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=Text=
=Text=
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 9, 1977 Mr. William McDonald, Director                      Serial No. 188/021974 Office of Management Information and                  PO&M/TAP:dgt Program Control                                Docket Nos. 50-280 U. s. Nuclear Regulatory Cormnission                                              50-281 Washington, D. C. 20555                            License Nos. DPR-32 DPR-37
                                                      -
RICHMOND, VIRGINIA 23261 May 9, 1977 Mr. William McDonald, Director                      Serial No. 188/021974 Office of Management Information and                  PO&M/TAP:dgt Program Control                                Docket Nos. 50-280 U. s. Nuclear Regulatory Cormnission                                              50-281 Washington, D. C. 20555                            License Nos. DPR-32 DPR-37


==Dear Mr. McDonald:==
==Dear Mr. McDonald:==
Line 24: Line 22:
Operating infonnation for Surry Power Station, Unit Nos. 1 and 2, for the month of April 1977 is attached.
Operating infonnation for Surry Power Station, Unit Nos. 1 and 2, for the month of April 1977 is attached.
Very truly yours,
Very truly yours,
                                                    .  ;-;
                                                   ..... * * ;. "( *'. { :_ l C ,  ./
                                                   ..... * * ;. "( *'. { :_ l C ,  ./
j C. M. Stallings Vice President-Power Supply and Production Operations Attachments cc: Mr. Nonnan C. Moseley 771320110
j C. M. Stallings Vice President-Power Supply and Production Operations Attachments cc: Mr. Nonnan C. Moseley 771320110
Line 75: Line 72:
                                                                                 . CORRECTIVE ACTIONS/COMMENTS Unit shutdown as directed by NRC e
                                                                                 . CORRECTIVE ACTIONS/COMMENTS Unit shutdown as directed by NRC e
to inspect S/G's~ Unit shutdown at end of report period. Time reflects one hour time change on 0200 4/24/77 *
to inspect S/G's~ Unit shutdown at end of report period. Time reflects one hour time change on 0200 4/24/77 *
                                                    ..
(1) REASON                          (2) METHOD A**EQUIPMENT fAILURE (EXPLAIN)      I-MANUAL 8- MAINT. OR TEST C- REFUELING D-REGULATORY RESTRICTION E-OPERATOR TRAINING AND LICENSE EXAMINATION f-ADMINISTRATIV.1:::
(1) REASON                          (2) METHOD A**EQUIPMENT fAILURE (EXPLAIN)      I-MANUAL 8- MAINT. OR TEST C- REFUELING D-REGULATORY RESTRICTION E-OPERATOR TRAINING AND LICENSE EXAMINATION f-ADMINISTRATIV.1:::
G--Ol'ERATIONAL ERROR 2-MANUAL SCRAM 3-AUTOMATIC SCRAM          -
G--Ol'ERATIONAL ERROR 2-MANUAL SCRAM 3-AUTOMATIC SCRAM          -
Line 82: Line 78:


==SUMMARY==
==SUMMARY==
:


