ML20101B974
| ML20101B974 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/01/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20101B976 | List: |
| References | |
| NUDOCS 9603150183 | |
| Download: ML20101B974 (7) | |
Text
i a nau l
/
UNITED STATES NUCLEAR REGULATORY COMMISSION
- g WASHINGTON, D.C. 20ea6-0001
)
4 l
WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE l
l l
Amendment No. 96 i
License No. NPF-42 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the
)
Wolf Creek Nuclear Operating Corporation (the Corporation), dated l
November 22, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the prcvisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the i
common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9603150183 960301 PDR ADOCK 05000482 p
, 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 96, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance and shall be implemented prior to startup from the eighth refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION hi
&m James C. Stone, Senior Project Manager Project Directorate IV-2 i
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 1, 1996
i ATTACHMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 3-2 3/4 3-2 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-9 3/4 3-9 3/4 3-12 3/4 3-12
3/4.3 INSTRUMENTATION l
l 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY:
As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
l i
SURVEILLANCE REQUIREMENTS l
4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1.
4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one train such that both trains are tested at l
1 east once per 36 months and one channel per function such that all channels l
are tested at least once every N times 18 months where N is the total number j
of redundant channels in a specific Reactor trip function as shown in the
" Total No. of Channels" column of Table 3.3-1.
l 1
i
-WOLF CREEK - UNIT 1 3/4 3-1
,. ~.
TABLE 3.3-1 (Continued)
TABLE NOTATIONS
- 0nly if the Reactor Trip System breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.
- The provisions of Specification 3.0.4 are not applicable.
1
- Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1) The applicable MODES for these channels noted in Table 3.3-3 are more restrictive and therefore applicable.
ACTION STATEMENTS ACTION 1 -
With the number of OPERABLE CHANNELS one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within 4
the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2 -
With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition within 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s-l b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1; and c.
Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85%
of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.
ACTION 3 -
With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:
a.
Below the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; or b.
Above the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.
ACTION 4 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.
WOLF CREEK - UNIT 1 3/4 3-5 Amendment No. M,43,96
a 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY:
As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVEILLANCE REQUIREMENTS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1.
4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific Reactor trip function as shown in the
" Total No. of Channels" column of Table 3.3-1.
WOLF CREEK - UNIT 1 3/4 3-1
g TABLE 3.3-1 l
REACTOR TRIP SYSTEM INSTRUMENTATION n
E W
MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE c=
FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION w
1.
1 2
1,2 1
2 1
2 3*,4*,5*
10 2.
Power Range, Neutron Flux a.
High Setpoint 4
2 3
1,2 2#
b.
Low Setpoint 4
2 3
l###,2 2f R
3.
Power Range, Neutron Flux, 4
2 3
1,2 2f
[
High Positive Rate 4.
Power Range, Neutron Flux, 4
2 3
1,2 2f High Negative Rate 5.
Intermediate Range, Neutron Flux 2
1 2
Ifff,2 3
6.
Source Range, Neutron Foux r
a.
Startup 2
1 2
2ff 4
b.
Shutdown 2
1 2
3,4,5 5
7.
Overtemperature AT 4
2 3
1,2 6#
I Four Loop Operation Ng 8.
Overpower AT 4
2 3
1,2 6#
g Four Loop Operation E
9.
Pressurizer Pressure-Low 4
2 3
1 6f z
P 10.
Pressurizer Pressure-High 4
2 3
1,2 6#
5
1 1
TABLE 3.3-1 (Continued) l TABLE NOTATIONS i
- 0nly if the Rcactor Trip System breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.
- The provisions of Specification 3.0.4 are not applicable.
l l
- Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1) The applicable MODES for these channels noted in Table 3.3-3 are more l
restrictive and therefore applicable.
ACTION STATEMENTS 1
ACTION 1 -
With the number of OPERABLE CHANNELS one less than the Minimum a
Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION 2 -
With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed j
provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition -
i within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; j
b.
The Minimum Channels OPERABLE requirement is met; however, j
the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1; and i
c.
Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85%
of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT i
POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.
1 ACTION 3 -
With the number of channels OPERABLE one less than the Minimum l
Channels OPERABLE requirement and with the THERMAL POWER level:
a.
Below the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; or b.
Above the P-6 (Intermediate Range Neutron Flux Interlock)
Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.
ACTION 4 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.
WOLF CREEK - UNIT 1 3/4 3-5 Amendment No. 4h43,96
TABLE 3.3-1 (Continued)
ACTION STATEMENTS (Continued) 4 ACTION 5 -
a.
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor Trip Breakers, and suspend all operations involving positive reactivity changes within the next hour.
P b.
With no channels OPERABLE, open the Reactor Trip Breakers, suspend all operations involving positive reactivity changes and verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 within I hour and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.
l ACTION 6 -
With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
a.
The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; and b.
The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing.of other channels per Specification 4.3.1.1.
ACTION 7 -
With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is operable.
ACTION 8 -
With less than the Minimum Number of Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.
ACTION 9 -
With the number of OPERABLE Reactor Trip Breakers one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one breaker may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1., provided the other breaker is OPERABLE.
ACTION 10 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or open the Reactor trip breakers within the next hour.
