View source for B16518, Monthly Operating Rept for May 1997 for Millstone Nuclear Power Station,Unit 3

{{Adams
| number = ML20141A566
| issue date = 05/31/1997
| title = Monthly Operating Rept for May 1997 for Millstone Nuclear Power Station,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 = B16518, NUDOCS 9706230091
| document type = MONTHLY OPERATING ANALYSIS REPORT, TEXT-SAFETY REPORT
| page count = 8
}}

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    -                                                                                 Roge Fury Rd. (Route Wih Watnfont, G W2385 8} Norihcast p Nuclear Energy                                                          susi,me weiear n,wer station Mrtheast % clear Energy Company l                                                                                     P.O. Ilos 128 l                                                                                     Waterford, CT 06385-0128                       I 1
i (860) 447-1791 Fax (860) 444-4277 The %rtheast Utilitin System                   j JUN I 219W Docket No. 50-423                 j B16518 l
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             ' US Nuclear Regulatory Commission                                                                                      .
Attention: Document Control Desk                                                                                       l Washington, D C. 20555 Millstone Nuclear Power Station Unit 3 Facility Operating License Num' oar NPF-49 Monthly Operatina Report for May 1997 l              In accordance with the reporting requirements of Technical Specification 6.9.1.5 i              for Millstone UnR No. 3, enclosed in Attachment 2 is the Monthly Operating                                            l Report for the month of May,1997.                                                                                     I l
l              Should you have any questions regarding this submittal, please contact Mr.
!              David Smith at (860) 437-5840.
I Very truly yours, f
NORTHEAST NUCLEAR ENERGY COMPANY
                                                                                                                        /
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!                                                                                     N
                                                                                          ~
                                                      . Hicks Unit Director - Millstone Unit 3 l              Attachments (2) cc:     H. J. Miller, Region 1 Administator W. D. Travers, Dr., Director Special Projecta A.C. Cerne, Senior Resident inspector, Millstone Unit No. 3 i
J. W. Andersen, NRC Project Manag. , Millstone Unit No. 3
    ^AD0RO                        ""
9706230091 970531
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f                                                                        Docket No. 50-423 B16518 l
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l                                                                                                       i Attachment 1 1
Millstone Nuclear Power Station, Unit No. 3 NNECO's Commitments June 1997 l

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          .                                                                                          i U.S. Nucl=r Regul:: tory Commission B16518%ttachmerit 1\Page 1
;                                                     Enclosure List of Regulatory Commitments The following table identifies those actions committed to by NNECO in this 4
document. Please notify the Manager - Nuclear Licensing at the Millstone Nuclear Power Station Unit No. 3 of any questions regarding this document or           !
;             any associated regulatory commitments.
Commitment                             Committed Date or Outage               I d
NONE                                   N/A i
1 W
t i                                                                                                    ;
                                                                                                     \
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4 Docket No. 50-423                     '
l B16518 1
l Attachment 2 Millstone Nuclear Power Station, Unit No. 3 Facility Operating License No. NPF-49                                                                        ;
May 1997 Monthly Operatina Report 1
l l
June 1997

U.S. Nucirr R gulttory Commission B16518\ Attachment 2\Page 1 REFUELING INFORMATION REQUEST May1997
: 1. Name of the facility:         Millstone Unit 3 l             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?
1 l             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:
None, i
: 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) _416 l
: 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 t
number of fuel assemblies:
;                  Present storaae caoacitv: 756.
No increase reauested.
: 9. The projected date of the last refueling that can be discharged to the spent i
fuel pool assuming present license capacity:
l                         End of Cvele 7.
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U.S. Nucle r Regulatory Commission B16518\ Attachment 2\Page 2 DOCKET NO. 50-423                             i UNIT Millstone Unit 3 DATE 06/03/97 COMPLETED BY K. W. Emmons TELEPHONE (860)447-1791 Ext. 6572 MONTH:      May-97 DAY      AVG. DAILY POWER LEVEL                              DAY   AVG. DAILY POWER LEVEL (MWe-Net)                                                          (MWe-Net) 1                        0                                  17                                0                    >
2                        0                                  18                                0 3                        0                                  19                                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                    r 15                        0                                  31                                 0                   i 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.                                                       l