e UNlTSurry Unit {12 DATE?fay                2, 1977 COMPLETEDBYE.                        P. DeWandel DOCKET N0._5_0_-_2_8...;;;l______
e UNlTSurry Unit {12 DATE?fay                2, 1977 COMPLETEDBYE.                        P. DeWandel DOCKET N0._5_0_-_2_8...;;;l______
Line 109: Line 104:
August 1977 - Steam Generator Inspection - 3 week~, -S~pt~ber 1"377 - Refueling J7.  *1F SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP/:__                    .*_-;__....
August 1977 - Steam Generator Inspection - 3 week~, -S~pt~ber 1"377 - Refueling J7.  *1F SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP/:__                    .*_-;__....
_.-_'~..,....-__
_.-_'~..,....-__
                                                                                                                    .*_-.._;_ _ _ _ _ _ __
: 18. UNITS IN TEST STATUS (PRIOR TO COM~1ERCIAL OPERATION) REPORT THE FOLLOWING; DA TE LAST        ~ATE FORECAST        ACHIEVED INITIAL CRITICALITY
: 18. UNITS IN TEST STATUS (PRIOR TO COM~1ERCIAL OPERATION) REPORT THE FOLLOWING; DA TE LAST        ~ATE FORECAST        ACHIEVED INITIAL CRITICALITY
                                                                   . INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION (1)    REACTOR AVAILABILITY FACTOR = HOURS REACTOR WAS CRITICAL                          X 100 HOURS IN REPORTING PERIOD (2)    UNIT AVAILABILITY FACTOR              = _H_O_U_R_S_G_E_N_E_R_A_TO_R_O_N_L_IN_E_ _ X lOO HOURS IN REPORTl~G PERIOD NET ELECTRICAL POWF.R GE!'IERATED (3)
                                                                   . INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION (1)    REACTOR AVAILABILITY FACTOR = HOURS REACTOR WAS CRITICAL                          X 100 HOURS IN REPORTING PERIOD (2)    UNIT AVAILABILITY FACTOR              = _H_O_U_R_S_G_E_N_E_R_A_TO_R_O_N_L_IN_E_ _ X lOO HOURS IN REPORTl~G PERIOD NET ELECTRICAL POWF.R GE!'IERATED (3)
Line 115: Line 109:
* MAX. DEPENDAIJLI:. (:APACITY l~!Wc*NE.T) X HOURS IN Rl:.PORTINli PERIOD FORCED OUTAGE HOURS (4)    t,JNIT FORCED Ol1TAGE RATE            C                                                                                  XlOO HOURS GENERA TOR ON LINE+ FORCED OUTAGE HOURS
* MAX. DEPENDAIJLI:. (:APACITY l~!Wc*NE.T) X HOURS IN Rl:.PORTINli PERIOD FORCED OUTAGE HOURS (4)    t,JNIT FORCED Ol1TAGE RATE            C                                                                                  XlOO HOURS GENERA TOR ON LINE+ FORCED OUTAGE HOURS


                                          *-*                                        -*
DOCKET NO.      _s_o_-2_8_1_ _
DOCKET NO.      _s_o_-2_8_1_ _
UNIT Surry /!2 DATE May 2, 1977 COMPLETED-BYE. P
UNIT Surry /!2 DATE May 2, 1977 COMPLETED-BYE. P
Line 124: Line 117:
Compute to the nearest whole megawatt.
Compute to the nearest whole megawatt.
* These figures will be used to plot a. graph for each reporting month. Note that by using maximum dependable capacity for the net electrical rating of the unit, there may be occasions when the daily average* power level exceeds the l 00% _line (or the restrkted power level line). In such cases, the average daily unit power output sheet should be foo~noted to cxpbin the apparen~ anomaly:
* These figures will be used to plot a. graph for each reporting month. Note that by using maximum dependable capacity for the net electrical rating of the unit, there may be occasions when the daily average* power level exceeds the l 00% _line (or the restrkted power level line). In such cases, the average daily unit power output sheet should be foo~noted to cxpbin the apparen~ anomaly:
,_ .. ,,..
                                                                                                                  '*,,
                                                                                                                  ;,
                                                                                                                  *, '
T.
T.


