ML20062F965

From kanterella
Jump to navigation Jump to search
Monthly Oper Rept for Nov 1978
ML20062F965
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 12/15/1978
From: Merson S
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20062F963 List:
References
NUDOCS 7812220077
Download: ML20062F965 (18)
v • d • e


Text

. .

OPERATING DATA REPORT DOCKET NO. 50-317 DATE 12-19-78 COMPLETED BY 9 9 % =nn TELEPHONE 301-23h 52h0 OPERATING STATUS

1. Unit Name: Calvert Cliffs No. 1 Notes
2. Reporting Period: Novernber,1978
3. Licensed Thermal Power (MWt): 2700
4. Nameplate Rating (Gross MWe): 910
5. Design Electrical Ratmg (Net MWe): dh5
6. Maximum Dependable Capacity (Gross MWep: 8h5
7. Maximum Dependable Capacity (Net MWe): 810
8. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report.Give Reasons:
9. Power Level To Which Restricted. lf Any (Net MWe):
10. Reasons For Restrictions. lf Anv:

This Month Yr.-to.Date Cumulative

11. Hours in Reporting Period 720 8016 31.261
12. Number Of Hours Reactor Was Critical 717.9 5935.9 25.639.5
13. Reactor Reserve Shutdown Hours 2.1 60.8 498.7
14. Hours Generator On Line 716.5 9762.8 2C 14h.4
15. Unit Reserve Shutdown linurs 0.0 0.0 0.0
16. Gross Thermal Energy Generated aMWH) 1.7hh.52h.0 13.811.6h M 60.109.479.h

~ ~

17. Gross Electrical Energy Generated iMWHi 587.366 _ _ . h.583.6LL 20.058.487
18. Net Electrical Energy Generated (MWH) 562.065 h.165.760 19.n h .694
19. Unit Service Factor 99.5 71.9 80.T
20. Unit Availability Factor 99.5 71.9 80.4
21. Unit Capacity Factor (Using MDC Neti 96.h 67.2 75.6
22. Unit Capacity Factor (Using DER Net) 92.h 6h.4 79.C
23. Unit Forced Outage Rate 0.5 9.0 6.6
24. Shutdawns Scheduled Over Next 6 Months (Type. Date, and Duration of Each t:

Calvert Cliffs No.1 is scheduled for a olanned outage starting Acril lb,1979 and will 'ce six weeks in duration for general inspecticn and refueling.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status tPrior to Commercial Operationi: Forecast Achieved l INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 7 812.2 2 0 0 T'l

4 .-

~

q

- 7 t< \ -

W

- . - p\.g .

x , t q y. , .,. ,

s k

  • w

\ N '

, ,sh

' , . .\ -

-"' ,_ OPERATING' DATA REPORT

- e.

~

, > ._ ,, , i' DOCKET NO. 50-118

,, 'b . DATE','9 1< 7A w COMPLETED By, 9 N "arann s i i <

TELEPHONE' " '" Coh0 <

, 4. ,

  • ~

OPERATING STITtk

1. Unit Name: "21 " N14'f= k 9 -
2. Reporting Peret.* 5er 1978 - -

m ,

3. Licensed Thermal . .): 2700' - ,_.*
4. Nameplate Rating (L...s MWe)- 911 '
5. Design Electrical Ratmg (Net MWe) Obb Y '
6. Maximum Dependable Capacity (Gross MWel: 8h5
7. Maximum Dependable Capacity (Net SIWE l. ~ 010 '

S. If Changes Occur in Capacity Ratings ahans Number 3 Through 7) Since Last Report. Give Reasons:

V

- 9. Power Level To Which Restricted. If Any INet AtWe): None

10. Reasons For Restrictions. lf Any: Performina evele two escalation to enver nhvnir =

testing.

This Month Yr to-Date Cumulative II. Hours In Reporting Period 720 8 01 A 1h.A1A

12. Number Of Hours Reactor Was Critical 663.9 6'h99.1

. 12'.2<8.0

13. Reactor Reserve Shutdowr: Hours 0.0 72.5 219.h
14. Hours Gen rator On.Line 657.3 6 hnh_<

19 081_6

15. Unit Reserve Shutdown llours 0.0 O.0 O.0
16. Gross Theruel Energy Generated (MWHI 1,557,861.6 lh.680.855.8. _29.010.0h8.6 .

