View source for B16581, Monthly Operating Rept for Oct 1997 for Mnps,Unit 3

{{Adams
| number = ML20199B087
| issue date = 10/31/1997
| title = Monthly Operating Rept for Oct 1997 for Mnps,Unit 3
| author name = Emmons K, Hicks G
| author affiliation = NORTHEAST NUCLEAR ENERGY CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000423
| license number = 
| contact person = 
| document report number = B16581, NUDOCS 9711180207
| document type = MONTHLY OPERATING ANALYSIS REPORT, TEXT-SAFETY REPORT
| page count = 8
}}

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                                                                                                  - Northemt Nuclear Energy cnagiany .
                             .                                                                      P.O But 128 Waterford, Cr 06385-0128 (860) 447 !?91 Fax (860) 444-4277 -
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Docket No. 50423 B16581 US Nuclear Regulatory Commission Attention: Document Control Desk -
Washington, D.C. 20555 Millstone Nuclear Power Station Unit No. 3 Facility Operating License Number NPF-49 Monthly Operatina Reoort for October 1997                                                                 >
In' accordance with the reporting requirements of Technical Specification 6.9.1.5 for Millstone Unit No. 3, enclosed in Attachment 2 is the Monthly Operating Report for the month of October 1997.
Should you have any questions regarding this submittal, please contact Mr. David Smith at (860) 437-5840.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY r
a
                                                                        . D. Hicks #
Director - Millstone Unit No. 3 l
Attachments (2) cc:        H. J. Miller, Region 1 Administrator W. D. Travers, Ph.D, Director Special Projects
[<C                   f A. C. Ceme, Senior Resident inspector, Millstone Unit No. 3 J. W. Andersen, NRC Project Manager, Millstone Unit No. 3 g
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Docket No. 50-423 B16581
                                                                                                                              ?
Attachment 1                                             -
Millstone Nuclear Power Station, Unit No. 3 NNECO's Commitments 1
l 4-November 1997 l
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U.S. Nuclear Regulatory Commission B16581%ttachment 1\Page 1 Enclosure List of Regulatory Commitments The following table identifies those actions committed to by NNECO in this document. Please notify the Manager - Regulatory Compliance at the Millstone Nuclear Power Station Unit No. 3 of any questions regarding this document or any associated regulatory commitments.
Committed Date or Commitment                               Outage NONE                                    N/A

                  .                                                   Docket No. 50-423     -
B16581 i
Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Facility Operating License No. NPF-49 October 1997 Monthly Operatina Report 1
November 1997 a'
l.

U.S. Nuclear Regulatory Commission B16581Wtachment 2Page 1 REFUELING INFORMATION REQUEST October 1997
: 1. Name of the facility:        Millstcne Unit 3                                _
: 2. - Scheduled date for next refueling outage: To be determined
: 3. Scheduled date for restart following refueling: To be determined
: 4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
NHL
: 5. Scheduled date(s) for submitting licensing action and supporting information:
None.
: 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
Ncne.
: 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
In Core: (a)        193             In Spent Fuel Pool: (b) ilf
: 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
Present storace caoacity: 756.
No increase reauested.
: 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
End of Cvele 7.

U.S. Nuclear Regulatory Commission B16581%ttachment 2Page 2 DOCKET NO.:        -50423
* UNIT:         Mille.one Unit 3 '
DATE:          11/1/97 COMPLETED BY:            K. W. Emmons TELEPHONE:          (860)447-1791 Ext. 6572 -           ,
                                                                                                                                    }
MONTH: Oct-97 DAY            AVO. DAILY POWER LEVEL                         DAY       AVG. DAIL'' POWER LEVEL (MWe-Net)                                                (MWe-Net) 1                         0                                    17                   0 2                         0                                    18                   0 3                          0                                   i.9                  0 4                          0                                  20                    0 5                          0                                  21                    0 6                          0                                   22                   0 7                          0                                   23                   0                      .>
8                         0                                   24                   0 9                          0                                   25                   0 10                         0                                   26                   0 11                         0                                    27                  0 12                         0                                    28                  0 13                         0                                    29                  0 14                         0                                    30                  0 15                         0                                   31                   0 16-                        0 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
I w i - i          .-                         ..

