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{{Adams
#REDIRECT [[PLA-1745, Monthly Operating Rept for June 1983]]
| number = ML20077H623
| issue date = 07/11/1983
| title = Monthly Operating Rept for June 1983
| author name = Kenyon B, Kuczynski L
| author affiliation = PENNSYLVANIA POWER & LIGHT CO.
| addressee name = Beebe M
| addressee affiliation = NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
| docket = 05000387
| license number =
| contact person =
| document report number = PLA-1745, NUDOCS 8308110143
| document type = MONTHLY OPERATING ANALYSIS REPORT, TEXT-SAFETY REPORT
| page count = 7
}}
 
=Text=
{{#Wiki_filter:o .
[                                   AVERAGE DAILY UNIT POWER LEVEL D                    I rf)          ....              3                                                          DOCKET NO.      50-387 Le                    ''                                                                              0"*
UNIT DATE duly 11, 1983
(+
g                                                                        COMPLETED BY d..A. Kuzcynski TELEPHONE 1 717)S42-2181 MONTH          Jun , 1983 DAY        AVERAGE DAILY POWER LEVEL                            DAY      AVERAGE DAILY POWER LEVEL (MWe-Net)                                                  (MWe-Net)
:                      1020                                g7                        638 2
1030 18 3                      1046                                39                        903 4                      1042                                20                      1017 5                      1044                                21                      1036 6                      1043                                                          1042 22 7                        987                                23                        1041
        *g                          1048 24 484 9                      1053                                25                            0 10                        1050                                26                            0 gg                        1045                                                              0 27 12 1041                                                              0 28 13                        1039                                29                            0 14                        4I4                                30                            0 15                          0                                3g 16                            0 INSTRUC110NS 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.
* Unit was declared commercial at 0001 on June 8,1983.
(9/77) l 8308110143 830711 l                    PDR ADOCK 05000 t                    R L
 
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OPERATING DATA REPORT l
0                                                        DOCKET NO.      50-387 O                  4s                                                                  DATE July 11, 1983 COMPLETED BY L.A. Kuczynski NfC SY                                                                      TELEPHONE (717)542-2181      ]
OPERATING STATUS Unit 1 Notes
: 1. Unit Name:        Su saueh anna Steam Electric Station
: 2. Reporting Period: June, 1983
* Unit was declared commercia:.
3293                                at 0001 on June 8, 1983
: 3. Licensed Thermal Fower (MWt):
1152
: 4. Nameplate Rating (Gross MWe):
: 5. Design Electrical Rating (Net MWe):      1065
: 6. Maximum Dependable Capacity (Gross MWe):
1072
: 7. Maximum Dependable Capacity (Net MWe).        1036
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7s Since Last Report. Give Reasons:
Items 6 and 7 will varv month-to-month until sufficient operating data has been gathered.
: 9. Power Level To Which Restricted if Any (Net MWe):        None
: 10. Reasons For Restrictions. If Any:      None This Month          Yr.-to-Date          Cumulative
: 11. Hours In Reporting Period                              552                  552                  552
: 12. Number Of Hours Reactor Was Critical                    351.6                351.6                351.6
: 13. Reactor Reserve Shutdown Haurs                          156.7              156.7                156.7
: 14. Hours Generator On-Line                                334.3                334,3                334.3
: 15. Unit Reserve Shutdown Hours                                0-                    0                    0
: 16. Gross Thermal Energy Gener ated (MWH) 1,050,000            1,050,000              1,050,000
: 17. Gross Electrical Energy Gencated (MWH)                341,760            341,760              341,760
: 18. Net Electrical Energy Generated (MWH)                329,910            329,910              329,910
: 19. Unit Service Factor                                      60.6                60.6                60.6
: 20. Unit Availability Factor                                  60.6                60.6                60.6
: 21. Unit Capacity Factor (Using MDC Net)                      57.7                57.7                57.7
: 22. Unit Capacity Factor (Using DER Net)                      56.1                  56.1                56.1
: 23. Unit Forced Outage Rate                                  39.4                39.4                39.4
: 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):
Unit 1/ Unit 2 Tie-in Outage to Commence November 7,1983.                          Scheduled to last 29 days.
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup:    3 July 1983
: 26. Units in Test Status (Prior to Commercial Operation):                      Forecast              Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (4/77 )
L
 