                                                                                                                              . '
DOCKET NO.        50-28\_ __
DOCKET NO.        50-28\_ __
UNIT SHUTDOWNS                            UNIT NAME      Surry f/2 DATE May 2, 1977 COMPLETED BYE. P~ DeWandel REPORT MONTH      APRIL 1977 TYPE                                    METHOD OF  .
UNIT SHUTDOWNS                            UNIT NAME      Surry f/2 DATE May 2, 1977 COMPLETED BYE. P~ DeWandel REPORT MONTH      APRIL 1977 TYPE                                    METHOD OF  .
                                                                                                                              -
F*FORCED  DURATION                    $HUTTING DOWN NO. DATE  S-SCHEDULED  (HOURS)    REASON (1)      THE REACTOR (2)          CORRECTIVE ACTIONS/COMMENTS 2-1  4/1/77      F      248. 5        A                  1          Primary to Secondary Leakage; the unit was shut down from beginning of the montl for inspection. CRDH problems we_re also experienced during recovery. Two CRDM's were replaced.
F*FORCED  DURATION                    $HUTTING DOWN NO. DATE  S-SCHEDULED  (HOURS)    REASON (1)      THE REACTOR (2)          CORRECTIVE ACTIONS/COMMENTS 2-1  4/1/77      F      248. 5        A                  1          Primary to Secondary Leakage; the unit was shut down from beginning of the montl for inspection. CRDH problems we_re also experienced during recovery. Two CRDM's were replaced.
2-2  "4/23/77      F        8.3        H                    3        Unit tripped from Hi-Hi S/G level during ramp down to perform PT-29.1 (Turbine*
2-2  "4/23/77      F        8.3        H                    3        Unit tripped from Hi-Hi S/G level during ramp down to perform PT-29.1 (Turbine*
Valve Freedom Test)            , .
Valve Freedom Test)            , .
                                      ..
(I) REASON                          (2) METHOD A* -EQUIPMENT FAILURE (EXPLAIN)    I-MANUAL B-MAINT. OR TEST                    2-MANUAL C- REFUELING D-REGllLATORY RESTRICTION E-Ol'ERATOR TRAINING AND SCRAM 3-AUTOMATIC SCRAM e
(I) REASON                          (2) METHOD A* -EQUIPMENT FAILURE (EXPLAIN)    I-MANUAL B-MAINT. OR TEST                    2-MANUAL C- REFUELING D-REGllLATORY RESTRICTION E-Ol'ERATOR TRAINING AND SCRAM 3-AUTOMATIC SCRAM e
LICENSE EXAMINATION F-ADMINISTRATIVE
LICENSE EXAMINATION F-ADMINISTRATIVE
                                                                                                              .
..                                                                          . G--Ol'ERA TIONAL ERROR (EXPLAIN)
..                                                                          . G--Ol'ERA TIONAL ERROR (EXPLAIN)
H-OTIIER (EXPLAIN)
H-OTIIER (EXPLAIN)

Latest revision as of 17:14, 22 February 2020

Submit Monthly Operating Report for the Month of April 1977
ML19105A316
Person / Time
Site: Surry  Dominion icon.png
Issue date: 05/09/1977
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: Mcdonald W
Office of Nuclear Reactor Regulation
References
Serial No. 188/021974
Download: ML19105A316 (7)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 9, 1977 Mr. William McDonald, Director Serial No. 188/021974 Office of Management Information and PO&M/TAP:dgt Program Control Docket Nos. 50-280 U. s. Nuclear Regulatory Cormnission 50-281 Washington, D. C. 20555 License Nos. DPR-32 DPR-37

Dear Mr. McDonald:

Operating infonnation for Surry Power Station, Unit Nos. 1 and 2, for the month of April 1977 is attached.

Very truly yours,

..... * * ;. "( *'. { :_ l C , ./

j C. M. Stallings Vice President-Power Supply and Production Operations Attachments cc: Mr. Nonnan C. Moseley 771320110

.e

- UNIT Surry Unit Ill DATE~?_1a~y_2~,_1_9_7_7__

COMPLETED BY E. P. DeWan<lel DOCKET No._s_o_-_2_s_o_____

OPERATING STATUS

l. REPORTI!',G PERIOD: _ _0_0_0_1_7_7__,04=0:--:1::------- THROUGH _ _ _2_4_0_0_7_70_4_3_0_ _ _ __

HOURS IN REPORTING PERlOD: _ _7_1_9_ _ _"""'""'~------------------.,.....,,...-

2. CUR RE NTL Y AUTHORIZED POWER LEVEL (MWth) 2441 MAX. pEPENDABL£ CAPACITY (MWe-NETJ
  • 775
3. LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED (IF ANY) ( M W e - N E T ) : - - - - - - - - - -
4. REASONS FOR RESTRICTION (IF ANY):

