ML19289C663
| ML19289C663 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/31/1978 |
| From: | Colombo R SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML19289C660 | List: |
| References | |
| NUDOCS 7901220075 | |
| Download: ML19289C663 (7) | |
Text
AVEP. AGE DAILY UNIT POWER LEVEL DOCKET NO.
50-312 UNIT Rancho Seco Unit 1 DATE 78-12-31 CO.\\fPLETED By R. W.
Colombo (916) 452-3211 TELEPflONE Af0NTil December, 1978 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
( AfWe Net)
(5tWe-Net )
0 17 n
0 2
18 0
0 3
19 0
0 0
4 20 0
73 5
21 6-0 353 22 0
673 7
23 0
8 24 882 9
0 887 25 0
885 10 26 O
II 27 891 12 0
895 28 0
732 13 29 0
34 30 777 is 0
652 31 0
16 INSTRUCTIONS on ibis conna[ilc nw P""#f INIin SfWe Net for each day in the reportin; nn>ntk Np g nst ti the nearest wh 19/77 )
m 9.01 2 2 0 0 76
~
UNIT SifUTDOWNS AND POWER REDUCT10NS DOCKET NO. 5 0 '11 ?
UNIT NAME P,nchn Rocn tenf t1 DATE 78-12-11 REPORT MONT11 December COMPl.ETED ILY R. 11. Colombo TELErilONE (91 M
!. 5 '- 1911
~
~.
E E
5?
3
$ $5 Licensee 5 r,
{"3 Cause & Correctne No.
Date g
3=
jg5 Event 3y a-Action to j~
E 35=
Repmt s
<E V 5'
Prevent Recurrence 6-g u
e o
21 781201 S
487.8 C
1 N/A N/A N/A 2nd Refueling Outage 22 781221 F
4.1 G
1 78-018/03L-0 ID INSTRU RCS Flow transmitter not valved in service.
Shutdown and placed transmitter in service.
23 781231 F
4.0 H
3 N/A CHI MECFUN Feed pumps tripped on overspeed causing Reactor trip on high pressure.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G. Instructions S: Scheduled A Equipment Failure (Explain) 1 -Manual for Preparation of Data Il Maintenance of Test 2-Man ual Sc~ ram.
Entry Sheets for Licensee C l'..rneling 3 Automatic Scram.
Event Report (LER) File (NUREG-D Rego. *ory Restriction 4-Ot her ( Explain) 0161)
I'. Operator Training & License Examination F Administrati.'e 5
G-Operational Error (!!xplain)
Exlubit I-Same Source (9/77)
Il Ot her (INplain)
OPERATING DATA REPORT DOCKET NO.
50-312 DATE 7 R-- 1 7-
'21
AMP' ETED BY R. W. rolombo TELEPliONE (916) - 4;2-3211 OPERATING STATUS
- 1. Urdt Name: Rancho Soco l'n f t 1 Notes Completed 2nd Refueling
- 2. Reporting Per:od: December 1978 Shutdown.
Commenced Cycle '!3 Operation December 21, 1978
- 3. Licensed Thermal Power t?.I'.s r s:
2772
@ 0750 lirs.
- 4. S.amep! ate Ratin; ! Gross MWet:
963
- 5. Design E! :trical R; tin;(Net 31We): 918 917
- 6. 5!nimum Dependabie C:'racity eGross \\ We):
073
- 7. Sinimum Dependab!e Capacity tNet \\lwel:
- 8. If Changes Oecurin Capacity R :in;s G: ems Number 3 Through 7) Since Last Report. Gise Reasons:
N/A
- 9. Power Lese! To which Re3:ricted. If An> tNet 3!We):
N ne
- 10. Renon, Fer Restrictions. If Any :
N/A This 5!onth Yr.-to-Date Cumulative II. H<v:rs in Reportin; Period 744 8,760 32,497
- 12. Namber Of f!m.r Reactor Was Critical 291.3 7.294.6 19.070.8
- 13. Reccrer Re ene s'.utdown flours 0
0 2,417.4
- 14. Ilours Ceacaror Oa-Line 248.1 7.044.7 18.163.2
- 15. Unit Resenc Shutdown flours 0
0 10.8
- 16. Grow Thr::ul Ercr;y Gen.ated I?.thiin 580.257 15.935.433 45.073.156
- 17. Grow Ek:trical Energy GenerateJ I?!hil 218.011 5.323.550 15.262.800
- 18. Net Elec:rira: Encr;y Generated i.\\lbit) 200,142 4,987,682 14,398,891
- 19. Unit S nice Factor 33.3 80.5 55.9
- 20. Unit \\sai:abifi:3 Factor 33.3 80.5 _
55.9
- 21. Unit Capeity Factor (Um.; ilDC Net t 30.8 65.2 50.8
- 22. Unit Capeg3 Factor (U3f a; DLR. Net )
29.3 62.0 48.3~
- 23. Unit forced Oata;e Rate 3.2 8.6 38.5
- 24. Shu: downs Sc.:eJaled Oser Nest 6 3fonths lT)pe. D.:te.and Dunnon of Each e:
Maintenance Shutdown, February 15, approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 25. If Shut Down i: End Of Report P.r;od. E3rinutcJ Da:e of Startu:,.
N/A
- 26. Unit,l. Fest Staruu Prior :o Commereal dyeution):
F orecast Achiesed INITI \\ L CRIT:C \\ LITY N/A N/A INITi \\L ELR r;'llh
_ N/A N/A CO\\l\\lERCI \\L Ol'EE \\ TION N/A N/A (0/77)
NARRATIVE SCOfAP.Y OF PLANT OPERATIONS Date 12-1 Plant shut down for second refueling outage.
