ML20064C318

Annual Operating Rept 9,Reporting Period:Jan-Dec 1993

ML20064C318
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1993
From:	Maynard O WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
WO-94-0020, WO-94-20, NUDOCS 9403090287
Download: ML20064C318 (11)

Text

,

t

,=

1 LF CREEK W@ NUCLEAR OPERATING C Otto L. Maynard Vice President Plant Operaftons February 28, 1994 WO 94-0020 U.

S.

Nuclear Regulatory Commission ATTN:

Document Control Desk Mail Station F1-137 Washington, D.

C. 20555

Subject:

Docket No. 50-402:

1993 Annual Operating Report for Wolf Creek Nuclear 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.

Also included in this report is information required by 10 CFR 20.407.

This report covers operations for the period of January 1, 1993, to December 31, 1993.

Very truly yours,

[c

?)l_../f '

Y k j 9 t' ( g '

(

otto L.'Maynard Vice President Plant Operations OLM/jad Attachment cc:

E.

S. Beckjord (NRC), w/a L.

J.

Callan (N RC ), w/a G. A.

Pick (NRC), w/a I g W.

D.

Reckley (NRC), w/a L. A.

Yandell (NRC), w/a f

i 7hi.',)

3 l i

pn Box 411/ Burkngton, KS 66839 / Phone. (3t6) 364-8831 9403090287 931231 An cauar pauraty Empiover Mer/scevtT PDR ADOCK 05000482 R

PDR

. ~ ~.

Attachment to WO 94-0020 Parje,1 of 10 P

4 4

N WOLF CBEEK NUCLEAR OPERATING CORPORATION A

WOLF CREEK GENERATING STATION DOCKET NO:

50-402 FACILITY OPERATING LICENSE:

HPF-42 ANNUAL OPERATING REPORT REPORT NO.

9 1

l l

l Reporting Period:

January 1, 1993 through December.31, 1993 i

I

' Attachment to wo 94-0020 Page.2 of 10 EXECUTIVE

SUMMARY

The purpose of the Annual Operating Report is to provide a comprehensive summary of the operating experience at Wolf Creek Generating Station.

The Annual Operating Fepot t also provides a summary of the major safety related maintenance activities completed during the year.

This report covers the-period beginning on January 1, 1993, and ending on December 31, 1993.

The Annual Operating Report is submitted in accordance with the requirements of Technical Specification 6.9.1.4 and contains the information required by l

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.

Also included in this report is the information on personnel monitoring. as required by 10 CFR 20.407.

In 1993, Wolf Creek Generating Station's availability factor was 79.9 percent and capacity factor (using maximum dependable capacity) was 79.6 percent.

Wolf Creek Generating Station experienced no unplanned reactor trips or forced power reductions.

The unit completed its sixth refueling outage in May, and underwent a power terate in November.

1 7

n I

l i

Attachment to WO 94-0020

'Page.3 of 10 1.

SUMMARY

OF OPERATING EXPERIENCE A summary of Wolf Creek Generating Station's operating experience and major safety related. maintenance activities completed during 1993 is provided by month below.

"1 hi s 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, 1993.

1 January The unit operated at or near 100 percent power throughout the month of January.

No major safety related maintenance' activities were performed during the month of January.

i February

~

The unit operated at or near 100 percent power throughout the month of February.

No major safety related maintenance activities were performed during' the month of February.

March The unit began the month at 100 percent power.

A 3% per. hour power decrease was initiated at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> March 3,

1993, '. to remove the unit from service for refueling.

The main generator output breakers Refuel VI.

~

were opened at 2353 hours0.0272 days <br />0.654 hours <br />0.00389 weeks <br />8.953165e-4 months <br /> March 4,

1993, to of fi cially commence Major safety related maintenance activities for March:

a.

Maintenance on 4160 Volt Bus NB02.

b.

Maintenance on Emergency Diesel Generator "B" thrust bearing and housing.

c.

Maintenance on Emergency Diesel Generator "B"

shaft.

d.

Maintenance on "A" RHR Pump motor rotor, e.

Eddy current testing on "B"

Steam Generator, f.

Work on Power Operated Relief Valves.

i i

7

~.

