ML20066D331

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Monthly Operating Rept for Sept 1982
ML20066D331
Person / Time
Site: Pilgrim
Issue date: 10/10/1982
From: Whitney G
BOSTON EDISON CO.
To:
Shared Package
ML20066D326 List:
References
NUDOCS 8211110286
Download: ML20066D331 (6)
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OPERATING DATA REPORT ,

50-293 DOCKET NO.

DATE 10/10/s4 COMPLETED BY G.G. Whitney TELEPHONE 617-746-7900 OPERATING STATUS Pilgrim 1 Notes

1. Unit Name: ,
2. Reporti'ng Period: September, 1982
3. Licensed Thermal Power (MWt): 1998.
4. Nameplate Rating (Gross MWe): 678.
5. Design Electrical Rating (Net MWe): 655. ,
6. Maximum Dependable Capacity (Gross MWe): 690.
7. Maximum Dependable Capacity (Net MWe): 670.
8. If Changes Occur in Capacity Ratings (Items Number-3 Through 7) Since Last Report. Give Reasons:

None

9. Power Level To Which Restricted,If Any (Ne't MWe None.
10. Reasons For Restrictions. If Any:

h/A This Month Yr. tc-Date Cumulative

11. Hours In Reporting Period 720.0 6551.0' 85991.0
        '12. Number Of Hours Reactor Was Critical-            _ _ 689.8                        4143.4           60176.7
13. React, r Reserve Shutdown Hours .

0.0 0.0 0.0

14. Hours Generator On-Line 676.7 3885.5 3610.s.*
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0 i
16. Gross Thermal Energy Generated (MWH) 1011264.U 6715848.0 99533736.0 .

l

17. Gross Electrical Energy' Generated (MWH) 342100.0 _, 2311130.0 33222364.0 l

! 18. Net Electrical Energy Generated (MWH) 329509.0 2224716.0 31919200.0

19. Unit Service Factor 94.0 59.3 67.6
20. Unit Availability Factor 94.0 59.3 67.6
21. Unit Capacity Factor (Using MDC Net) 68.3 50.7 55.4 l
22. Unit Capacity Factor (Using DER Net) 69.9 51.8 56.7

}

23. Unit Forced Outage Rate 6.0 7.9 9.9 l ,
24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):

i Maintenance outage to commence October 9, 1964 Unit Operating l 25. If Shut Down At End Of Report Period. Estimated Date of Startup: l

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION I

8211110286 821012 I PDR ADOCK 05000293 i R PDR (9/77') I

TMA%7W/8thdr@CLC LLLW16 50-293 DOCKET NO. I UNI't. Pilgrim 1 DATE 10/10/82 

                                                                                  '                                                                 'U*           "*7 COMPLETED BY 617-746-7900
                                    -                                                                                            TELEPHONE SEPTEMBER, 1982 MONTH
                                                                                                                                                                     ~

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) g

25. 491.

2 16. gg' 488. 3 19 4 488. 20 489. 

         .                      .         491.                                                                                  488.
         >                                                                                   21 6

492. ., .490. 

        -                                 481.                                               23 509.

492. 

                                                                                                ~

496. S 24 496. 3, 490. . 9 10 496. 26 451. g3 496. ,. 489. 12 493. ,3 491. g3 493. 29 490. 494. 479. ! 496. , N/A 15 21 16 504. j INST?tUCTIONS - t l On this format.!ist the. average dsHy unit powe. levelin MWe-Net for each day in the reponing month. Compute to the nearest whole megswatt. i I 

                                  -                                                                                                                        (0/77 )

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4 , UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-293 UNIT NAME -m grim i DATE 10/10/82 COMPLETED ay G.G. Whitney REPORT 4f 0NTil . SEPTEMBER, 1982 617-746-7900 TELEPIIONE 3 c - Ihle 

                                                                                                                                   ;,      .!'E        3   3.ys&  3 Licensee         ['t,      E*                    Cause & Corrective No.                                                                 g-      Eg           s                  Event         g                                                             -

P 

                                                                                                                                           $E           5  jigg         Repint #        to O       8.']t                      Action to Prevent Recurrence 6

27 82/09/01 F 43.3 A 3 N/A HC HTEXCH Scram due to low vacuum in Main 

                                                                                                                                                                                    -                       Condenser during backwash.

28 82/09/03 F 0.0 A 5 82-036/03L CD VAI. VEX MSIV 'D' line shut. Suspect stem broken. October outage set to de-termine cause and make repair. i l 4 1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions - S: Scheduled A Equipment Failur.c(Explain) I-Manual for Preparation of Data D Maintenance of Test 2-Manual Scram. Entry Shecis for 1.icensee C-Refu-ling 3-Automatic Scram. - Event ReporI(LER) File (NUREG , 

                                                                                                                       ,          D Regulatory Restriction                              4-Osher (Explain)                 0161)

E-Operator Training & License Examinailun F Administrative 5 G.Operailonal Error (Explain) Exhibis 1 - Same Source 

 .                                              (9/77)                                                                            Il Other (Explain) l

e REFUELING INFORILATION p 

          . The following refueling information is included in the Monthly Rep' ort as requested in a letter to Mr. G. C. Andognini dated January 18, 1978:

For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request.

