ML19347B574
| ML19347B574 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/10/1980 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML19347B573 | List: |
| References | |
| NUDOCS 8010150369 | |
| Download: ML19347B574 (9) | |
Text
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l CONNECTICUT YM;KEE ATCMIC POWER COMPMiY I
IIADDMI NECK PLANT IlADDAM, CONNECTICUT 4
MONTilLY OPERATING REPORT NO. 80-9 i
FOR TIIE MONTil 0F SEPTDGER, 1980 O
801015 c. 349
4 l
PLANT OPERATIONS 1
The following is a chronological description of plant Operations for the month of September, 1980.
9/1/80 The plant was operating at 100% full power at the beginning of the month.
l 9/3/80 At 1620 hrs, Bank "B" rods were found to be moving with Bank "A" rods with selector switch in Bank "A" position during routine Control Rod exercise.
Rod 4
control system repaired and retested satisfactorily at 1905 hrs.
9/4/80 Power range Channel 32 out of service at 0955 hrs.
Channel 32 repaired and returned to service at 1446 hrs.
i 9/9/80 Load runback to 65% full power occurred at 1239 hrs.
During investigation of a 480V ground on Bus 5 the load was transferred from Bus 5 to Bus 6.
Contacts on an SDX D1 relay in the load runback circuit did not fully make up following the transfer causing a load runback to occur. The contacts were cleaned and the circuit was successfully tested. The plant i
was returned to full power at 1805.
9/10/80 EG-2A was out of service due to a control power failure alarm at 2045 hrs.
" Start one" breaker was repaired. EG-2A retested and returned to service at 1100 hrs. on 9/11/80.
9/26/80 Commenced load reduction to take plant off line for turbine balance program at 2301 hrs.
4 j
9/27/80 Plant wassoff line at 0539 hrs.
9/29/80 Cencrator was phased to line at 2226 hrs. following five balance moves in the exciter, main generator and H.P. Turbine.
1 9/30/80 Load was at 150 MWe and holding for steam generator chemistry at 0019 hrs.
Commenced load increase from 25% power at 1413 hrs.
Plant was at 90% full power and increasing to 100% full power at the end j
of this report period.
f I
l I'
~ - - -
EFFECT SPECIAL PRECAUTIONS.
SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFEIY OR COMPONENT CAUSE RESULT.
OPERATION REPETITION DURING REPAIR Power Range 32 Full power Load runback None Replaced drawer wi.th spare Load runback jumper amplifier and Ili Trip installed during change drifting Sig. period-over ically coming in.
No actual l'oad runback occurred as 2 channels are required to function RMS 34 Grounded cable No reading None Replaced cable Local monitoring Spent Fuel Pit Monitor Power Range 31.
Unknown 111 Trip coming None Replaced drawer with spare Load runback jumper in randomly installed during change over Letdown flow Dirty nozzle Low letdown None Cleaning nozzle None indicator in transmitter flow indication
- 1 FU Reg. Valve Packing Leak Valve Sticking None Replaced valve.
Found Aux. Feed in oper.
shaft galled.
