ML20197C984
| ML20197C984 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/01/1978 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20197C969 | List: |
| References | |
| NUDOCS 7811210269 | |
| Download: ML20197C984 (7) | |
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OPERATING DATA REP 0llT l
DOCKET NO. 50 293 DATE 11/08/78 COMPLETED hY C.M.daTIIiey TELEPil0NE 617-746-7900 OPER AT!NG C.TATUS I
Pilgrim I' Notes
- 1. Unit Narae:
- 2. Reportin; Period:
October, 1978 1990*
- 3. Licensed Thermal Power (MWt):
676*
- 4. Nameplate Ra:ing (Cross MWe):
655
- 5. Design Electrical R:: tin;t (Net MWe):
690
- 6. Maximum Dependable Capacity (Gross MWe):
670
- 7. Maxirnum Dependable Capacity (Net MW'e):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report Give Reasons:
- 9. Power Level To Which Restricted,1f Any (Net MWe):
- 10. Reasons For Restrictions. !f Any:
N/A This Month Yr..to Date Cumulatise
- 11. Ilours In Reporting Period 745.0 7296,0 51672.0
- 12. Nmnber Of liours Reactor Was Critical 310.1 5927.0 35583.7
- 13. Rear: tor Resene Shutdown flours 0.0 0.0 0.0
- 14. Ilot rs Generator On.Line 289.9 5816.6 34258.6
- 15. Unit fleserve Shutdown liours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH)
'i 'D A 4 0. 0 10452696.0 55604928.0
- 18. Net Electric.il Energy Generated (MWil) 174049.0_
, 3580920.0 18160454 o
- 17. Gross Electric::1 Ener;:y Generated (MWii) 180970.0 3443610.0 17428506.0
- 19. Unit Service Factor 38.9 79.7 66.3
- 20. Unit Avaihtbility Factor 38.9 79.7 66.)
- 21. Unit Capacity Factor (Uning MDC Net) 34.9 70.4 50.3
- 23. Unit Forced Outane Rate 61.1 72.1 51.5
- 22. Unit Caps. city Factor (Using dei! Netj 35.7 10.0 11.Z
- 24. Shutdowns 1,chedt. led Over Next 6 Months (Type. Date, and Duration of E.ich):
NONE M OMRAM, 25, if Shut Down At End Of Report Period.Estimnted Date of Startup:
- 20. Units in Test Status IPtmr to Connuercul Operation n Forecast Achie.ed INIII \\ L CitiTICA 1.lTY INITIAL ELECTRICITY C051Ml:llCI AL OPER ATION (1/'! ? )
l 7811210467
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AVERAGE DAILY UNITPOWER LEVEL 50-293 DOCKET NO, -
Pilgrim I g,
DATE COMPLETED BY C.M.Gaffney TELEPif0NE 617-746-7900 OCTOBER, 1978 MONTil DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (Mbe Net)
(MWe Net)
I
- 662, 17 0,
- 661, 0,
g 3
651-0
- 662, 0,
4 0
663.
O, 5
- 664, 0,
6
- 662, 0*
7 23 8
656-0 595.
O, 9
10 0,
0
'6 1;
0, 0,
0-
- 121, 12 13 0,
468 0
230 14 IS 0,
559 3,
16 0
INSTRUCTIONS On this ferrnat, hst the sera;e Ja:ly urit pimer lese!in MWe Net for ea:h da) in the reportine month. Compure to the nearest wnole m:gr.oit.
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(1817 7 )
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.e' 50-293 UNITSliUTDOWNS AND POWER REDUCTIONS DCCi:ET NO.
UNIT NAM E Pilgrim I DATE 11/08/78 OCTOBER, 1978 COMPLETED aY C.M.Gaffney R EFC.7T MONTII TELE P;Ic,NE 617-746-7900 5 =rn 5 3
=
ra N...
D3 e i
S _3
?5E li '" Scc 5%
Cause & cor rective 53 fh*C"'
3.2 0
5 3.3 93 Auron to j'
Present Recurrence 3 05 j RcPort
- mV a:
E 6
15 10/09/78 F
438.4 H
3 78 048/03L HA INSTRU Turbine Trip, Dif ferential Over current Relay 16 10/28/78 F
6.9 H
3 Turbine Trip, Exciter Ground,
Replaced Brushes 17 10/30/78 F
9.8 H
3 Reactor Scram, Hi APRM, Control Valve Testing I
2 3
4 l': Foried Reason:
Method:
Exhibit G -Instructions 5: St htdu!ed A E.iuipment Failure (Explain) 1 -Man ual for Preparation of Data B Maintenance of Test 2-Manual Scram.