. 17 Gross Elec:rical Energy Generated (MWHi 521.880 .... h .867.672 9.699.och h96,591

~ ~

18. Net Electri<al Energy Generated (MWH) h.621.h39 9.162.793
19. Unir Sernce Factor 91'3 79.9 82.7
20. Unit Availability Factor 91'3 79.9 82.7
21. Unit Capacity Factor tusing MDC Neil 85.1 71.2 77.h
22. Unit Capacity FactorIUsing DER Net) 81.6 68.2 7h_9
23. Unit Forced Outage Rate 1.0 7.6 6.2
24. . Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each1:
25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status tPrior to Commercial Operationi: Forecast Achieved INITIAL LRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i I

. (9/77)-

+ ,

AVERAGE D AILY L' NIT POWER LEVEL DOCKET NO.40-117 LWIT Oalvert Cliffs No.

DATE 12-15-78 COMPLETED BY S.D.Mers en TELEPHONE 301-23h-52ho MONTH Nove ner. 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) IMWe-Net)

I 833 17 833 2 811 18 310 3 681 g9 71h 4 699 20 7h0 3 788 21 8th 6 811 22 838 7 92h 23 816 8 808 24 8c4 9 748 25 i73 10 7h 8 . 26 787 11 7h1 27 83h 12 813 yg g33 13 73h 29 813 14 788 30 811 15 697 3, 16 41<

i INSTRUCTIONS i

On this format. list the average d2dy unit power levelin MWe Net for each day in the reporting month. Compute to the neare<t whole megawatt.

i i

19/77)

I i

+,, ,

h AVERAGE D AILY UNIT POWER LEVEL DOCKET NO.60-318 UNIT Calvert Cliffs flo. .

DATE 12-15-78 COMPLETED BY S .D .Mers on TELEPHONE 301-23h-52h0 MONTH November. 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe Net) IMWe-Net t i h C1 17 687 2 M Is -

3 770 39 -

4 710 20 211 5 706 2I 804 6 681 8h9 22 7 786 850 23 s All 24 852

~9 807 25 8h5 10 _ 710 26 776 II 768 27 840 12 768 842

'22 IJ 771 9.1,9 29 14 781 '

854 30 15 h77 3t I6 719 N,

_s INSTRUCTIONS 1 On this format. list tne average daily unit power level m MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

1

- (9/77) m --a v-

DOCKET NO. 50-317 UNITSHUTDOWNS AND POWER REDUCTIONS UNIT NAME c, vert m i r es No.1 DATE 12/16/78 Mov- 1978 LETED W S. D. Wmn REPORT MONT11 TELEPHONE 101 '11b Ohn

- E e

$? 3 y E ~; Lecensee E r, {"' , Cause & Coreccleve No. 1)ase h 5@ 4 2s5: Ev(ni p g'8 Action to ,

W

$= 5 2C 53 2 Repent a mO u

o Prevent Recursente -

6 78-17 781116 F 3.5 o 3 ri/A ZZ ZZZZZZ Forced outage due to an operational error while by-passing the condensate filter system. This resulted in a trip of No.12 Steam Generator Feed Pump due to low suction pressure.

Low steam generatop lovel caused a reacter trip.

d i 2 3 4 F: Forced Reason: Method: Esti ibit G - Insisuttions S: Scheduled A-Equipraent Failure (Explam) l-Manual for Preparati.m of Data 11 Maintenance or Tes 2-Manual Scram. Entry Shecis fo 1.icensee C Refueling 3-Automatic Scram. Event Reposs ll l R 6 Fde INURLG-D-Regulatory Restsiction 4-Osher (Explain) 0161) l -Operator Tsaining & license Examination F Admmistrative 5 G-Operational Essor (Explain) Exhibit i . Same Source 19/77) 11 Othes (Explain)

~

KE 50-318 UNITSifUTDOWNS AND POWER REDUCTIONS g NAME " Calvert Cliffs No. 2 DATE 12-19-78 COMPLETED By S. D. mr nn REPORT MONTil Nov. 1978 TELEPi40NE 101-9% Ohn

.53 "g

~g hh*h Leocasce [v, Cause & Cossective .

