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#REDIRECT [[BECO-84-045, Application for Amend to License DPR-35,consisting of Proposed Tech Spec Change 84-02 Allowing Increased Core Flow]]
| number = ML20087L075
| issue date = 03/20/1984
| title = Application for Amend to License DPR-35,consisting of Proposed Tech Spec Change 84-02 Allowing Increased Core Flow
| 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-84-045, BECO-84-45, NUDOCS 8403270010
| package number = ML20087L078
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 3
| project =
| stage = Request
}}
 
=Text=
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BOaTON EDISON COMPANY A00 SOvLaTON ETREET BOSTON, MASSACHUSETTS 02199 March 20, 1984 wtLLIAM O. HARRIN3 TON I.'U" ""'"~                                                                                                              Proposed Change 84-02 Mr. Domenic 8. 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 Proposed Technical Specification Chance to Allow Increased Core Flow
 
==Dear Sir:==
 
l                Pursuant to 10CFR50.90, Boston Edison Company hereby proposes the attached                                                                                    .
modification to Appendix A of Operating License No. DPR-35. This modification will-allow the Pilgrim Nuclear Power Station to operate at core flows above the rated flow. The filing fee for this proposed modification was submitted                                                                                    .
              . by letter f rom W.D. .Harrington to R.M. Diggs, dated January 11, 1984 (BECo 84-008).
Very truly yours, DMV/kmc Attachment One 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 1that 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 Commission expires: ve4.44 v.a/                            3 /983                                        ANNotaryhPut/licI/O
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,                  PDR ADOCK 05000293                                              -
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                                        , . . . - -              , . _ . , . . . -            . - ,    , , - ~ . , . - _ - , , _ . .          - . - - - . , - - , - -
 
Proposed Technical Specification Chance to Allow Increased Core Flow Proposed Chance The proposed change involves the Pilgrim Nuclear Power Station Technical
                . Specifications, Appendix A, Sections 3.2 and 3.11, Protective Instrumentation                                                                                                        ,
and Reactor Fuel Assembly, respectively. 3pecifically, the proposed changa is shown on attached Technical Specification Pages 55 and 205H, and is described below.
                      ' 1. It is proposed that an additional restriction be made to require tha
:                          rod block monitor maximum trip level setting to be set at 107% power i                          for core flows of 100% rated or greater. This restriction is to be added to Footnote 2 of Table 3.2.C. Instrumentation that Initiates Rod Blocks, on Technical Specification Page 55.
In addition to the above, it is proposed that Technical Specification Page 55 be revised to correct a typographical error on the third line of Hote 1.
: 2. It is preposed that the Pilgrim Power / Flow Map, Technical                                                                                                                ,
'                          Specification Figure 3.11-9 (Page 205H), be expanded to include the region bounded by the points (power, flow): (1005, 1005), (1005, 107.5%), (80%,112.5%), (50%,112.5%), and (50%,1005).                                                                                                                        i Reason for_ Chance r
With the exception of correction of the typographical error, the proposed changes are requested to allow increased core flow at Pilgrim. The use of increased core flow would permit greater flexibility in operation and result in increased energy output at Pilgrim. For example, time would be saved i                during startup maneuvers when pre-conditioning interim operating management recommendation (PCIDMR) limitations are greatest.
j The additional restriction proposed for the rod block monitor mitigates the effects of a rod withdrawal error during power operation at core flows greater than 100% rated. At core flow greater than 100% rated, the rod withdrawal error becomes the limiting transient. But by removing the flow dependence of the rod block trip for flows greater than 100% (i.e., installing a constant 107% trip at such flows), the effects of this transient are mitigated. For
;              . flows greater than 100% rated, the proposed constant 107% power rod block trip is more conservative than the presently required flow-biased.setpoint.
                -Safety Considerations i
This change 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.
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                      -Sianificant Hazards Consideratione.
                      .It has been determined that the amendmant request involves no significant hazards consideration. Under the NRC's regulations in 10CFR50.92, this means that. operation of the Pilgrim Nuclear Power Station in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
The NRC.has provided guidance concerning the application of standards for determining whether license amendments involve significant hazards considerations by providing certain examples (48 FR 14870). One example of an amendment that is considered -not likely to involve a significant hazards consideratic is "...(iv) A relief granted upon demonstration of acceptable operation froin an operating restriction that was imposed because acceptable operation was not yet demonstrated. This assumes that the operating restriction and the criteria to be applied to a request for relief have been established in a prior review and that it is justified in a satisfactory way that the criteria have been met." Relief is requested from the operating restriction placed by the Pilgrim Power / Flow Map, Technical Specification Figure 3.11-9. The demonstration of acceptable operation for this requested
[
relief is provided by the attached General Electric Safety Review of Pilgrim E                      Nuclear Power Station, Unit No.1 at Core Flow Conditions Above Rated Flow v                  .Throughout Cycle 6, NEDO-30242, dated August, 1983, including Supplement 1 and i
Errata. Sheet. The demonstration of acceptable operation for this requested relief.~for Cycle 7 operation at Pilgrim is provided by the General Electric t-                      Boiling Water Reactor Supplemental Reload Licensing Submittal for Pilgrin L                        Nuc1' ear Power Station Unit'1, Reload 6, 22A1694, October 1983. This reload l                      licansing submittal was transmitted to the NRC by letter dated December 28, 1983. The results of'these analyses show that the current technical specifications with incorporation of the additional rod block monitor restriction on Technical Specification Fage 55 are adequate to preclude the
!                        violation of any safety limits during operation of Pilgrim within the extended
!                        power / flow map in revised Technical Specification Figure 3.11-9.
l Schedule of Change This change will be put into effect upon Boston Edison's receipt of approval by the Commission.
1 Fee Determination l                        Pursuant to 10CFR170,12, Boston Edison proposes that this is a Class III l                        change. The filing fee for this proposed Class III change was submitted by s
letter from W. D. Harrington to R. M. Diggs, dated January 11, 1984 ( BECo 84-008).
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