12-19 Reactor critical (10-8 amps).
Commenced Low Power Physics Testing.
(1845) 12-21 Completed Low Power Physics Testing (0750)
Reactor at 17% Power.
Closed OCB's.
(1453)
Opened OCB's.
Reactor at 10-8 amps.
(1904)
Closed OCB's.
(2115)
Reactor at %40% Full Power.
12-22 (2220)
Reactor at %70% Full Power.
12-23 (0320)
Reactor at N75% Full Power.
(2120)
Ren tor at %87% Full Power.
12-27 (1522)
Reactor at 100% Full Power.
12-29 Reduced Reactor Power to 75% to complete BOC Physics Testing.
12-30 (1438)
Reactor at 100% Full Power.
12-31 (0805)
Turbine / Generator Trip.
(1003)
Reactor Critical.
(1211)
Closed OCB's.
(1530)
Reactor at 89% Full Power.
(1911)
Reactor at 100% Full Power.
PERSONNEL CHANGES REQUIRING REPORTZNG No personnel changes that roquire reporting in accordance with Technical Specifications Figure 6.9-2 were made in December, 1978.
MAJ0R ITEMS OF SAFETY RELATED MAINTENANCE 1)
Replaced casing flange gasket on'P-26LA, Decay Heat Pump Loop A.
2)
Replaced coupling flanges and bolts on Diesel Driven Fire Pump P-996.
3)
Replaced seats and adjusted Reactor Building Purge inlet and outlet valves (SFV-53504 and SFV-53605, SFV-53604).
4)
Replaced one Reactor Vessel internal vent valve ~ and repaired 3 o the :s.
5)
Reinstalled drive gear tripper pin in "B" Decay heat cooler outlet valve SFV-26040, 6)
Repaired two rigid pipe support hangers and rebuilt one hydraulic sway suppressor (snubber) on the "B" Decay Heat System (LER 78-17).
7)
Performed eddy current inspection of OTSG Tubes.
See supplenent attached to this report.
SUMMARY
OF CHANCES MADE IN ACCORDANCE WITH 10 CFR 50.59(b).
1)
Installation of thermocouples in four charcoal filters it. the Reactor Building Purge Exhaust Fan.
2)
Installation of ionization detectors in areas of the plant that contain combustibles and equipment or cable required for mafe shutdown and cooldown.
3)
Modification to provide trip of diesel fuel oil pumps on activation of the C0 system in the diesel generator rooms and 3
initiation trip of supply and exhaust fans when they blocking CO2 have started due to a SFAS start signal.
REFUELING INFORMATION REQUEST 1.
Name of Facility - Rancho Seco Unit 1 2.
Scheduled date for next refueling shutdown - March 1980.
3.
Scheduled date for restart following refueling - May 1980.
4.
Technical Specification change or other license amendment required -
a) Change to Rod Index vs. Power Leval Curve (TS 3.5.2) b) Change to Core Imbalance vs. Power Level Curve (TS 3.5.2) c) Tilt Limits (TS 3.5.2) d)
Safety Equipment Testing (TS 3.3.3) 5.
Scheduled date(s) for submitting proposed licensing action - January 1980.
6.
Important licensing considerations associated with refueling - None.
7.
Number of fuel assemblies a)
In the core - 177 b)
In the Spent Fuel Pool - 112 spent.
8.
Present licensed spent fue1 capacity - 579.
9.
Projected date of the last refueling that can be discharged to the Spent Fuel Pool - 1987.
SUPPLEMENT TO MONTliLY PLANT OPERATIONS REPORT EDDY CURRENT INSPECTION OF OTSG TUEES 1978 REFUELING OUTAGE DESCRIPTION A-0TSG B-0TSG No. of Tubes Inspected Bundle-Lane:
3.5% = 540 Tubes Bundle-Lane:
3.2% = 501 Tubes Lane:
4100%
= 373 Tubes Lane:
%100%
= 363 Tubes Total 913 Tubes Totc1 364 Tubes No. of Tubes Plugged 0
0 Location of Indications Dents (1 to 3 mils ) at Upper Dents (1 to 3 mils) at Upper Tube Sheet in %54% of the Lane Tube Sheet in %46% of the Lane Tubes (205 tubes).
Tubes (167 tubes).
Dents (5 to 6 mils) at 15th Dents (5 to 6 mils) at the Tube Support Plate in 7 tubes 15th Tube Support Plate in of tube bundle (excluding the 5 tubes of the tube bundle lane area).
(excluding lane area).
Denting indications at Tube Denting indications at Tube Support Plate were observed Plate were observed during during the previous inspection the previous inspection but but were so small as to be were so small as to be inter-interpreted as permiability preted as permiability variation.
Growth attributed variation.
Growth attri-to vibration.
buted to vibration.
Other indications noted are Tube 66-130 was inspected (per as follows:
SMUD letter of 10/8/77 to Region V) with no indications Tube 75/22 <20% OD @ #1 TSP noted.
& #2 TSP Tube 58/87 <20% OD between LTS
& 1 TSP Tube 53/86 <20% OD between LTS
& 1 TSP Tube 60/43 38% OD 0 15th TSP (No growth from indication observed last year and noted on NCR S-768 Rev 1)
Location of Plugged Tubes NA NA General Description of 4100% of Lane (3 rows either Same as "A" where inspected tubes side of the open tube lane to are located the WY Axis) and %3% random sanple of the remainder of the entire tube bundle.
Type of Inspection All tubes; 100% of length at Same as "A" 400 Kilz (some lane tubes were
.c
.