No. Date k s 2s5 Event gy mo 3 A6 tion to 6-3E 5 j;gg Repost a g' Prevent Recurrence 6

78-19 781115 F 3.5 A 1 IER-039 CB PIPEII Forced outage due to excessive reactor coolant leakage. Plant returned to service after isolating a cracked weld on #21B Reactor Coolant Pump middle seal pressure transmitter sensing line.

78-19 781117 s 56.1 B 1 N/A ZZ ZZZZZZ Scheduled outage in ordeF to repair No. h Main Turbine Governor Valve.

78-20 781120 F 3.2 H h N/A ZZ ZZZZZZ Forced outage due to late return from previous scheduled outage.

I 2 3 4 F: Forced Reason: Method: Exhibit G. Insisuctions S: Scheduled A Equqinent Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Autunutic Scram. Event Report ILERI File INURLG.

D-Regulatory Restsiction 4-01her (Explain) 01611 IAlperator Training & License Examination F Adnunistrative 5 G-Operational Essur IExplain) Exhibit I . Sanw Source 19/77) it Other IExplain)

r Updated:

12/12/78 REFUELING INFORMATION RE00EST

1. Name of Facility:

Calvert Cliffs Nuclear Power Plant, Unit No.1

2. Scheduled date for next Refueling Shutdown:

April 14, 1979

3. Scheduled date for restart following refueling:

May 22, 1979 l

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Resumption of operation after refueling will require changes to Technical Specifications. The changes will be such as to allow l operation of the plant with a fresh reload batch and reshuffled Core.

5. Scheduled date(s) for submitting proposed licensing action and supporting information.

February 5,1979

6. Important licensing considerations associated with refueling.

Reload previousfuel will be similar to that reload fuel inserted into the cycle.

Selected fuel assemblies will be modified by installation of sleeves in the Guide Tubes.

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

a) 217 b) 228*

Spent Fuel Pools are cantnon to Units 1 and 2 -

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

1056 Licensed 728 Currently Installed

$#/Mdiffdd//g/P74WWdd 650 Addition is planned **

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

3dWid#dN/J7H/ October, 1983 **

Infomation which has changed since last monthly report.

Updated:

lIIll0 REFUELING INFORMATION REQUEST

1. Name of Facility I

Calvert Cliffs Nuclear Power Plant, Unit No. 2

2. Scheduled date for next Refueling Shutdown:

October 6, 1979 **

3. Scheduled date for restart following refueling:

November 8, 1979 4 Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Resumption of operation after refueling will require changes to Technical Specifications. The changes will be such as to allow operation of the plant with a fresh reload batch and reshuffled Core.

5. Scheduled date(s) for submitting proposed licensing action and supporting infomation.

l July 6,1979 **

6. Important licensing considerations associated with refueling.

Reload fuel Cycle 3 of Unit will1.be similar to that reload fuel inserted into the

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217 (b) 228*

Spent Fuel Pools are comon to Units 1 and 2

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been required or is planned, in number of fuel assenblies.

1056 Licensed 728 Currently Installed

  1. 9/A#fff#/fi/pl### 650 Addition is planned **
9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

3dpt#Wdtt/J9# October,1983 **

Infomation which has changed since last monthly report.

i

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE - November 1978 l n/l At the beginning of this reporting period, Unit 1 was operating at 873 We with the reactor at 97% power. Reactor power being limited by the Environmental Technical Specification (ETS) 10*F limit on main condenser circulating water o T.

11/2 Reduced load to 710 We at 2100 to investigate salt water leakage into i

the main condeoser.

[

11/4 Increased load to 8h3 We at 2330 after plugging 2 tubes. Reactor

  • power was limited to 95% by the ETS 10'F limit on main condenser I circulating water 4 T.

11/5 I

Reduced load to 700 We at 2000 to clean main condenser water boxes. ,

11/6 Increased load to 873 W e at 0415 reactor power remained limited to 9T% by the ETS 10'F limit on main condenser circulating water o T.

