ML19290E883

Monthly Operating Rept for Feb 1980

ML19290E883
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/05/1980
From:	CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML19290E881	List: ML19290E880 ML19290E883
References
NUDOCS 8003170260
Download: ML19290E883 (8)

Text

{{#Wiki_filter:. CONNECTICUT YANKEE ATOMIC P0b'ER COMPANY HADDAM NECK PI).NT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT NO. 80-2 FOR THE MONTH OF FEBRUARY, 1980 8 003 7 70 Qgo

PLANT OPERATIONS The following is a chronological description of plant operations for the month of February, 1980. At the beginning of this report period the plant was operating at 605 MNe, 100% power. On 2/3/80 the unloading ano storing of last shipment of new fuel was completed. 52 new fuel assembl.es are in new fuel storage racks. On 2/4/EO, EG2A was out or service for maintenance. Retested and returned to service on same day. On 2/4/80 pressurizer pressure dropped to 1992 psig due to spurious opening of PR-SOV-570 and PR-MOV-269. Operator closed valves and restored pressurizer pressure to normal. On 2/6/80 fire pressure maintenance pump was returned to service following pump overhaul. On 2/6/80 load was reduced to 530 MWe due to broken air line on heater drains tank normal level control valve. Line was repaired and plant returned to full power at 0245 hours on 2/7/80. On 2/16/80 load was reduced to 500 MWe and "A" circulating water pump was removed from service due to motor ground. On 2/17/80 load was reduced to 400.MWe to perform turbine stop and control valve test. Test completed and load returned to 500 MWe on same day. On 2/19/80 load was reduced to 345 MWe to check condenser tubes in "C" and "D" water boxes. Two tubes were plugged in each waterbox. Load was returned to 575 MWe on same day. On 2/20/80 load was reduced to 125 MWe due to steam generator chemistry specifications. Load was increased to 180 MWe for better feed water control. Maintenance removed "C" Cire. pump motor and installed it on "A" cire pump. "B" condenser water box checked for tube leaks. Plugged two tubes in "B" waterbox. ON litt/80 steam generator chemistry in specs. and load increase was started. On 2/22/80 all circulating water pumps were returned to service and load increased to 100% power. On 2/26/80 the main stack monitor failed. Hourly sampling procedure instituted. I&C changed detector and main stack monitor was returned to service at 0100 hours on 2/27/80. On 2/29/80 "B" charging pump out of service to change motor driven oil pump. Returned to service same day.

EFFdCT SPECIAL PRECAUTIONS SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR EG2A Frequency Meter Unknown Meter inaccurate None Replaced freq. meter None Required. EC2A never inoperable for this season "B" Waste Gas Faulty diaphragm Minor gas leak None Replaced diaphragms "A" waste gas compressor Compressor into PAB available MA0947 (2/7/80) "B" charging pump Leaking Mech. Oil leak None Replaced pump "A" charging pump available main lube oil pump seal Pressurizer Pressure Unknown Opening of P0ftV None due to Removed from service Closed MOV 569 and racked Controller PC 401-1 570 and MOV 569 oper. action checked unit, found no the breaker open Reduced press-problem urizer pressure below Tech. Spec limit Loop #1 Steam Flow Faulty Feedback Indication None Removed from service and Inserted trip signal Indicator slidewire and would not follow replaced motor and slide-indication drive measured wire motor variable loop #2 Feedwater Worn positioner Excessive air None Replaced all worn parts in Clamped valve in position regulating valve seat demand and valve valve positioner and controlled flow using positioner instability bypass valve RMS Channel 14 Main Faulty G.M. Failed low None Replaced tube Samples taken by plant as Stack Rad. Monitor Tube per Tech. Spec. Req.

cONNFCTICUT YAllEEE REACTOR CCOLAN T DATA MONTH: FEBRUARY 1980 R FAClQ8_.CQ.0LoilT ANALYSIS 7;fNIMUM AVERAGE MAXIMUM PH D 25 DEGREES C 6.38E+00 : 6.79E+00 : 7.12E+00 : e n v ro ir T T U T T v n'tmgs/rM) n inFAnn : 9,nzE4on ? ?,or)E4n1 : CHLORIDES (PFM)

(4.00E-02 : (4.00E-02 : s4.00E-02 :

DISSOLVED OXYGEN (PPB)

<5.00E+00 : <G.00E+00 : (5.00E+00 :

POROM._ red) 1.34E*02 : 1.93Ein'! ;- 3.32E+0'? : LITHIUd ( PPrf ) 5.00E-OL : 8.36E-01 : 1.25E+00 : TOTAL SAMMA ACT. (UC/ML) 5.1SE+00 8.12E+00 : 9.44E+00 : r omg 4,4

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rips w 3 1, ing_nq, a g a p. n, c, a p y.n o I-131/[-133 RATIO 7.70E-01 : ?.14E-01 : 1.17E+00 : CRUD (MG/ LITER) 1.00E-02 : 3.50E-02 5.00E-02 : TP CIUM (t!C/ML) t.21;+00 : 2. 9 "< E + 0 0 ? 3.60E+00 : M ish'OLiEN (GU/M3) 3.4SE+01 4.74E+v1 : 6.74EYO1 : AERATED LTOUID WASTE PROCESSED (GAi.l ONS): 7.67E+04 WASTE LIGUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 4.44E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 6.40E-02 po r tenv r n c:c r p > m e c. v ir,w p a rr I n si i n g q p rc p s;ny7c3, n,nogino mesp

AVERACE DAILY UNIT POWER LEVEL DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE March 5,1980 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 MONTH: Februarv, 1980 DAY AVERAGE DAILY POUER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 578 17 471 2 577 18 479 3 577 19 429 4 578 20 419 5 578 21 195 6 565 22 558 7 575 23 578 8 578 24 579 9 579 25 579 10 578 26 579 11 578 27 579 12 578 28 579 13 578 29 577 14 576 30 15 575 31 16 536 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for cach day in the reporting month. Complete the nearest whole megawatt. (9/77)

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,,.c _ REFUELING TNFORMATION REOUEST 1. Name of facility Connecticut Yankee Atomic Power Company 2. Scheduled date for next refueling shutdown. April, 19SO 3. Schedaled date for restart following refueling. Approximately cight to 12 weeks from shutdown date. 4. (a) L'111 refueling or resumption of operation thereaf ter require a technical specification change or other license a=cacment? No technical specification changes are anticipated at this date. (b) If answer 4.s yes, what, in general, will these be? N/A (c) If answer is no, has the reload fuel design and core configuratica been reviewed by your Plant Safety Review Cncmittee to determine whether any unreviewed safety questions are associated with the core relcad (Ref.10 CFR Section 50.59)? Uhen the above stated documents are received from the fuel vendor they will be reviewed in ac.cordance ulti 10CrR50.59 to deteraine if any unreviewed safety questions are associated uitt the (d) If no such review has taken place, when is it scheduled? core reloa N/A 5. Scheduled date(s) for submitting proposed licensing action and supporting informatien. There are no scheduled dates because of (4) above. 6. Important licensing considerations 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. Tne number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool. (a) 157 (b) 340 8. The present licensed spent fuel pool storage capacity and the sisc of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblics, 1168 9. The projected date of the last refueling that can be disclarged to the spent fuel pool assu:aing the present licensed capacity. 1994 to 1995

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