.._. _.._.--_ _. -, -. _ _ _ _ - _ _.. _.. - _ - _.. _ _ _ - - -. ~. _ _ _.. _ _.. _.. _ _,_ _.- _. _..

1-Attachment to WO 94-0020 Page,4 of 10 Ac ril i

The unit remained shutdown the entire. month of April, 1993,- as activities associated with Refuel VI continued.

The unit began the i

s month with all fuel removed from the core.

The plant entered Mode 6, Refueling, on April 6,

when fuel loading for Cycle VII commenced.-

s' Mode 5, Cold shutdown, was entered on April 16, and continued through the end of the month.

3i Major safety related maintenance activities for April:

a.

Maintenance on "B" Centrifugal Charging Pump, i

F i

b.

Maintenance on "A" and "B" Emergency Diesel Generators.

c.

Maintenance on Pressurizer Safety Relief Valves.

l t ay j

The unit completed its sixth refueling outage in May, the generator output breaker being closed May 17, 1993 at 0719 hours0.00832 days <br />0.2 hours <br />0.00119 weeks <br />2.735795e-4 months <br />.

Power ascension activities then took place, with the unit reaching full power at 0937 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.565285e-4 months <br /> May 21, 1993, and remaining at or near full power for the remainder of the month.

' +

i No major safety related maintenance activities were performed during f

1 the month of May.

- l June

{

4 The unit operated at or near 100 percent power throughout the month-

{

of June, j

No major safety related maintenance activities were performed during i

the month of June.

l i

July 4

The unit operated at or near 100 percent power throughout the month of July.

l

~

No major safety related maintenance activities-were performed:during the month of July.

August e

The unit operated at or near 100 percent power throughout the month i

of August.

i No. major safety related maintenance activities were performed during i

the month of August.

t J :

a t

I ow-T-er wr-w a wmw %.nw

+e.---.ww+---m

.. w w%.-.-------m-+-..--.-,-,-_--------,-.----...-~.-4.--m,--,w-ee-%

w,-.-4,-.----+==.---=-,#-r-.-.

,. -w-n-=c

^

l

Attachment to WO 94-0020 Page 5 of.10 September The unit operated at or near 100 percent power throughout the' month of September.

No major safety related maintenance activities were performe'd during the month of September.

October The unit operated at or near 100 percent power throughout the month of October.

No major safety related maintenance activities were performed during the month of October.

November On November 18, 1993, the unit was placed at 95% power in preparation for a power terate f rom 3411 MW(t) to 3565 MW (t).

On November 20, 1993, maximum rated thermal power was changed to 3565 MW(t).

The unit was placed at 97% power after power rerate for. the duration of the month, as a result of turbine nozzle inlet restrictions.

No major safety related maintenance activities were perf ormed - during the month of November.

r,lecembe r The unit operated at or near 97 percent power throughout the month of December.

Full power could not be achieved due to turbine nozzle -

inlet restrictions.

No major safety related maintenance activities were performed during the month of December.

2.

SUMMARY

OF OUTAGES AND FORCED POWER REDUCTIONS Provided below is a summary of the 1993 outages and forced power reductions of over 20 percent of design power level where the reduction extended for more than four hours.

1.

Start Date:

03/03/93 Completion Date:

05/17/94 Type:

Refueling Duration:

1758.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> f.

Reason: Manual shutdown on March 3, 1993 for sixth. refueling outage.

e l

-n

4 -

1 Attachment to WO 94-0020 l

Page 6 of 10 i

i 3.

EXPOSURE INFORMATION

[

a.

