ML19225A167
| ML19225A167 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/30/1979 |
| From: | Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19225A166 | List: |
| References | |
| MOR-790630, NUDOCS 7907180508 | |
| Download: ML19225A167 (5) | |
Text
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AVEhAGE DAILY UNIT T0hlR LEVEL DOCKET NO.
50-312 Rancho Seco Unit 1 g.lT DATE 79-06-30 COMPLETED BY -
coln-kn TELEP110NE (916) 452-3211 MONT!!
J ine 1979 DAY AVER AGE D \\lLY P0hER LEVEL DAY AVERAGE DAILY P0bER LEVEL (MWe Net)
(MWe Net) 1 0
37 0
0 2
gg o
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
0 7
23 0
0 g
2-1 0
9 0
25 0
10 0
26 0
0 11 27
'O 12 0
2S 0
0' 0
13 39 14 0
30 0
15 0
3; 16 0
INSTRUCTIONS Oa this fer:nat,hst the asco;e J:ih unit p m er I:.ef in Mv/c Net for och day m the reportm' month. Compute to the neare.t whe:: n:-:put:
c (9/77 )
~
7907180 EOk /(
OPERATING DAh'A REPORT DOCKET NO.
50-312 DATE 7 9-(M-3f)
COSIPLETED ItY - R.
b' Colombo TELEPilONE (910) ~a2-3211 OPERAllNG ST \\Tl'S No'es USNRC Order
- 1. Unit Name:
Rancho Soco I. i t 1 n
Mo. 7590-01 rescinded June 1979
- 2. Reporting Penod:
27, 1979
- 3. Licen ed T hennal Power IMh t p:
0 63
- 4. Nameplate Ratin tGrms \\lhel:
918
- 5. Design Licctrical R : ting (Net MWe):
917
- 6. Maximum Depeadabic Cap.icity (Grow 51We):
- 7. htaximum Dependable Capacity INet MWe):
873
- 8. If Changes Occu in Capacity Ratines IItems Number 3 Through 7) Since Last Report. Gise Reasons:
USNRC Order No. 7590-01 rescinded June 27, 1979
- 9. Power Lesel To hhich Restricted. If Any (Net MWe):
0 (until 6-27-79)
- 10. Reasons for Restrictions. lf Any:
USNRC Order No. 7590-01 This Month Yr to-Date Cumulatis e 720 4,343 36,840
- 11. Ilours In Rerortmg Pen. d o
2.4 2,797.5 21.868.3
- 12. Numter Of flours Reactor was Critical
.6
- 13. Reactor Resene Shutdown liours 1,319.2 3,936.6
- 14. Ilour> Gencrator On-L iae 0
2,703.7 20,866.9
- 15. Unit I!cscne Shutdown 11 urs 720 1.185.5 1,196.4
- 16. Gross Therma! Ener;y Generated IMFil, 0
7.415.643
_.5 2J 8 9. P ', o
- 17. Gross Electrical Eneigy Generated iMhlil O
2.451.321 _
17.714.!21
- 18. Net Flectric.:! E::ersy Generated (MWil) 0 2,329,628 16,728,518
- 19. Unit Senice f actor 0
62.2 56.6
- 20. Ui.it.\\sailabi!it3 raetor 100.00 89.5 59.9
- 21. Unit Ca;ucity Factor (Using MDC Net) 0 61.4 52.0
- 22. Unit Cap city Factor iUsing DEit Net) 0 58.5 49.5
- 23. Unit forced Oauge Rate 0
3.4 35.4
- 24. Shutdowns Schedoled Oser Lxt 6 Months tT> re. Date,and Duration of Each):
None
- 25. If Shut Down \\t En.1 Of Report Period. Estimated Date of Startup:
Julv 5.
1979
- 26. Units in Test Status tPrior to Com.aercial O.eration):
Forecast AchieseJ i
INin\\L CRlllC \\LITY N/A sN/A h
INITI \\L FLECll lCITY N/A N/A COMMERCI \\l. Ol'1 R \\110N N/A N/A P1/77)
s UNIT S!!UTDOWNS AND POWER REDUCI!ONS DOCKET NO
"-l
'WE F M'o ho I"it 1 DATE 79-06-30 COMPLETEl> llY R-k'. Co1nrho REPORT MONTil June TELEPIIONE 916-452-3211 5g 3
) E' h E -r, he Cause & Correctise
.censee o
No.