1. The name of this facility is Pilgrim Nuclear Power Station, Docket Numb ~er 50-293.
2. Scheduled date for next Refueling Shutdown: Sep tember, 1983, ,. l .
3. Scheduled date for restart following refueling: November, 1983 .
4. -

, . 5. Due to their similarity, requests 4, 5, & 6 are responded to

collectively:
6. The fuel, which had been loaded during the 1981 scheduled refueling outage, is of the same P8x_8R, design,, as loaded the previous outage con-sisting of 112 P8DRB282 assemblies and 60 P8DRB265 as'semblies.
7. (a) There are 580 fuel assemblies in the core. ~

(b) There are 936 fuel assemblies'in th'e speSt fuel pool.

8. (a) The station is presently licensed to store 2320 spent fuel assemblies.

The actual spent fuel storage capacity is 1770 fuel assemblies at present. (b) The planned spent fuel storage capacity is 2320 fuel assemblies.

9. With present spent fuel in storage, the spent fuel pool now has the dapacity to accommodate an additional 834 fuel assemblies.

O O e 

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f w. .. . HAJOR SAFETY RELATED HAINTENANCE MONTil SEPTEMBER, 1982 

    ,                                           i                                                                                 .

J CORRECTIVE ACTION SYSTEM COMPONENT MALFUNCTION _ . CAUSE ,HAINTENANCE l TO PREVENT RECURRENCE ASSOCIATED LER HPCI HPCI R02301-60 N/A Design Change Moved from outlet Design change to rectify pres- LER 82-035/ . Flow Orifice side of E-202 to'. sure spike forces on condenser 03L-0 inlet side. gasket. IIPCI IIPCI E-202 b1cwn gasket high pressure Replaced gasket Moved R0 2301-60 and changed LER 82-035/ gasket material. 03L-0 llVAC A0-N 92 broken drive linkage adjust- Ins, tall neti drive Increased. surveillance frequency gear ment gear, until results justify a return Not issued as to original schedule, of this date. IIVAC A0-N 90 and cracked drive linkage adjust- Install new drive See above. A0-N 92 N/A gear. ment. gear. . I RCIC 'MO-1301-25 lost remote stuck contacts ' cleaned contacts. Isolated event (last occurred Not issued as RCIC suction operation on controller in 1976) of this date. valve i. - a llPCI MO-2301-35 Motor burned not determined Rewind motor Isolated event (last occurred Not issued as 11PCI suction out. as yet. in 1972) UO #72-4 of this date from torus Reacti- - 

                                                                                                                                                 ~ ~       ~ ~~ ~~

C ol CRD Accumu- Pressure Loss N2 Leak Insert rod and Repair Leak ~ N/A~ ~ ~ lator electrical disarm l

r--- . 3 

      ,'       .                                                            BOSTON EDISON COMPANY                                                                                                    ,
                                                                      .PILCRIM NUCLEAR POWER STATION

[ Summary of Operations for SEPTEMBER, 1982 l On 9/1/82, at 0159, a scram occurred due to low condenser vacuum during a backwash. Also during this period, a design change and repairs to HPCI were completed. Reactor was made critical at 0622. Continued' reactor power increase to 80%, where power was held for repairs to "A" RFP inboard seal.- On 9/3/82 the "A".RFP seal was replaced and the pump returne'd to service , "D" Main Steam Line' isolated causing power to be res-tricted to 75%. On 9/7/82, power was. reduced for one hour when travelling screens became fouled with seaweed.during rough seas. "B" seawater pump was secured in order to get screens moving. Power was. returned to 75% when screens were cleaned. Power remained at 75% until 9/15/82 when, during an attempt to increase power in accordance with Safety Evaluation #1470, turbine control became unstable at , 79% power ; power was reduced to 77%. Pressure swings at 77%. power on 9/16/82. caused power to be reduced to 75%, but when swings were still evident, power was reduced to 74% and pressure remained steady. IPR swing kept power at 75% until 9/22/82 when power was increased to 78%. Reactor power was reduced to 50% on 9/23/82 to perform required surveillances. Power was then returned to highest obtainable without incurring control valve , oscillations. Reactor power was reduced to 50% on 9/25/82 to backwash and heat treat main condenser. Power was returned to 75% until 9/30/82 when power was dropped to 50% to insert control rod 22-51 and its three symmetrical rods, due t an accumulator N2'leali, thshn ~r} turned to 75% power. SAFETY / RELIEF VALVE CHALLENGES FOR THE MONTH OF SEPTEMBER, 1982 Requirement: TM1 T.A.P. II.K.3.3 

                                                         , There were no challenges to the Safety / Relief Valves                                                  ,

durihg this mohth. 1 c l k f 1 i l 

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