NUMBER OF PERSONNEL AND MMi-REM BY WORK AND JOB FUNCTION REPORT - 1993-IERSONNEL (> 100 mrem )I TOTAL MAN-REM2 WORK AND JOH Fl'NCTION STATION UTILITY CONTRACT STATION UTILITY CONTRACT l

EfE"FOa OFiiXTIONS AND SURVE!Li/WCE MAINTENANCE N4D CONSTRUCTION '

O O

4 0.565 0.000 1.811 l

OLERATIONS 11 0

0 4.286 0.300 0.272 HEALTH PHYSICS AND MB 22 0

33 6.992 0.051 9.742 SUPERVISORY AND OFFICE STAFF 5

0 2

1.706 0.021 1.171 FNGINEERING STAFF 7

0 4

2.697 0.190 0.909 ROUTINE FLANT MAINTENANCE MAINTENANCE AND CONSTRUCTION 14 0

28 6.323 0.000 14.593 OPERATIONS 2

0 0

0.501 0.010 0.026 HEALTH rilYSICS AND LAB 0

0 0

0.338 0.010 0.354 1

CUf ERVISORY MlD OFFICE STAET 2

0 0

1.123 0.005 1.013 ENGINEERING STAFF 0

0 0

0.406 0.000 0.201 INSERVICE INSEECTION MAINTENANCE AND CONSTRUCTJON 16 0

17 3.974 0.000 4.116 l

OFERATIONS O

O O

0.054 0.000 0.010 HEALTH PHYSICS AND LAD 1

0

'12 0.544 0.000 3.288 e

SUEERVISORY AND OFFICE STAFF 3

0 2

1.166 0.000 1.207 l'

ENGINEERING STAFF 3

1 27 0.958 0.123 14.607 SPECIAl,ILANT MAINTENANCE l

MAINTENANCE AND CCHSTRUCTION 34 0

123 10.463 0.013 40.804

]

OIERATIONS 1

0 0

0.171 0.000 0.001 NEALTH OHYSICS AND LAB 5

0 4

2.087 0.000 1.911 SUPERVISORY MID OFFICE STAFF 4

0 2

1.090 0.000 1.858 ENGINEERING STAFF 4

0 22 1.987 0.134 5.480 WASIE IFiOCESSING MAINTENANCE AND CONSTRUCTION 1

0 0

0.561

'0.010 0.292

[

I

}

OPERATIONS 0

0 1

0.092 0.000

'O.457 j

HEALTH OHYSICS AND LAD 20 0

23 6.870 0.010 6.%2 DU1'ERVISORY AND OFFICE STAF F 1

0 0

0.180 0.00n 10.010 ENGINEERING STAFF 0

0 0

0,000 0 000 0.000 REENELING MAINTENANCE AND COMTRUCTION 35 0

36 7.429 0.000 7.962 OIERATIONS 1

0 0

0.462 0.000 0.134 HEALTH EHYSICS AND LAD 3

0 2

0.847 0.000 2.244 I

SUEERVISORY AND OFFICE STAFF 2

0 2

0.647 0.021 0 452 l

ENGINEERING STAFF 0

0 1

0.349 0.031 1.756 l

TOTA l

MAmTENANCE AND CONSTPUCTION 100 0

208 29,315 0.024 69.638 OIERATIONS 15 0

1 5.567 0.316 0.900 g

i-HEALTH FHYSICS AND LAB 51 0

74 17.679 0.072 24.101 I

SUTE RVISORY AND OFE ICE STAFT 17 0

8 5.912 0.046 5.711 I

ENGINEERING STAFF 14 1

54 6.398 0.477 16.954 l

EIU.ND TOTALS 197 1

34b 64.871 0.938 117.304 I

(

Number of persennel > 100 mren based on EIC data 2

i l

Tetal man-rem based on ratio of Plc clata applied to TLD data Actual total n, Rem = 183154 (numbers may vary due to rounding)

I I

I i

i F

6 I

=

f l

e e v nrer...

..-e-=.e-m.--eere--ww..-.n.

--e.-.-

-:r---

.v

--,---.--.-m.,

.-r-3--.

..w--

---

nsw-w.m.-.w

.-- we e m

_~..-

~

. ~

~ _...

~

Attachment to WO 94-0020

, ' Page 7 of 10 b.

PERSONNEL MONITORING REPORT

1. In 1993, 1728 individuals were provided personnel monitoring devices.

This information is provided in accordance with 10 CFR 20.407 (a) (2).

~

i This total includes the number of individuals. required to be reported.

under 10 CFR 20. 4 07 (a) (1).

2.

Below is a statistical summary report of the personnel monitoring information recorded for individuals for whom personnel monitoring was provided in 1993 in accordance with the requirements ' of 10 CFR 20.407(b).

