ML19332C470: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:, | {{#Wiki_filter:, | ||
4 | 4 | ||
,, 4 4 | ,, 4 4 | ||
.,s | .,s i - | ||
i - | |||
. The Light 1 P.0, Box 1700 Houston. Thas 77001 (713) 228 9211 E caton Lighting & Power ___._. | . The Light 1 P.0, Box 1700 Houston. Thas 77001 (713) 228 9211 E caton Lighting & Power ___._. | ||
L 4 | L 4 | ||
Line 36: | Line 27: | ||
^ | ^ | ||
U. S. Nuclear Regulatory Commission Attention: Document Control Desk | U. S. Nuclear Regulatory Commission Attention: Document Control Desk | ||
- Washington, DC-- 20555 | - Washington, DC-- 20555 South- Texas Project Electric Generating Station Units 1 6 2 ,. | ||
South- Texas Project Electric Generating Station Units 1 6 2 ,. | |||
Docket Nos. STN 50 498'& 50-499 Month 1v Ooerr. ting Reports for October. 1989 - | Docket Nos. STN 50 498'& 50-499 Month 1v Ooerr. ting Reports for October. 1989 - | ||
Pursuant to 10CFR50.71(a) and South Texas Project Electric Generating Station (STPEGS) Technical Specification 6.9.1.5, attached are the Monthly i Operating Reports.for October, 1989. , | Pursuant to 10CFR50.71(a) and South Texas Project Electric Generating Station (STPEGS) Technical Specification 6.9.1.5, attached are the Monthly i Operating Reports.for October, 1989. , | ||
If yoti should have any questions on this matter, please contact - | If yoti should have any questions on this matter, please contact - | ||
Mr. C. A. Ayala at (512) 972-8628. | Mr. C. A. Ayala at (512) 972-8628. | ||
nett Manager : | nett Manager : | ||
Support Licensing i i | Support Licensing i i | ||
Line 52: | Line 37: | ||
: 2) STPEGS Unit 2 Monthly Operating Report - October, 1989 - | : 2) STPEGS Unit 2 Monthly Operating Report - October, 1989 - | ||
.i 1. | .i 1. | ||
l | l 091'1280168 891031 DR ADOCK 0500 93 p).] | ||
091'1280168 891031 DR ADOCK 0500 93 p).] | |||
A1/023.NL5 A Subsidiary of Houston Industries incorporated | A1/023.NL5 A Subsidiary of Houston Industries incorporated | ||
.ac | .ac | ||
,-... c P L | |||
,-... c P | |||
L | |||
.1 | .1 | ||
'' ST-HL-AE 3296 m Houston Lighting & Power Company File No.: CO2 | '' ST-HL-AE 3296 m Houston Lighting & Power Company File No.: CO2 | ||
'" ' South Texas Project Electric Generating Station Page 2 cc: r | '" ' South Texas Project Electric Generating Station Page 2 cc: r | ||
' : Regional Administrator Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel y 611'Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 1700 llouston, TX 77001 | ' : Regional Administrator Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel y 611'Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 1700 llouston, TX 77001 | ||
- George Dick, Project Manager - | - George Dick, Project Manager - | ||
' U.S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Center | ' U.S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Center 1100 circle 75 Parkway J. I. Tapia. Atlanta, GA 30339-3064 | ||
1100 circle 75 Parkway J. I. Tapia. Atlanta, GA 30339-3064 | |||
- Senior Resident Inspector c/o U. S. Nuclear Regulatory Dr. Joseph M. Hendrie Commission 50 Be11 port Lane P. 0.' Box 910 Be11 port, NY 11713 Bay City, TX- 77414 D. K. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman & Holtzinger, P.C. Texas Departmen* of Ilealth 1615 L Street, N.W.- 1100 West 49th Street Washington, DC 20036 Austin, TX 78704 R. L. Rango/R P. Verret Central Power & Light Company | - Senior Resident Inspector c/o U. S. Nuclear Regulatory Dr. Joseph M. Hendrie Commission 50 Be11 port Lane P. 0.' Box 910 Be11 port, NY 11713 Bay City, TX- 77414 D. K. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman & Holtzinger, P.C. Texas Departmen* of Ilealth 1615 L Street, N.W.- 1100 West 49th Street Washington, DC 20036 Austin, TX 78704 R. L. Rango/R P. Verret Central Power & Light Company | ||
, P. 0.' Box 2121 Corpus Christi, TX 78403 J.LC. Lanier | , P. 0.' Box 2121 Corpus Christi, TX 78403 J.LC. Lanier Director of Cenerations City of- Austin Electric Utility 721 Barton Springs Road Austin,1DC 78704 | ||
Director of Cenerations City of- Austin Electric Utility 721 Barton Springs Road Austin,1DC 78704 | |||
- R. J. Costello/M. T. Hardt City.Public Service Board P. O. Box 1771 L San' Antonio, TX 78296 1' | - R. J. Costello/M. T. Hardt City.Public Service Board P. O. Box 1771 L San' Antonio, TX 78296 1' | ||