THIS CUMULATIVE REPORTING PERIOD YR TO DATE TO DATE S. HOURS REACTOR WAS CRITICAL. ......****** 254~ ~

  • 1849.2 24,403.6
6. REACTOR RE~ER VE SHUTDOWN HOURS ******* 0 0 0
7. HOURS GENERA TOR ON LINE .....*.******** 254.6 1780.0 232680.0
8. UNIT RESERVE SHUTDOWN HOURS .**.******* 0 Q 0
9. GROSS THER~iAL ENERGY GENERA TED (MWH) .*......************* 619,793 4,301,804 53,390,160
10. GROSS ELECTRICAL ENERGY GENERATED (~IWH) ..**.*.*********** ; ** 204,835 1,428,015 17,506,378
11. NET ELECTRICAL ENERGY GENERATED (MWH) *...*.*******.*************** 195,185 1,360,299 16,604,064
12. REACTOR AVAILABILITY FACTOR (1) .******** 35.4% 64.2% . 63. 9%
13. UNIT AVAILABILITY FACTOR (2) **..*.****** 35. 4 ~~ 61. 8% 62.0%
14. UNIT CAPACITY FACTOR (3) ....*..***.**** 35.0% 61.0% 56.1%

1S. UNIT FORCED OUTAGE RATE (4) .....******* 0% 4.5% 20.9%

16. SHUTDOWNS SCHEDULED TO BEGIN IN NEXT 6 MONTHS (STATE TYPE, DATE, ASD DURATION OF EACH):

Tnspectjon of Steam Generators - 9/10/77 for 3 weeks

17. iF SHUT DOWN AT END OF REPORT PERJOD. ESTl~IATED DATE OF STARTUP: _ _ _ 5_/8_*_/_7_7_______
18. UNJTS IN TEST STATUS (PRIOR TO CO~IMERCIAL OPE RATION) REPORT THE FOLLOWING:

DATE LAST DATE FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION

'HOURS REACTOR WAS CRITICAL (1) REACTOR AVAILABILITY FACTOR = X 100 HOURS IN REPORT!:SG PERIOD HOURS GENERATOR ON LINE (2) llNJT AVAlLABILITY FACTOR = ------------x HOURS IN REPORTl:-:_G PERIOD 100 NET ELECTRICAL POWER GENERATED (3). UNIT CAPACITY FACl"OR "'

MAX. DEPENDABLI:. CAPACITY (MWc-t-;ET) X HOURS IN REPORTING PERIO!)

F'ORCED OUT AGE HOURS (4) UNIT FORCED Ol'T AGE RA TE C HOURSGENERATORO-S-.L-1-~-E-+_F_O-RC-£-.D-O_U_T_A_G_E_l_iO-U-,R-S--XlOO

.e e DOCKET NO. 50-280 UNIT Surry #1 DATE May 2, 1977 COMPLETED BY E. P. DeWandel

. AVERAGE DAILY UNIT POWER LEVEL MONTH __AP_R_I_L_1_9_7_7_ _ _-,..-

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-net) DAY (MWe-net) 773.5 0 1 17 768.6 0 2 18

. 768. 7 0 3 19 4 769.0 20 0 5 770. 3 . 21 0 6 77li. 8 22 0 7 770.2 23 0 8 769.0 24 0 9 770.7 25 0 10 769.4 26 0 428.8 0 11 27 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 16 0 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS On this fonn, list the average daily unit power level in l\i\Ve-net for each day in the reporting month.

Compute to the nearest whole megawatt.