Date g
g j
~,g i $
F,'
37 n-3 Action to H
fE 5
jg
,. r t :r mV
}U Prevent Recurrence Q
7 79-06-01 S
648 D
1 N/A N/A N/A USNRC Order No. 7590-01 issued May 8, 1979 7
79-06-28 S
72 F
1 N/A N/A N/A Prerequisite testing of AFW and plant heatup in preparation for startup i
2 3
4 F: Forced Reason:
Method:
Exhibit G - Instructions S: Schedu!cd A-lipiipment Failure (Explain) 1 Manual for Preparation of Data B Maintenance or Test 2-Man ual Scram.
En'ry Sheets for 1.icensee g
C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-G D Regulatory Restriction 4-Other (Explain) 0161) d
- 12. Operator Training & Liecnse Examination O
v.Au mimst rai ne s
G. Operational Error (Explain)
Exhibit !- Same Source (9/77) g@
Il-Other (Explain)
/
.p-NARRATIVE SUSC1ARY O' PLANT OrERATIONS DATE 6-1 Reactor in told shutdown, continued with plant rodifications specified in USNRC Order No. 7590-01.
6-15 Cocpleted STP-828.
Testing of Reactor Trip from Generator / Turbine Trips and/or Loss of Main Feedwater 6-20 Completed S7P-613, Auxiliary Feedwater Flow Indicator Permanent Installation Functional Test 6-27 USNRC Order No. 7590-01 Rescinded.
6-28 (1050)
Started two (2) Reactor Coolant pumps in preparation for RCS Ileatup 6-30 Completed SP 207.020, RCS Inservice !!ydro Test; test satisfactory.
(1524)
All control rods at 100% withdrawn.
(1531)
Commenced deboration to take reactor crit:c al.
(2137)
Reactor Critical (2228)
Reactu: at 2% power.
(2328)
Reactor at 10% power.
PFRSONNEL CIIANCES REQUIRING REPORTING No personnel changes that require reporting in accordance with Technical Specifications Figure 6.9-2 were made ir June, 1979.
MAJOR ITEMS OF SAFETY-RELATED 3L\\INTENANCE 1.
Replaced bearings and cleaned motor on Nuclear Raw Water Pump P-472B.
2.
Installed and tested ultrasonic flowneter system on eaca auxiliary feedwater line.
3.
Rebuilt relief valve (PSV-48701) on Lube Oil Cooler for the A Decay Eleat Pump.
4.
Disconnected and blev doun air lines to all air-operated isolation valves to assure no water in the lines following instrument air dryer repair work.
(~$$'
SUT!ARY Or' Cl!ANGES StADE IN ACCORDANCE 'ilTii 10 CFR 50.59 (b)
&s 1.
Addition of a control grade trip of the Reactor ca loss of main feedwater and/or Turbine Generator Trip.
2.
Additic. of a key switch and annunciation in the control r oc. f or bypasr.ine the control grade reactor trip on loss of feedwater.
}1TUELI:;C 1: 70PSiT10 ; REQUE',T Rancho Seco Unit 1 1.
1: ace of racility:
2.
Schedu:cd date for next refueling shutdown:
April 1980 Jun 1980 3.
Echeduled date fo.' restart follcuing refueling:
4; Technical Specification change or other license anendaent required:
a) Change to nod indcy. vs. Power Level Curve (TS 3.5. 2) b) Change to Core I balance vs. Pouer Level Curve (TS 3.5.2)
'c) Tilt Linit., (TS 3'.5.2) d) Safety Equipaent Testing (TS 3.3.3)
Februarv 1980 5.
Scheduica date(s) for submit tina proposed licensing action:
None licensing considerations associated with refueling:
6.
It,po rt en t 7.
Utmber of fuel assemblies:
a) In the core:
177 122 b) In the Spent Fuel Fool:
S.
Present licensed spent'f uel capacity:
570 9.
frojected date of the last refueling that can be discharged 2987 to the Spent Fuel Pool:
r 0
9