ML20128N261
| ML20128N261 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/30/1996 |
| From: | Cannon R, Olivier L BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BECO-LTR#96-087, BECO-LTR#96-87, NUDOCS 9610160334 | |
| Download: ML20128N261 (7) | |
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Tech. Sptc. 6.9.A.2 h
Boston Edison Pilgrim Nuclear Power Staten Rocky Hdi Road Plymouth, Massachusetts 02360 i
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1 L J. Olivier Vice President Nuclear operations October 11, 1996 and station oirector BECo Ltr. #96 087 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Docket No. 50-293 License No. DPR-35 SEPTEMBER 1996 MONTHLY REPORT in accordance with Pilgrim Nuclear Power Station Technical Specification 6.9.A.2, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning. Should you have any questions concerning this report, please contact me directly.
s cp J. Olivier RLC/dmc/9458 i
Attachment cc: Mr. Hubert Miller Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident inspector l
l 9610160334 960930' PDR ADOCK 05000293 R
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160072
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4 OPERATING DATA REPORT DOCKET NO.
50-293 NAME:
Pilarim CGAPLETED BY:
R.L. Cannon ELEPHONE:
_L508) 830-8321 i
,dPORT MONTH September 1996 OPERATING STATUS NOTES 1.
Unit Name -
Pilgrim I 2.
Reporting Period September 1996 3.
Licensed Thermal Power (MWt) 1998 4.
Nameplate Rating (Gross MWe) 678 5.
Design Electrical Rating (Net MWe) 655 I
6.
Maximum Dependable Capacity (Gross MWe) 696 i
7.
Maximum Dependable Capacity (Net MWe) 670 1
8.
If Changas Occur in Capacity Ratings (Item Number 3 Through 7) Since Last Report, Give Reasons:
No Chanaes i
9.
Power Level To Which Restricted, if Any (Net MWe): None 10.
Reasons For Restrictions, if Any: N/A This Month Yr-to-Date Cumulative.
11.
Hours in Reporting Period 720.0 6575.0 208727.0 12.
Hours Reactor Critical 431.3 6171.8 132437.9 13.
Hours Reactor Reserve Shutdown 0.0 0.0 0.0 14.
Hours Generator On-Line 415.2 6137.1 127961.0 15.
Hours Unit Reserve Shutdown 0.0 0.0 0.0
.16.
Gross Thermal Energy Generated (MWH) 765315.0 11881061.0 228183231.0 l
17.
Gross Electrical Energy Generated (MWH) 2_58120.0 4059840.0 77337164.0 18.
Net Electrical Energy Generated (MWH) 248164.0 3910432.0 74354054.0 19.
Unit Service Factor 57.7 -
93.3 61.3 20.
Unit Availability Factor 57.7 93.3 61.3 21.
Unit Capacity Factor (Using MDC Net) 51.4 88.8 53.2 22.
Unit Capacity Factor (Using DER Net) 52.6 90.8 54.4 23.
Unit Forced Outage Rate 0.0 0.0 11.5 4
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)-
RFO-11, February 2,1996,42 days 25.
If Shutdown at ind of Report Period, Estimated Date of Startup -
UNIT OPERATING
. ~.. -...... -
i i
i AVERAGE DAILY UNIT POWER LEVEL J
DOCKET NO, 50-293 NAME:
Pilarim COMPLETED BY:
R.L. Cannon i
TELEPHONE:
(508) 830-8321 REPORT MONTH September 1996 a
J j
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net).
1
-652 17 607 2
546 18 7
.l' 3
496 19 0
4 593 20 0
5 655 21 0
l 6
652 22 0
i i
7 353 23 0
8 538 24 0
9 655 25 0
10 656 26 0
i 11 647 27 0
i 12 654 28 0
13 653 29 0
14 649 30 21 15 654 5
l 16 653 i
i This format lists the average daily unit power level in MWe-Net for each day in the reporting month, computed l
to the nearest whole megawatt.
1 4
i l
OPERATIONAL
SUMMARY
DOCKET NO.
50-293 NAME:
Pilarim COMPLETED BY:
R.L. Cannon TELEPHONE:
(508)830-8321 REPORT MONTH September 1996 Th3 unit started the reporting period at 100 percent core thermal power (CTP) where it was maintained until S:ptember 2,1996, at approximately 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br /> when power was reduced to approximately 72 percent due to a 345 kv line being out of service due to a hurricane. Following restoration of the 345 kv line, reactor power was raised to approximately 90 percent CTP on September 2,1996, at approximately 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br />.
Th3 hurricane's effect on the plant lead to a degree of main condonser tubesheet fouling and subsequent d: graded performance of the main condenser. Reactor power was limited to maintain main condenser parameters with in operationallimits. To maintain hotwell temperature below 120 degrees Fahrenheit, reactor power was maintained at approximately 90 percent CTP until 0555 on September 3,1996, when reactor power was raised to 95 percent CTP. On September 3,1996, at approximately 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> reactor power w s reduced to approximately 50 percent CTP to perform a backwash of the main condenser. Following completion of the main condenser backwash, power ascension commenced at approximately 2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br /> on S:ptember 3,1996. Reactor power reached approximately 80 percent CTP at approximately 0215 on S:ptember 4,1996, when a pre-conditioning ramp rate was established. This was maintained until 1900 t
hours on September 4,1996, when 100 percent CTP was achieved.
