ML20100H077
| ML20100H077 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/31/1995 |
| From: | Maynard O WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| WO-96-0022, WO-96-22, NUDOCS 9602270053 | |
| Download: ML20100H077 (9) | |
Text
.
9 o
WFLF CREEK NUCLEAR OPERATING CORPORATION Otto L. Maynard vio. erenm.ni operation.
February 22, 1996 WO 96-0022 U.
S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Station F1-137 Washington, D. C.
20555
Subject:
Docket No. 50-482:
1995 Annual Operating Report for Wolf Creek Generating Station Gentlemen:
The attached Annual Operating Report is being submitted pursuant to Wolf Creek Generating Station, Unit No.
1, Technical Specifications 6.9.1.4 and 6.9.1.5.
This report covers operations for the period of January 1, 1995, through December 31, 1995.
a Very truly yours, I
Otto L. Mayna OLM/jad Attachment i
cc:
L. J. Callan (NRC), w/a D. N. Graves (NRC), w/a W. D. Johnson (NRC), w/a J.
F. Ringwald (NRC), w/a j
J.
C.
Stone (NRC), w/a i
i I
9602270053 951231 PDR ADOCK 05000482 R
PUR 200150
/ g I
(
P.O. Bcx 411/ Burlington, KS 66839 / Phone: (316) 364-8831 An Equal Opportunity Employer MT/HC/ VET
)
Att:chment to NO 96-0022 Page 1 of 8:
1 m
h WOLF CREEK NUCLEAR OPERATING CORPORATION i
WOLF CREEK GENERATING STATION i
i DOCKET NO:
50-482 i
FACILITY OPERATING LICENSE: NPF-42 r
ANNUAL OPERATING REPORT REPORT NO. 11 2
a l
Reporting Period: January 1, 1995 through December 31, 1995 f
4 a
e e-
t Attcchment to WO 96-0022 Page 2 of 8 1
i EXECUTIVE
SUMMARY
This Annual Operating Report provides a summary of the operating experience at Wolf Creek Generating Station.
This report also provides a summary.of the major safety-related r..aintenance activities completed during the year, and covers the period beginning on January 1,
- 1995, and ending on December 31, 1995.
~
This Annual Operating Report is submitted in accordance with the requirements of Technical Specification 6.9.1.4 and contains the information required by Technical Specification 6.9.1.5.
The format of this report is similar to that provided in Regulatory Position C.1.b of Regulatory Guide 1.16, Revision 4,
August, 1975.
In 1995, the availability factor for Wolf Creek Generating Station (WCGS) was 98.5 percent with a capacity factor (using maximum dependable capacity) of W.7 percent. WCGS experienced a reactor trip in March. During the shutdown, several maintenance activities were completed.
In June, a circulating Water Pump trip resulted in reduced power operation for one day for troubleshooting and maintenance.
In September, WCGS experienced brief periods of manually initiated power fluctuation for maintenance.
In November, a pressurizer Power Operated Relief Valve (PORV) was inadvertently opened and immediately reclosed.
b b
a l
f
~
Attcchment to WO 96-0022 Page 3 of 8 1.
SUMMARY
OF OPERATING EXPERIENCE A summary of Wolf Creek Generating Station's operating experience and major safety-related maintenance activities completed during 1995 is provided by month below.
This information has been previously submitted in accordance with the requirements of Technical Specification 6.9.1.8 in the Monthly Operating Reports for January through December, 1995.
January The unit operated at or near 100% power, Modo 1, from January 1,
- 1995, through January 31, 1995.
February The unit operated at or near 100% power, Mode 1, from February 1,
- 1995, through February 28, 1995.
March The unit operated at or near 100% in Mode 1 from March 1 through March B.
At 1445, March 8, 1995, Wolf Creek experienced a reactor trip due to a faulty Reactor Trip Manual Actuation Switch.
While the unit was shut down, on March 10, 1995, the Solid State Protection System (SSPS) for both "A" and "B"
trains was modified in response to an industry concern, and to enhance system reliability.
