ML20040H511

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Monthly Operating Rept 82-1 for Jan 1982
ML20040H511
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 02/10/1982
From: Donna Anderson
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20040H508 List:
References
NUDOCS 8202180326
Download: ML20040H511 (9)
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{{#Wiki_filter:g a CONNECTICUT YANKEE ATOMIC POWER COMPANY llADDAM NECK PLANT llADDAM, CONNECTICUT MONTIILY OPERATING REPORT NO. 82-1 FOR TIIE MONTil 0F JANUARY 1982 8202180326 820212 PDR ADOCK 05000213 R PDR

f ~ U PLANT OPERATIONS: The following is a summary of plant. operations for the month of January 1982: The plant operated at full power'until January 2 at-1503 hours when a load reduction was commenced to plug -leaking condenser tubes in the "B" Waterbox. Load increase began at- 0455 hours on January 3 and. full i power was reached at 0800. i On January 8 at 0645 the unit started a load decrease due to a leak on the boric acid filter bypass valve, BA-V-388. Repairs to the boric acid filter bypass valve were completed and the unit reached full power.at 1340 hours. It was necessary to reduce the plant load three more times during the-month due to condenser-tube leakage. Load was reduced on-January 12, 20 and 25 for short. periods of time as a result of this problem. An evaluation is in progress to determine the cause and solution to the condenser tube leakage. On January 31.at 0600 hours the plant experienced a reactor and turbine trip. This trip was caused by a piace of metal shim stock making contact with and shorting out several diodes on' the exciter diode wheel. The extent of damage -is still being ~ determined.

un.... SYSTDI CN CORRECTIVE ACTION T.*KE.1 TO PROVICE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR RE!.CTOR S WETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING RETAIR NO REPORTABLE Eql'IPMENT FAILURE 1 OR JANUARY, 6 ee h k 0 9 e 0 e / W

N4 plum qu u 4m .-s .. ~.. ~.........., SYSTEM CN CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE-TAKEN TO PREVENT FOR REACTOR SAFEU COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR FEEDWATER FLOW Faulty diodes in Loss of feedwater NONE Replaced converter. Manual operation of voltage converter. flow indication feedwater. Constant found loose and control in operator surveillance solder connection automatic. of feed and steam flow. in voltage Converter. F0WER ' RANGE CIIANNEL Faulty detector. CII 31, A detector NONE Replaced detector. None. Shutdown spiking. Mode 2. e. G e e e e .!a e ~ O 6-.B, e

AVERAGE DAILY UNIT POWER LEVEL DOCKET No.- 50-213 Conn.-Yankee UNIT Haddam Neck DATE 2-10-82 COMPLETED BY D.~ Anderson TELEPHONE (203) 267-2556 MONTH: January 1982 DAY AVERAGE DAILY POWER LEVEL-DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 579 17 578 2-511 18 577 577 3 527 19 535 4 579-20 579 193 .5 21 575 6: 578 22 580 7 23 577-565 8 24 579-578 9 25 514 578 10 26 576 578 11 577 27 354 577 12 28 378 576 13 29 i 577 579

4 30

-578 145 ig 31 578 16 INSTRUCTIONS On this format, list the average daily unit power Icvel in MWe-Net for each day in the reporting month. Complete the nearest whole megawatt. (9/77)

t s CONNECTILUT YANKEE REACTOR COOLANT DATA nuttitit--f ANUAR Y 178.- s .1 i REACIOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM o0........................................................... + g ;ng r- _, u-, n n. e, n t-, nn.

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g i CONDUCTIVITY (UMHOS/CM) 1.17E+01' 1.76E+01 : 2.10E+01 : l CilLORIDES (PPM)

<5.00E-02 : <5.00E-02 : <5.00E-02 :*

f.:ISSOL-VED-OKYGEN-+PPEG

'5rOOE400 :

'.5. OGE+OO C5.OGEt00 DDRON (PPM) 9.51E+02 : 1.02E+03 : 1.13E+03 : LITHIUM (PPM) 1.30E+00 : 1.63E+00 1 95E+00 : i U T AL enttMtr-AtH. ' U e/ tit-; } 1.'2C 01 ; i.30C 00 ./OE!00 : \\ 10 DINE-131 ACT. (UC/ML) 6.28E-03 : 6.58E-02 1.08E+00 1-131/I-133 RATIO 3.53E-01 : 8.44E-01 : 1.12E400 - -efdiD-ftiG-/t-fi ER ) 1-<-1 rOOE-02 -:1. OGE-02 : :1.GOE-02 : TRITIUM (UC/ML) 3.82 E-01 : 2.04 E+00 2.83E+00 : HYDROGEN (CC/KG) 2.25E+01 : 2.43E+01 : 2.55E+01 : } AERATED LIGUID WASTE PROCESSED (GALLONS): 2.00E+05 .f 3.95E+04 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (OALLONS)* ftVER AGE-PP+HARY LE AK--RATE (C ALLONC PEF: IMUTC)* j.12E -0 2 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): 0.00E+00 l1 i i s 5 e 'g L \\

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UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME Conn. Yankee DATE 2/10/82 COMPLETED BY D. Anderson REPORT MONTil January 1982 TELEPIIONE (203)267-2556 rE EwU U cm n 00 ms M E Licensee Se E*o Cause & Corrective No. Date E. U$ E .E U # Event UE 8.3 Action to E2 $23 $5$ Report # 37g gu Prevent Recurrence u A Mmg 82-01 820112 N/A 0 A N/A N/A N/A N/A Load reduction due to condenser in leakage. 82-02 820121 N/A 0 A N/A N/A N/A N/A Reduced power to plug tubes in "D" and "B" waterboxes. 82-03 820131 F 18.0 A 3 N/A ZZ ZZZZZZ Turbine and reactor trip. Trip caused by 8 loss of generator field,' Loca ted six blown fuses on main exciter. I i 4 1 2 3 4 Method: Exhibit C-Instructions F Forced Reason: S Scheduled A-Equipment Failure (Explain) H-Other(Explain) 1-Manual for Preparation of Data B-Maintenance or. Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File D-Regulatory Restriction 4-Other(Explain (NUREG-0161) E-Operator Training & License Examination' F-Administrative 5 Exhibit 1 Same Source G-Operational. Error (Explain

o ~. REFUELING INFORETION REQUEST 1.... Name of facility Connecticut Yankee Atomic Power Company '2 Scheduled date for next refueling shutdown.

  • February 1983.

3. Scheduled date for restart following refueling. Mid March 1983 ' 4. (a) Will refueling or resumption of operation thereafter requite 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 fuel design and core configuration been reviewed by your Plant Safety Review Co=mittee to determine whether any unreviewed safety questions are associated with the . core reload (Ref.10 CFR Section~ 50.59)? When documents are received from vendor t' hey are reviewed in accordance with 10CFR 50.59 to determine' if unreviewed safety questions are core reload associated. (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 dated because of (4) above. 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design. cr performance analysis methods, significant changes in fuel design, Lew operating procedures. None 7. The number of fuel asscsblics (a) in the core and. (b) in the spent fuel storage pool. (A) 157 (B) 441 8. The present licensed spent fuel pool storage capacity and the sire I of any increase in licensed storage capacity 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 fuel pool assuming the present licensed capacity. 1994 to 1995 I e l . - -.. - -}}

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