ML19210D137: 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:.%.VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION MONTHLY OPERATING REPORT MONTH Jan. | {{#Wiki_filter:. | ||
YEAR 1979 (Revised 11-05-79) | % | ||
. | |||
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION MONTHLY OPERATING REPORT MONTH Jan. YEAR 1979 (Revised 11-05-79) | |||
SUBMITTED: | SUBMITTED: | ||
\%J'A cxA SUPERIflTENDENT - OPERATIONS APPROVED:.MANAGER () | \% J'A cxA SUPERIflTENDENT - OPERATIONS APPROVED: | ||
. | |||
.OPERATING DATA REPORT DOCKET NO. 50-338 DATE 11-5-79 D**D | MANAGER () | ||
7,06 1367 7 911200 f7I | |||
.- | |||
. | |||
: 3. Licenwd Thermal Power (51Wt): | OPERATING DATA REPORT DOCKET NO. 50-338 | ||
* ' ~ ' DATE 11-5-79 D**D D 3 ] Co3!PLETED 11Y W. R. Madison | |||
947 | , | ||
gj ,J,} (1,, TELEPflONE 703_ 894-5151 OPERATING STATUS | |||
.- | |||
: 1. Unit Name: | |||
Morth Anna Notes . | |||
: 2. Reporting Period: | |||
nuaq Im WenseQ | |||
: 3. Licenwd Thermal Power (51Wt): 2775 | |||
, | |||
: 4. Nameplate Rating (Grod51We): 947 ' ' | |||
: 5. Design Electrical Rating (Net 51We): 907 | |||
: 6. 51aximum Dependable Capacity (Gross 51We): | : 6. 51aximum Dependable Capacity (Gross 51We): | ||
: 7. Sf aximum Dependable Capacity (Net SIWE): 090 | |||
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Though 7) Since Last Report, Give Reasons: | : 8. If Changes Occur in Capacity Ratings (Items Number 3 Though 7) Since Last Report, Give Reasons: | ||
N/A 9. Power Level To Which Restricted,if Any (Net 51We): | N/A | ||
N/A 10. Reasons For Restrictions,if Any: | : 9. Power Level To Which Restricted,if Any (Net 51We): N/A ._ | ||
N/A | : 10. Reasons For Restrictions,if Any: N/A | ||
: 11. ilours In Reporting Period 744 744 5,761 12. Number of Flours Reac:or Was Critical 640.7 640.7 ~5,327.5 0 0 96.8 | . . | ||
: 15. Unit Reserve Shutdown flours 0 0 0 16. Grms Thermal Energy Gener::ed (31Wil) 1,710,165 1,710,165 13, | _ | ||
: 20. Unit Availability Factor 86.1 86.1 92.5 21. Unit Capacity Factor (Using 51DC Net) | - | ||
This 51onth ._ _ Yr..to.Date Cumulative | |||
*24. Shutdowns Scheduled Over Next 6 Slonths(Type.Date.and Duration of Each): | : 11. ilours In Reporting Period 744 744 5,761 | ||
Snubber Inspection April 1979, I week | : 12. Number of Flours Reac:or Was Critical 640.7 640.7 ~ 5,327.5 | ||
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup: | : 13. Reactor Reserve Shutdown IIours 0 0 96.8 | ||
February 3,1979 | : 14. Ilours Generator On-Line 640./ 640.7 5,292.4 | ||
: 26. Units In Test Status (Prior to Commercial Operation): | : 15. Unit Reserve Shutdown flours 0 0 0 | ||
Foreca>t Achieved.INITIA L CRITICA LITY INITIAL ELECTRICITY C05151ERCI AL OPERATION 1367?)D7 ml 50-333 UNIT SHUTDOWNS AND POWER REDUCTIONS y | : 16. Grms Thermal Energy Gener::ed (31Wil) 1,710,165 1,710,165 13,9062 960 | ||
: 17. Cross Elec:rical Ener;y Generated (SiWFI) 544,465 , | |||
COMPLETED BY __lL_R._Ea discn TELEPl!CNE (703) 894-5151 | 544,465 4,444,902 | ||
.**=-No.Date-._5 y}h[f Licernee 5-r,~Cause & Corrective | : 18. Net Electrical Energy Generated (51WH) | ||
Sl 3,4TO 513,410 4.177,990 | |||
: 19. Unit Service Factor 80.I 86.I 92.5 | |||
Repacked MOV-1700 residual heat removal systun isolation valve, also outage was extended for other primary and secondary maintenance. | : 20. Unit Availability Factor 86.1 86.1 92.5 | ||
: 21. Unit Capacity Factor (Using 51DC Net) _ | |||
Entry Sheets for Liecmee C Refueling 3-Automatic Seram. | 76.8 76.8 80Tti | ||
Event Repo.t (LER) Fi!c lNUREG- | : 22. Unit Capacity Factor (Using DER Net) 76.I 76.1 80.0 | ||
0161)g E-Operator Training & License Examination F-Administotive 5 G-Operational Error (Explain) | : 23. Unit Forced Outage Rate 13.9 13.9 3.2 | ||
Exhibit I - Same Source | * | ||
*Se/77) Attached Sheet !!-Other ( E xplain) | : 24. Shutdowns Scheduled Over Next 6 Slonths(Type.Date.and Duration of Each): | ||
