View source for BECO-83-301, Application for Proposed Tech Spec Change 83-15 to License DPR-35,correcting Error in GE Oct 1983 Reload Licensing Submittal for Restart from Refueling Outage 6

{{Adams
| number = ML20083H705
| issue date = 12/28/1983
| title = Application for Proposed Tech Spec Change 83-15 to License DPR-35,correcting Error in GE Oct 1983 Reload Licensing Submittal for Restart from Refueling Outage 6
| author name = Harrington W
| author affiliation = BOSTON EDISON CO.
| addressee name = Vassallo D
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000293
| license number = 
| contact person = 
| document report number = BECO-83-301, NUDOCS 8401090405
| package number = ML20083H708
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 2
| project = 
| stage = Request
}}

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* EOSTON EDISON COMPANY 800 BOYLsTON STREET BOSTON. MASSADHUBETTs 02199 WILLIAM D. HARRINGTON ermeen viss ensesecut
  -a                                                                                                 December 28, 1983 BEco 83-301 Proposed Change 83-15 Mr. Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.       20555 License No. DPR-35 Docket No. 50-293 Reload 6 Submittal and ProDosed Chances to Technical SDecifications Attachments:   1. General Electric Boiling Water Reactor Supplemental Reload Licensing Submittal for Pilgrim Nuclear Power Station, Unit 1, Reload 6, 22A1694, October 1983.
: 2. Errata and Addenda Sheet 3, dated October 1983, to Loss of Coolant Accident Analysis Report for Pilgrim Nuclear Power Station, NEDO-21696, August 1977.
: 3. Proposed Changes to Technical Specifications for Reload 6.

==Dear Sir:==

The sixth refueling outage at the Pilgrim Nuclear Power Station began on December 10, 1983. The General Electric Reload Licensing Submittal in Attachment 1 provides plant-specific information to supple:nent Topical Report NEDE-240ll-P-A-6, General Electric Standard Application fo' Reactor Fuel (GESTAR-II). Together.. these documents provide the justification for safe operation of Pilgrim during Cycle 7. The addendum to the General Electric Loss of Coolant Accident Analysis Report of August 1977 is provided in Attachment 2 to update that report f ?r the barrier-type fuel that will be used in Reload 6.
In our review of the General Electric Reload Licensing Submittal in Attachment 1, an error was noted on the upper right hand graph in Figure 5                                                      Plant
           ' Response to MSIV Closure,100% Power,107.5% Flow (Page 13).                                                      Curve 3 is labeled the relief valve flow curve, but it actually represents the sum of safety and relief valve flows. This error does not affect the conclusions of the reload submittal and the corrected page will be submitted upon receipt from General Electric.
All transients which are the basis of the Pilgrim license were reviewed for Reload 6. .Those transients which are critical with respect to safety margins 8401090405 831220 poo0m --g                                                  4[   -                             -      - - - - - - - -

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CDRON ' EECON COMPANY Mr. Domenic'B. Vassallo, Chief Page 2 and sensitive to the core' reload parameter changes were reanalyzed. The Reload Submittal in Attachment'l includes the effects of the use of the extended load line limit that was approved on November 22,11983 in.Technica1' Specification Amendment No.~72.
           ~ Boston. Edison has proposed changes to the Technical Specifications to increase the safety ~ relief valve simmer margin at Pilgrim by -letter from W. D.
Harrington to~ D. B. Vassallo, dated April 5, 1983. In addition, under separate cover, Boston Edison intends to request changes to Technical Specifications to allow increased core flow at Pilgrim. In anticipation of your approval of these changes, the General Electric Supplemental Reload Licensing. Submittal in Attachment 1 includes the ef fects of the use of these operating flexibility options -during. Cycle 7. Because operation of Pilgrim without these options is conservative, the reload submittal remains valid for Cycle 7 operation even if these options are not approved.
Pursuant to 10CFR50.90, Boston Edison. hereby proposes the modifications to Appendix A of- Operating License No. DPR-35 that are provided in Attachment 3.
These proposed modifications are required for our restart from Refueling Outage #6. .The filing fee for'these proposed modifications will be forwarded under separate-cover.
Very truly yours, DMV/ksc N
Attachments 1 signed original and 39 copies cc: Mr. Robert M. 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 W. D. Harrington, who, being duly sworn, did state that he is Senior Vice President - Nuclear of the Boston Edison Company, the applicant herein, and that he is duly authorized to execute and file the submittal contained herein in the name and on behalf of the Boston Edison Company and that the statements in said submittal are true to the best of his knowledge and belief.
My Consnission. expires: o& a/, /fss                                                            ///
(         Notary [ublic
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