Revised 11/15/89 i | Revised 11/15/89 i | ||
L4/NRC/ | L4/NRC/ | ||
: n. . | : n. . | ||
n Q ''i ., | n Q ''i ., | ||
' k, ATTACHMENT I I | |||
' k, | |||
ATTACHMENT I I | |||
' . ST HL AE 321/ ' | ' . ST HL AE 321/ ' | ||
PAGE_.L-OE,f.-. ..,. .. _ | PAGE_.L-OE,f.-. ..,. .. _ | ||
u . , | u . , | ||
-i. | -i. | ||
E t | E t | ||
4 7" | 4 7" | ||
SOUTH TEXAS PROJECT ' | SOUTH TEXAS PROJECT ' | ||
p ELECTRIC GENERATING STATION UNIT 1 , | p ELECTRIC GENERATING STATION UNIT 1 , | ||
Line 108: | Line 68: | ||
OCTOBER 1989 HOUSTON-LIGHTING AND POWER CO. | OCTOBER 1989 HOUSTON-LIGHTING AND POWER CO. | ||
NRC DOCKET NO. 50-498 e LICENSE NO.'NPF-76 j i | NRC DOCKET NO. 50-498 e LICENSE NO.'NPF-76 j i | ||
Reviewed r: "! !39 C | Reviewed r: "! !39 C | ||
General Supervisor Date | General Supervisor Date | ||
Line 114: | Line 73: | ||
'P$fi[ Engineering anager 'Date Approve'd By: h\h , ' h\\\\ 71 ' | 'P$fi[ Engineering anager 'Date Approve'd By: h\h , ' h\\\\ 71 ' | ||
Plant'fianager -\ bade p | Plant'fianager -\ bade p | ||
1 1 | 1 1 | ||
pm pr ' | pm pr ' | ||
-} | -} | ||
.; . | .; . | ||
s u f, , | s u f, , | ||
L,- | L,- | ||
b - | b - | ||
ATTACHMENT / | ATTACHMENT / | ||
, Monthiv Sa=<rv. | , Monthiv Sa=<rv. | ||
k~ .ST PAnrKLAE 1 OE 7[ N | k~ .ST PAnrKLAE 1 OE 7[ N STPEGS Unit' l was returned to service following refueling on 10/19/89 at. | ||
STPEGS Unit' l was returned to service following refueling on 10/19/89 at. | |||
'1106. ' The unit remained derated until 10/29/89 for reactor performance testing and low pressure turbine stationary blade stress monitoring. . | '1106. ' The unit remained derated until 10/29/89 for reactor performance testing and low pressure turbine stationary blade stress monitoring. . | ||
On 10/30/89 the unit' was derated to ~95% reactor power to allow maintenance. | On 10/30/89 the unit' was derated to ~95% reactor power to allow maintenance. | ||
on a feedwater pump. | on a feedwater pump. | ||
i | i | ||
+ | + | ||
L k | L k | ||
l | l C | ||
i f | |||
f | |||
u4 ATTACHMENT I | |||
u4 | |||
ATTACHMENT I | |||
. ST.HL AE. 3 2 Y OPERATINC DATA REPORT _.P l [.tl. g O f.I . | . ST.HL AE. 3 2 Y OPERATINC DATA REPORT _.P l [.tl. g O f.I . | ||
DOCKET NO. 50 498 UNIT 1 DATE Epv. 6. 1989-COMPLETED BY 'A.P. Rent TELEPHONE 512/972-7786 OPERATING STATUS | DOCKET NO. 50 498 UNIT 1 DATE Epv. 6. 1989-COMPLETED BY 'A.P. Rent TELEPHONE 512/972-7786 OPERATING STATUS | ||
'1. REPORTING PERIOD: 10/01-10/31 GROSS HOURS IN REPORTING PERIOD: 745 | '1. REPORTING PERIOD: 10/01-10/31 GROSS HOURS IN REPORTING PERIOD: 745 | ||
;2. CURRENTLY AUTiiORIZED POWER LEVEL (MWt): 3800 MAX. DEPEND. CAPACITY (MWe Net): 1250.6 DESIGN ELECTRICAL RATING-(MWe-Net): 1250.6 | ;2. CURRENTLY AUTiiORIZED POWER LEVEL (MWt): 3800 MAX. DEPEND. CAPACITY (MWe Net): 1250.6 DESIGN ELECTRICAL RATING-(MWe-Net): 1250.6 | ||
Line 169: | Line 104: | ||
: 6. REACTOR RESERVE SHUTDOWN HOURS........... | : 6. REACTOR RESERVE SHUTDOWN HOURS........... | ||
: 7. HOURS GENERATOR ON LINE.................. 311.4 4332.9 6738.9_ | : 7. HOURS GENERATOR ON LINE.................. 311.4 4332.9 6738.9_ | ||
-8. UNIT RESERVE SHUTDOWN HOURS.............. 0 0 0 | -8. UNIT RESERVE SHUTDOWN HOURS.............. 0 0 0 l' | ||
l' | |||
: 9. GROSS THERMAL ENERGY GENERATED-(MWt)..... 783890 15374296 '24188817 4 | : 9. GROSS THERMAL ENERGY GENERATED-(MWt)..... 783890 15374296 '24188817 4 | ||
: 10. GROSS ELECTRICAL ENERGY GENERATED (MWH) . , 252630 5216370 8208600 11.~ NET ELECTRICAL ENERGY GENERATED (MWH).... 219398 _ | |||
: 10. GROSS ELECTRICAL ENERGY GENERATED (MWH) . , 252630 5216370 8208600 | |||
11.~ NET ELECTRICAL ENERGY GENERATED (MWH).... 219398 _ | |||
4890335 7681827 | 4890335 7681827 | ||
: 12. REACTOR SERVICE FACTOR................... 54.6% 61.7% 67.3% , | : 12. REACTOR SERVICE FACTOR................... 54.6% 61.7% 67.3% , | ||
Line 187: | Line 114: | ||
: 15. UNIT AVAILABILITY FACTOR........... ..... 41.8% 59.4% 64.8% | : 15. UNIT AVAILABILITY FACTOR........... ..... 41.8% 59.4% 64.8% | ||
: 16. UNIT CAPACITY FACTOR (Using MDC)......... 23.6% 53.6% 59.1% | : 16. UNIT CAPACITY FACTOR (Using MDC)......... 23.6% 53.6% 59.1% | ||
: 17. UNIT CAPACITY FACTOR (Using Design MWe).. 23.6% 53.6% 59.1% | : 17. UNIT CAPACITY FACTOR (Using Design MWe).. 23.6% 53.6% 59.1% | ||
