ML19211A261
| ML19211A261 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 11/30/1979 |
| From: | Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19211A260 | List: |
| References | |
| NUDOCS 7912170278 | |
| Download: ML19211A261 (8) | |
Text
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NARRATIVE SD' MARY OF PLINT OPERATIONS r
11-1 thru Plant operatin2 at approximately 100% full power. Performed 11-16 routine surveillance and preventive maintenance items.
11-17 (0016)
Started reducing Reactor power from 100% (%910 MWe) at 15 L'/ minute to inspect inaccessible snubbers in the Reactor Building and to initiate the new under/over voltage protection scheme for the vital buses,
f (0107)
Generator off line (opened OCB's 220 and 230).
(0109)
Tripped Turbine.
-0 (0130)
Holding Reactor at 10 amps.
8 (2233)
Maintenance /nodifications complete - reactor at 8% power.
(2338)
'Reacter at 157 power.
(2358)
Generator on line (closed OCB's 220.and 230).
11-18 (0011)
Raising Reactor power to 92%. At 17% power (%170 MWe), the "B" Reheater Safety Valve lifted and would not reseat.
Started load reduction.
(0215)
Generator off line (opened OCB's 220 and 230).
i (0408)
Generator on line (closed OCB's 220 and 230).
l (0409)
Raising Reactor power.
(0449)
Reactor at 17% power (%170 MWe).
The "B" Reheater Safety Valve lifted and would not reseat. Separated from grid (opened OCB's 220 l
and 230).
I (0700)
Closed OCB's and began Reactor power escalation.
l (0721)
' Stopped escalation due to "B" Reheater Safety Valve failin~g to reseat.
(0730)
Reactor at 25*: (%220 MWe).
Began reducing power to separate from grid to perform repairs to "B" Reheater Safety Valve.
(0843)
Generator off line (opened OCB's 220 and 230).
(1123)
Repairs complete - generator on line (closed 00B's 220 and 230).
(1124)
Raising Reactor power.
1591 346 7 9121'J O 2 78'
. (1231)
Stopped power ascent at 55% power (400 W e) due to vacuum problem and power imbalance.
(1514)
Problems improved. Started increasing power to 92%.
(1545)
Reactor at 72% power (672 We).
(1710)
Reactor at 88% power (800 We) for 2-hour hold.
(2035)
Increasing Reactor power to 100%.
4 (2330)
Reactor at 100% full power.
11-19 (0102)
Began reducing power to 10%, developed electro hydraulic oil leak
}
on #1 Intercept Valve.
(0131)
Reactor at 20% power (180 We).
l l
(0135)
Turbine generator at 90 We (10% power).
I (0528)
Started increasing Reactor power to 92% af ter replacing "0" ring in ill Intercept Trip Solenoid Valve.
(0835)
Reactor at 87% power (785 We) for 2-hour hold.
(1035)
Raising Reactor power to 100%.
(1110)
Reactor at 100% full power.
f 11-25 (0147)
Secured Makeup Pump due to weld leak at intersection of Drain Valve SIM-579 line and HPI header (23620-4" CA) on discharge side of M.U.
l Pump (p-236). Started shutdown at 1 W / minute.
(0240)
Increased shutdown rate to 10 W/ minute due to the leak being non-isolable from supply header.
(0355)
Unit off line (opened OCB's 220 and 230).
(0357)
Tripped Turbine.
l (0420)
Reactor at 10-8,mp3, (0612)
Tripped Reactor.
I (1630)
Stopped RCS cooldown at 430 F and 1500 psig.
(2130)
Leak secured. Started RCS heatup.
i 1591 347
'-26 j
(0415)
Reactor in Hot Shutdown Mode.
(0550)
Started deboration of Reactor Coolant System.
~
1
-3_
(1335)
Reactor critical.
~
(1414)
Reactor at 10 amps.
(1424)
Reactor at 1% power.
(1530)
Reactor at 10% power.
(1600)
Reactor at 12% power.
(2210)
Maintained Reactor at 12% power while processing water to restore the Reactor Coolant Drain System Tank level to sufficient level to allow normal power operation.
11-27 (0100)
Started "A" HPI and secured Makeup Pump due to low oil pressure alarm.
(0800)
Reactor at 12% power.
(1210)
Unit on line (closed OCB's 220 and 230).