U/8 Reduced load to 700 We at 2200 to clean main condenser water boxes.

t 11/9 Increased load to 877 We at 0800. Reactor power remained limited j to 965 by the ETS 10*F limit on main condenser circulating water 4 T.

Reduced load to 730 We at 1645 to invettigate salt water leakage into L

4 the main condenser.

11/10 Increased load to 872 W e at 0530 after the salt water leak disappeared.

Reactor power remained limited to 95% by the ETS 10'F limit on main condenser circulating water 4 T. Reduced load to 725 W e at 1210 to i

investigate salt water leakage into the main condenser.

U/11 Increasen load to 870 We at 1345 after plugging one tube. Reactor

circulating water a T.

n/13 Reduced load to 733 We at 0600 to investigate salt water leakage into the main condenser.

I 1

s

11/14 Increased load to 873 We at 1130 after the leak disappeared.

Reactor power was limited to 95% by the m 10*F limit on main condenser circulating water d T.

11/15 Reduced load to 730 We at 0015 to investigate salt water leakage into the main condenser.

11/16 At 0628 while increasing load to capacity after plugging 2 tubes the reactor tripped on icy steam generator level after a feed pump tripped on low suction pressure while an operator was attempting to bypass the condensate precoat filter system. The reactor was i brought critical at 0825 and the unit paralleled at 0958. Fun load operation (863 We) resumed at 2000. Reactor power was limited to 95% by the EIS 10*F limit on main condenser circulating water o T.

11/19 Reduced load to 738 We at 0100 to investigate salt water leakage into the main condenser.

11/20 Resumed full load operation (877 We) at 2015. Reactor power was limited to 98% by the EIS 10*F limit on main condenser circulating water o T.

n/2h Reduced load to 727 We at 1809 to investigate salt water leakage into the the main condenser.

n/25 Resumed full load operation (870 We) at 1320 after plugging 1 tube.

Reactor power remained limited to 95% by the ETS 10*F limit on main condenser circulating water 6 T.

I n/26 Reduced load at 738 W e at 0020 to investigate salt water leakage into the main condenser. Full load operation (867 We) resumed at 1300 after plugging 1 tube. Reactor power remained limited to 955 by the ETS 10*F limit on main condenser circulating water 4 T.

n/30 At the end of the reporting period, Unit 1 was operating at 863 We with tne reactor at 95% power, power being limited by the ETS 10*F limit on main condenser circulating water a T.

1

l

SUMMARY

OF UNIT 2 OPERATING EXPERIDICE - November 1978 l

n/1 At the beginning of this reporting period Unit 2 was operating at )

i h12 !Ge with the reactor at 50% power while performing cycle two '

escalation to power physics testing.

At 0900 began increasing load to 100% power physics plateau.

n/2 At 1600 stopped power increase with the unit operating at 818 We.

Reactor power limited to 95% by the Technical Specification (TS) limi-tations op Unrodded Planar Radial PeaHnr Factor (Fxy T) and Unrodded Integrated Radial Peaking Factor (FrT ),

n/3 Reduced load to 716 We at 2150 to main clean condenser water boxes, n/k Continued reduced power operation after discovering a salt water leak at 0730. Resumed full load operation (862 MWe) at 2100. Reactor power was limited to 97% by the TS limit on FxyT and Fr T, 11/5 Reduced load to 715 We at OkOS to investigate salt water leakage into the main condenser.

11/7 Full load operation (865 We) resumed at 0850 after plugging 1 tube.

Reactor power was limited to 95% by the TS limit on FxyT and FrT, n/9 Reduced load to T30 We to main clean condenser water boxes.

11/10 Began increasing load to capacity. Stopped load increase at 8k0 We at 1h36 when main turbine number four governor valve stem became dis-connected from its operator.

Load was reduced to 810 We at 1530 in order to shut main turbine number four governor valve.

n/15 The unit was taken off line at 1400 in order to locate the source of reactor coolant system leakage in excess of Technical Specification limits. The reactor was maintained critical. The unit was paran eled i

at 172h, after isolating a cracked weld on 213 reactor coolant pump l

l I -___

middle seal pressure transmitter sensing line. Increased load to 807 We. Reactor power was limited to 89% by the TS limit on FxyT and FyT, 11/17 Increased power to 836 We at 1800, maximum obtainable with main turbine number four governor valve shut.

