View source for BECO-86-001, Application for Amend to License DPR-35,consisting of Proposed Change 86-01,revising Tech Spec Sections Re Operation of Recirculation Sys.Amend in Response to ASLB 840126 Order.Fee Paid

{{Adams
| number = ML20137C078
| issue date = 01/06/1986
| title = Application for Amend to License DPR-35,consisting of Proposed Change 86-01,revising Tech Spec Sections Re Operation of Recirculation Sys.Amend in Response to ASLB 840126 Order.Fee Paid
| author name = Harrington W
| 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-86-001, BECO-86-1, NUDOCS 8601160188
| package number = ML20137C081
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS &amp; PERMITS
| page count = 5
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:a BOSTON EDl50N COMPANY GOD BOYLsTON STREET BOSTON, massachusetts 02199 WILUAM D. HARRtNGTO N season wees ensesosssy
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January 6, 1986 BECo 86-001 Proposed Change 86-01 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 OPR-35 Docket 50-293 Proposed Technical Specification Change Single Recirculation Loop Operation

==Dear Str:==

Pursuant to 10CFR50.90, Boston Edison Company hereby proposes the attached modification to Operating License No. DPR-35 and Appendix A of the license.
This modification revises sections concerning operation of the recirculation system. This is proposed in response to the Atomic Safety and Licensing Board order dated January 26, 1984, and supersedes all previously proposed recirculation system Technical Specifications.
Very ticly yours, nw MTL/kmc                                                                  W" Attachments One Original and 39 copies cc:     See.next page Commonwealth of Massachusetts)
County of Suffolk                )
Then personally appeared before me William D. Harrington, who, being duly sworn, did state that he is Antor Vice President - Nuclear of 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 Boston Edison Company and that the statements in said submittal are true to the best of his knowledge and belief.
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  =-     BOSTONEDISONCOMPANY 6    Mr.-John A. Zwolinski, Olrector
        .gagua{y6,1986' s
cc: .Mr. Robert M. Hallisey, Director.        !
Radiation. Control Program Massachusetts Dept. of Public Health
:600 Washington Street, Room 770 Boston, MA
                         -    02111 Mr. John F. Doherty 318 Summit Ave. -Apt. 3-Brighton,-MA    02135 b
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Attachment A                                )
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==References:==
 ~1)    Proposed Technical Specification Change #81-02 dated May 12, 1981 (BECo #2.81.94) - Superseded oy this proposal
: 2)  " Pilgrim Nuclear Power Station Single Loop Operation",
General Electric Company, NED0-24268, June 1980 with Errata and Addends Sheet No. 1, September 1980
: 3)  NRC {{letter dated|date=August 26, 1982|text=letter dated August 26, 1982}} (BECo. #1.82.261)
: 4)  BECo {{letter dated|date=April 11, 1983|text=letter dated April 11, 1983}} (BECo #2.83.87)
: 5)  BECo {{letter dated|date=October 25, 1983|text=letter dated October 25, 1983}} (BECo #2.83.265)
: 6) ASLB Order dated January 26, 1984 (BECo #1.84.064)
: 7)  BECo Proposed T.S. Change 85-10 dated 8/9/85 (2.85.147)
Proposed Change This change will allow Pilgrim Nuclear Power Station to be operated at up to 50% of rated power with one recirculation loop out of service. The attached license and Technical Specification pages contain the following changes:
License No. DPR-35 Page 3, item 3.E " Recirculation Loop Inoperable". This condition of License would be deleted with this proposed change.
Table of Contents Section 3/4.6.F was changed from " Jet Pump Flow Mismatch" to " Recirculation Pumps".
Safety Limit / Limiting Safety System Setting To Section 1.1.A add "for two recirculation loop operation (1.08 for single loop operation greater than 24 hrs.)" and "(1.08)".
Various equations for Fuel Cladding Integrity have been modified for adjustments required when in the single loop mode of operation:
2.1.A.I.a - APRM Flux Scram Trip Setting 2.1.8       - APRM Rod Block Trip Setting Figure 2.2.1 has been deleted.
These changes provide additional long term fuel cladding protection by adjusting instruments to correspond to the reduced flow through the reactor core.

Limiting Conditions of Operation (LCO's)/ Surveillance Requirements
    'Various equations have been modified for adjustments required when in the single loop mode of operation:
Table 3.1.1 - APRM Trip Level Setting Table 3.2.C - APRM Upscale
                  - APRM Downscale Sections 3/4.6.F have been retitled " Recirculation Pumps" instead of " Jet Pump Flow Mismatch." This is more consistent with the LCO's and Surveillance Requirements.
LC0 3.6.F.2 has been reworded from requiring a shutdown due to an inoperable recirculation pump, to allowing single loop operation up to 507. rated power.
LCO 3.6.F.3 has been added to assure all appropriate instrument settings are made.
LCO 3.11.A has been modified to account for single loop operation.
LCO 3.11.C.2.a has been modified to specifically state two recirculation loop operation.
LC0 3.11.C.2.b was added for single loop operation Minimum Critical Power Ratio (MCPR).
   -Table 3.11-1 added appropriate values for single loop operation.
Figures 3.11-1 through 6 were modified to include values for single loop operation.
Bases The bases for Sections 1.1.A, 2.1, 2.1.A. 2.1.8, 3.11.A, and 3.11.C have been modified with the appropriate reference for single loop analysis (GE NEDO-24268) and other pertinent information.
Miscellaneous Changes (Page renumbering)
Due to the changes made in this proposal, the following pages are being added or deleted for simpilfication:
Delete:  page 8a page 10 page 21 Add:  page 127a Delete:  page 205-ci Page 205-c2 Reason for Change The loss of a single recirculation pump is not an improbable event at an operating BNR. While the time required to procure necessary parts and to repair the loop depends on the nature of the failure, any loss of operating o
capacity would have a significant effect on plant availability. Modifying the Technical Specifications as requested will increase availability without reducing the safety of plant operation.
Safety Considerations Pilgrim Station's original FSAR includes a statement that the plant may be operated with one recirculation pump out of service. Therefore, this change does not involve 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 It has been determined that the amendment 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 wc,uld not (1) involve a significant increase in the probability or consequences of an accident previously evaluated because single loop operation was considered in the original safety analysis of Pilgrim Station, or (2) create the possibility of a new or different kind of accident from any accident previously evaluated because single loop operation was considered in the original design and documented in the FSAR of Pilgrim Station, or (3) involve a significant reduction in a margin of safety since the basis for single loop thermal limits assumes safe operation up to 80%
power attainable (see Reference 2 page 3-1); hence limiting power to 50%
     ~1ntroduces further conservatism and adds to the safety margin associated with single loop operation.
Schedule of Change BECo letter of October 25, 1983 (Reference 5) discusses a new procedure which must be approved by our Operations Review Committee (0RC) prior to use by the plant staff. This procedure will not be addressed by ORC until NRC approval of this proposed technical specification.
Therefore, this change will become effective upon ORC approval of the procedure for Single Loop Operation.
Fee Determination
     -Pursuant to 10CFR170.12(c), an application fee of $150.00 is included with this proposed amendment.
PLEASE NOTE - Table 3.1.1 is also the subject of Proposed Change 85-10 (Reference 7).
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