: 18. UNIT FORCED OUTAGE RATE.. ............... 0% 4.9% 7.3% | : 18. UNIT FORCED OUTAGE RATE.. ............... 0% 4.9% 7.3% | ||
: 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): | : 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): | ||
Scheduled 55 day refueling outage to begin April 7, 1990. | Scheduled 55 day refueling outage to begin April 7, 1990. | ||
: 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A | : 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A | ||
e - - | e - - | ||
4' | 4' | ||
<; | <; | ||
i. | i. | ||
Hi ' | Hi ' | ||
- ATTACHMENT I | - ATTACHMENT I | ||
Line 213: | Line 129: | ||
PArJ + OF_(_. . j | PArJ + OF_(_. . j | ||
.i | .i | ||
). . | ). . | ||
5 DOCKET NO, 50-498 | 5 DOCKET NO, 50-498 | ||
! UNIT 1 | ! UNIT 1 | ||
> DATE Nov. 6. 1989 -3 | > DATE Nov. 6. 1989 -3 COMPLETED BY A.P. Kent- | ||
COMPLETED BY A.P. Kent | |||
-TELEPHONE ' 512/972-7786 | -TELEPHONE ' 512/972-7786 | ||
.c ;ITH _ OCTOEER r | .c ;ITH _ OCTOEER r | ||
i DAY " AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe Net) | i DAY " AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe Net) 1 0 17 0 2 0 18 2 3 , | ||
1 0 17 0 | |||
2 0 18 2 3 , | |||
0 19 14 l | 0 19 14 l | ||
'4 0 20 190 l: | '4 0 20 190 l: | ||
5 0 21 ' 245- | 5 0 21 ' 245- | ||
: 6. 0 22 367 , | : 6. 0 22 367 , | ||
7 0 23 492 _ | 7 0 23 492 _ | ||
Line 246: | Line 149: | ||
: 14; O 30 1219 15 0 31 1201 16 0 | : 14; O 30 1219 15 0 31 1201 16 0 | ||
- ~. | - ~. | ||
3. | 3. | ||
.. . . 3 | .. . . 3 IN-Y | ||
IN-Y | |||
: UNIT SHUTDOWNSTAND POWER REDUCTIONS' A~ | : UNIT SHUTDOWNSTAND POWER REDUCTIONS' A~ | ||
DOCKET NO. 50-498 '. | DOCKET NO. 50-498 '. | ||
UNIT 1 DATE' Nov. 6.'1989 COMPLETED.BYiA.P! Kent TELEPHONE 512/972-7786 | UNIT 1 DATE' Nov. 6.'1989 COMPLETED.BYiA.P! Kent TELEPHONE 512/972-7786 | ||
. REPORT MONTH OCTOBER | . REPORT MONTH OCTOBER 1 '2 3 4 5 No. Date Type Duration Reason Method of Licensee System Component "Cause & Corrective Action to (Hours) Shutting' Event Code Code Prevent Recurrence Down Raport # | ||
1 '2 3 4 5 No. Date Type Duration Reason Method of Licensee System Component "Cause & Corrective Action to (Hours) Shutting' Event Code Code Prevent Recurrence Down Raport # | |||
Reactor 89-10 890805 S 410.2 C 4 N/A' N/A .N/A Manual shutdown for refueling and scheduled maintenance. | Reactor 89-10 890805 S 410.2 C 4 N/A' N/A .N/A Manual shutdown for refueling and scheduled maintenance. | ||
89-11 891018 S 10.7 .B 1 N/A TA ~ .TRB Manual turbine trip due-to indications of water intrusion. It was determined that'the cause was faulty instrumentation and no intrusion occurred. (Reactor Critical)' | 89-11 891018 S 10.7 .B 1 N/A TA ~ .TRB Manual turbine trip due-to indications of water intrusion. It was determined that'the cause was faulty instrumentation and no intrusion occurred. (Reactor Critical)' | ||
Line 267: | Line 162: | ||
H-Other (Explain)- PAGE S OF f i | H-Other (Explain)- PAGE S OF f i | ||
_ . . _ _ _ _ _ - - - . _ - n-____. . . - . . _ , __ ._ ___..__a | _ . . _ _ _ _ _ - - - . _ - n-____. . . - . . _ , __ ._ ___..__a | ||
= | = | ||
8 , 1 | 8 , 1 b, . . . . . - - -. ; | ||
. 9 l | |||
b, . . . . . - - -. ; | n' . - | ||
. 9 | |||
ATTACHMENT / - | ATTACHMENT / - | ||
ry: | ry: | ||
' ST-HL AE. 72 9/ ' | ' ST-HL AE. 72 9/ ' | ||
PORVs and Safety Valves Si pggg g gp g- | PORVs and Safety Valves Si pggg g gp g- | ||
;NO PORVs or-, Safety Valves were challenged during this. reporting period.- . | ;NO PORVs or-, Safety Valves were challenged during this. reporting period.- . | ||
; | ; | ||
r F | r F | ||
'I i b | 'I i b | ||
i | i s | ||
t i | |||
1 - | |||
li [ | li [ | ||
T I | T I | ||
t | t | ||
Line 306: | Line 185: | ||
* w. | * w. | ||
.t, | .t, h: . | ||
; | ; | ||
ATTACHMENT 2.- | ATTACHMENT 2.- | ||
T: . ST.HL-hE 311' | T: . ST.HL-hE 311' PAGE I OF ( | ||
PAGE I OF ( | |||
L | L | ||
. SOUTH TEXAS PROJECT t_ ' | . SOUTH TEXAS PROJECT t_ ' | ||
ELECTRIC GENERATING STATION UNIT 2 MONTHLY OPERATING REPORT | ELECTRIC GENERATING STATION UNIT 2 MONTHLY OPERATING REPORT | ||
:- OCTOBER 1989 HOUSTON LIGHTING AND POWER CO, NRC DOCKET NO. 50-499 LICENSE NO. NPF-80 Reviewed B Md b General Supervisor Datu | :- OCTOBER 1989 HOUSTON LIGHTING AND POWER CO, NRC DOCKET NO. 50-499 LICENSE NO. NPF-80 Reviewed B Md b General Supervisor Datu | ||