  • TI1cse figures will be used to plot a graph for each reporting month. Note that by using maximum dependable capacity for the net electrical rating of "the unit, there may be occasions when the daily average power l~vcl exceeds the 100% line (or the restricted power level line). In such cases, the average daily unit power output sheet should be footno.ted to explain the apparent anomaly.

I .

DOCKET NO. 50-280 UNIT SHUTDOWNS UNIT NAME Surry Ill DATE~r_1a~y-*_2~,_1_9_77~-

COMPLETED BY _,...E_._P_._n_e_W_a_n_de_l REPORT MONTH APRIL 1977 TYPE METHOD OF *,

F-FORCED DURATION ~HUTTING DOWN NO.

I-1 DATE 4/11/T S-SCHEDULED s

(HOURS) 464.4 REASON (1)

D THE REACTOR (2) 1

. CORRECTIVE ACTIONS/COMMENTS Unit shutdown as directed by NRC e

to inspect S/G's~ Unit shutdown at end of report period. Time reflects one hour time change on 0200 4/24/77 *

(1) REASON (2) METHOD A**EQUIPMENT fAILURE (EXPLAIN) I-MANUAL 8- MAINT. OR TEST C- REFUELING D-REGULATORY RESTRICTION E-OPERATOR TRAINING AND LICENSE EXAMINATION f-ADMINISTRATIV.1:::

G--Ol'ERATIONAL ERROR 2-MANUAL SCRAM 3-AUTOMATIC SCRAM -

.,. (EXPLAIN) 11-0TIIER (EXl'I.AIN)

I

SUMMARY

e UNlTSurry Unit {12 DATE?fay 2, 1977 COMPLETEDBYE. P. DeWandel DOCKET N0._5_0_-_2_8...;;;l______

OPERA TING ST ATUS

1. REPORTING PERIOD: _ _0_0_0_1_7_70_4_0_1_ _ _ _ _ _ THROUGH _ _ _ _2_4_0_0_7_70_4_3_0_ _ __

HOURS IN REPORTING PERIOD: __7_;1;:..;;9_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

2. CURRENTLY AUTHORIZED POWER LEVEL (~1Wth) 2441 MAX. pEPENDABLE CAPACITY (~1We-NET) ___7a...7'-'5---
3. LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED (If ANY) (MWe-NETl=----------
4. REASONS FOR RESTRICTION (iF ANY):

THIS C'JMULATIVE REPORTING PERIOD YR TO DATE TO DATE S. HOURS REACTOR WAS CRITICAL *..********** 474.0 145Ll 21,770.0

6. REACTOR RESERVE SHUTDOWN HOURS ..***** 0 0 0
7. HOURS GENERATOR ON LINE *..************ 1433.6 21,379.0
8. UNIT RESER VE SHliTDOWN HOURS .******.*** 0 0 0
9. GROSS THERMAL ENERGY GENERATED (MWH) .**.****** , * , * , * * * * *
  • 1,117,303 3,386,703 48,731,330
10. GROSS ELECTRICAL ENERGY

<iENERATED (M',VH) * * * * * * * * * * * * * * * * * * * *

  • 367,110 1,127,370 15,993,744
11. NET ELECTRICAL ENERGY GENERATED (MWH) ***************.*** ~,, *** , *** 349,246 1,071,009 *15,166,711
12. REACTOR AVAILABILITY FACTOR (1) ******* ;
  • 65.9% so. 4r: 62.1%
13. UNIT AVAILABILITY FACTOR (2) .*. ***.****** 64 ,3% fl.2.8% 61. Q%
14. UNIT CAPACITY FACTOR (3) ..**.********** 62.7% ~s. o;~ 55.8%

IS.* UNIT FORCED OUTAGE RA TE (4) ...*******.* 35.7% 50.2% 28.0%

. 16. SHUTDOWNS SCHEDULED TO BEGIN IN NEXT 6 MONTHS (STATE TYPE, DATE, AND DURATION QEEACH):

August 1977 - Steam Generator Inspection - 3 week~, -S~pt~ber 1"377 - Refueling J7. *1F SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP/:__ .*_-;__....

