ML20053C217

Monthly Operating Rept for Apr 1982

ML20053C217
Person / Time
Site:	Pilgrim
Issue date:	05/14/1982
From:	Mcloughlin M BOSTON EDISON CO.
To:
Shared Package
ML20053C211	List: ML20053C210 ML20053C217
References
NUDOCS 8206010580
Download: ML20053C217 (8)

Text

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OPERATING DATA REPORT DOCKET NO.

50-293 DATE 05/14/82 COMPLETED BY M. T. McLoughlin TELEPHONE 617-746-7900 OPERATING STATUS

1. Unit Name:

Pilgrim I Nom April, 1982

2. Reporting Period:

1998.

3. Licensed Thermal Power (MWt):

678.

4. Nameplate Rating (Gross MWe):

655.

5. Design Electrical Rating (Net MWe):

690.

6. Maximum Dependable Capacity (Gross MWe):

670.

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since List Report. Give Reasons:

1 None None

9. Power Level To which Restricted. If Any (Net MWe):

10. Reasons For Restrictions,if Any:

N/A This Month Yr.-to.Date Cumulative 719.0 2879.0 82319.0 I1. Hours in Reporting Period 572.3 646.5 56679.8

12. Number Of Hours Reactor Was Critical

13. React-Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator On.Line 444.0 449.0 54726.9

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 651048.0 651048.0 93468936.0

17. Gross Electrical Energy Generated (MWH) 221410.0 221410.0 31132644.0 212585.0 212585.0 29907069.0

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor 62.4 15.6 66.5 62.4 15.6 66.5 l

20. Unit Availability Factor 44.1 11.0 54.2

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 45.I 11.3 55.5 17.8 17.8 10.1

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date and Duration of Each):

None

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

Unit Operating

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Si*d 8206010

• n

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION Summary of Operations for April, 1982 On April 1, the reactor was critical and power was being increased in prep-aration for a turbine roll. At 0203 hours0.00235 days <br />0.0564 hours <br />3.356481e-4 weeks <br />7.72415e-5 months <br />, commenced turbine roll and increased speed. At 0213 it was observed that there was no oil flowing from the #7 bearing. The turbine was immediately tripped, investigation conducted, and reactor power reduced to hot standby. At 1246 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.74103e-4 months <br /> the main steam isolation valves went closed due to high reactor water level and the reactor scrammed.

While awaiting repairs to the turbine bearing, the reactor was brought critical for operator training on April 2 from 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br /> until 1805 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.868025e-4 months <br />.

At 1805 the reactor was brought sub-critical and placed in cold shutdown at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br />.

l On April 5, at 0013 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> the reactor was made critical and plant heat up commenced. At 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br /> a reactor shutdown was initiated due to a disparity in reactor water level instrumentation. At 0528 hours0.00611 days <br />0.147 hours <br />8.730159e-4 weeks <br />2.00904e-4 months <br /> the level disparity was corrected and reactor heat up recommenced.

1 On April 8, after turbine bearing repairs were completed, the mode switch was placed in RUN at 0153 hours0.00177 days <br />0.0425 hours <br />2.529762e-4 weeks <br />5.82165e-5 months <br />. At 0436 hours0.00505 days <br />0.121 hours <br />7.208995e-4 weeks <br />1.65898e-4 months <br /> the unit was synchronized to the grid and power was increased to 25%. At 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br /> the unit was taken off the grid for turbine control and overspeed testing. At 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> the reactor scrammed on high pressure due to turbine testing. The Reactor was again f

brought critical at 2212 hours0.0256 days <br />0.614 hours <br />0.00366 weeks <br />8.41666e-4 months <br />.

1 At 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> on April 9, the mode switch was placed in RUN and at 1521 hours0.0176 days <br />0.423 hours <br />0.00251 weeks <br />5.787405e-4 months <br />, i

the unit was again synchronized to the grid and power was increased to 25%.

l At 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br /> the unit was taken off the grid for turbine control and overspeed testing.

The unit was again synchronized to the grid at 0153 hours0.00177 days <br />0.0425 hours <br />2.529762e-4 weeks <br />5.82165e-5 months <br /> on April 10 and power increased in accordance with PC10MR's, until 1535 hours0.0178 days <br />0.426 hours <br />0.00254 weeks <br />5.840675e-4 months <br /> on April 11 when it was observed that excessive hydrogen seal oil was showing up in the gen-erator liquid level detectors while increasing hydrogen pressure on the generator.

Power was reduced to 50% and an investigation conducted. Hydrogen pressure on the generator and seal leakage decreased. Reactor power was then increased to obtain 500 MWe output as limited by the hydrogen pressure.

[

t On April 16 at 2302 hours0.0266 days <br />0.639 hours <br />0.00381 weeks <br />8.75911e-4 months <br /> the unit was taken off line for a mini outage to l

repair the hydrogen seal. The reactor was maintained in Hot Standby until April 19 when the seal repairs were completed. At 1038 hours0.012 days <br />0.288 hours <br />0.00172 weeks <br />3.94959e-4 months <br />, the mode switch was claced in RUN and the unit was synchronized to the grid at 1137 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.326285e-4 months <br />.

Power was increased per PCIOMR control.

f j

The unit continued to operate for the remainder of April with fluctuations for condenser delta temperature, condensate demineralizer delta pressure, turbine i

pressure controller problems, and fouling of the seawater scieens. Maximum i

reactor power attained during the month was 96%.

page 1 of 2 i

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Safety / Relief Valve Challenges for April, 1982 Report Requirement: TMI T. A.P.