' Reviewed By: // 87 l Pl[rfdEngineering(tanager 'Da'te l Appr'oved By: 11 , D h\85 | ' Reviewed By: // 87 l Pl[rfdEngineering(tanager 'Da'te l Appr'oved By: 11 , D h\85 Plant Manager- T bale # | ||
Plant Manager- T bale # | |||
I | I | ||
'l | 'l | ||
!^ s, ! | !^ s, ! | ||
l | l g | ||
g | |||
g.- | g.- | ||
c | c | ||
.e . | .e . | ||
9 E. ATTACHMENT 2., | |||
9 | |||
E. ATTACHMENT 2., | |||
Monthly Su===ry | Monthly Su===ry | ||
. ST-HL AE J 2. W PAGE 1 OF ( | . ST-HL AE J 2. W PAGE 1 OF ( | ||
Line 352: | Line 211: | ||
t- A Notice of Unusual Event (NOUE) was declared on 10/18/89 at 1208 when a-Feedwater Isolation Valve's Nitrogen pressure was below its technical specifi-cation value. - The NOUE was terminated at 1211 on 10/18/89 when Nitrogen pressure was restored to the' valve. | t- A Notice of Unusual Event (NOUE) was declared on 10/18/89 at 1208 when a-Feedwater Isolation Valve's Nitrogen pressure was below its technical specifi-cation value. - The NOUE was terminated at 1211 on 10/18/89 when Nitrogen pressure was restored to the' valve. | ||
.The unit concluded the report period at 100% reactor power. | .The unit concluded the report period at 100% reactor power. | ||
l I I | l I I | ||
e I t | e I t | ||
l'. I l | l'. I l | ||
'l | 'l | ||
m+ | m+ | ||
bt L | bt L | ||
m | m | ||
~~ | ~~ | ||
'~ | '~ | ||
Line 375: | Line 226: | ||
- ' OPERATING DATA REPORT PAGE 3 OF ( | - ' OPERATING DATA REPORT PAGE 3 OF ( | ||
-j. | -j. | ||
DOCKET No. 50-499 UNIT 2 DATE Nov. 3. 1989 4 | DOCKET No. 50-499 UNIT 2 DATE Nov. 3. 1989 4 | ||
COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 , | COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 , | ||
OPERATING-STATUS | OPERATING-STATUS | ||
: 1. REPORTING PERIOD: 10/01-10/31 GROSS HOURS IN REPORTING PERIOD: 745 . | : 1. REPORTING PERIOD: 10/01-10/31 GROSS HOURS IN REPORTING PERIOD: 745 . | ||
: 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3800- | : 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3800-MAX. DEPEND. CAPACITY (MWe-Net); 1250.6 > | ||
DESIGN ELECTRICAL RATING (MWe-Net): 1250.6 POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe-Net): None 3. | |||
MAX. DEPEND. CAPACITY (MWe-Net); 1250.6 > | |||
DESIGN ELECTRICAL RATING (MWe-Net): 1250.6 POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe-Net): None | |||
3. | |||
.4. REASONS FOR RESTRICTION (IF.ANY): N/A THIS MONTH. YR-TO DATE CUMULATIVE- | .4. REASONS FOR RESTRICTION (IF.ANY): N/A THIS MONTH. YR-TO DATE CUMULATIVE- | ||
: 5. NUMBER OF HOURS REACTOR WAS CRITICAL..... 695.2 2900.8 2900.8 | : 5. NUMBER OF HOURS REACTOR WAS CRITICAL..... 695.2 2900.8 2900.8 | ||
: 6. REACTOR RESERVE SHUTDOWN HOURS........... 0 0 0 | : 6. REACTOR RESERVE SHUTDOWN HOURS........... 0 0 0 7.. HOURS GENERATOR ON LINE.................. 689.5 2771.7 2771.7 | ||
7.. HOURS GENERATOR ON LINE.................. 689.5 2771.7 2771.7 | |||
: 8. _ UNIT R.' SERVE SHUTDOWN HOURS...-............ 0 0 0 | : 8. _ UNIT R.' SERVE SHUTDOWN HOURS...-............ 0 0 0 | ||
: 9. CROSS THERMAL ENERGY CENERATED (MWt) . . . . 2579773 9258454 9258454 | : 9. CROSS THERMAL ENERGY CENERATED (MWt) . . . . 2579773 9258454 9258454 | ||
Line 397: | Line 241: | ||
: 11. NET ELECTRICAL ENERGY GENERATED (MWH).... 832187 2946843 2946843 | : 11. NET ELECTRICAL ENERGY GENERATED (MWH).... 832187 2946843 2946843 | ||
: 12. REACTOR SERVICE FACTOR................... 93.3% 89.5% 89 5% | : 12. REACTOR SERVICE FACTOR................... 93.3% 89.5% 89 5% | ||
: 13. _ REACTOR AVAILABILITY FACTOR.............. 93.3% 89.5% 89.5% | : 13. _ REACTOR AVAILABILITY FACTOR.............. 93.3% 89.5% 89.5% | ||
: 14. UNIT SERVICE FACT 0R...................... 92.6% 85.5% 85.5% | : 14. UNIT SERVICE FACT 0R...................... 92.6% 85.5% 85.5% | ||
Line 408: | Line 251: | ||
: 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A | : 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A | ||
1 7a y , | 1 7a y , | ||
, . y | , . y c ATTACHMENT 1 AVERAGE DAILY UNIT POWER' LEVEL | ||
, HA Tg OF ( | , HA Tg OF ( | ||
f | f | ||
~ | ~ | ||
DOCKET NO. -50'499 UNIT '2 DATE Eov.-3. 1989 COMPLETED BY A.P. Kent | DOCKET NO. -50'499 UNIT '2 DATE Eov.-3. 1989 COMPLETED BY A.P. Kent TELEPHONE 512/972 7786 MONTH October 1 | ||
