ML19242D082

Monthly Operating Rept for Jul 1979

ML19242D082
Person / Time
Site:	Rancho Seco
Issue date:	07/31/1979
From:	Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML19242D075	List: ML19242D074 ML19242D082
References
NUDOCS 7908140482
Download: ML19242D082 (7)

Text

AVERAGE DAILY U.% T POhEll LEVEL DOCKET NO. -

50-112 IlNIT Rancho Seco l' t 1 79-06-30 DATE COMPLETE D BY

.R. ti. Colorbo TELEPl!ONE (916) 452-3211 MONTil Y

DAY AVER AGE D $.lLY P0hER LEVEL DAY AVERAGE D \\lLY FOuER LEVEL (SDVe Net) tMive Net) r 1

0 g7 861 2

862 I8 3

0 19 859 4

0 20 727 5

88 21 0

'6.

532 22 0

7 819 467 23 8

866 24 852 867 9

7 860 10 867 26 866 II 867 27 868 12 620 865 28 13 613 29 869 715 14 30 856 857 15 31 856 16 860 INSlRL'CTIONS om as e u. n,, e e s,,y u xc:, r.,_ i,,,n, snvc.N,, rc, c,,,m, m n,,,,,,,,,,,,, g, c,,,_.,,,

s Ihe nen, e..ie n:egns, "

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OPERATING DATA REPORT DOCKET NO. 5_0-312 I) ATE 79-07-31 COMPLETED 11Y R. Is'. Colombo

'I ELEPilONE 916-452-3211 OPER ATING ST A T US

1. Unit Name:

Rancho Seco Unit Notes Shut down July 20 for July 1979

2. Reporting Period:

approximately 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> to 2772

3. Licensed Thermal Power t\\1hii:

modify several pipe supports 963

4. Namet>! ate Ratinc iGross MWe r to the criteria in I&E

5. Design Electrical Rr. tin;(Net MWe):

0I8 Bulletin 79-02.

6. 'Slatimum Dependab!c C.,pacity iGross MWel:

O'7

7. 51aximum Dependable Capacity (Net MWe):

873

8. If Changes Occur it' Capacity Rat;ngs (Items Number 3 Through 7) Since last Report. Gise Reasons:

N/A

9. Power Lesel To Wh::h Restricted. If Any (Net MWel:

N/A

10. Reasans For Restricti<,n3. If Any:

N/A This..lonth Yr. to-Date Cumulatise 744 5087 37584

11. Ilours In Reporting Period

12. Number Of !!"urs Reacter was Critical 601.o 3199.4 99470.9

13. Reactor Resene Shutdown liours 0

1519.2 39',5.6

14. Ilours Generator on-Line 573.8 3277.5

15. Unit Rewne Shutdoun flours 13.8 1109.3 ~

21440.7 1210.2 1,546,232 8,961,925 54,035,081

16. Gross Thermal Energv Generated t \\ lull)

17. Goss L!cctrical Enern (,ener:ned i'.th11, 480,799_ _,_

2,932,120 18.194,920 IE. Net E!ectrical Energ) GenerateJ (Mu ll; 450,527 2,780,155 17,179,045

19. Unit Senice Fceior 77.1 64.4 57.0

20. Unit Auibbib:y I utor 79.0 88.0 60.3

21. Unit Capacity Factor (Using \\lDC Neti 69.4 62.6 52.4

22. Unit Capasity Factor tUwag DE't Net, 66.0 59.5 49.8

23. Unit Fereed Ontas 1: ate 21.4 7.1 35 1

24. Shutdowns Scheduled Oser Nest 6 Months iTy pe. Date, and Duration of Eachl-.

None

25. If Shut Down At I nd 01 Report PerioJ. E timated Date of Startup-N/A

26. Units in lest Status t Pnor to Commercial Opr.itioni Forecast Achiesed

/A

,N/A INil l1L CP.lTIC \\l l f Y INill AI. E LI C I RICI T Y N/A N/A COililLI Clit. 011 R 1110N N/A

-N/A cogO 10/77)

50-312 UNIT SilUTDOWNS AND POWER REDUCTIONS DOCNET NO. _ UNI T N A'.!E Rj n c h o % en I'n i t 1 DA!E Z.9.-R7:31 itEPORT MONTI: July COMPEE II D 11Y R-W- Col # 3 ggg.;,DONE (91M 452-3211 CJ l r 't [? 3 kY Licensee Eg h., Cause d Corr:ctise No. 13.s t e g 3g ( .3 :l 5 Event yg g3 Actio i to fE y ,f; f = Report a mU 5 Prevent Ret urrence 2, ~, V c o s 6 w.