On March 11, 1995, retorquing activities were completed to stop a minor leak on the Excess Letdown Heat Exchanger. At 0412 on March 12, 1995, AE V322 encapsulation (which was found leaking during containment inspection) was successfully repaired.
The plant was maintained in Mode 3 until entering Mode 2 at 0902 on March 12, 1995, with the reactor critical.
The plant was returned to Mode 3 at 2153 to resolve the discrepancy in the Estimated critical Condition (ECC) and actual critical conditions.
The plant entered Mode 2 at 0529, March 13, 1995, and entered Mode 1,
at 0947, March 13, 1995.
On March 14, 1995, at 0541, the unit was synchronized to the grid. Due to problems with a power sensing relay in the Electro-Hydraulic Control (EHC) cabinet which prevented switching the EHC control power from House Power to the Permanent Magnet Generator (PMG) power, the generator output breakers were reopened at 1703, and at 1713, the main turbine was manually tripped to allow repairs.
The unit remained at approximately seven (7) percent reactor power while repairs were made.
The Turbine was then synchronized to the grid at 2230 and power was increased.
The plant reached 100% power at 2140, March 16, 1995.
On March 18, at 0046, the plant commenced power reduction to 35%
for retest of STS AC-001.
The purpose of the power reduction to 35% was to retest Control Intercept Valve (CIV) 3 in accordance with STS AC-001,
" Main Turbine Valve Cycling Test."
When this test was performed March 15,
The surveillance was completed j
satisfactorily and power was increased.
Power was returned to 100% at 2328, and rod control was placed in automatic at 2330, March 18, 1995.
The plant operated at Mode 1,
and approximately 100%, through the rest of the month.
.~
Attcchment to'WO 96-0022 Paga 4 ef 8
. / -
4 i
1 The unit operated at or near 100% power, Mode 1,
from April 1,
- 1995, through April 31, 1995.
1 MAE t
The unit operated at or near 100% power, Mode 1,
from May 1,
- 1995, l
through May 31, 1995.
dunt f
The unit operated at or near 100% power, Mode 1,
from June 1,
- 1995, I
through June 17, 1995.
On June 18 at 2025, the "C"
Circulating Water l
Pump trlpped, and the unit was stabilized at 65% power, Mode 1. The pump trip was caused by the Field Monitor Relay actuation due to a burned
]
spot on the Field Potentiometer.
On June 18, at 2115, the unit commenced increasing Reactor power, which was stabilized at 74% for j
troubleshooting.
Power increase commenced again on June 19, at 1201, and the plant returned to 100% power, Mode 1, at 1527 on June 19, 1995.
2 The unit continued to operate at or near 100% power, Mode 1, until June
~
28, 1995, at 0237, when power was reduced to 71%, Mode 1, in preparation j
for removing "B"
Circulating Water Pump from service for maintenance.
l Power was returned to 100% power, Mode 1, at 1650 on June 28, 1995.
Power remained at or near 100% power, Mode 1, through the remainder of I
June, 1995.
1 JMlX The unit operated at or near 100 % power, Mode 1,
from July 1,
- 1995, j
through July 31, 1995.
August The unit operated at or near 100 % power, Mode 1, from August 1,
- 1995, through August 31, 1995.
A.
=
Attachment to WO 96-0022 Page 5 of 8 Santember The unit operated at or near 100% power, Mode 1, from September 1,
- 1995, through September 17,
- 1995, at 1200 when power was reduced at approximately 1.3% per hour for the scheduled outage of the Benton Line.
On September 18, 1995, at 0405, the unit stabilized at 78% power, 948 MWe.
On September 20, 1995, at 1329, the Benton Line was restored to service, and at 1427, the unit commenced power increase at 3% per hour from 947 MWe.
The unit experienced load loss caused by Turbine control irregularities during power increase, and at 1543, the unit stabilized at 760 MWe.