Estimated whole body exposure range Number of (Rem) individuals in each range Measurable exposure...........

................................. 753 Measurable exposure less than 0..........

..................... 450

.1 to 0.25.................................................. 251 0.25 to 0.5

......................................... 185 0.5 to 0................

................. 71 0.75 to........................................................

16 1.0 to 2.0

........................................ 2 2.0 to 3.0

.................................................... 0 3.0 to 4.0..................................................... 0 4.0 to 5.0..................................................... 0 5.0 to 6.0..................................................... 0 6.0 to 7.0..................................................... 0 7.0 to 8.0..................................................... 0 I

8.0 to 9 0

.......................................... 0

+

9.0 to 10.0.................................................... 0 10.0 to 11.0

.................... 0 11.0 to 12.0................................................... 0 12.0.......................................................... 0

,-- - - ~, -,.

---,,.w..

e

-.,v.

~.

-n

Attachment to WO 94-0020

• Page,8 of 10 4.

SINGLE RELEASE OF RADIOACTIVITY OR RADIATION EXPOSURE GREATER THAN ' 10 PERCENT OF ALLOWABLE ANNUAL VALUES During 1993, there was no single release of radioactivity greater than ten percent of the allowable annual value.

On April 2,

1993, an Auxiliary Operator who had been working in the Radiologically Controlled Area was discovered to have a highly localized area of contamination on his left thigh.

The contamination was de t e rttined to be a discreet radioactive particle which probably originated from previous draining of the Reactor Cavity to a Containment drain trench.

The particle is believed to have been subsequently transferred to the operator when he was venting the Safety Injection System to the same drain trench.

The exposure was conservatively estimated, using the VARSKIN computer code, to be 33.902 Rem (eight micro-curie hours) to the skin of the whole body.

This exposure exceeded the 10 CFR 20.101 quarterly dose limit of 7.5 Rem for the skin of the whole body, but did not exceed the NRC Enforcement Policy on hot particles of 75 micro-curie hours.

This event was reported as Licensee Event Report 482/93-006-00.

5.

CHALLENGES TO THE PORVS AND SAFETY VALVES During 1993, there were no challenges to the Pressurizer Power Operated Relief Valves (PORVs) or Safety Valves.

6.

INDICATIONS OF FAILED FUEL During the sixth refueling

outage, a

broken fuel rod

segment, approximately 12 inches in length, was found protruding from fuel assembly F67 at core position H-6.

Subsequent inspections revealed additional defective fuel rods in fuel assemblies F43, F54 and F67.

Grid-to-rod fretting was identified as the principle failure mechanism.

Extensive investigations into these defects and those identified during the fifth refueling outage were indeterminate in identifying the exact root cause(s) for the failure mechanism.

However, fluid elastic i

instability of the fuel rods in the reactor core is considered to be a potential cause of the grid-to-rod fretting condition.

The Reactor Coolant fission product activity through the end of the year t

indicated only the presence of tramp uranium.

No defective fuel rods were predicted by the Iodine activity, Fission Gas activity, or the Fuel Reliability Indicator (FRI).

1 7.

REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL 3h.CIFICATION 3.4.8 LIMITATION On March 5,

1993, following reactor shutdown for the sixth refueling outage, it was determined through analysis that the specific activity of the RCS had exceeded the Technical Specification (T/S) 3.4.8.a limit of l

1 microcurie per ml Dose Equivalent I-131 (DEI).

The analysis results of the sample taken at 0403 hours0.00466 days <br />0.112 hours <br />6.66336e-4 weeks <br />1.533415e-4 months <br /> on March 5,

1993,-indicated 2.114 3

microcuries per ml DEI.

Maximum cleanup flow through the -Chemical and Volume Control System (CVCS) mixed bed demineralizer was maintained during the time that the specific activity exceeded the T/S limit.

The DEI was back within the limits of T/S by 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> on March 5, 1993.

l

-a

.. ~,

Attachment to WO 94-0020 Page 9 of 10 The following information is provided in accordance with T/S 6.9.1.5.c:

a.

Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was. exceeded:

On March 3, 1993, at 0403 hours0.00466 days <br />0.112 hours <br />6.66336e-4 weeks <br />1.533415e-4 months <br />, reactor power was approximately 100 percent.

