boston Edison Company and that the statements in said submittal are true to the best of his knowledge and belief.
My commission expires:     d O s>12/ ABS -             A>]M                >
DATE''                   N
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    .       Proposed Change The proposed change involves the Pligrim Nuclear Power Station Technical Specifications, Appendix A, Section 3.ll.A and the figures associated with it. Specifically, the proposed changes are to am,end a reference in 3.11.A and add Figure 3.11-7.
Figure 3.11-7 is added to provide the maximum average planar linear heat generation rate (MAPLHGR) versus planar average exposure curves for fuel type BP80RB300. BP8DRB300 is to be used during Reload 7 at-Pilgrim, in addition to
           ' the fuel types currently reflected in curves found in Figures 3.11-1 through
          '3.11-6.
Reason For Change The addition of General Electric BP8DRB300 fuel to the Pilgrim core requires the addition of this Figure because this new fuel type has not been previously licensed to operate at PNPS.
Safety Considerations This amendment request does not present an unreviewed safety question as defined in 10CFR50.59. It has been reviewed and approved by the Operations Review Committee and reviewed by the Nuclear Safety Review and Audit Committee.
Significant Hazards Considerations (1)' Will operation of the facility in accordance with the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Operating Pilgrim Station in accordance with the proposed amendment will not result in a significant increase in the probability or consequences of an accident because the characteristics of type BP8DRB300 fuel is not significantly different from fuel types previously reviewed and approved for use in Pilgrim's core.
Analysis demonstrating this has been performed by General Electric.
The method is contained in NEDE-24011-P-A-7-US of August 1985, which
  '                      was submitted to the NRC September 24, 1985 for review in accordance with the criteria of Section 4 of the Standard Review Plan (NUREG 0800).
The Emergency Core Cooling System models used to determine the effects of a loss of coolant accident (LOCA) in accordance with 10CFR50.46 and Appendix K indicate no increased probability or consequences resulting from installing BP80RB300 fuel into the PNPS core. The results of that analysis did generate a new MAPLHGR curve, represented in Figure 3.11-7, which may be incorporated as an amendment to technical specifications.
Operating Pilgrim in conformance to Figure 3.11-7 results in no significant increase in the probability or consequences of an accident previously evaluated.

(2) Will operation of the facility in accordance with the proposed amendment j~         create-the possibility of a new or different kind of accident from any accident previously evaluated?-
Operating Pilgrim Station in accordance with the proposed amendment will not create the possibility of a new or different kind of
                                                          ~
accident from any accident previously evaluated because the various analyses performed in accordance with the NRC approved methodologies and computer models identified above indicate that conformance to proposed Figure 3.11-7 is enveloped by previously evaluated accidents.
(3) Will operation of the facility in accordance with the proposed amendment involve a significant reduction in a margin of safety?
Operating Pilgrim Station in accordance with the proposed amendment will not involve a significant reduction in a margin of safety because analyses conducted in accordance with NRC approved methodologies demonstrate that the margin of safety remains substantially unchanged by the incorporation of BP80RB300 into the Pilgrim core. Such incorporation does require the addition of Figure 3.11-7. Operation in accordance with Figure 3.11-7 will ensure that no significant reduction of a safety margin occurs.
For the reasons provided above Boston Edison believes that this proposed amendment does not present a significant hazards consideration.
Schedule of Change This change will be put into effect upon Boston Edison's receipt of NRC approval. Please note that this amendment is needed prior to startup from RF0 #7.
Fee Determination Pursuant to 10CFR170.12, Boston Edison has enclosed a check for $150.00 as an application fee.}}