ML20009D172
| ML20009D172 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 07/10/1981 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20009D171 | List: |
| References | |
| NUDOCS 8107230252 | |
| Download: ML20009D172 (9) | |
Text
t, CONNECTICUT YANKEE ATOMIC POWER COMPANY BADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT NO.- 81-6 FOR THE MONTH OF JUNE 1981 810E230252 810710
~
'PDR ADOCK 05000213'
-R PDR.
___ _ ___ _b
PLANT OPERATIONS The'following is a chronological description of plant operations for the month
~
.of June 1981:
The plant was operating at full power (587 MWe) at the beginning of this report period and remained at full power until 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on June 7,1981 when a load
. reduction das commenced for a turbine stop and control valve test.
Turbine
' Control valves were satisfactorily tested at 0252 hours0.00292 days <br />0.07 hours <br />4.166667e-4 weeks <br />9.5886e-5 months <br /> on June 7, 1981 with load at 350 }G&e. Load increase was commenced at 0322 hours0.00373 days <br />0.0894 hours <br />5.324074e-4 weeks <br />1.22521e-4 months <br /> with plant reaching full load ~at 0710 hours0.00822 days <br />0.197 hours <br />0.00117 weeks <br />2.70155e-4 months <br />. The plant remained at full power throughout the
- remainder of this report period.
6-1-81'
'B' isolated phase duct cooling fan returned to service at 1441 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.483005e-4 months <br />.
f 2-81.
'A' isolated phase duct cooling fan out of service for maintenance.
6-3-81'
'B' auxiliacy S/G feed pump found' operating with steam control valve full open at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />. Tested
'A' auxiliary feed pump for avail-ability. Steam centroller to 'B' auxiliary feed pump repaired by replacing ruptured diaphragm.
'B' auxiliary feed pump retested and returned to service at 1650 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.27825e-4 months <br />.
' 6-4-81
Test ran 'A' auxiliary feed pump and removed 'E' auxiliary feed pump from service at 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br />.
'B' auxiliary feed pump retested and
[
returned 1:a service at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />.
'A' isolated phase duct cooling fan returned to service at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />. 7-81 Backwashed all condenser weter boxes while at reduced load for valve test at 0321 hours0.00372 days <br />0.0892 hours <br />5.30754e-4 weeks <br />1.221405e-4 months <br />.
6-10-81 LEG 2A out of service at 0645 for maintenance.
Retested and returned to service at-1325 hours.
6v11-81 I&c replaced power range drawer for Channel 31 at 0755 hours0.00874 days <br />0.21 hours <br />0.00125 weeks <br />2.872775e-4 months <br />.
Experienced spurious power spikes.
6-15 'A' isolated phase duct cooling fan out of service for maintenance 0730 to 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.
6-16-81
'B' auxiliary steam generator feed pump out of service for main-tenance 0702 to 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br />.
'B' charging pump out of service 0828 to 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br /> for repair of oil leak.
6-17-81
'B' HPS1 pump out of service for maintenance 0630 to 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.
-Completed slight load decrease and isolated the normal level control line from LA to 1B feedwater for repair of steam leak at 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br />.
Repaired leak and returned to full power at 1347 hours0.0156 days <br />0.374 hours <br />0.00223 weeks <br />5.125335e-4 months <br />.
6-18-81
'A' HPS1 pump out of service for maintenance at 0633 hours0.00733 days <br />0.176 hours <br />0.00105 weeks <br />2.408565e-4 months <br />.
Ratested and returned to service at 1329 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.056845e-4 months <br />.
6-24-81
. 'A' auxili.;y feed pump out of service for maintenance at 0705 hours0.00816 days <br />0.196 hours <br />0.00117 weeks <br />2.682525e-4 months <br />.
Retested and returned to service at 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br />.
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I 3PECIAL PRECAUTIONS !
Page of 2 EFFECT ON CORRECTIVE ACTION TAKEN TO PROVIDE SYSTEM OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY g ',... ' *
/
COMPONENT.
CAUSE RESULT
- OPERATION REPETITION DURING REPAIR
'B' Terry Turbine' Failure of dia-Terry Turbine None Replaced Diaphragm None Required Steam Control Valve phragm in the started,?p to.
actuator caused full speed-by old age and heat.
',B' Charging Pump No malfunction--
None flone Reset timer to more HoneRequire(
f slight set point conservative ~value
]_
drift t*
CH. 31 NIS Possible deteri-Spiking in None
.None N/A oration of detec-Channel
.{
tor, cable, and/
t or connector.
Possibly caused
{
i by heat and/or t
radiation.
I' Charging Pump Oil Leaking oil-Oil leak None Tightened coupling nut and
' A' pump available Cooler fitting--caused by resealed pipe fittings pipe Joint, sealer failure.