Following unit maintenance on Turbine control, at 2030 power was increased at 3% per hour. On September 21, 1995, at 1800, the unit stabilized at 100% power. On September 22, 1995, at 2003, the unit began power reduction at 3% per hour for additional Turbine control maintenance. On September 23, 1995, at 0558, the unit stabilized at 75%
power.
Maintenance was completed, and on September 23, at 1108, power was increased at 3% per hour.
On September 23, 1995, at 2222, the unit stabilized at 100% power, and maintained power through the remainder of September.
October The unit operated at or near 100% power, Mode 1, through the month of October, 1995.
j November I
The unit operated at or near 100% power, Mode 1,
through the month of November, 1995.
On November 3,
1995, at 1403, during the restoration section of Surveillance Test STS BB-004, *RCS Water Inventory Balance," the Reactor Operator inadvertently opened pressurizer Power Operated Relief Valve (PORV) BB PCV 456.
The PORV was immediately reclosed.
Reactor Coolant System pressure dropped to 2214 PSIG, but was restored to 2220 PSIG by 1405.
December The unit operated at or near 100% power, Mode 1, through the month of Z-December, 1995.
t s
/
Attachment to WO 96-0022 Page 6 of 8 2.
SUMMARY
OF OUTAGES AND FORCED POWER REDUCTIONS Provided below is a summary of the 1995 ' outages and forced power reductions of over 20 percent of design power level where the reduction extended for more than four hours:
1.
St art Date: March 8, 1995 Completion Date: March 18, 1995 Tyna:
Forced Duration:
249 hours0.00288 days <br />0.0692 hours <br />4.117063e-4 weeks <br />9.47445e-5 months <br /> Reason: Reactor trip caused by a faulty Reactor Trip Manual Actuation Switch.
2.
Start Date: June 18, 1995 Completion Date: June 19, 1995 Type Forced Duration:
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> Reason "C"
(Power reduction) 3.
Start Date: June 28, 1995 cnmpletion Date: June 28, 1995 Tyst: Scheduled Duration:
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Reason:
"C" Circulating Water Pump Maintenance.
(Power reduction) 4.
Start Date:
September 17, 1995 completion Date:
September 23, 1995 Type: Scheduled Duration:
80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> Reason: Scheduled outage of the Benton Line.
(Power reduction) 5.
Start Date: September 23, 1995 completion Date:
September 23, 1995 Tyna: Scheduled Duration:
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> Reason: Turbine Control Maintenance.
(Power reduction) b I
l 1
1
4 AttSchment to WO 96 0022 Pcg3 7 of 8 e
3.
EXPOSURE INFORMATION
- a. NtNBER OF PERSCINEL AND MAN RH4 BY NCRK AND JOB FUCI'ICN REPORT - 1995 WOLF CREEK NUCLEAR OPERATING CORPORATION - WCGS PO BOX 411 BURLINGTON, KANSAS 66839 LICENSE:
NPF-42 REGULATORY GUIDE 1.16 INFORMATION INTERIM REPORT FOR:
950101 PO 951231 PERSONNEL ( > 100 mrem )
TOTAL MAN. REM WORK AND JOB FUNCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT REACTOR OPERATIONS AND SURVEILLANCE MAINTENANCE AND CONSTRUCTION O
O O
0.306 0.000 0.134 OPERATIONS O
O O
0.685 0.120 0.001 HEALTH PHYSICS AND LAB 8
1 0
3.032 0.124 0.000 SUPERVISORY AND OFFICE STAFF 1
0 0
0.499 0.075 0.042 ENGINEERING STAFF 0
0 0