At 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on March 3,

1993, a 3% per hour power reduction was commenced for the sixth refueling outage.

The unit

- 6 entered Mode 3 Hot Shutdown, at 0314 hours0.00363 days <br />0.0872 hours <br />5.191799e-4 weeks <br />1.19477e-4 months <br /> on March 5, 1993, and remained at 0% power until 0403 hours0.00466 days <br />0.112 hours <br />6.66336e-4 weeks <br />1.533415e-4 months <br /> on March 5,

1993, when the sample was drawn,

b. Results of the isotopic analyses for radiciodine:

Sample I-131 I-132 I-133 I-134 I-135 DEI DATE r. TIME UCI/ML UCI/ML UCI/ML UCI/ML UCI/ML UCI/ML 3/4/93 1318 3.021E-02 6.219E-02 4.425E-02 4.374E-02 4.148E-02 4.863E-02 3/4/93 2048 9.721E-02 1.454E-01 1.062E-01 6.502E-02 7.748E-02 1.388E-01 3/5/93 0403 1.738E+00 5.963E-01 1.191E+00 3.149E-02 3.899E-01 2.114E+00 3/5/93 0550 1.564E+00 4.794E-01 1.035E+00 1.062E-02 3.017E 1.887E+00 3/5/93 0802 1.456E+00 4.321E-01 8.867E-01 2.255E-03 2.210E-01 1.729E+00 3/5/93 0832 1.365E+00 4.207E-01 8.203E-01 0

2.000E-01 1.618E+00 3/5/93 1002 1.351E+00 4.048E-01 7.724E-01 0

1.631E-01 1.588E+00 3/5/93 1158 1.251E+00 3.854E-01 6.763E-01 0

1.226E-01 1.458E+00 3/5/93 1400 1.067E+00 3.453E-01 5.395E-01 0

8.825E-02 1.232E+00 3/5/93 1607 9.701E-01 3.230E-01 4.589E-01 0

7.016E-02 1.112E+00 3/5/93 1755 8.748E-01 3.089E-01 3.974E-01 0

5.369E-02 9.979E-01 3/5/93 2025 6.829E-01 2.689E-01 2.8515-01 0

3.035E-02..7.722E-01

c. Cleanup system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded:

The cleanup flow through the CVCS mixed bed demineralizer-was approximately 110 gallons per minute for the 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to exceeding the limit of 1 microcurie per gram.

This cleanup flow.was maintained while the DEI I-131 limit was exceeded,

d. Time duration when the specific activity of the primary coolant exceeded the radiolodine limit:

The specific activity of the RCS exceeded the T/S 3.4.8.a limit of 1

)

microcurie per gram Dose Equivalent I-131 for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> and 52 minutes This occurred from 0403 hours0.00466 days <br />0.112 hours <br />6.66336e-4 weeks <br />1.533415e-4 months <br /> until 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> on March 5, 1993.

A new HOH form mixed bed demineralizer was placed in service and Reactor Coolant System boration was in progress during this l

period.

These factors extended the time that the DEI limit was exceeded.

e.

Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration that the specific activity was above the steady-state level:

See Graph 1:

"RCS Iodines" l

i i

' l

.m,-

m>

De n WOLF CREEK GENERATING STATION S{

ucI/ML RCS I-131 S I-133 ACTIVITY uci/m2 k

10 10*

2 I

I-131 (L)

O I

ms 8

y O

o I-133 (A) 0 RCS 10 10

_...__..g.._.._

g j

l

\\

\\

4A 10

9

. \\

10

\\ \\

z

\\

)

/

\\

A

\\

,.9 e- - - -e - # -. _e_. - e. - - -e- - - -e _

A

\\

A A

'\\.

/

\\

l&

/

\\

\\

/

\\\\

l 10' i

\\

= 10' l

k

\\

y-+

,-+ -+~,

s

.\\g l

k4

\\.

h..

h

-3

-3 e

i e

i i

e i

i e

i i

2 2

2 2

2 2

2 03 07 03 03 03 05 03 09 02 27 03 01 02 25 1993 1993