(1321)
Reactor at 30P. power (450 M7e) and holding for improved balance.
(1450)
Began increasing Reactor power to 727. for 5-hour hold.
(1553)
, Reactor at 72% power (640 MLe) for 5-hour hold.
(2100)
Holding power - waiting completion of leak rate calculation.
11-28 (0255)
Received acceptable leak rate calculation and began power escalation to 92%.
(0408)
Reactor at 92% (820 MWe) for 2-hour hold.
(0613)
Raising power to 100%.
(0645)
Stopped power.escalatios t 97% power due to inability to place d8 Condtnsate Polisher in service (inlet valve will not open).
11-29 (0000)
Reactor at 90% (820 MRe).
(1228)
Raising Reactor power to 100%.
(1318)
Reactor at 100% (900 MWe).
1591 348
-4 PERSON';EL CHA'*CES REQUIRING REPORTING No personnel changes t' at require reporting in accordance with Technical Specifications Figure 6.9-2 were made in November, 1979.
MAJOR ITEMS OF SAFETY-RELATED MAINTENANCE 1.
Continued inspection / testing of pipe supports; repaired or replaced as necessary to meet the new criteria covered in Bulletin 79-02.
2.
Rebuilt and/or filled three snubbers found low on oil during snubber inspection. (LER 79-16, LER 69-18).
3.
Changed setpoints of over/under voltage protection scheme for the Vital Buses-4.
Repaired weld on stub of Drain Valve SIM-579 line at intersection with HPI Header (23620-4"-CA) on discharge side Makeup Pump (LER 79-19).
SUMMARY
OF CHANGES MADE IN ACCORDANCE WITH 10 CFR 50.59(b) i No chances, tests, or experiments were completed in September, 1979, which constituted a change in a safety analysis report description.
I 1591 349 I
i 0
P00R ORGINAL REFUELI::C I:TCP?.ATIO:* REQUEST Rancho Seco Unit 1 1.
1: ace of Facility:
January 19, 1979 Scheduled da:e for next refueling shutdown:
2.
March, 1979 Scheduled date for restart following refueling:
'3.
Technical Specification change or other license anendment required:
4.
Change to Rod Inder. vs. Power Level Curve (TS 3.5.2) a)
Change to Core I: balance vs. Pouer Level Curve (TS 3.5.2) b)
c) Til: Limits (TS 3.5.2) d) Safety Equip =cnt Testing (TS 3.3.3).
December. 1970 Scheduicd date(s) for sub=itting proposed licensing action:
S.
None Impercent licensing considerations associated with refueling:
6.
7.
Nu,cber of fucl assc=blies:
a) In the core:
177 b) In the Spent Fuel Pool:
112 579 8.
Present licensed spent' fuel capacity:
5rojected date of the last refueling that can be discharged 9.
to the Spent Fuel Fool:
lo87 1591 350 a
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AVERAGE DAILY UNIT POhEI LEVEL 50-312 DOCKET NO.
R UNIT ancho Seco Unit I 79-11-30 DATE CO\\lPLETED BY R. 11 Colombo TELEPliONE 916-452-3211 MONTH
% e-ka.
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL Olhe Set) paye.Ner; I
867 0'
37 2
868 18 333 3
868 19 654 867 4
20 860 21-854 5
865 6
860 863 22 7
865 23 865 8
866 861 24 9
868 93 25 867 10 26 0
863 11 27 231-862 -
12 28 764 863 13 814 29 862 861 14 30 15 3;
16 861 INSTRUCTIONS On this (Or::n:, hst :he nera;c daily un:t power leselin.\\tWe Net for e eh day in the report:ne :n nth. C.>mpure to the nearest whoie megnot:-
1591 351 (9/771 e
ar en
P00R O hNO OPERATING DATA REPORT Ul DOCKET N0 50-312 DATE 79-11-30 CO3fPLETED BY R.
t' Colombo l
TELEPHONE 916-452-3211 OPERATING STATUS
- 1. Unit Name:
Rancho Seco Unit One Notes Scheduled outage on
- 2. Reportin; Period:
November 1979 November 17 to inspect-inaccessible snubbers and to
- 3. Licensed Thermal Power t.'lWts:
2772 initiate the under/over
- 4. Nameplate Rating IGross SIVe):
963 voltage protection scheme
- 5. Design Electrical R: ting (Net 31We t:
019 for the vital buses.