ACTION 11 -
With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
WOLF CREEK - UNIT 1 3/4 3-6 Amendment No. 12,25,'3,02,96
7 TABLE 4.3-1 l
c k
REACTOR TRIP SYSTEN INSTRUNENTATION SURVEILLANCE REQUIREMENTS E
TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED a
1.
Nanual Reactor Trip N.A.
N.A.
N.A.
R(ll)
N.A.
1,2,3*,4*,5*
2.
Power Range, Neutron Flux a.
High Setpoint S
D(2,4)
Q N.A.
N.A.
1,2 N(3,4)
Q(4,6)
R(4,5) b.
Low Setpoint S
R(4)
S/U(1)
N.A.
N.A.
l###,2 R
3.
Power Range, Neutron Flux, N.A.
R(4)
Q N.A.
N.A.
1,2 High Positive Rate Y
4.
Power Range, Neutron Flux, N.A.
R(4)
Q N.A.
N.A.
1,2 High Negative Rate 5.
Intermediate Range, Neutron S
R(4,5)
S/U(1)
N.A.
N.A.
l###,2 Flux 6.
Source Range, Neutron Flux S
R(4,5)
S/U(1),Q(9)
N.A.
N.A.
2##,3,4,5 l
7.
Overtemperature AT S
R Q
N.A.
N.A.
1,2 8.
Overpower AT S
R Q
N.4.
N.A.
1,2 y
9.
Pressurizer Pressure-Low S
R Q
N.A.
N.A.
1 3
10.
Pressurizer Pressure-High S
R Q
N.A.
N.A.
1,2 11.
Pressurizer Water Level-High S R
Q N.A.
N.A.
1
'm
- 12. Reactor Coolant Flow - Low S
R Q
N.A.
N.A.
I
TABLE 4.3-1 (Continued)
{
BEACTQR TRR SYSTQLINSTRLMENTATION SURVEILLAEE REQIlIREMENTS cs TRIP E
ANALOG ACTUATING N00ES FOR E
CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE g
FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REQUIRED
[
13.
Steam Generator Water Level-S R
Q(15)
N.A.
M.A.
1, 2 Low-Low 14.
Undervoltage - Reactor N.A.
R N.A.
Q N.A.
1 Coolant Pumps 15.
Underfrequency - Reactor N.A.
R N.A.
Q N.A.
1 Coolant Pumps 16.
a.
Low Fluid Oil Pressure N.A.
R N.A.
S/U(1,10)
N.A.
1
[
b.
Turbine Stop Valve N.A.
R N.A.
S/U(1,10)
N.A.
1 4
Closure o
17.
Safety Injection Input from N.A.
N.A.
N.A.
R N.A.
1, 2 ESF 18.
Reactor Trip System Interlocks L
a.
Intermediate Range l
Neutron Flux, P-6 N.A.
R(4)
R N.A.
N.A.
2N b.
Power Range Neutron Flux, P-8 N.A.
R(4)
R N.A.
N.A.
I c.
Power Range Neutron Flux, P-9 N.A.
R(4)
R N.A.
N.A.
1 g
y n
F i
M
=
-~
TA8tt 4.3-1 REACTOR TRIP _SYS1EN INSIRUNENTATION SURVEILLANCE REQUIRENENTS r,
TRIP i!!
ANALOG ACTUATING NODES FOR W
CHANNEL DEVICE WHICH i
CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE g
FUNCTIONAL UNIT CHECK CAtlBRATION TEST TEST LOGIC TEST IS REQUIRED
- 18. Reactor Trip System Interlocks (continued) w d.
Power Range Neutron Flux, P-10 N.A.
R(4)
R N.A.
N.A.
1, 2 i
e.
Turbine Impulse Chamber Pressure, P-13 N.A.
R R
N.A.
N.A.
I
- 19. Reactor Trip Breaker N.A.
N.A.
N.A.
M(7,16)
N.A.
1, 2, 3*, 4*, 5* l 2
- 20. Automatic Trip and Interlock Logic N.A.
N.A.
N.A.
N.A.
M (7) 1, 2, 3*, 4*, 5*
l
- 21. Ret: tor Trip Bypass Breaker M.A.
N.A.
N.A.
M(17),R(18)
N.A.
1,2,3*,4*,5*l 1
i
?
l if l
On
= - - - - -. _ - - - - -
a TABLE 4.3-1 (Continued)
TABLE NOTATIONS
- 0nly if the Reactor Trip System breakers happen to be closed and the control rod drive system is capable of rod withdrawal.
- Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1)
If not performed in previous 31 days.
(2)
Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(3)
Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 3%. The provisions of Specification 4.0.4 are i
not applicable for entry into MODE 2 or 1.
(4)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5)
For Source Range detectors, integral bias curves are obtained, evaluated, and compared to manufacturer's data.
For Intermediate Range and Power Range channels, detector plateau curves shall be obtained, evaluated, and compared to manufacturer's data.
For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into Mode 2 or 1.
(6)
Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(7)
Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(9)
Quarterly surveillance in MODES 3*, 4* and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.
(10) Setpoint verification is not required.
- (11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).
(12) Deleted.
- Complete verification of OPERABILITY of the manual reactor trip switch circuitry shall be performed prior to startup from the first shutdown to Mode 3 occurring after August 14, 1992.
WOLF CREEK - UNIT 1 3/4 3-12 Amendment No. 12,25,55,03,96
. _.