Entry Sheets for 1.icensee C-Refusling 3-Automatic Strain.
Event Repunt i1.ER) File (NUREG-D Retniatory Restriction 4-Other (Explain) 0161)
I' Operator Training & IJtense Exa nination F-Ad nu n nt rat i.e 5
G-Operational Eiror (Explain)
Exinbit ! - Same Source 07/77) 11 Other (Explaini b
BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION DOCKET No. 50-293 Summary of Operating Experience for October, 1978 The month of October began with the unit operating at 100% power level and it remained there until Fbnday, October 9,1978 At 2121 hours0.0245 days <br />0.589 hours <br />0.00351 weeks <br />8.070405e-4 months <br /> the reactor scrammed ou a Load Rejection caused by a trip of the Cencrator Lockout Relay.
The trip occurred as a result of a Nuclear Plant Operator attempting to change a burned out bulb for Auxiliary Transformer phase indication on Panel C-3.
The bulb's socket broke and grounded to the panel causing a current surge which activated the Differential Over current Relay Logic.
Subsequent to the scram, it was observed that relief / safety valves RV-203-3A and 3C had opened and one or both had not reclosed. The Watch Engineer ordered TORUS cooling initiat ed and relief valves 3A & 3C cycled in accordance with station procedure 2.4.28 (Relief / Safety Valve Malfunction). A definite noise and pressure change was observed when RV-203-3A was cycled, however, there was no change noted when RV-203-3C was cveled. Approximately 20 minutes after the scram, with reactor pressure around J30 PSIG, RV-203-3C closed. The cool-down rate during the 20 minute period as indicated on recorder 42-TR-151 A&B, was 2940F/ hour.
After RV-203-3C closed, pressure and temperature were ellowed to increase to minimize the ef fects of the blowdown. Approximately 35 minutes later, with reactor pressure about 630 PSIC, RV-203-3C opened again. This resulted in-another blowdown which again J asted for approximately 20 minutes before RV-203-3C closed at around 200 PSIG. The cooldown rate during this period was 2550F/ hour.
The pressure and temperature were allowed to increase again and no further incidents of relief valve opening occurred. Extrapolation of the cooldown rates f rom 42-TR-151 A&B show that the cooldown rate did not exceed the 1000F/hr.
limit of Technical Specification 3.6. A.1 when averaged over a one hour period.
l The reactor was manuvered to a cold condition for replacement of CV-203-30 l
In addition, RV-203-3B was replaced as it has exhibited excessive tail pipe l
temperatures.
On October 11, 1978 while performing routine surveillance testing on "B"
Diesel Generator in accordance wich Surveillance Procedure 8.9.1 (Manually Start and Load Each D/C Once/Fbnth), the generator output breaker tripped af ter the unit had been operating at rated load for approximately 16 minutes.
It was observed that generator voltage had gone to zero and the diesel was secured.
A check of Bkr. 152-609 showed a flag on Differential Relay for phase "A"
and a differential lockout trip was in.
Further investigation showed "B" and "C" windings reading 1000 megs, and "A" winding 6 megs. A sizzling sound could be heard on the "A" windings.
A reactor startup was in progress at the time of occurrence with group 1 i
and 2 control rods withdrawn. Control rods were inserted to full-in position and reactor placed in cold shutdown condition for repairs to the Diesel Generator.
., - ___.. _ _.. _,., _ _,, ~, _.
4 This event occurred as a result of a short from a coil to the stator caused by loose laminations. A partial changeout of the coils would have required de-rating the capacity of the unit so a complete changeout was conducted.
Acceptance testing conducted during and after the installation consisted of the following:
- 1) each coil was Hi-Potted by. G.E., 2) ring testing for hot spots, 3) Impediance check of rotor and 4) Power factor teet by Doble Engineering.
As coils were installed a current was fed through the stator to raise the temperature above ambient and the coils were varnished to further reduce the possibility of loose laminations.
Upon completion of the repairs the system was returned to normal and on October 26, 1978 Surveillance Test 8.9.1 was conducted again. During the per-formance of this test, rated load conditions could not be achieved. Maximum kw loading which could be achieved was 2300 kw.