Snubber Inspection April 1979, I week | |||
50- | : 25. If Shut Down At End Of Report Period. Estimated Date of Startup: February 3,1979 | ||
__UllIT FLAME florth Anna | : 26. Units In Test Status (Prior to Commercial Operation): Foreca>t Achieved | ||
. | |||
INITIA L CRITICA LITY INITIAL ELECTRICITY C05151ERCI AL OPERATION 1367 ?)D7 ml | |||
o 50-333 UNIT SHUTDOWNS AND POWER REDUCTIONS y t _ borth Anna ~ | |||
DATE Il-S-79 January 1979 (Revised) COMPLETED BY __lL_R._Ea discn REPORT MONT11 TELEPl!CNE (703) 894-5151 | |||
. | |||
** | |||
= - | |||
No. Date | |||
-, | |||
- | |||
._5 y | |||
,= | |||
}c h[f | |||
:- | |||
Licernee Event 5-r, u7 c2 | |||
~ | |||
Cause & Corrective Action to S j@ -N | |||
, 3 -j ] Report : A0 ,! C Present Re.mtrence | |||
- | |||
c - | |||
5 i | |||
i I 79-01 790127 F 103.3 A* 1 LER/R0 79-012 CF VALVEX Manual reactor, turbine generator shutdown due to excessive unidenti-fied primary plant leakage. Repacked MOV-1700 residual heat removal systun isolation valve, also outage was extended for other primary and secondary maintenance. g | |||
$ | |||
GED t | |||
E@ | |||
b 2@ | |||
EB C::ta | |||
' | |||
, | |||
ul : 3 4 | |||
& F: Forced Reason: Method: Exhibit G - Instructions N S: Scheduled A-Eqmpment Fai!ure (Explain) 1 -Manual for Preparation of Data B Maintenance of Test 2-Manual Seram. Entry Sheets for Liecmee s C Refueling 3-Automatic Seram. Event Repo.t (LER) Fi!c lNUREG-o D Regulatory Restriction 4-Other ( Explain ) 0161) g E-Operator Training & License Examination F-Administotive 5 G-Operational Error (Explain) Exhibit I - Same Source N | |||
*Se/77) e Attached Sheet !!-Other ( E xplain) | |||
NOTE: Outage 79 01 | |||
Page 1 of 1 UflIT SHUTDOWil AtlD P0'.!ER REDi]CTIOllS DOCKET i;0. 50-333_ | |||
EXPLAllATI0tl SHEET REPORT !!OllTil Janirary | |||
_ __UllIT FLAME florth Anna YEAR 1979 DATE 11-5-79 COMPLETED BY W. R. f4ADIS0tl 79-01 (A) Excessive packing gland leakage from fl0V-1700, the residual heat removal system suction valve, of greater than 1 gallon per minute. | |||
Technical specifications permit primary plant unidentified leakage of 1 gpm or less. The unit was rer.oved from service and the reactor shutdown at 1641. The plant was then cooled down and depressurized. | Technical specifications permit primary plant unidentified leakage of 1 gpm or less. The unit was rer.oved from service and the reactor shutdown at 1641. The plant was then cooled down and depressurized. | ||
The maintenance was completed on 1-28-79 at 1940. The plant was heated to 547 F on 1-29-79 at 1245 and a leakrate calculation was performed. | The maintenance was completed on 1-28-79 at 1940. The plant was heated to 547 F on 1-29-79 at 1245 and a leakrate calculation was performed. | ||
Agairi leakage was excessive. | Agairi leakage was excessive. It was determined that the pressurizer spray valves were leaking between their bodies and bonnets. The plant was then cooled down and depressurized to allow maintenance. January shutdovin 78-33 continued into February 1979. | ||
It was determined that the pressurizer spray valves were leaking between their bodies and bonnets. The plant was then cooled down and depressurized to allow maintenance. January shutdovin 78-33 continued into February 1979. | 1d7309 | ||
1d7309:}} | :}} |
Revision as of 13:39, 19 October 2019
ML19210D137 | |
Person / Time | |
---|---|
Site: | North Anna ![]() |
Issue date: | 11/05/1979 |
From: | Wil Madison VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
To: | |
Shared Package | |
ML19210D121 | List: |
References | |
NUDOCS 7911200575 | |
Download: ML19210D137 (4) | |
Text
.
%
.
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION MONTHLY OPERATING REPORT MONTH Jan. YEAR 1979 (Revised 11-05-79)
SUBMITTED:
\% J'A cxA SUPERIflTENDENT - OPERATIONS APPROVED:
.
MANAGER ()
7,06 1367 7 911200 f7I
.