TELEPHONE 512/972 7786 MONTH October 1 | |||
3 | 3 | ||
-DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)- (MWe Net) | -DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)- (MWe Net) | ||
Line 425: | Line 263: | ||
i 10' _ | i 10' _ | ||
'1247 26- 1247 | '1247 26- 1247 | ||
' 11' 1238 27 1246 | ' 11' 1238 27 1246 12 1232 28 1245 3 1 | ||
13~ 901- 29 1243 14 0 30 1244 i l l l ' 15 0 31 1242 16- ~S58 m..& | |||
12 1232 28 1245 3 1 | |||
13~ 901- 29 1243 14 0 30 1244 i l l l ' 15 0 31 1242 16- ~S58 | |||
m..& | |||
.;_ , | .;_ , | ||
UNIT SHIT 1 DOWNS AND POWER REDUCTIONS ~ c DOCKET NO. 50-499 | |||
UNIT SHIT 1 DOWNS AND POWER REDUCTIONS ~ c | |||
DOCKET NO. 50-499 | |||
* UNIT '2' DATE Nov. 3. 1989-COMPLETED BY A.P. Kent | * UNIT '2' DATE Nov. 3. 1989-COMPLETED BY A.P. Kent | ||
. TELEPHONE 512/972-7786 REPORT MONTH OCTOBER 1 | . TELEPHONE 512/972-7786 REPORT MONTH OCTOBER 1 | ||
No. Date Type Duretion Reason Method of Licensee System Comporent Cause 6 Corrective Action to (Hcurs) Shutting Event Code Code- Prevent Recurrence Down Report # | No. Date Type Duretion Reason Method of Licensee System Comporent Cause 6 Corrective Action to (Hcurs) Shutting Event Code Code- Prevent Recurrence Down Report # | ||
Reactor | Reactor 89-09 891005 F 0.0 A 5- N/A KV FLT Reactor power was reduced to ~58% due to indications of high winding temperatures on Open Loop Auxiliary Cooling Water Pump Motors. After the air filters on the motors were cleaned reactor power was increased. | ||
89-09 891005 F 0.0 A 5- N/A KV FLT Reactor power was reduced to ~58% due to indications of high winding temperatures on Open Loop Auxiliary Cooling Water Pump Motors. After the air filters on the motors were cleaned reactor power was increased. | |||
89-10 891013 F 55.5 A 3 2-89-026 JC IB Reactor / Turbine trip occurred frt,m a high neutron flux negative rate detection on two of four power range neutron moni-toring channels. The exact cause of the detected negative rate could not be deter-mined, but has been attributed to a Control Rod dropping due to an intermit-tent high resistance connection in its stationary gripper circuit diode. The faulty diode was replaced. The root cause of the event is under investigation. | 89-10 891013 F 55.5 A 3 2-89-026 JC IB Reactor / Turbine trip occurred frt,m a high neutron flux negative rate detection on two of four power range neutron moni-toring channels. The exact cause of the detected negative rate could not be deter-mined, but has been attributed to a Control Rod dropping due to an intermit-tent high resistance connection in its stationary gripper circuit diode. The faulty diode was replaced. The root cause of the event is under investigation. | ||
1 F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983 S: Scheduled A-Equipment Failure (Explsin) ,1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Cont. of Existing -- | 1 F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983 S: Scheduled A-Equipment Failure (Explsin) ,1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Cont. of Existing -- | ||
E-Operator Training & License Exam Outage ~ATT/sCHMENT 1 F-Administ.rative 5-Reduction ST-HL-AE- 12. # | E-Operator Training & License Exam Outage ~ATT/sCHMENT 1 F-Administ.rative 5-Reduction ST-HL-AE- 12. # | ||
G-Operational Errot (Explain) 9-Other PAGE y ()F 6 | G-Operational Errot (Explain) 9-Other PAGE y ()F 6 H-Other (Explain) | ||
H-Other (Explain) | |||
.g | .g | ||
?A | ?A | ||
; ? .g | ; ? .g | ||
.' 4 i p | .' 4 i p | ||
- If-.. ' - ATTACHMENT 2. - | - If-.. ' - ATTACHMENT 2. - | ||
u . ST-HL AE flid | u . ST-HL AE flid | ||
Line 468: | Line 287: | ||
n - - | n - - | ||
s f | s f | ||
h. | h. | ||
k b | k b | ||
m h | m h | ||
l 1 | |||
l l | |||
l-l l-e.. ,s i | |||
l | |||
l | l | ||
[ ''}} | [ ''}} |
Revision as of 15:21, 31 January 2020
ML19332C470 | |
Person / Time | |
---|---|
Site: | South Texas |
Issue date: | 10/31/1989 |
From: | Kent A, Mcburnett M HOUSTON LIGHTING & POWER CO. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
References | |
ST-HL-AE-3296, NUDOCS 8911280168 | |
Download: ML19332C470 (14) | |
Text
,
4
,, 4 4
.,s i -
. The Light 1 P.0, Box 1700 Houston. Thas 77001 (713) 228 9211 E caton Lighting & Power ___._.