'A' H.P.S.I. Pump Leaking fittings, Seal water leak None Recoated fittings and
'B' pump available Seal Water caused by vibra-tightened tion and pipe joint sealer failure.
'B' H.P.S.I. Pump Leaking fittings, Seal water leak None Recoated fittings and
'A' pump available
" Seal Water caused by vibra-tightened tion and pipe joint sealer failure.
N
'a 'B' Auxiliary Feed Sight glass fail- 011 leak None Replaced sight glass
' A' pump available
, Pump ure --caused by j
fatigue h
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Page 2 Of 2
'8' EFFECT SPECIA1,IRECAljTIONS F-
,. ~ ~
ON.
ConRECTIVE ACTION TAKEN TO 1ROVIDE SYSTEM SAFE TAKEN TO PREVENT FOR 1". ACTOR SAFEIY MALFUNCTION OR COMPONENT CAUSE RESULT OPERATION REPETITTON DURING REPATR
'A' Terry furbinq' Sight glass 011 leak Hone-Replaced gasket on sight
'B' pump available Sight Glass gasket failure--
glass Reason--age.
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Switch Gear Room Reason ur.known
' Intermittent None vendor--nothing found, but while system was out of Problem was investigated by Fire watch was established; Halon System trouble alarm service.
problem disappeared.
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RE UTbik^CbbLdUS DATA MONTH: JUNE 1981 l
M, Fi M t..-.,.."W*
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M. T..i,f T. Si. f f M
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(H 9 25 DEGREES.C 6.50E+00 :
6.69E+00 :
6.90E+00 :
r
..,m,01 1.79E+01 :
5,,0N90Ciavais s ui va,w..,
-.,vm.vv A
EHLORIDES (PPM)
- <4 00E : <4 00E-02
-<4.00E-02 :
hISSOLVED OXYGEN (PPB)
. : <5.00E+00 : <5.00E+00 : <5 00E+00 :
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,a w a r m. a w a.,
w w w
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w
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=wa r ww iwi,
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. :. 7.00E-01 :
1.32E+00 :
2.00E+00 :
LITHIUM-(PPM) 2.86E+00 :
3.49E+00 :
4.33E+00 :
IOTAL GAMMA ACT.-(UC/ML)
HHHNE-t-31MT r-( UC/".L )
1.5^E ^2 :
1."OE-O?-:
2.31E-02'
- 131/I-133 RATIO 6.74E-01 :
7.96E-01 :
1.05E+00 :
}UD~(MG/ LITER) sR 3.<1.00E-02 : <1.00E-02 : <1.00E-02 :
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.- i-5.695Ebi i 5.955EbI i 5.55EEUI i p....................................................................
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^EP^TED LIOUID L' ASTE o90 CESSED ' C^.LLONS-M--1. 6?E+05
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4.41E+04
%ASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):
. AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):
2.95E-01 "RI."ARY TG-SEGONDARY LEAK-RATE 441AEb9HS-PER-MI-NU-TE-)-:
0.00E400 i
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e f-1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-213 t
Conn. Yankee UNIT Haddam Neck
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DATE July 10, 1981 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 JUNE 1981 gg DAY AVERAGE DAILY POWER LEVEL
' DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 562 17 552 562 18 556 2
564 19 553 3
564 20 552 4
552 563 21 5
550 560 22 6
554 529 23 7
553 560 24 8
552 560 25
.9 556 561 26 10 557 562 27 g
555 560 28 555 29 13 30 24 31 1.5 16 INSTRUCTIONS On this format, list the average daily unit power icvel in HWe-Net for each day in the reporting month.
Complete the nearest whole megawatt.
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150-213 UNIT 51:UTUOWNS ANDiONER REUUCT:pNS ' '
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ITNAME
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I) ATE July 10. 1981
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JUNE 1981 COMPT.ETED itY Reactor Ennineering REPG~tT MONTil 1 Et.I.I'l!ONE (203) 267-2556 J
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No unit; shutdowns or signifi, cant.
1 power reductions during the month i
of June 1981,repor. ting period.
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4 liafiihis G. Insituctioas l' l..and Iteamn:
Metliod:
4 5 5.liedulc l A l:iguipment I ailuicItaplain) l Manisal fo PrcParalum ul1)aia i
ll.M.sisitenance os Te:,i 2.Maianal Seraan.
I:iiss) Slice:S los I keince
(*.ltelnelung
.l. Auf oinalle Strain.
1 sen Itepoil l1.1 It i l'ile INilRl.C.
- 1) llegul.itoiy ltesteiction 441llica (!!aplalia)
Ulbli l tleci.ito li.inung A Iinnse I nauiinatline i
I binunnisaine Ii t Ipes.iiinn.il I s ans ll~.a pl.nlo)
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- NeN8C CPEPATINC STATUS *"hlRT COMPLETES Of KACTOR DICIIEERINCoeses
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DOCFET NO.