At 2327 while shutting the unit down for repairs to main turbine number four governor valve the reactor tripped on loss of load due to 22A feed water heater high level.

11/20 The reactor was brought critical at 07k8 and the unit paralleled at 1110.

11/21 Increased load to maximum capacity (900 We). Reactor power was limited to 98% by the Environmental Technical Specification (ETS) 10*F limit on main condenser circulating water 4 T.

11/25 Reduced load to 713 W e at 2215 to clean main condenser water boxes.

11/26 Full load operation (890 We) resumed at 0815 Reactor power was limited to 98% by the ETS 10*F limit on main condenser circulating vater o T.

At 1219 control element assembly (CEA) 3 drop into the core. Reactor power was immediately reduce to 70% in accordance with Technical Specifications. CEA 3 was withdrawn back to the group at 1450. Full load operation (893 We) resumed at 1910. Reactor power remained limited to 98% by the ETS 10*F limit on main condenser circulating water o T.

11/30 At the end of this reporting period Unit 2 was performing cycle 2 l escalation to power physics testing. Unit 2 was operating at 890 We

. l vith reactor power limited to 98% by the ETS 10*F limit on main condenser circulating waterd T.

SAFETY-RELATED HAINTENANCE ,

UNIT I -

GROUP INSTRUMENT & CONTROL HONTH NOVEMBER YEAR 1978 ,

MALFUNCTION SYSPD4 OR COMPONENT MR NO. - DATE CAllSE RESIILT CORRFMIVE ACTION Safety injection IC-78-46 2/16/78 Solenoid valve coil 1-SV-633 would not Replaced solenoid Tank 12A Vent Valve shorted open valve coil 1-SV-633 ESFAS Channel ZF 0-78-2515 8/3/78 Isolation module is Received a trip signal Replaced defective 12 SGIS (Steam Gen. defective on B-logic 12 SGIS module Isol. Signal)

ESFAS Sensor Channel ZD IC-78-101 4/17/78 +15 VDC power supply Loss of +15 volt D.C. Replaced power output is zero volts on sensor channel ZD supply Diesel Cooler #11 0-78-1953 6/15/78 1-SV-1587 defective 1-CV-1587 went closed Replaced solenoid Service Water Inlet restricting flow cf valve Valve 1-SV-1587 cooling water Diesel Cooler #12 0-78-1954 6/15/78 1-SV-1588 defective 1-CV-1588 went closed Replaced solenoid Service Water Inlet restricting flow of valve Valve 1-SV-1588 cooling water

SAFETY-RELATED MAINTENANCE UNIT I & II .

GROUP ELECTRICAL MONTl! NOVEM ER YEAR 1978 MAT RINCTION SYSPD4 OR COMPONENT MR NO. - DATE CAUSE l RESULT CORRECTIVE ACTION High Pressure Loader 0-78-3444 10/30/78 12 MSIV loader solenoid 12 MSIV will not Replaced solenoid 1-SV-9669 l-SV-9669 coil shorted partial stroke within valve coil specified time 4KV Bus 21 Under E-78-199 10/26/78 Under voltage relay Bus 21 under voltage Replaced under Voltage Relay shorted trip on channel ZD of voltage relay 127/B-21-E Engineered Safety Features Actuation System 21 Battery Charger E-78-085 4/18/78 Charger output causing Electrical interference Replaced SCR electrical interference on reactor protective and insulated system and Unit one heat sink from annunciation ground

SAFETY-RELATED MAINTENANCE ,

UNIT I & II GROUP MECHANICAL MAINTENANCE MONTH GCTOBER YEAR 1978 MALFUNCTION SYf7 PEN OH COMPONENT MR NO. - DATE CAUSE RESULT CORHFIM'IVE ACTION