L 4
November 15, 1989 ;
ST-HL-AE 3296 File No.: G02 .
^
U. S. Nuclear Regulatory Commission Attention: Document Control Desk
- Washington, DC-- 20555 South- Texas Project Electric Generating Station Units 1 6 2 ,.
Docket Nos. STN 50 498'& 50-499 Month 1v Ooerr. ting Reports for October. 1989 -
Pursuant to 10CFR50.71(a) and South Texas Project Electric Generating Station (STPEGS) Technical Specification 6.9.1.5, attached are the Monthly i Operating Reports.for October, 1989. ,
If yoti should have any questions on this matter, please contact -
Mr. C. A. Ayala at (512) 972-8628.
nett Manager :
Support Licensing i i
MAM/BEM/n1 Attachments: .1) STPEGS Unit 1 Monthly Operating Report - October, 1989 <
- 2) STPEGS Unit 2 Monthly Operating Report - October, 1989 -
.i 1.
l 091'1280168 891031 DR ADOCK 0500 93 p).]
A1/023.NL5 A Subsidiary of Houston Industries incorporated
.ac
,-... c P L
.1
ST-HL-AE 3296 m Houston Lighting & Power Company File No.: CO2
'" ' South Texas Project Electric Generating Station Page 2 cc: r
' : Regional Administrator Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel y 611'Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company Arlington, TX 76011 P. O. Box 1700 llouston, TX 77001
- George Dick, Project Manager -
' U.S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Center 1100 circle 75 Parkway J. I. Tapia. Atlanta, GA 30339-3064
- Senior Resident Inspector c/o U. S. Nuclear Regulatory Dr. Joseph M. Hendrie Commission 50 Be11 port Lane P. 0.' Box 910 Be11 port, NY 11713 Bay City, TX- 77414 D. K. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman & Holtzinger, P.C. Texas Departmen* of Ilealth 1615 L Street, N.W.- 1100 West 49th Street Washington, DC 20036 Austin, TX 78704 R. L. Rango/R P. Verret Central Power & Light Company
, P. 0.' Box 2121 Corpus Christi, TX 78403 J.LC. Lanier Director of Cenerations City of- Austin Electric Utility 721 Barton Springs Road Austin,1DC 78704
- R. J. Costello/M. T. Hardt City.Public Service Board P. O. Box 1771 L San' Antonio, TX 78296 1'
Revised 11/15/89 i
L4/NRC/
- n. .
n Q i .,
' k, ATTACHMENT I I
' . ST HL AE 321/ '
PAGE_.L-OE,f.-. ..,. .. _
u . ,
-i.
E t
4 7"
SOUTH TEXAS PROJECT '
p ELECTRIC GENERATING STATION UNIT 1 ,
i MONTHLY OPERATING REPORT
OCTOBER 1989 HOUSTON-LIGHTING AND POWER CO.
NRC DOCKET NO. 50-498 e LICENSE NO.'NPF-76 j i
Reviewed r: "! !39 C
General Supervisor Date
- Reviewed By: // I!N
'P$fi[ Engineering anager 'Date Approve'd By: h\h , ' h\\\\ 71 '
Plant'fianager -\ bade p
1 1
pm pr '
-}
.; .
s u f, ,
L,-
b -
ATTACHMENT /
, Monthiv Sa=<rv.
k~ .ST PAnrKLAE 1 OE 7[ N STPEGS Unit' l was returned to service following refueling on 10/19/89 at.
'1106. ' The unit remained derated until 10/29/89 for reactor performance testing and low pressure turbine stationary blade stress monitoring. .
On 10/30/89 the unit' was derated to ~95% reactor power to allow maintenance.
on a feedwater pump.
i
+
L k
l C
i f
f
u4 ATTACHMENT I
. ST.HL AE. 3 2 Y OPERATINC DATA REPORT _.P l [.tl. g O f.I .
DOCKET NO. 50 498 UNIT 1 DATE Epv. 6. 1989-COMPLETED BY 'A.P. Rent TELEPHONE 512/972-7786 OPERATING STATUS
'1. REPORTING PERIOD: 10/01-10/31 GROSS HOURS IN REPORTING PERIOD: 745
- 2. CURRENTLY AUTiiORIZED POWER LEVEL (MWt)
- 3800 MAX. DEPEND. CAPACITY (MWe Net): 1250.6 DESIGN ELECTRICAL RATING-(MWe-Net): 1250.6
- 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe-Net): None
'4. REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUMULATIVE S. NUMBER OF HOURS REACTOR WAS CRITICAL..... 407.1 4501.3 6998.2 l
0 0 0 -(
- 6. REACTOR RESERVE SHUTDOWN HOURS...........