OPERATING DATA REPORT DOCKET NO. 50-338
- ' ~ ' DATE 11-5-79 D**D D 3 ] Co3!PLETED 11Y W. R. Madison
,
gj ,J,} (1,, TELEPflONE 703_ 894-5151 OPERATING STATUS
.-
- 1. Unit Name:
Morth Anna Notes .
- 2. Reporting Period:
nuaq Im WenseQ
- 3. Licenwd Thermal Power (51Wt): 2775
,
- 4. Nameplate Rating (Grod51We): 947 ' '
- 5. Design Electrical Rating (Net 51We): 907
- 6. 51aximum Dependable Capacity (Gross 51We):
- 7. Sf aximum Dependable Capacity (Net SIWE): 090
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Though 7) Since Last Report, Give Reasons:
N/A
- 9. Power Level To Which Restricted,if Any (Net 51We): N/A ._
- 10. Reasons For Restrictions,if Any: N/A
. .
_
-
This 51onth ._ _ Yr..to.Date Cumulative
- 11. ilours In Reporting Period 744 744 5,761
- 12. Number of Flours Reac:or Was Critical 640.7 640.7 ~ 5,327.5
- 13. Reactor Reserve Shutdown IIours 0 0 96.8
- 14. Ilours Generator On-Line 640./ 640.7 5,292.4
- 15. Unit Reserve Shutdown flours 0 0 0
- 16. Grms Thermal Energy Gener::ed (31Wil) 1,710,165 1,710,165 13,9062 960
- 17. Cross Elec:rical Ener;y Generated (SiWFI) 544,465 ,
544,465 4,444,902
- 18. Net Electrical Energy Generated (51WH)
Sl 3,4TO 513,410 4.177,990
- 19. Unit Service Factor 80.I 86.I 92.5
- 20. Unit Availability Factor 86.1 86.1 92.5
- 21. Unit Capacity Factor (Using 51DC Net) _
76.8 76.8 80Tti
- 22. Unit Capacity Factor (Using DER Net) 76.I 76.1 80.0
- 23. Unit Forced Outage Rate 13.9 13.9 3.2
- 24. Shutdowns Scheduled Over Next 6 Slonths(Type.Date.and Duration of Each):
Snubber Inspection April 1979, I week
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: February 3,1979
- 26. Units In Test Status (Prior to Commercial Operation): Foreca>t Achieved
.
INITIA L CRITICA LITY INITIAL ELECTRICITY C05151ERCI AL OPERATION 1367 ?)D7 ml
o 50-333 UNIT SHUTDOWNS AND POWER REDUCTIONS y t _ borth Anna ~
DATE Il-S-79 January 1979 (Revised) COMPLETED BY __lL_R._Ea discn REPORT MONT11 TELEPl!CNE (703) 894-5151
.
= -
No. Date
-,
-
._5 y
,=
}c h[f
- -
Licernee Event 5-r, u7 c2
~
Cause & Corrective Action to S j@ -N
, 3 -j ] Report : A0 ,! C Present Re.mtrence
-
c -
5 i
i I 79-01 790127 F 103.3 A* 1 LER/R0 79-012 CF VALVEX Manual reactor, turbine generator shutdown due to excessive unidenti-fied primary plant leakage. Repacked MOV-1700 residual heat removal systun isolation valve, also outage was extended for other primary and secondary maintenance. g
$
GED t
E@
b 2@
EB C::ta
'
,
ul : 3 4
& F: Forced Reason: Method: Exhibit G - Instructions N S: Scheduled A-Eqmpment Fai!ure (Explain) 1 -Manual for Preparation of Data B Maintenance of Test 2-Manual Seram. Entry Sheets for Liecmee s C Refueling 3-Automatic Seram. Event Repo.t (LER) Fi!c lNUREG-o D Regulatory Restriction 4-Other ( Explain ) 0161) g E-Operator Training & License Examination F-Administotive 5 G-Operational Error (Explain) Exhibit I - Same Source N
- Se/77) e Attached Sheet !!-Other ( E xplain)
NOTE: Outage 79 01
Page 1 of 1 UflIT SHUTDOWil AtlD P0'.!ER REDi]CTIOllS DOCKET i;0. 50-333_
EXPLAllATI0tl SHEET REPORT !!OllTil Janirary
_ __UllIT FLAME florth Anna YEAR 1979 DATE 11-5-79 COMPLETED BY W. R. f4ADIS0tl 79-01 (A) Excessive packing gland leakage from fl0V-1700, the residual heat removal system suction valve, of greater than 1 gallon per minute.
Technical specifications permit primary plant unidentified leakage of 1 gpm or less. The unit was rer.oved from service and the reactor shutdown at 1641. The plant was then cooled down and depressurized.
The maintenance was completed on 1-28-79 at 1940. The plant was heated to 547 F on 1-29-79 at 1245 and a leakrate calculation was performed.
Agairi leakage was excessive. It was determined that the pressurizer spray valves were leaking between their bodies and bonnets. The plant was then cooled down and depressurized to allow maintenance. January shutdovin 78-33 continued into February 1979.
1d7309