  1. 22 MSIV 2-SV-4b48 0-78-1243 11/19/78 2-SV-4048 would not MSIV would not partial Rebuilt solenoid stroke w/ coil energized stroke valve block
  1. 22 MSIV #2 High 0-78-2247 11/18/78 Pump would not develop Pump ran continuously, Pressure Pump Rebuilt pump and adequate discharge would not shut off in discharge relief pressure "AUT0"-mode. valve Unit II Containment M-78-2283 7/26/78 Broken cam follower on Door inoperable Replaced cam Personnel Airlock door operating mechanism follower, performed (Inner Door) necessary operator adjustments.
  1. 22 Containment Cooler 0-78-2302 7/19/78 Upper bearing failure Fan unbalanced, noise, Replaced / repaired (Fan) severe wear of bearing bearing / housing, housing balanced fan blades

L SAFETY-RELATED MAINTENANCE UNIT II CROUP INSTRllMENT & CONTROL l

MONTH NOVEMBER YEAR 1978 MALFUNCTION SYSFEM OR COMPONENT MR NO. - DATU CAUSE RESULT CORHECTIVE ACTION Reactor Coolant Loop 0-78-25D9 8/2/78 Defective RTD's Channel A Tc (Tempera- Replaced RTD's 21A Cold Leg Temp. 2-TE-ll2CA and ture cold leg) indica- 2-TE-ll2CA and 2-TE-112CA 2-TE-122CA tion is not responsive 2-TE-122CA and to changes Reactor Coolant Loop 22A Cold Leg Temp.

2-TE-122CA Reactor Coolant Loop 2-IC-78-134 9/23/78 Output of transmitter Dutput of transmitter Replaced transmit-21B Flow Transmitter is erratic and out was both erratic and ter 2-PDT-lllB of tolerance. Due out of tolerance during to electronic failure STP.

I SAFErY-RELATED MAINTENANCE ',

UNIT II GROUP INSTRUMENT & CONTROL HONTH NOVEMRER YEAR 1978 HALFUNCTION SYSTEN OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Nuclear Instrumentation 2-IC-78-153 10/19/7 1 Proportional counters Failed plateau test Replaced propor-Wide Range Channel L-A are not responsive procedure tional counters (2-NE-001) Propor-tional Counters ESFAS 21 Steam Genera- 0-76-5074 12/18/76 Defective isolation Output voltage is not Replaced isolation tor Pressure Channel module with-in specified module ZG Isolation Module limit 2-E/E-10130 l

l ESFAS Channel ZD Bus 0-78-3351 10/23/78 Defective under Module tripped and Replaced under l 21 Under Voltage voltage module will not reset voltage module  ;

Module l 1

1 Nuclear Instrumentation 2-IC-77-109 5/17/78 Incore detectors are Fitteen of forty five Replaced fifteen Incore Detectors defective incore detectors have incore detectors low resistance readings

)

SAFErY-RELATED MAINTENANCE .

UNIT II GROUP INSTRtNENT & CONTROL MONTH NOVEMBER YEAR l970 MAI/cDNCTION SYf7 PEN OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION 22 Heat Exchanger 0-78-2362 7/20/78 Defective Bailey Valve failed to open Replaced Bailey Salt Water Outlet controller pilot valve within specified time controller pilot 2-CV-5212 during STP valve Nuclear Instrumentation 2-IC-78-129 9/21/78 Defective 15V D.C. Supply voltage -15 volt Replaced power 2-HI-002 Power Supply power supply D.C. found to be lower supply than specified limits during STP

  1. 21 Containment Spray 0-78-2944 9/17/78 Solenoid valve Unable to open Repaired solenoid Header Charcoal Filter stuck open 2-CV-4159 valve Isolation Valve 2-51-4159 Nuclear Instrumentation 2-IC-78-123 9/8/78 Discriminator board Channel D not respond- ne;, laced dis-Wide Range Channel D has low output ing to changes in criminator board (2-NI-004) calibrate signal level Pressurizer Pressure 0-78-3359 10/23/78 Defective oscillator Pressurizer pressure Replaced oscillator Transmitter 2-PT-lD0Y module indication went to zero

-. - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ .

Retrieved from "https://kanterella.com/w/index.php?title=ML20062F965&oldid=2727919"