ML20125C301
| ML20125C301 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/30/1992 |
| From: | Link B, Peterson D WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-92-140 VPNPD-92-363, NUDOCS 9212110133 | |
| Download: ML20125C301 (10) | |
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Wisconsin Elecinc POM R COMPAN Y gwm 2.s n w v. g r, n_ iz,,w mn n... ma VPflPD-92-363 NRC-92-140 December 9, 1992 Document Control Desk U.S.
NUCLEAR REGULATORY COMMISSION Mail Station P1-137 Washington, DC 20555 Gentlemen:
LLQCELTS 50-266 AND 50-301
]j0llTHLY OPERATING REPORTS POINT BEACH NUCLEAR PLANT, UNITS 1 ANQ_1 Attached are monthly operating reports for Units 1 and 2 of the Point Beach Nuclear Plant for the calendar month of November 1992.
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-<c e Bob Link Vice President Nuclear Power MPB/jg cc:
L. L.
Smith, PSCW NRC Regional Administrator, Region III NRC Resident Inspector
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FOINT BEACil NUCLEAR PLAST DOCKET NO.
9M66 l
AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach, Un;t 1 MONTH NOVEMBER - 1992 DATE December 7,100 COMPLETED BY D. C. Peterson TELEPIIONE 414/755-r21 l
AVERAGE AVERAGE l
AVERAGE DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL DAY MWe NET DAY MWe NET DAY MWe NET l
4XS 1
493 11 493 21 l
2 493 12 494 22 497 3
402 13 49 23 495 404 24 491 4
493 14 5
492 15 474 25 403 26 403 16 402 6
491 7
492 17 493 27 405 8
492 IS 494 23 493 9
493 19 493 29 403 10 494 20 403 30
__ 493 rr esa (03-M) i s
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y POINT BEACli NUCLEAR PLANT Docket No.
%-266 Unit Name Point Beach, Unit 1 UNIT SillTFDOWNS AND POWER REDUCTIONS Date December 7.1991 Completed By D. C. Petery REPOPT MONTII NOVEMBER - IW2 Telephece No.
4 14
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Method of Shutting No.
Date Ty;M Duratic,n Reasoc Down I.ise:tsee Even Systera Compenent Cause and Correcive Actran 2
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e F: Forced Reason-
' Method:
- Exhibit G - Instructions 2
S: Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG4161)
D - Regulatory Restriction 4 - Continuation of E - Operater Training &
Previous Shutdowa Licensing Exam 5 - Reduced Load F-Administrative 6 - Other (explain)
' Exhibit I - Same Source G - Operational Error (explain)
II - Other (explain)
PBF-002Sb 03-90)
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I DOCKET NO.
50-266 UNIT NAME Point Beach Unit 1 DATE December 7, 1992 COMPLETED BY D.
C.
Peterson TELEPHONE 414/755-2321, Ext. 361 Unit 1 operated at approximately 490 MWe average daily power level throughout this sport period with no significant power reductions.
During this period, two reportable events were issued for Unit 1.
LER 92-008-00, reactor trip following closure of main steam isolation valve 1MS-2018 during the performance of quarterly surveillance testing.
LER 92-009-00, common to both units, component cooling water system surge tank vent valves outside design basis due to non-safety related closure circuitry.
Safety-related maintenance included the following:
1.
Replaced and rewired a cracked relay component on electrical section (C-002) of the main control board.
2.
Minor adjustment to' potentiometer on the emergency diesel generator voltage speed relay board to establish proper diesel voltage at the time of breaker closing.
3.
Rotated collar on the stem of the rad waste steam trip valve (SA-9) to prevent binding which was affecting the valve opening time.
6.
Spent fuel pit heat exchanger service water return throttle valve (SW-660) was removed and flanges installed as a temporary modification until valve can be replaced due to a pin hole leak in original valve body.
5.
Sediment was flushed out of service water line to Unit 2 turbine-driven auxiliary f eedwater pump, 2P29 using local drains.
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POlhT BEACH NUCLEAR PLANT DOCKET NO.
50-301
~
AVERAGE DAILY UNIT POWER LEVEL UNIT NAME Point Beach. Unit 2-MONTH NOVEMBER - 1992 DATE December 7.1992 COMPLETED BY D. C. Peterson i
TELEPHONE 414/755-2321 1
i i~'
AVERAGE AVERAGE AVERAGE l
DAILY DAILY DAILY POWER LEVEL POWER LEVEL POWER LEVEL I
-DAY MWe NET DAY MWe NET DAY MWe NET i
?
1
-2 11
-2 21 471 s
'2
-2 12
-4 22 476 I
3
-2 13
-12 23 477 t
'4
-2 14
-13 24 473 i
l
~ 5
-2 15
-14 25 477 i
6
-2 16
-14 26 474 1
l 7
-3 17
-15 27 476 8
-10 IS 32 28 476 I
. 9
-8 19 1 )
29 476 i
4 10
-2 20 344 30 475 i
n 4
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PBF-002Sa 4
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5 POINT BEACH NUCLEAR PLANT Docket No.