II.K.33 No Safety / Relief Valve challenges experienced during the Month of April, 1982.

page 2 of 2

_I

AVERAGE DAILY UNIT POWER LEVEL 50-293 DOCKET NO.

Pilgrim I WIT 05/14/82 DAE f.T. McLoughlin I

COMPLETED BY 617-746-7900 i

APRIL, 1982 MONTH i

I DAY AVERAGE D AILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe. Net)

(MWe. Net) l 0

0 g7 1

2 0

gg 0.

0.

175.

3 39 4

0.

20 463.

0.

544.

5 31 6

0.

22 532.

j 0.

478.

7

,3 21.

477.

3 24 0.

535.

9 25 10 106.

26 637.

11 m

27 As1.

306.

609.

12 23 415.

603.

13 29 663.

14 30 N/A l

15 477.

31 16 462.

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INSTRUCTIONS On this format. list the average daily unit power levelin MWe Net for each dsy in the reponing month. Compute to the nearest whole megawat I

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I REFUELING INFORMATION i

The following refueling information is included in the Monthly Report as requested in a letter to Mr. G. C. Andognini dated January 18, 1978:

For your convenience, the information supplied has been enun.erated so that i

each number corresponds to equivalent notation utilized in the request.

1.

The name of this facility is Pilgrim Nuclear Power Station, D2)cket Numlier 50-293.

2.

Scheduled date for next Refueling Shutdown:

Sep tember, 1983 l

3.

Scheduled date for restart following refueling: November, 1983-4.

(See 5 below) 5.

Due to their similarity, requests 4, 5, & 6 ard responded to collectively:

6.

The fuel,' which had been loaded during the 1981 scheduled refueling outage, is of the same P8x8R desi.gn, as loaded the previous outage con-sisting of 112 P8DRB282 assemblies and 60 P8DRB265 assemblies.

7.

(a). There are 580 fuel assemblies in the core.

J (b) There are' ' 36 fuel assemblies in the speIt fuel pool.

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8.

(a)

The station is presently licensed to store 2320 spent fuel assemblies.

l The actual spent fuel storage capacity is 1770 fuel assemblies at j

present.

1 (b) The planned spent fuel storage capacity is 2320 fuel assemblies.

l 9.

With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 834 fuel assemblies.

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APRIL 1982 MAJOR SAFETY RELATED MAINTENANCE CORRECTIVE ACTIO!!

ASSOCIATED SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE TO PREVENT RECURRENCE LER D

30 SWS Pump Piping None N/A Inspection N/A Inspection'of Interior Piping D

29 "A" RBCCW Piping N/A N/A Inspection N/A 4

"A"

& "B" Sam-N/A N/A Preventive N/A ple Pumps Stack Maintenance

~

4 "A"

& "B" Rx N/A N/A Preventive N/A Bldg. Sample Maintenance

• 64 Diesel Didn't Meet Tim-Tack Isolated Event UNASSIGNED ing Specs Switcher 82-008/01X-0 Various MOV Limitorque Missing Jumpers Construc-Install if found Engineering Support Request gener-tion or missing.

ated to investigate additional Maint.

circuits as they are worked on.

error 46K 24 "B" Battery Low Specific Age Replace two N/A N/A Gravity cell groups 14 Core Spray valve None Under in-Replace broken Under investigation M/A MOV. 1400-4B vestigation bolts e

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PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE (ISC)

Month April, 1982 CORRECTIVE ACTION LER SYSTEM COMPONENT MALFUNCTION CAUSE I&C TO PREVENT RECURRENCE ASSOCIATED 14 Yarway Level Erroneous Level Air in Back filled SP 82-0'4 82-011/0lT 8

Inst.

Readings Reference Reference Leg Leg 23 H1'Cl Hi Temp Temp Switch Unable to New switch Temp Switch to be sent to 82-13/03L Isolation failed to close determine installed manufacturer to determine actual

, Switch cause 23, HPCI High Calculations-for G.E.

Recal. Flow Recal. Flow Switches to new setpoint 82-07/0lX 13 RCIC Flow 300% flow in provided Switches provided by Engineering.

12 RWCU Trips error.

original set points in error 0

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50-293 IINil SilUIDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME PILGRIM I DATE 05/14/82 COMPLETED BY M.T. McLoughlin REPORT MONill APRIL, 1982 617-746-7900 ELEPil0NE t

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$ $3 I itensee

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Cause & Corrective No.

D.r. t g

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jg5 Event 3?

Action to go F

$E 35c Report #

uf u Present Recurrence o

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O 18 81/09/26 S

172.6 C

2 N/A RC FUELXX Refuel / Modification Outage 19 82/04/08 F

36.8 P

3 N/A HA XXXXXX Turbine testing caused high Rx. pressure 20 82/04/16 F

60.6 A

1 NA HA XXXXXX Hydrogen seal oil leak.

Rx. to reduced pressure, then standby for repairs.

I 2

3 4

F: Forced Reason:

Mettual:

Exhibit G - Instructions S: Scheduled A. Equipment Failure (Explain) 1 -Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram-Entry Sheets for I.icensee C Refueling 3 Automatic Scram.

Event ReporI (LER) File (NUREG-D-Regulatory Restriction 4-Ot her (Explain) 0161)

E Operator Training & l.icense lixamination F Administrative 5

G Operational livror (Explain)

Exhibit 1 - Same Source

• ,(9/77)

Il Other (Explain)