ML19095A323

Submit Operating Report for the Month of July, 1976

ML19095A323
Person / Time
Site:	Surry
Issue date:	08/02/1976
From:	Dewandel E Virginia Electric & Power Co (VEPCO)
To:	Office of Nuclear Reactor Regulation
References
Download: ML19095A323 (3)

Text

I.. -

• ~:

OPERATING STATUS.

l.

REPORTING PE RIOD: __ o-'-o_o'--'1"--_-'-7..:..6-C;.0 __

7-"-0=1~. -----.;...,/~

HOU RS IN R EPO R Tl NG PER 10 D: __

_;7:._4-'--4-'------:::-:-:~-~~1JS"tre;;:::;:;;:=;f"fi~~-----___:-=::-::--

2.

CLIRRENTLY AUTHO~IZED POWER LEVEL (MWth) 2441 B

APACITY (MWe*NETJ 788.

3.

LOWEST POWER LEVEL TO WHICH SPECIFICALLY RESTRICTED (IF ANY) (MWe-NET): _________ _

4.

REASONS FOR*RESTRICTION (IF ANY):

THIS REPORTING PERIOD S.

HOURS REACTOR WAS CRITICAL......... :...

6.

REACTOR RESERVE SHU1DOWN HOURS.....*.

7.

HOURS GENERA TOR ON LINE...............

8.

l'NIT RESER VE SHUTDOWN HOURS.*.*.*..*..

9.

GROSS THER~tAL ENERGY GENERATED (~1WH).*....**. ~ *..**..*.

~ **

10.

GROSS ELECTRICAL ENERGY GENERATED (:-V1WH)........ :............

l l.

NET ELECTRICAL E~~ERGY GENERATED (MWH) 12.. REACTOR AVAILABILITY FACTOR {I)..*. *...**

13.

U.NIT AVAILABILITY FACTOR (2) :...........

UNIT CAPACITY FACTOR (3)...............

UNIT FORCED OUTAGE RATE (4)............

568.8 0

565.1 0

1,322,138 417,655 395.817 76.5%

__ l.6_Jf%

67. 5~~

24.1%

CUMULATIVE YR TO DATE TO DATE

~~2.7 202979.1 0

0 42453.6 20)298.l 0

0 10,627,132 45,409,820 3,440,915.

14,892,458

~_,1.Z_Q_,]37 14.117,217 87.7%

66.3%

sz '] %

__ 6.L2.%_

81. 2%

56'. 6%

12.8%

22.5%

14.

15.

16.

SHUTDOWNS SCIIEDULED TO BEGIN IN NEXT 6 ~!ONTHS (STATE TYPE, DATE, AND DlJRATION OF EACH):

Refueling - October 15,.1976 - 6 weeks

17.

IF SHUT DOWN AT END.OF REPORTPt.RIOD, ESTIMATED DATE OF STARTUP:_:_N.1.../..:...1\\'-----------

18.

UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) REPORT THE FOLLOWING:

(1)

REACTOR AVAILABILITY FACTOR (2)

L'NITAVAILABIL!TY FACTOR (3)

UNIT CAPACITY FACTOR (4)

UNIT FORCED OUTAGE RATE INITIAL CRITICALITY INITIAL ELECTRICAL POWER GENERATION COMMERCIAL OPERATION HOURS REACTOR WAS CRITICAL HOURS IN REPORnNG PERIOD HOURS GENERATOR ON 1.INE HOliRS IN REPORTING PERIOD x 100 x 100 DATE LAST DATE FORECAST ACHIEVED 8400 NFT ELf.C'TRICr\\'L POWER GENERATED

--'--~~~~--~------~

MAX. DEPENDABLE CAPACITY (M\\\\'c-NET) X HOURS IN Rl'J'ORTING l'EKlOD

.l*,,

FORCED OUTAGE HOURS ______

... __... _------X JOO HOURS GESERATOR ON LINE+ FORCED OUT,\\GE HOURS

f

~

DOCKET NO. 50 __ -_28_0 __ _

UNIT Sur~y. #1 DATE August 2, 1976 COMPLETED BY E. P. Dei-landel AVERAGED.AJLY UNIT POWER LEVEL MONTH July, 1976 AVERAGE DAILY POWER LEVEL DAY (M\\'.Ye-net)

AVERAGE DAILY POWER LEVEL DAY (MWe-net) 1 720.4 17 a*

2 723 2 18 3

727.0 19 0

4 725.0 20 0

5 722.9 21 0

6 722.8 22 284.0 7

699.7 23 596.0 8

723.9 24 400.0 9

723.6 25 727.9 10 723. 6 26 652.7 11 726.8 27 751.9

. 12 723.9 28 748.6 13 726.8 29 747.2 14 714.3

30.

15 4.1 31 737.3 738.9 16 0

DAILY UNIT POWER LEVEL FORM INSTRUCTIONS On this form, list the average daily unit po\\yer level in M\\Ve-net for each day in the reporting month.

Compute to the nearest whole megawatt; These figures will be 'used to plot '1 gr*aph for* each reporting month'. Note that by using m:iximum dependable capacity for the net electrical ratiilg of the unit, there may be occasions when the daily average power level exceeds the l 00% line (or. th:e restricted power level line). In such cases, tht:

average daily unit power output sheet should be footnoted to explain the app:i.rent a.nomaly.

"[

DOCKET NO. 50'.""280 UNIT SHUTDOWNS UNIT NAME Surry #1 DATE Aug List 1, 1976 COMPLETED BY E. p. OeV/andel REPORT MONTH July,* 1976 TYPE METHOD OF F*FORCED DURATION

. ~HUTTING DOWN NO.

DATE S-SCHEDULED (HOURS)

REASON (1)

THE REACTOR (2).

CORR.ECTIVE ACTIONS/COMMENTS

~+-----+-~-+--~-+-~-4-~~~-+--~~~~_c__~~-

76-8 7 /15/76 F-Forced 76-9 7 /26/76 F-Forced

SUMMARY

177.5 A

1.4 H

Manual & Automatic Scrc.m Automatic Scram A-Primary to Secondary leaks.in A,B, & C S/G's. An automatic trip occurred dur-ing manual shutdown due to *feedwater control system sensitivity. Repaired 1 eCI ks.

H-A~tomatic Trip during protection logic testing resulting from Rx trip bkr.

By-pass bkr. position indicator.malfunc-tiona Corrective action will be initiat~

ed next refueling outage.

(I) REASON (2) ~.\\ET! !OD A EQUm.tENT FAILUltE (EXPLAIN) li

• MAINT. Olt TEST C-REFt;ELING D-IU:GllLATOR Y RESTRICTION

£-OPERATOR TRAINING AND LICENSE EXAMINATION F-ADMINlSTRATIVE G--OPERA TIONAL ERROR (EXPLAIN)

H--OTllER (EXPLAIN)

I-MANUAL 2-MANUAL SCRAM 3-ALITOMATIC SCRAM