- 7. HOURS GENERATOR ON LINE.................. 311.4 4332.9 6738.9_
-8. UNIT RESERVE SHUTDOWN HOURS.............. 0 0 0 l'
- 9. GROSS THERMAL ENERGY GENERATED-(MWt)..... 783890 15374296 '24188817 4
- 10. GROSS ELECTRICAL ENERGY GENERATED (MWH) . , 252630 5216370 8208600 11.~ NET ELECTRICAL ENERGY GENERATED (MWH).... 219398 _
4890335 7681827
- 12. REACTOR SERVICE FACTOR................... 54.6% 61.7% 67.3% ,
l 13. REACTOR AVAILABILITY FACTOR.............. 54.6% 61.7% 67.3%
- 14. UNIT SERVICC FACT 0R. .................... 41.8% 59.4% 64.8%
l
- 15. UNIT AVAILABILITY FACTOR........... ..... 41.8% 59.4% 64.8%
- 16. UNIT CAPACITY FACTOR (Using MDC)......... 23.6% 53.6% 59.1%
- 17. UNIT CAPACITY FACTOR (Using Design MWe).. 23.6% 53.6% 59.1%
- 18. UNIT FORCED OUTAGE RATE.. ............... 0% 4.9% 7.3%
- 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Scheduled 55 day refueling outage to begin April 7, 1990.
- 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A
e - -
4'
<;
i.
Hi '
- ATTACHMENT I
- 3. ;. ST-HL AE 11.1/ i I AVERAGE DAILY UNIT POWER LEVEL .
PArJ + OF_(_. . j
.i
). .
5 DOCKET NO, 50-498
! UNIT 1
> DATE Nov. 6. 1989 -3 COMPLETED BY A.P. Kent-
-TELEPHONE ' 512/972-7786
.c ;ITH _ OCTOEER r
i DAY " AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe Net) 1 0 17 0 2 0 18 2 3 ,
0 19 14 l
'4 0 20 190 l:
5 0 21 ' 245-
- 6. 0 22 367 ,
7 0 23 492 _
l L 8 0 24 754
~9~ 0 25 916 942 -'
10 . 0 26 l
11 0 27 974 1
' 12 ' 0 28 1118 1
~13 0 29 1222
- 14; O 30 1219 15 0 31 1201 16 0
- ~.
3.
.. . . 3 IN-Y
- UNIT SHUTDOWNSTAND POWER REDUCTIONS' A~
DOCKET NO. 50-498 '.
UNIT 1 DATE' Nov. 6.'1989 COMPLETED.BYiA.P! Kent TELEPHONE 512/972-7786
. REPORT MONTH OCTOBER 1 '2 3 4 5 No. Date Type Duration Reason Method of Licensee System Component "Cause & Corrective Action to (Hours) Shutting' Event Code Code Prevent Recurrence Down Raport #
Reactor 89-10 890805 S 410.2 C 4 N/A' N/A .N/A Manual shutdown for refueling and scheduled maintenance.
89-11 891018 S 10.7 .B 1 N/A TA ~ .TRB Manual turbine trip due-to indications of water intrusion. It was determined that'the cause was faulty instrumentation and no intrusion occurred. (Reactor Critical)'
89-12 891018 S 12.7 B 9 N/A TA TRB Turbine Overspeed Test. (Reactor Critical) 1 1 2 S F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983 S: Scheduled A-Equipment Failure-(Explain) 1-Manual B-Maintenance or Test 2-Manual' Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction '4-Cont. of Existing E-Operator Training 6. License Exam -Outage' F-Administrative 5-Reduction ._ ATTACHMENT \
G-Operational Error (Explain)' 9-Other. . ST.HL-AE- 72 9 4 -
H-Other (Explain)- PAGE S OF f i
_ . . _ _ _ _ _ - - - . _ - n-____. . . - . . _ , __ ._ ___..__a
=
8 , 1 b, . . . . . - - -. ;
. 9 l
n' . -
ATTACHMENT / -
ry:
' ST-HL AE. 72 9/ '
PORVs and Safety Valves Si pggg g gp g-
- NO PORVs or-, Safety Valves were challenged during this. reporting period.- .
r F
'I i b
i s
t i
1 -
li [
T I
t
/
-- -e w
- w.
.t, h: .
ATTACHMENT 2.-
T: . ST.HL-hE 311' PAGE I OF (
L
. SOUTH TEXAS PROJECT t_ '
ELECTRIC GENERATING STATION UNIT 2 MONTHLY OPERATING REPORT
- - OCTOBER 1989 HOUSTON LIGHTING AND POWER CO, NRC DOCKET NO. 50-499 LICENSE NO. NPF-80 Reviewed B Md b General Supervisor Datu
' Reviewed By: // 87 l Pl[rfdEngineering(tanager 'Da'te l Appr'oved By: 11 , D h\85 Plant Manager- T bale #
I
'l
!^ s, !
l g
g.-
c
.e .
9 E. ATTACHMENT 2.,
Monthly Su===ry
. ST-HL AE J 2. W PAGE 1 OF (
STPECS Unit 2 began the reporting period at 100% reactor power.
Reactor power was reduced to ~58% on 10/05/89 due to indications of high winding temperatures on_Open Loop Auxiliary Cooling Water pump motors. The unit returned to full power at 0140 on 10/06/89.
On 10/13/89 at 1745 a reactor / turbine trip occurred from a high neutron flux negative rate detection on two of four power range neutron monitoring channels.
4 The unit went back on line at 0115 on 10/16/89.-
t- A Notice of Unusual Event (NOUE) was declared on 10/18/89 at 1208 when a-Feedwater Isolation Valve's Nitrogen pressure was below its technical specifi-cation value. - The NOUE was terminated at 1211 on 10/18/89 when Nitrogen pressure was restored to the' valve.