          $ $A Q                    '                                                                                                                                                        .
p      %                5
* UNIT SHUTDOWNS AND POWER REDUCTIONS                  DOCKET NO. 50-387                                                  '
kD E NIC S f[                                     REPORT MONTH June. 1983 UNIT NAME One COMPLETED BY DATE July 11. 1983 TELEPflONE (717)542-2181 L.A. Kuczynski
                                                          %    B                            E 50      "E    *Y3        Licensee    En        Eg                  Cause & Corrective No.            Date            h      j$        $    3g5          Event N        hV Action to H
                                          $=        5    j ;5 g      Repor #    mo        g                    Prevent Recurrence 8
12        061483              F        61      A        3          N/A      CC      VALVEX    Scram caused by a momentary three                                            '
times normal main steam line radiation level. High rad. level caused by an air slug  passed          through the core.
The air slug originated from a conden-sate demineralizer which had its vent line blocked by some gasket-type mater ial which prevented proper venting.
Investigation into action to prevent recurrence is still under investigation 13        062483              F    156.7        A        3    83-092/03L    EA      TRANSF    A startup transformer failed in ser-vice. This caused a reactor scram and main turbine trip on RPV high level.
Present replacement transformer will be replaced with transformer having automatic load tap changing.
I                              2                                                3                              4 F: Forced                    Reason:                                          Method:                          Exhibit G - Instructions S: Scheduled                  A-Equipment Failure (Explain)                    1-Manual                          for Preparation of Data B-Maintenance of Test                            2-Manual Scram.                  Entry Sheets for Licensee C-Refueling                                      3-Automatic Scram.                Event Report (LER) File (NUREG-D-Regulatory Restriction                        4-Other (Explain)                0161)
E-Operator Training & Ucense Examination F-Administrative                                                              5 G-Operational Error (Explain)                                                      Exhibit I - Same Source (9/77)                          Il-Other (Explain)
 
m SUSQUEHANNA STEAM ELECTRIC STATION Docket Number 50-387  Date July 11, 1983 Completed by L.A. Kuczynski Telephone (717)542-2181 Challenges to Main Steam Safety Relief Valves Five minutes after the scram on June 15, 1983, reactor pressure reached 1080 psig and safety relief valve "E" automatically opened to relieve the pressure.
It reseated properly.
Changes to the Offsite Dose Calculation Manual See attachment.
Major Changes to Radioactive Water Treatment Systems None.
e w - ____- -_.
 
l ATTACHMENT TO June, 1983, Monthly Operating Report Changes to the Offsite Dose Calculation Manual O
t 1
1
 
These revised pages were made effective on April 27, 1983 upon signature by the Manager-Nuclear Support.
Changes have been denoted by revision bars in the right margin. The reasons for the changes are as follows:
To reflect the current text of the applicable Technical Specifications where they are quoted (Pages 7, 8, 9, 14, 15, 16, 21, 25, 26, 30, 32, 34, 39a, 40, 48) .
t                To clarify the fact that dose rate calculations are performed monthly  ,
as well as "when necessary" (vent monitor alarm) (Page 3).
To include applicable 10CFR20 dose rate standards in the table of radiological effluent objectives and standards (Page 6) .
To clarify the fact that Table 3 meteorological data is for sample purposes only. For dose calculations for the Semi-annual Radio-active Effluent Release Report, actual meteorological data from the report period is used (Pages 17, 18, 19, 25, 27).
To change the dose parameters for radionuclides other than noble gases via the ground plane pathway. The former values, which were based on total body dose factors for standing on contaminated ground, were less conservative than the current values, which are based on skin dose from standing on contaminated ground (Page 20) .
To include the statement that, when calculating doses to gauge com-pliance with Specification 3.11.2.5, the ventilation exhaust treatment system operability specification, only doses from I-131, tritium, and particulates with half-lifes greater than eight days shall be included. This is because, by definition in Tech. Spec. Definition 1.47, the ventilation exhaust treatment system is not considered to have any effect on noble gas effluents (Page 34) .
To add Appendix D, which presents site specific values used in the LADTAP II code to calculate doses from liquid effluents (Pages D-1, ,
D-2, D-3).
9
 
PPaL( Pennsylvania Power & Light Company Two North Ninth Street
* Allentown, PA 18101 + 215 / 770-5151 i
Bruce D. Kenyon Vice President-Nuclear Operations                                                                    ,
215/770-7502 l
July 14, 1983 Director, Data Automation &                                '
Management Information Division Attention: Mr. M. R. Beebe Management Information Branch Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C.          20555 SUSPUEHANNA STEAM ELECTRIC STATION MONTHLY OPERATING REPORT - JUNE 1983 ER 100450                          FILE 841 PLA-1745                                                                          Docket No. 50-387
 
==Dear Mr. Beebe:==
 
The June 1983 monthly operating report for Susquehanna SES Unit 1 is attached.
The Unit was declared commercial at 0001 on June 8, 1983.
Very truly yours, s
B. D. Kenyca
[ Vice President-Nuclear Operations Attachment cc:  Dr. Thomas E. Murley                                            INPO Records Center Regional Administrator-Region I                                Suite 1500 U.S. Nuclear Regulatory Commission                              1100 Circle 75 Parkway 631 Park Avenue                                                Atlanta, Georgia 30339 King of Prussia, PA 19406 Director                                                        Mr. '.homas E. Pollog          I Office of Inspection and Enforcement                            Department of Environmental U.S. Nuclear Regulatory Commission                                              Resources Washington, D.C.          20555                                Bureau of Radiation Protection Attn      Document Control Desk (12 copies)                    P. O. Box 2063 Harrisburg, PA 17120 Mr. G. Rhoads - NRC Mr. R. Perch - NRC llg}}

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