Ons hundred percent CTP was maintained until approximately 0007 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> on September 7,1996 when reactor power was reduced to approximately 50 percent CTP in preparation for control rod pattem change.
On September 7,1996, at upproximately 1142 hours0.0132 days <br />0.317 hours <br />0.00189 weeks <br />4.34531e-4 months <br /> reactor power was raised to approximately 70 percent CTP where it was maintained for surveillance and maintenance activities. On September 7,1996, at app oximately 2246 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.54603e-4 months <br /> reactor power was reduced to approximately 50 percent CTP in preparation for a th:rmal backwash of the main condenser. At approximately 0740 hours0.00856 days <br />0.206 hours <br />0.00122 weeks <br />2.8157e-4 months <br /> on September 8,1996, power asc:nsion commenced to increase reactor power to 100 percent CTP. One hundred percent CTP was achieved on September 8,1996, at approximately 2043 hours0.0236 days <br />0.568 hours <br />0.00338 weeks <br />7.773615e-4 months <br /> where it was maintained until approximately 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on September 11,1996, when reactor power was reduced to approximately 90 percent CTP to make mechanical adjustments to feed water regulating valve "A" At approximately 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, reactor CTP w s raised to 100 percent where it was maintained until approximately 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on September 17,1996, wh:n a normal plant shutdown was initiated due to a crack in the shell of the reactor building closed cooling water (RBCCW) heat exchanger. At 0150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> on September 18,1996, the plant was taken off-line to facilitate maintenance to the Loop "B" RBCCW heat exchanger. On September 29,1996, at approximately 2140 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.1427e-4 months <br />, the reactor was brought to power, and the generator was synchronized to the grid at approximately 1850 on September 30,1996. The period ended with the reactor in power ascension with the reactor at approximately 81 percent CTP.
SAFETY REllEF VALVE CHALLENGES MONTH OF SEPTEMBER 1996 Requirement:
NUREG-0737 T.A.P. II.K.3.3 Th:re were no safety relief valve challenges during the reporting period.
An SRV challenge is defined as anytime an SRV has received a signal to operate via reactor pressure signal (ADS) or control switch (manual). Reference BECo Ltr. #81-01 dated January 5,1981.
REFUELING INFORMATION DOCKET NO.
54293 NAME:
Pilarim COMPLETED BY:
R.L. Cannon
(
TELEPHONE:
(508) 830-8321 REPORT MONTH September 1996 l
Th3 following refueling information is included in the Monthly Report as requested in an NRC letter to BECo, 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 Number 50-293.
2.
Scheduled date for next refueling shutdown: February 1,1997.
3.
Scheduled date for restart following next refueling: March 14,1997.
4.
Due to their similarity, requests 4,5, & 6 are responded to collectively under #6.
5.
See #6.
1 6.
The new fuel loaded during the 1995 refueling outage (RFO-10) is of a different design than that loaded in the previous refueling outage and consists of 136 new fuel assemblies.
7.
(a)
There are 580 fuel assemblies in the core.
(b)
There are 1765 fuel assemblies in the spent fuel pool.
8.
(a)
The station is presently licensed to store 3859 spent fuel assemblies. The spent fuel storage capacity is 2891 fuel assemblies. However,23 spent fuellocations cannot be used due to refuel bridge limitations.
(b)
The planned spent fuel storage capacity is 3859 fuel assemblies.
9.
With present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 1103 fuel assemblies.
PILGRIM NUCLEAR POWER STATION MAJOR SAFETY RELATED MAINTENANCE DOCKET NO.
50-293 NAME:
Pilorim COMPLETED BY:
R.L. Cannon TELEPHONE:
(508) 830-8321 REPORT MONTH September 1996 SYSTEM COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ASSOCIATED ACTION TO LER PREVENT RECURRENCE RBCCW Heat exchanger Through-wall crack Cyclic fatigue Performed a weld Modify heat LER 96-008-00 in end bell repair exchangerin RFO-11 Oth r maintenance activities performed in accordance with contingency outage schedule plus emergent issue maintenance activities.
r i
6 9
m
.m
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-293 NAME-Pilorim COMPLETED BY:
R. L. Carinon TELEPHONE:
(508) 830-8321 REPORT MONTH September.1996 i
METHOD OF LICENSE SYSTEM COMPONENT CAUSE & CORRECTIVE i
TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO PREVENT NO.
DATE 1
(HOURS) 2 REACTOR REPORT 4
5 RECURRENCE 20 09/02/96 F
0.0 B
N/A N/A N/A N/A Power reduction due to a 345 6
kv line being out of service.
[
21 09/03/96 S
0.0 B
N/A N/A N/A N/A Pcwer reduction due to rod pattem change.
A/A Power reduction to perform a i
22 09/G7/96 S
0.0 B
N/A N/A N/A thermal backwash of the l
l 23 09/07/96 S
0.0 B
N/A N/A N/A N/A Power reduction to perform backwash of main condenser l
24 09/17/96 F
291.4 A
1 96-008-00 CC HX A through-wall longitudinal crack in channel cylinder due to fatigue caused by cyclic loading o. the attached lower partition plate. The crack was weld repaired. New channel design to be installed in RFO-11.
I 1
2 3
4&5 F-Forced A-Equip Failure 1-Manual Exhibit F & H S-Sched B-Main or Test 2-Manual Scram Instructions for C-Refueling 3-Auto Scram Preparations of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report
& License Examination 9-Other (LER) File (NUREG-1022)
F-Admin G-Operator Error H-Other 4
.