.The unit concluded the report period at 100% reactor power.
l I I
e I t
l'. I l
'l
m+
bt L
m
~~
'~
L ATTACHMENT 2
,? -
ST HL AE J11(
- ' OPERATING DATA REPORT PAGE 3 OF ( -j.
DOCKET No. 50-499 UNIT 2 DATE Nov. 3. 1989 4 COMPLETED BY A.P. Kent TELEPHONE 512/972-7786 , OPERATING-STATUS
- 1. REPORTING PERIOD: 10/01-10/31 GROSS HOURS IN REPORTING PERIOD: 745 .
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3800-MAX. DEPEND. CAPACITY (MWe-Net); 1250.6 >
DESIGN ELECTRICAL RATING (MWe-Net): 1250.6 POWER LEVEL TO WHICH RESTRICTED (IF ANY)(MWe-Net): None 3.
.4. REASONS FOR RESTRICTION (IF.ANY): N/A THIS MONTH. YR-TO DATE CUMULATIVE-
- 5. NUMBER OF HOURS REACTOR WAS CRITICAL..... 695.2 2900.8 2900.8
- 6. REACTOR RESERVE SHUTDOWN HOURS........... 0 0 0 7.. HOURS GENERATOR ON LINE.................. 689.5 2771.7 2771.7
- 8. _ UNIT R.' SERVE SHUTDOWN HOURS...-............ 0 0 0
- 9. CROSS THERMAL ENERGY CENERATED (MWt) . . . . 2579773 9258454 9258454
- 10. CROSS ELECTRICAL ENERGY GENERATED (MWH).. 873300 3124030 ,
3124030
- 11. NET ELECTRICAL ENERGY GENERATED (MWH).... 832187 2946843 2946843
- 12. REACTOR SERVICE FACTOR................... 93.3% 89.5% 89 5%
- 13. _ REACTOR AVAILABILITY FACTOR.............. 93.3% 89.5% 89.5%
- 14. UNIT SERVICE FACT 0R...................... 92.6% 85.5% 85.5%
- 15. UNIT AVAILABILITY FACTOR. .............. 92.6% 85.5% 85.5%
- 16. -UNIT CAPACITY FACTOR (Using MDC)......... 89 3% 72.7% 72.7%-
- 17. UNIT CAPACITY FACTOR (Using Design MWe).. 89.3% 72621 72.7%
- 18. UNIT FORCED OUTAGE RATE,................. 7.4% 13.0% 13.0%
,19. SHUTDOWNS SCHEDULED OVER NEX16 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Scheduled 44 day outage to begin November 4, 1989 for Bottom Mounted Instrumentation Inspection and Turbine Inspections.
- 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A
1 7a y ,
, . y c ATTACHMENT 1 AVERAGE DAILY UNIT POWER' LEVEL , HA Tg OF (
f
~
DOCKET NO. -50'499 UNIT '2 DATE Eov.-3. 1989 COMPLETED BY A.P. Kent TELEPHONE 512/972 7786 MONTH October 1 3
-DAY- AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)- (MWe Net) ^' 1- 1108 17 1233 2 1237 .18 1240 , -l 3 1194 -19 '1239 4 1238 20 1216 5 -. 1112 21 1243 6- 1239 22 1242-7- 1242 23 1243 8 124." 24 1244 9 1247 25 1235 !
i 10' _
'1247 26- 1247 ' 11' 1238 27 1246 12 1232 28 1245 3 1
13~ 901- 29 1243 14 0 30 1244 i l l l ' 15 0 31 1242 16- ~S58 m..&
.;_ ,
UNIT SHIT 1 DOWNS AND POWER REDUCTIONS ~ c DOCKET NO. 50-499
- UNIT '2' DATE Nov. 3. 1989-COMPLETED BY A.P. Kent
. TELEPHONE 512/972-7786 REPORT MONTH OCTOBER 1
No. Date Type Duretion Reason Method of Licensee System Comporent Cause 6 Corrective Action to (Hcurs) Shutting Event Code Code- Prevent Recurrence Down Report # Reactor 89-09 891005 F 0.0 A 5- N/A KV FLT Reactor power was reduced to ~58% due to indications of high winding temperatures on Open Loop Auxiliary Cooling Water Pump Motors. After the air filters on the motors were cleaned reactor power was increased. 89-10 891013 F 55.5 A 3 2-89-026 JC IB Reactor / Turbine trip occurred frt,m a high neutron flux negative rate detection on two of four power range neutron moni-toring channels. The exact cause of the detected negative rate could not be deter-mined, but has been attributed to a Control Rod dropping due to an intermit-tent high resistance connection in its stationary gripper circuit diode. The faulty diode was replaced. The root cause of the event is under investigation. 1 F: Forced Reason: Method: IEEE 805-1983 IEEE 803A-1983 S: Scheduled A-Equipment Failure (Explsin) ,1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Cont. of Existing -- E-Operator Training & License Exam Outage ~ATT/sCHMENT 1 F-Administ.rative 5-Reduction ST-HL-AE- 12. # G-Operational Errot (Explain) 9-Other PAGE y ()F 6 H-Other (Explain)
.g ?A ; ? .g .' 4 i p - If-.. ' - ATTACHMENT 2. -
u . ST-HL AE flid
PORVs and Safety Valves Sn- ry ;PAGE 6 0F # ;__
i y .No PORVs or: Safety Valves were challenged during this reporting period. n - - s f h. k b m h l 1 l l l-l l-e.. ,s i l [ }}