50 13 1.
tm!T h u t.... CONN. TANYlT ATONIC P0uCR CO.
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- 2.
PEPORT!N; PEPI13....JtrME 1901 DATE.... JULY 10, 1981 C0"PLETED BT....D. ANDER$4N. antum gag.
3.
LICE 15E3 THie*AL PCWIPmTI....lg15 TELEPHCeE f *0D 247- !56
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- 4 WAIPLA!E P ATIN;t?9M1 WEl... 600.3 l
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~ 5, E;;;N E'.ECTs!*AL PAT!NG' NET WEl... 5%)
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6.
PAI!"UN CEFENit.!LE CAPACITt(C8055 PWEl... 54Z 7.
PAI!9.M LE7Eh340LE CAPACITT(hET NEl....M5 I. IF CHANCE 3 OCCW IN CAPACITT RATIEtt!TEMS 3 TistodD4 715tNCE LAST MPORTe CIVE MASCII5G;.Dous '~~~**~~
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- 10. PEASON FOR FEST4tCT!0N. IF SAT....M/A
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PCECR LDEL TO WHICN RESTRICTED. IF ANT (NET to o....WONE THIS K PORTING PEPIOD TR. TO DATE CUMIAATIVE TO DATE 18.
MGPS IN PEPORTING PERICO 720.0 4343.0 118319.0 e 4335.8
~~ 102707.7 e ' ~
T12.~~ ieJMPER OF H09R3 THE REACTOR WAS CRITIQiL~ -~~ 7Z0.0 '
l 13.
PEACTOR PESEP'd SHUTDOWN HOUR 3 0.0 f.l.
18U.5 e 14 HOUo1 CENEPATC4 ON LINE 720.0 4326.0 17847.0 e
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tm!T PetEP'K SHUTDOWN HOUP3
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- 16.... CRM3 THEP.*AL EHEPCT CENEPATES (med.- 1310216,.... - -
- 7752702, 169304995.
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CPM 1 ELECTRICAL thEP;T CEhERATE3 (med 419967.
2553668.
554%d85T.
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- IET ELECTpfCAL ENEPOT CENGATED (mett 400227
- 2437448. ~ ~ ~ ~ -' " - ~5:15*E 4.
100.0 19.6 82.7 e 19.
UNIT SER'JICE FACTOR
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UNIT AJAILA3!LITT FACTOR 100.0 99.6 83.0 e
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UNIT CAPACITT FACTCR (USINC PDC IET)
- - ~ ~ ~ ~ ~ 100.2 ~ ~
- ~~~~-~~ ~ 101.1 "--
-- ~ ~ ~
82.6 e - - - * " * - - ~ ~ ~ ~ ~ ' "
74.4 e
- 22.'~' tm!T Ci#ACITT FACTGR (USING CER NET) 95.8 96.0 23.
UNIT F0PCED OUTA?E FATE 0.0 0.4 6.6 e
'24.-
SHUTDOWN 1 $CHEDULED 74R NEIT & MONTHS (TTPEsDATE ANO DURATIoll 0F EA00. 7.REPUEL1110 POR Coat 11.' APPROIIMATELT SEPTDISER 26, 1941f POR SIX WEEKS I
'25.- ' ' IF $HUTC0".N AT EN3 CF PEPORTING PERIO0e EST!!OTED DATE OF $TARTUP....W/A 26.
(m!T1 IN TEST STATUStPRICR TO Com'ERCIAL OPERATICN)....N0T APPLICABLE
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Conne.cticut $nkee Atomic Power Company Scheduled deste for next refueling shutdown.
s September / October 1981 3.
Scheduled date for restart following refueling Approximately six to eight weeks.
4.
(a) Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
No technical specification changes are anticipated at this ti.ne.
(b)
If answer is yes, what, in general, will these be?
N/A (c) If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to. determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
When the above stated documents are received from the fuel vendor they will be reviewed in acenrdance with 10CFR50.59 to determine if.any unreviewed safety questions are associated with the Core reload.
(d)
If no such review has taken place, when is it scheduled?
N/A-5.
' Scheduled date(s) for submitting proposed licensing action and supporting information.
There are no scheduled dates because of (4) above.
6.
Important licensing consideration associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
None
- 7. - The rumber of - fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(a) 157 (b) 38'9
~
- 8. - The present licensed spent fuel pool storage capacity and the size of any
. increase in licensed storage capreity that has been requested or is planned, in number of fuel assemblies.
1168' 9,
The projected date of the last refueling that can be discharged to the spent
.l fuci pool assuming the present, licensed ::apacity.
1994 to 1995
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