_.-_'~..,....-__

18. UNITS IN TEST STATUS (PRIOR TO COM~1ERCIAL OPERATION) REPORT THE FOLLOWING; DA TE LAST ~ATE FORECAST ACHIEVED INITIAL CRITICALITY

. INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION (1) REACTOR AVAILABILITY FACTOR = HOURS REACTOR WAS CRITICAL X 100 HOURS IN REPORTING PERIOD (2) UNIT AVAILABILITY FACTOR = _H_O_U_R_S_G_E_N_E_R_A_TO_R_O_N_L_IN_E_ _ X lOO HOURS IN REPORTl~G PERIOD NET ELECTRICAL POWF.R GE!'IERATED (3)

  • UNIT CAPACITY FACTOR
  • MAX. DEPENDAIJLI:. (:APACITY l~!Wc*NE.T) X HOURS IN Rl:.PORTINli PERIOD FORCED OUTAGE HOURS (4) t,JNIT FORCED Ol1TAGE RATE C XlOO HOURS GENERA TOR ON LINE+ FORCED OUTAGE HOURS

DOCKET NO. _s_o_-2_8_1_ _

UNIT Surry /!2 DATE May 2, 1977 COMPLETED-BYE. P

  • DeWandel AVERAGE DAILY UNIT PO'\-\'ER LEVEL MONTH ___AP~R_I_L_l_9_7_7_______

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-net) DAY (MWe-net) 1 0 17 765.3 0 766.0 2 18 0 .. 766.3 3 19 4 0 20 766.1 5 0 21 76704 6 0 22 767.4 7 0 23 .750. 6 0 24 398.7 8

0

  • 762. 2 9 25 10 0 26 764.0 11 400.0 27 766.1 12 762.S 28 76605 13 764~9 29 764.0 14 762 2 30 765.1 15 762.6 31 16 723.8 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS On this form, list the average daily unit" power le--cl in MWc-net for each day in the reporting month.

Compute to the nearest whole megawatt.

  • These figures will be used to plot a. graph for each reporting month. Note that by using maximum dependable capacity for the net electrical rating of the unit, there may be occasions when the daily average* power level exceeds the l 00% _line (or the restrkted power level line). In such cases, the average daily unit power output sheet should be foo~noted to cxpbin the apparen~ anomaly:

T.

DOCKET NO. 50-28\_ __

UNIT SHUTDOWNS UNIT NAME Surry f/2 DATE May 2, 1977 COMPLETED BYE. P~ DeWandel REPORT MONTH APRIL 1977 TYPE METHOD OF .

F*FORCED DURATION $HUTTING DOWN NO. DATE S-SCHEDULED (HOURS) REASON (1) THE REACTOR (2) CORRECTIVE ACTIONS/COMMENTS 2-1 4/1/77 F 248. 5 A 1 Primary to Secondary Leakage; the unit was shut down from beginning of the montl for inspection. CRDH problems we_re also experienced during recovery. Two CRDM's were replaced.

2-2 "4/23/77 F 8.3 H 3 Unit tripped from Hi-Hi S/G level during ramp down to perform PT-29.1 (Turbine*

Valve Freedom Test) , .

(I) REASON (2) METHOD A* -EQUIPMENT FAILURE (EXPLAIN) I-MANUAL B-MAINT. OR TEST 2-MANUAL C- REFUELING D-REGllLATORY RESTRICTION E-Ol'ERATOR TRAINING AND SCRAM 3-AUTOMATIC SCRAM e

LICENSE EXAMINATION F-ADMINISTRATIVE

.. . G--Ol'ERA TIONAL ERROR (EXPLAIN)

H-OTIIER (EXPLAIN)

SUMMARY

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