0.362 0.019 0.001 ROUTINE PLANT MAINTENANCE MAINTENANCE AND CONSTRUCTION O
O O
1.172 0.015 0.275 OPERATIONS 0
0 0
0.149 0.018 0.000 HEALTH PHYSICS AND LAB 0
0 0
0.289 0.033 0.000 SUPERVISORY AND OFFICE STAFF 0
0 0
0.561 0.001 0.181 ENGINEERING STAFF 0
0 0
0.587 0.015 0.043 INSERVICE INSPECTION MAINTENANCE AND CONSTRUCTION O
O O
0.073 0.000 0.003 OPERATIONS 0
0 0
0.002 0.000 0.000 HEALTH PHYSICS AND LAB 1
0 0
0.190 0.000 0.000 SUPERVISORY AND OFFICE STAFF 0
0 0
0.027 0.000 0.000 ENGINEERING STAFF 0
0 0
0.032 0.000 0.004 SPECIAL PLANT MAINTENANCE MAINTENANCE AND CONSTRUCTION 1
0 4
0.631 0.092 0.965 OPERATIONS 0
0 0
0.000 0.000 0.000 HEALTH PHYSICS AND LAB 0
0 0
0.206 0.013 0.000 SUPERVISORY AND 05FICE STAFF 0
0 0
0.099 0.000 0.000 ENGINEERING STAFF 0
0 0
0.085 0.004 0.000 WASTE PROCESSING MAINTENANCE AND CONSTRUCTION O
O O
0.274 0.000 0.018 OPERATIONS 1
0 0
0.416 0.003 0.047 HEALTH PHYSICS AND LAB 3'
O O
1.912 0.014 0.000 SUPERVISORY AND OFFICE STAFF 0
0 0
0.088 0.000 0.000 ENGINEERING STAFF 0
0 0
0.018 0.000 0.000 REFUELING MAINTENANCE AND CONSTRUCTION O
O O
0.053 0.000 0.000 OPERATIONS 0
0 0
0.057 0.000 0.000 HEALTH PHYSICS AND LAB 0
0 0
0.017 0.001 0.000 SUPERVISORY AND OFFICE STAFF 0
0 0
0.040 0.000 0.000 ENGINEERING STAFF 0
0 0
0.044 0.000 0.002 TOTALS 1
MAINTENANCE AND CONSTRUCTION 1
0 4
2.509 0.107 1.395 CPERATIONS 1
0 0
1.310 0.141 0.048 HEALTH FHYSICS AND LAB 12 1
0 5.646 0.185 0.000 SUPERVISORY AND OFFICE STAFF 1
0 0
1.313 0.076 0.223 I
ENGINEERING STAFF 0
0 0
1.127 0.039 0.050 GRAND TOTALS 15 1
4 11.905 0.547 1.716 Number of personnel > 100 mrem based en PIC data Total man. rem based on ratio of PIC data applied to TLD data Actual total mrem = 14169 (numbers may vary due to rounding) 1 i
Attechment-to WO 96-0022
.Page 8 of 8 i
4.
SINGLE RELEASE OF RADIOACTIVITY OR RADIATION EXPOSURE GREATER THAN 10 PERCENT OF ALLOWABLE ANNUAL VALUES During 1995, no single release of radioactivity exceeded 10 percent of the allowable annual value.
l 5.
CHALLENGES TO THE PORVS AND SAFETY VALVES On November 3,
1995, at 1403, during the restoration section of Surveillance Test STS BB-004, "RCS Water Inventory Balance," the Reactor Operator inadvertently opened Pressurizer PORV BB PCV 456.
The PORV was immediately reclosed.
Reactor Coolant System pressure dropped to 2214 PSIG, but was restored to 2220 PSIG by 1406.
6.
INDICATIONS OF FAILED FUEL on June 30, 1995 the initial indication of failed fuel was observed.
The Xenon-133/ Xenon-135 activity ratio began an upward trend.
By the end of 1995, the Reactor Coolant fission product activity continued to increase. Assuming average assembly power, it was estimated that 3 to 6 leaking fuel pins existed.
No power reductions of sufficient magnitude occurred to assess the failed assembly burnup.
The defects appeared to have opened significantly er.ough to allow the increase in the Reactor Coolant I-134 and Np-239 concentrations.
The actual number of defects will be determined during Refuel VIII.
7.
REACTOR COOLANT SYSTEN SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL SPECIFICATION 3.4.8 LINITATION l
The Reactor Coolant System Specific Activity did not exceed the Technical Specification 3.4.8 limitation during 1995.