U.S. Nuclear Regulatory Commission B16581%ttaement 2Page 3 UNIT NAME: Millstone Unit 3
                                           .                                                                                                                                        DATE: 11/01/97.
                                 .-                                                                                                                                      COMPLETED BY:      K. W. Emmons TELEPHONE: (860)447 1791 Ext 6572 OPERATING STATUS
: 1. Docitet Number                                                                                                        50-423 2.' Reporting Period                                                                                                     Oct.97                       Notes:
: 3. Utility Contact                                                                                                       K. W. Emmons
: 4. Uconced Thermal Power (MWt):                                                                                       3411
: 5. Nameplate Rating (Gross MWe):                                                                                           1253
: 6. Design Electrical Rating (Ne' MWe):                                                                                      1153.6
: 7. Maximum Dependable Capacity (Gross MWe):                                                                                 1184.20
: 8. Maximum Dependable Capacity (Net MWe):                                                                                   1137.00
: 9. If Changes Occur in Ccpacity Ratings (items Number 4 Through 8) Since Lsst Report, Give Reasc,ns:
N/A
: 10. Power Level To WNch Hestricted, if any (Nat MWe):                                                                              0
: 11. Reasons For Restrictions, if Any:                              NRC Category til Facility: NRC Confirmatory Order requiring implementation of an ndependent corrective action verification program; NRC Order requiring a third-party review of the employee concerns program at Millstone Station; design basis verification response pursuant to 10CFR50.54(fl.
This Month        Yr.-To-Date        Cumulative
: 12. H6urs in Reporting Period                                                                                                               745.0            7296.0          101040.0 13 Number Of Hours Reactor Was Critical                                                                                                       0.0                0.0           67080.1
: 14. Reactor Reserve Shutdown Hours                                                                                                            0.0                0.0            6525.8
: 15. Hours Generstor On-Line                                                                                                                   0.0                0.0           65912.4
: 16. Unit Reserve Shutdown Hours                                                                                                               0.0                0.0                0.0
: 17. Gross Thermal Energy Generated (MWil)                                                                                                     0.0                0.0     216937728.1
: 18. Grnas Electrical Energy Generated (MWH1                                                                                                   0.0                0.0      74905103.1
: 19. Net Electrical Energy Generated (MWH)                                                                                                 -4661.5          -48809.0        71:'47910.5
: 20. Unit Service Factor                                                                                                                       0.0                0.0               65.2
: 21. Unit Availability Factor                                                                                                                  0.0                0.0               65.2
: 22. Unit Capacity Factor (Using MDC Net)                                                                                                      0.0                0.0               61.9
: 23. Unit Capacity Factor (Using DER Net)                                                                                                      0.0                0.0               61.1
: 24. Unit Forced Outage Rate                                                                                                                 100.0              100.0               26.9
: 25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Shutdown ht time of this report.
: 26. If Unit Shutdown At End Of Report Feriod, Estimated Date of Startup:                                                                          To be determined.
: 27. Units in Test Status (Prior to Commercial Operatior.):
Forecast -         Achieved INITIAL CRITICAUTY                                                                      N/A                N/A
 .                                                                                         INITIAt. ELECTRICITY                                                                    N/A                N/A COMMERCIAL OPERATION                                                                    N.'A               N/A t            .        .

                                          ' u.s. Nucieer Reguistory Commission B16581%ttachment 2Page 4 UNIT SHUTDOWNS AND POWER REDUCTIONS
                                                                                                                                                                                                                                              *[
e 1
DOCKET NO.:                50423 UNIT NAME:                Batmanna that 3 DATE:                1141-97                                            .
COMPLETED BY:                  K. W. Emmons                                        !
TELEPHONE:                 13001447-1721 X8572                               4 FCPORT MONTH = October 1997 No.         Date    . Type'         Duration              Reason
* Method of           Ucense          System :     Component              Cause & C..-c; (Hours) .                          Shuttmg             Event           Code'        Code'                         Accon to                                              .,
Down Reactor'       Report #                                            Prevent Recurrence 96-01 03-30-96             F           745.                  B/D           4               96-006-00           BA               ISV      Valves inoperatde due to onomet desen deficeneses, in that c,i                                       [
!                                                                                                                                                                                    smproper valvs dessen did not                                        ;
meet GDC 57. Corrective accon                                        -
is to instar vendor kit to moddy valve disk to meet GDC 57.
Conenued shutdown:NRC                                                l Category le facility; NRC -
* Corwirmetury Order regumne
!                                                                                                                                                                                    independent correcove accon                                          ,
i venhcanon: NRC Order regumns third 14rty review of Mdistone                                       i Stocon employee concoms
,                                                                                                                                                                                    program; deogn beeis venficsson for response to NRC pursuant to                                      ,
10CFM50.54(fl.
                                             'F: Forced                  Reason                                                   ' Method                                        'IEEE Standard 805-1984, S: Scheduled                A - Equipment Failure (Explain)                            1 - Manuel
* Recommended Pracaces                                              t
,                                                                         B - Mstenance or Test                                      2 - Manuel Scram                                 for System idoneficecon in
<                                                                         C - Re.Neling                                              3 - Automatic Scam                               Nucteer Power Plants and D - Regulatory Restriction                                 4 - Continued from Previous Month                Related FacArtees*
E - Operator Training & Ucense Examination                 5 - Power Reduction (Duration = 0)
F- Administrative                                          6 - Other (Explain)                          "IEEE Standard 903A-1983, G - Operational Error (Explain)                                                                             *Recommendec8 Practices                                             i H - Ot'w (Explain)                                                                                          for Uneque edentificacon in Pbwer Plents and Reis*.ad Facitsies - Component
!                                                                                                                                                                                     Funecen _ ., .
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