50-301 Unit Name Point Beach Unit 2 UNIT SIIUTDOWNS AND POWER REDUCTIONS Date December 7.1092 Completed By D. C. Peterson REPORT MONTH NOVEMBER - M92 Telephone No.
414/755-2321. Ext. 361 Method of Shutting Cause and Corrective Action Licensee Event System Component Duration No.
Date Type'
- (IIeun)
Reason pe m n,3 Report No.
Code' Code' To Prevent Recurrence 2
Scheduled refueheg and mainrenance outage U2RIS. Major work items include-inspection 3
920926 5
419.0 C
1 and eddy current testmg of steam generators; seplacement of safety injecten MOV SM B.
C moten with 15 Ft45 motors; D02 battery panet replacemenr, prcmde safeguards 480V buses 2-DC3 and 2-BG8 with str pping separation for non-safety related breakers; mechanical and electrical modification to the main steam isolation va!ves; and c!imination of NIS rod drep turbine rueback signal. Outar tended 5 days due to emergent =crk resultmg from Event V, check vane leakag-testa n.
'F: Forced Reason:
' Method:
' Exhibit G - Instructiens 2
S:. Scheduled A - Equipment Failure (explain) 1 - Manual for preparation of B - Maintenance or Testing 2 - Manual Scram data entry sheets C - Refueling 3 - Automatic Scram LER file (NUREG-0161) l D - Regulatory Restriction 4 - Continuation of E - Operator Training &
Previous Shutdown Licensing Exam 5 - Reduced Load F-Administrative 6 - Other (explain)
' Exhibit I - Same Source G - Operational Error (explain) j.
H - Other (explain)
' PDF-CD2Sb (03-90).
j o.-
-. +
- i DOCKET NO.
50-301 UNIT NAME Point-Beach Unit 2 DATE December-7, 1992 COMPLETED BY D. C.
Peterson TELEPHONE 414/755-2321, Ext. 361 Unit 2 was returned to service on November 18 af ter completing a refueling outage.
The unit operated at approximately 173-MWe-i average daily power level for this report period.
Full power operation is being limited to.95% because the reactor coolant flow measurement indicator flow is just above the Technical Specification limit.
Another measurement is planned as it is believed the results of the initial flow measurement are lower than actual.
During this period the following reportable events were issued for Unit 2:
LER 92-004-02, improper sequencing of emergency safety features was resubmitted to provide an update to the corrective actions taken in response to this event.
LER 92-005-00, steam generator tube degradation, 3G tubes were plugged in the "A"
steam generator and 49 tubes were plugged in the "B"
LER 92-006-00, inadvertent ESF actuation as a result of as-built wire tracing.
LER 92-007-00, inadvertent ESF actuation as a result of improper surveillance testing.
A safeguards bus was mistakenly de-energized causing automatic starting of the emergency diesel generator.
Safety-related maintenance included the following:
I 1.
Cleaned overload dash pots for all three phases of the j
normal power supply to the 480 safeguards. bus 2B-32 after breaker tripped prematurely while. attempting to restart primary auxiliary building exhaust fan.
2.
Removed, cleaned and' reinstalled window flange on the containment--inner airlock window.
3.
Eliminated the NIS rod drop turbine runback signal by installing a plant modification.
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4.
Non-regenerative heat exchanger inlet test connection valve, CV-369, stem separated from plug.
Welded in a new valve.
5.
Replaced gasket and torqued residual heat removal to letdown crossconnect valve, CV-369A, to correct body to bonnet leakage.
6.
Repacked charging line flow control outlet isolation valve, CV-384, to stop leakage.
7.
Installed static transfer capability for yellow 125 volt DC to 120 volt AC inverter under a plant modification.
9 Replaced train B loop B reactor coolant flow trip matrix relay due to failed contacts.
9.
Replaced spray additive tank outlet valve's I/P transducer due to erratic and non-repeatable output.
Spray additive tank level decreased by 2% during innervice test.
10.
Drained, filled and flushed the containment spray system as necessary to reduce the concentration of sodium.
Refueling water storage tank was also contaminated.
The sodium was introduced via the spray additive tank outlet valve during inservice testing.
11.
Installed a new shaft, modified the shaft non-operator end closure arrangement and changed the location of the limit switches and the closing spring of the main steam isolation valves.
12.
Secured counter weight on arm and installed live-loaded packing system on the steam header non-return check valve.
13.
Removed high spots and polished bur in the packing area of the steam generator blowdown isolation valves, 2MS 5989 and 2MS 5959.
14.
Replaced train
- B",
power range, low power trip matrix relay due to loud chattering during surveillance testing.
15.
Time delayed relay on AMSAC shutdown panel was found out of tolerance.
It was replaced.
._