Replaced stem, plug and rcpacked MA 1269 Sticky Relay Bank B Rods None Cleaned and tested relay None required Rod Control followed Bank A with Bank A selected a
MA 1320,'MA 1321 III resistance Spurious load None Replaced relay SDX-D1 None Required MA 1287 contact on SDXD1 runback Load Runback system Relay SDXD1 relay failed itA 1290 Age Start 1 breaker None Replaced breaker None--redundant start EC2A inoperable circuit available (would not close)
I
EFFECT SP".CI AL P:U: CAUTIONS 3 ts;E.i ON CORRECTIVE ACTION TAKEN TO PRO'JIDE OR
(
MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFE W-REPETITION DURING RTPAI.h COMPONENT-CAUSE RESULT OPERATION MA 1310 Faulty pulser Slave cycler None Replaced pulser None required Rod Control System failure alarra Pulser Unit MA 1328 Loose Shifted to None Installed new normal None required--alternate Semi Vital Bus connections in alternate supply supply transformer source available 1ormal Supply normal supply transformer O
t
]
=1 CONNECTICUT YANKEE REACTOR COOLANT DATA 110 NTH: SEPTEMBER 1980 EACTOR COOLANT ANALYSIS MINIhuM AVERAGE MAXIMUM 110 25 DEGREES C 5.81E+00 :
6.20E-100 :
6.45Ef00 :
)
ONDUCTIVITY (UMHOS/CM) 7.10E+00 :
1.54E+01 :
2.50E+01 :
HLORIDES ( PPri)
- <4.00E-02 : <4.00E-02 : <4.00E-02 :
ISSOLVED OXYGEN (PPB)
- <5.00E+00 : <5.00E+00 : <3.00E+00 :*
ORON (PPM) 1.01Et03 :
1.10E+03 :
1.35E103 1
1 ITHIUM (PPM) 7.50E-01 1.64Et00 :
2.50E+00 :
OTAL GA?1MA ACT. (UC/ML) 9.26E-01 :
3.06E+00 :
4.12E+00 :
30 DINE-131 ACTE (UC/ML) 1.11E-02 :
1.82E-02 :
2.16E-02 :
3-131/I-133 RATIO 7.10E-01 :
7.81E-01 :
0.40E-01 :
RUD (MG/ LITER) 2.83E-03 :
1.06E-02 :
1.50E-02 :
RITIUM (UC/ML) 2.43E+00 :
3.22E+00 :
3.79E+00 :
YDROGEN (CC/KG) 2.20E+01 :
2.39E+01 :
2.70E+01 :
f
".'..~'.......;.....,....................................................
AERATED LIQUID WASTE PROCESSED (GALLONS):
9.68E+04 MASTE LIQUID PROCESSED THROUGH DORON RECOVERY (GALLONS):
2.46E+04 l
AVERAGE PRIMARY LEAK RATE (GALL 0tlS PER MINUTE):
2.17E-01 PRIt1ARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):
0.00E+00 j
4
_. - =.
i l
AVERAGE DAILY UNIT POWER LEVEL l
l l
DOCKET NO.
50-213 Conn. Yankee l
UNIT IInddam Neck l
l DATE Oct. 10, 1980 i
l i
COMPLETED BY Reactor Engineering t
l TELEPil0NE (203) 267-2556 MONTil:
September 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) i 1
545 17 560 2
543 18 562 3
544 19 566 4
547 20 566 5
549 21 563 6
550 22 559 l
7 550 23 559 l
'8 551 24 562 9
524 25 564 l
10 553 26 561 11 555 27 44 n
558 28 13 558 29 2
14 556 30 234 15 558 31 l
560 16 IllSTRUCTIONS On this format, list the averdge daily unit power level in MWe-Net for eac15 day in tlic reporting month.
Complete the nearest whole megawatt.
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- TtC OPEPAT!!:G STATUS REPO;IT CC:PLETED BY P.EACT0ft El;",1fEElit:r.*****
ECCi~ET ::3 50-113 (m)
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9 6
REFUELING I!;FORMATIOM RF.QUCST 1.
Name of facility Connecticut Yankee Atomic Power Company 2.
Scheduled date for next refueling shutdown.
September / October 1981 3.
Scheduled date for restart following refueling Approximately six to eight weeks.
4.
(a) Uill refueling or resumption of operation thereafter require a technical specification change or other license amendment?
No technical specification changes are anticipated at this time.
(b)
If answer is yes, what, in general, will these be?
N/A (c)
If answer is no, has the reload fuci design and core confi;,uration 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 accordance 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 S.
Scheduled date(s) for submitting proposed licensing action and supporting information.
There are no scheduled dates because of (4) above.
6.
Inportant licens.ing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unrevicwed design or performance analysis methods, sigr.ificant changes in fuel design, new operating procedures.
None 7.
The number of fuel assemblics (a) in the core and (b) in the spent fuel
- storage pool.
(a) 157 (b) 389 8.
The present licensed spent fuel pool storage capacity and the size of any increase in liccused storage capacity that has been requested or is planned, in number of fuel ass ablics.
1168
-ar 9.
The projectcd date of the last refueling that can be discharged to the spent fuci poc1 assuming the present licensed capacity.
1994 to 1995
..