- 6. Staximum Dependable Capacity aGross SIWE):
917 l
- 7. Sfaximum Dependable Capacity (Net 31Wep:
073
- 8. If Changes Occur in Capacity Rating (Items Number 3 Through 7) Since Last Report. Gise Reasons:
N/A
- 9. Power Level To Which Restricted. If Any (Net 31We):
^
- 10. Reasons For Restrictions. If Any:
N/A This 5!onth Yr.-to.Date Cumulatise
- 11. Hours in Reporting Period 720 8,016 40,513
- 12. Number Of Hours Reactor has Critical 691.8 6,258.7 25,329.5
- 13. Reactor Rewrve Shutdown Hours 0
1,557.7 3,975.1 l4'. Hours Generator On.Line 634.5 6,034.1 24,197.3
- 15. Unit Resene Shutdown Hours 0
1,199.3 1,210.2
- 16. Cross Thermal Ener y Generated t>!WH, 1,709,887 16,463,692 61,536,848
- 17. Gross Electrical Ener; Generated s'.t'Vili 544,771 5,353,130 20,615.930
- 18. Net Electrica! Ener;> Generated salhHj 514,811 5,075,584 19,474,474
- 19. Unit Service Factor 88.1 75.3 59.7
- 20. Unit Availability Factor 88.1 90.2 62.7
- 21. Unit Capacity Factor iUsing.\\lDC Net) 81.9 72.5 55.1
- 22. Unit Capacity Factor (Using DER Net 77.9 69.0 52.4
- 23. Unit Forced Ot. tap Hate 9.0 6.2 32.7'
- 24. Shutdown > Scheduled Oser Nest 6 Stanths tT pefDate.and Dur:tian of Eachi:
3 Refueling: Januarv 1980-duration approximate 1v 60 days.
- 25. If Shur Down At End Of Report PericJ. Estimated D.ne of Startup-N/A
- 26. Units in Test Status. 'rior to Co;nmeresal Operarmn s:
Forecast Achiesed INITIAL CRIT!r \\ LITY
^
INITi \\L ELECTRICITY
__ N/A N/A CO.\\l\\:ERCITL Ol'ER A1 ION 4
s, o 15 91 2 52 (W77:
I UNIT SliUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-312 UNIT NAstE Rancho Seco Unit 1 D.\\10 79-11 '10 REPOltT MON 111_ November. 1979 COMPI.E II:D IlY R. W.
Colombo 1EErPilONE 916-452-3211
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14 79-11-17 S
22.8 B
1
~ N/A N/A N/A Inspected inaccessible snubbers and initiated the new under/over voltage protection scheme for the vital buses.
15 79-11-18 F
1.9 A
1 N/A N/A N/A "B" Reheater Safety Valve lifted and would not rescat.
16 79-11-18 F
2.2 A
1 N/A N/A N/A "B" Reheater Safety Valve lifted and would not resent.
(
17 79-11-18 F
2.7 A
1 N/A N/A N/A "B" Reheater Safety Valve lifted and g
would not resent.
Valve repaired.
]
18 79-11-19 F
0 A
1-N/A N/A N/A Reduced Reactor power to 10% due to an Electrohydraulic oil leak on #1 Q
Intercept Valve. Valve Trip Solenoid repaired.
19 79-25-79 F
55.9 A
1 79-019/03 L-0 SF PIPEXX Took Reactor to ilSD due to a weld leak O
at intersection of inlet stub of Q
SIM-579 drain 1ine and 4" llPI header.
v o o te vo n n e r,,,1 -
1 2
3 4
F: Forced Itc.non:
Method:
Exhibit G Instructions S: Scheduled A.I'luipment Failure (Explain) 1 Manual for Preparation of Data ll Maintenance or Test 2 Manual Scram.
Entry Sheets for 1.ieensee C Itchiclinr.
3-Automatic Scram.
Event ReporI (LL R) File (NUREG-D.Itcr."Id'"'y itesiriction 4-Ot her (Explain) 01611 I: Operator Training & License Examination F. Adenini.t rative 5
G. Operational Error (Explain)
' (9/77) 11-O her(Explain)
Exhibit I Same Source 9
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