The Woodward Governor was re-placed in kind and on October 27, 1978 Surveillance 8.9.1 was conducted satisfactorily.
Surveillance Procedure 8.M.3-1 (Simulated Auto Initiation of Diesel Generators) was conducted satisfactorily on October 27 and the unit was returned to operable status.
During this outage many of the required instrument and electrical surveil-lances that are required to be done every fif teen months were completed.
At the conclusion of all required surveillances, the control rods were withdrawn and the reactor was taken critical at 1900 hrs, on Friday, October 27 The turbine-generator was synchronized onto the grid at 0344 on Saturday, October 28th. However, the turbine had to be taken of f the line at 0530 hrs, due to an exciter brush problem.
It was synchorinzed onto the grid at 1227 hrs, on Saturday, October 28th.
The power level was steadily increased until Monday, October 30th. During the early morning hours the operating crews were conducting required surveil-lances when the reactor scrammed at 0516 hours0.00597 days <br />0.143 hours <br />8.531746e-4 weeks <br />1.96338e-4 months <br />. The operators immediately recovered from the scram, began pulling control rods at 0723 hrs, had the reactor critical at 1031 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.922955e-4 months <br /> and synchronized the turbine-generator onto the grid at 1500 hrs.
The month closed out with the unit at 85% power and increasing in power level under the guidance of Reactor Engineering Personnel. _
PILGRIM NUCLEAR POWER STATION Month OCTOBER M IOR SAFETY RELATED TAINTENANCE h5~EM CC:GCNENT I
MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION ASSOCIATED l
LER mo unevirv7 pernnnryce
~
W nding failed Short Replaced None 78-049/03L4
'B' DIESEL i
D/G GEN.
D/G
'B' DIESEL GEN.
Would not accept Governor Replaced Governor Sent Governor out to be evaluated N.A.
full load Malfunction 1
Recirc!DC BREAKER 72-Underrated coils Design Replace Changed out undervoltage coil per 77-9/3L 933 POWER SUPPLY PDCR 76-89 lTORECIRC.
i M.G.
I AITX. OTT, PIHP DC BREAKER 72-HPCI 944 POWER SUPPLY"Under rated" coils Design Replace Changed out under voltage coil per 77-9/3L TO MO-2301-3 PDCR 76 89 i
Leaking pilot a.
Ins talled re-ADS RELIEF VALVE Valve Blowdown Purchasing of new design top 78-048/03 filter plug 6 built SN-8 on SN-86 works from G.E.
L-0 pilot valve line b.
Rebuilt valve MRii id-2453
~
Leaking a.
Installed re-Purchasing of new design top workt 78 048/
RELIEF VALVE High tail pipe temr>-
pilot valve ADS SN-2 built SN-10 on from G.E.
03L-0 t
line.
b.
Rebuilding valve MR#78-2452 1
I Rx.
Rx. vessel drair Bonnet flange leaking Blow bonnet Reweld bonnet Seal weld bonnet flange N.A.
Vessel i valve gasket flange l
t I
s 1-
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c REFUELING INFORMATION t
The following refueling information is included in the Monthly Report as rqquested in a letter to Mr. G. C. Andognini dated January 18, 1978 For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request.
1 The name of this facility is Pilgrim Nuclear Power Station, Docket No. 50-293 2
Scheduled date for next Refueling Shutdown:
January 1980 3.
Scheduled date for restart following refueling:
April, 1980 4
5.
Due to their similarity, requests 4, 5 & 6 are responded to collectively:
6 The fuel, which is presently expected to be loaded during the next scheduled shutdown, may be reload fuel of a new design and may therefore require a proposed license submittal and technical specification changes.
It is not possibic, however, to supply pertinent information on dates.
As information concerning fuci design, core configuration, Operational Review Committee determinations, proposed licensing action, and technical specification submittals becomes available, it will be forwarded to you.
7 (a) There are 580 fuel assemblies in the core.
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(b)
There are 580 fuel assemblies in the spent fuel pool.
8 (a) 1he station is presently licensed to store 2320 spent fuel assemblies.
The actual spent fuel storage capacity is 1070 fuel assemblies and new high density fuel storage racks are in the process of being installed.
(b) The planned spent fuel storage capacity is 2320, fuel assemblies.
9.
With present spent fuel storage capacity, the spent fuel pool does not have the capacity to accommodate an additional 580 fuel assemblies.
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