l U.S. NuCirr Regul: tory Commission B16518\ Attachment 2\Page 3 l                                                                                                              UNIT NAME Millstone Unit 3 DATE 06/03/97 COMPLETED BY K. W. Emmons TELEPHONE (860)447-1791 Ext 6572                  l OPERATING STATUS 1
l       1. Docket Number _                                              50423                                                                           l l      2. Reporting Period                                              May-97                            Notes:
: 3. Utility Contact                                               K. W. Emmons                                                                   '
(      4. Licensed Thermal Power (MWt):                                       3411
!      5. Nameplate Rating (Gross MWe):                                           1253                                                                 l
: 6. Design Electrical Rating (Not MWe):                                  1153.6                                                                  l
: 7. Maximum Dependable Capacity (Gross MWe):                           1184.20
: 8. Maximum Dependable Capacity (Not MWe):                             1137.00                                                                   I
: 9. If Changes Occur in Capacity Ratings (Items Number 4 Through 8) Since Last Report,                                                           l Give Reasons:
N/A
: 10. Power Level To Which Restricted, If any (Not MWe):                         0                                                               j
: 11. Reasons For Restrictions, if Any:           NRC Category lli Facility; NRC Confirmatory Order requiring                                    !
implementation of an indopendent corrective action verification program; NRC Order requiring a third-party review                              I of the employee concerns program at Millstone Station; design basis verification response pursuant to 10CFR50.54(f).
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This Menth         Yr.-To-Date            Cumulative            l
: 12. Hours in Reporting Period                                                          744.0                  3623.0'            97367.0 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 Generator On-Line                                                               0.0                    0.0             65912.4 -
: 16. Unit Reserve Shutdown Hours                                                           0.0                    0.0                       0.0
: 17. Gross Thermal Energy Generated (MWH)                                                  0.0                    0.0       216937728.1
: 18. Gross Electrical Energy Generated (MWH)                                               0.0                    0.0        74905103.1
: 19. Not Electrical Energy Generated (MWH)                                            -4864.1                -23899.6        71272819.9
: 20. Unit Service Factor                                                                    0.0                    0.0                    67.7
      ' 21. Unit Availability Factor                                                              0.0                    00                     67.7
: 22. Unit Capacity Factor (Using MDC Net)                                                  0.0                    0.0                    64.3
: 23. Unit Capacity Factor (Using DER Net)                                                  0.0                    0.0                    63.5
: 24. Unit Forced Outage Rate                                                            100.0                   100.0                    23.8
: 25. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Shutdown at time of this report.
: 26. If Unit Shutdown At End of Report Period Estimated Date of Startup:                          To be determined.
: 27. Units in Test Status (Prior to Commercial Operat;on):
Forecast               Achieved INITIAL CRITICALITY                                      N/A                  N/A INITIAL ELECTRICITY                                      N/A                  N/A COMMERCIAL OPERATION                                     N/A                  N/A l
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U.S. Nucl:ar Regulatory Commission                                                                                                                                                                                                                                                                                                                                                        .
816518%ttachment 2\Page 4                                                                                                                                                                                                                                                                                                                                                                       .
UNIT SHUTDOWNS AND POWER REDUCTIONS I
DOCKET NO. 50-423 UNIT NAM 5       Millstone Unit 3 DATE                                   06-03-97 COMPLETED BY         K. W. Emmges                                                    .
TELEPHONE (860) 447-1791 X 6572 i
REPORT MONTH: May 1997 No.        Date Type'                                          Duration Reason:                                    Method of                                                License            System                                                                                 Component            Cause & Corrective                                                                         -
(Hours)                                             Shutting                                                 Event             Code'                                                                                   Code'                     Action to Down Reactor
* Report #                                                                                                                       Prevent Recurrence 96-01 03-30-96    F                                              744      8/D                                                       4                                       96-006-00                     BA                                                                                  ISV     Valves inoperable due to original design deficiencies, in that an improper valve design did not meet GDC 57. Corrective action is to install vendor kit to modify                                                        ,
i                                                                                                                                                                                                                                                                                                                        valve disk to meet GDC 57.                                                                        !
Continued shutdown: NRC Category 111 facility; NRC Confirmatory Order requiring independent corrective action venfication:
NRC Order requmng third-party review of Millstone Station employee concems program; design basis verification for response to NRC pursuant to                                                                       ,
10CFR50.54(f).
;                   'F: Forced
* Reason
* Method                                                                                                                     lEEE Standard 805-1984,                                                                            !
A - Equipment Failure (Explain)                                                                                                                1 - Manual
* Recommended Practices S: Scheduled B - Maintenance or Test                                                                                                                       2 - Manual Scram                                                                                                            for System Identification in C - Refueling                                                                                                                                 3 - Automatic Scram                                                                                                         Nuclear Power Plants and                                                                          .
D - Regulatory Restriction                                                                                                                    4 - Continued from Previous Month                                                                                           Related Facilities" E - Operator Training & License Examination                                                                                                   5 - Power Reduction (Duration = 0)                                                                                                                                                                                            ;
                                                                                                                                                                                                                                                                                                                      'IEEE Standard 803A-1983, F - Administrative                                                                                                                            6 - Other (Explain)
G - Operational Error (Explain)                                                                                                                                                                                                                                            " Recommended Practices H - Other (Explain)                                                                                                                                                                                                                                                       for Unique identification in Power Plants and Related                                                                          1 Facilities - Component Function identifiers"                                                                              ;
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