=

7 79-07-01 S 13.8 F 1 N/A N/A N/A Continuation of last month's " Prerequisite testing of AFW and plant heatup in preparation for I startup." 8 /9-07-01 F 97.6 B 3 N/A N/A N/A Rx trip due to high precsure resultin* from STP-070 TAux. Feedwater Flow Test). Repaired weld on Aux. System Line and performed other maintenance. 9 79-07-12 F 5.0 A 3 N/A N/A N/A Rx trip due to pressure transmitter malfunction which was equated to turbine overspeed. 10 79-07-20 F 53.8 F 1 79-007/01-T-0 CF SUPORT Pipe supports having safety factor of <2 according to I.E. Bulletin 79-02 analysis. I 2 3 4 F: Forced Rer,on : Method : Ex!ubit G -Instructions S: Sched uled A i:quipment Failure (Explain) 1-Manual for Preraration of Data B-M.iinten.ince or Test 2 M.mual Scram. Entry Sheets for Licemec C ItefueEng 3-Automatic Scram. Event Report (l.i R) Eile (NUREC-D-Regulatory :kstriction 4-Other (Explain) 0161)

1. Opentor Trammg1 License Examination F Adnune,t rante 5

G-Operation.n 1:iror (Explain) Exhibit 1 Same Source (9/77) Il Other (Explain)

NA~t'1ATIVE St' OL\\RY OF PLANT OPE'tATIO"S DATE 7/1/79 (0000) Reactor at 15% Full Power (0855) Lowered reactor to 13% power (1348) Reactor tripped (high pressure) 7/4/79 (1030) Reactor in heatup mode 7/5/79 (0730) Reactor critical (0750) Reactor at 2.5% power (1239) Completed STP-070, " Aux. Feedwater Flow Test" (1500) Reactor at 15% FP (1525) Generator en line (closed OCB's) (2340) Reactor at 50% power increasing to 70% (420 'Ble) 7/6/79 (1126) Reactor at 70% power, commenced 5-hour hold (1600) Increasing to 92% power 7/7/79 (1738) Started increasing to 100% power (1946) Unit at 100% 7/8/79 (0530) Completed Auxiliary Feedwater Pump P-319 portion of STP-071, Auxiliary Feedwater Endurance Test 7/10/79 (1235) Completed Auxiliary Feedwater Pump P-318 portion of SIP-071, Auxiliary Feedwater Endurance Test 7/12/79 (1717) Reactor trip on turbine-generator trip I ') I (1909) Reactor critical (2216) Generator en line (Closed OCB's)

DATE Page 2 7/13/79 (24C3) Reactor at 327 pover (0115) Started increasing reactor to 50% power (0255) Reactor at 50% (0712) Increasing reactor to 92? power (1230) Reactor at 90%, commenced 2-hour hold (1510) Started increasinc, to 100% power (2115) Reactor at 1007 power 7/14/79 (1740) Overspeed Protection Control f ailed. All intercept valves closed. Lowered reactor power to 3 0 ';. Took manual control of turbine (2205) Increasing to 927 power 7/15/79 (0000) Reactor at 87% commenced 2-hour hold (0159) Reactor at 100% power 7/20/79 (1615) Started reactor pewer decrease at 1 Mh'/ minute (2210) Transferred au>:. trans. loads to SU transformers (2245) Opened OCB's 220/230 (2247) Pushed Turbine trip button (2320) Reactor in HSD 7/23/79 (0117) Reactor critical (0431) Generator en line (closed OCB's) (0542) Reactor at 500 power g 7 '/' \\- ,o(, (0650) Started increasing to 72* power (1510) Started increasing to 92% power

DATE Page 3 7/23/79 (Continued) (1805) Reactor at 87% power commenced 2-hour hold (2107) Reactor at 100% power PERSOLEL CHANGE.ilEQElHING_.PIECRII'iE_ No personnel changes that rer;uire reporting in accordance with Technical Specifications Figure 6.9-2 were made in July, 1979. MAJOR _ LIE'dS OF SAFETY-RELATEIllAL:iIE'M 1CF. m 1) Conducted inspection test of all pipe support anchors in Class 1 systems. Made modifications to those anchors that did not meet the new criteria covered in Bulletin 79-02.

Reference:

LER 79-07. 2) Replaced "B" Decay Heat Pump (P-2615) outboard seal.

Reference:

LER 79-08. SDDIARY OF CHA':CES MADE IN ACCORDANCE 'JIT" 10 CFR 50.39(b) No changes, tests, or experiments were completed in July, 1979, which constituted a change in a safety analysis report description. f

11FUELI::C I::TOPSTIO:: REQEST Rancho Seco Unit 1 1. 2:are of Facf 3 f ty: February 1980 2. Scheduled date for next refueling shutdown: __ April 1980 ~3. Scheduled date for restart following refueling: 4: Technical Specification change or other license anendaent required: a) Change to nod Inde:'. vs. Power Level Curve (TS 3.5.2) b) Change to Core I balance vs. Pouer Level Curve (TS 3.5.2) c) Tilt Limits (TS 3'.5.2) ~ d) Safety Equipment Testing (TS 3.3.3) Decenber 1979 5. Scheduica date(s) for subaitting proposed licensing action: licensir.g considerations associated with ref ueling: None 6. Ieportant 7, 1:ucter e.f fuel assenblies: a) In the core: 177 b) In the Spent Fuel Pcol: 112* O. Present licensed spent fuel capacity: 579 9. frojected date of the last refueling that can be discharged to the Spent Fuel Pool: 3987

• Prev,ious reports of 122 were in error.

j7 7 i

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