ML20101Q666
| ML20101Q666 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/04/1996 |
| From: | Stone J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20101Q669 | List: |
| References | |
| NUDOCS 9604120257 | |
| Download: ML20101Q666 (7) | |
Text
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4 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20066 4001
- '+9.....,o WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMEN 0 MENT TO FACILITY OPERATING LICENSE e:
l Amendment No. 99 l
License No. NPF-42 1.
The Nuclear Regulatory Comission (the Comission) 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 March 8, 1996, as supplemented by letter dated March 26, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and l
regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:
(i) 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the
~
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.
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i 9604120257 960404 PDR ADOCK 05000482 PDR
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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 F,cility 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. 99, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are 1
hereby incorporated in the license.
The Corporation shall operate the facility in accordance with the Technical Specifications and the a
Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMISSION
/Wids James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 4, 1996
'I i
ATTACHMENT TO LICENSE AMENDMENT NO. 99 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 INS'ERT l
2-2 2-2 2-4 2-4 3/4 2-16 3/4 2-16
+-
2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS
_ REACTOR CORE 2.1.1 The combination of THERMAL POWER, operating loop coolant temperature (T,yg) pressurizer pressure, and shall not exceed the limits shown in Figure 2.1-1 for four loop operation.
l APPLICABILITY:
MODES 1 and 2.
l l
ACTION:
~ ~ = = = ~
Whenever the point defined by the combination of the highest oper ting loop average temperature and THERMAL POWER has exceeded the appropriate pres-l surizer pressure line, be in HOT STANDBY within I hour, and comply with the requirements of Specification 6.7.1.
1 i
REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2 b5 psig.
APPLICABILITY:
MODES 1, 2, 3, 4, and 5.
ACTION:
MODES I and 2:
Whenever the Reactor Coolant System pressure has exceeded 2735 psig be l
inNOTSTANDBYwiththeReactorCoolantSystempressurewithinitslimit within I hour, and comply with the requirements of Specification 6.7.1.
MODES 3, 4, and 5:
l Whenever the Reactor Coolant System pressure has exceeded 2735 psig reducetheReactorCoolantSystempressuretowithinitslimitwithln 25 minutes, arjd. comply with the requirements of Specification 6.7.1.
l i
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WOLF CREEK - UNIT 1 2-1 l
,,m
680 Unacceptable Operation 660 2400 psia
~
/
... ~.... ~.........,, '
,.,.... ~.. ~
g, d 640 W
2000 sia P
c
.... r y
2250 psia /'.....,' \\.,
T 620 3
p.
2 1925 psia
__.,...*...,,,.i s
.c es i
g 2_ 600 i,
Acceptable Operation i
i 580 i
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i 7 -
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560 O.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power FIGURE 2.1-1 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION WOLF CREEK - UNIT 1 2-2 Amendment No. 64,99
TABLE 2.2-1
[
REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 5
E, SENSOR i
o TOTAL ERROR
[
FUNCTIONAL UNIT ALLOWANCE ('A)
I fSi TRIP SETPOINT ALLOWABLE VALUE j
i 1.
Manual Reactor Trip N.A.
N.A.
N.A.
N.A.
N.A.
E i
2.
Power Range, Neutron Flux
[
a.
High Setpoint 7.5 4.56 0
5109% of RTP*
$112.3% of RTP*
b.
Low Setpoint 8.3 4.56 0
s25% of RTP*
s28.3% of RTP*
3.
Power Range, Neutron Flux, 2.4 0.5 0
s4% of RTP* with s6.3% of RTP* with Hloh Positive Rate a time constant a time constant 22.ieconds 22 seconds
'4.
Power Range, Neulean Flux, 2.4 0.5 0
s4% of RTP* with s6.3% of RTP* with High Negative Rate a time constant a time constant
. seconds 22 seconds
[
5.
Intermediate Range, 17.0 8.41 0
s25% of RTP*
535.3% of RTP*
Neutron Flux f
6.
Source Range, Neutron Flux 17.0 10.01 0 s10 cps sl.6 x 10 cps 5
5 7.
Overtemperature AT 7.0 5.39 1.67 See Note 1 See Note 2 8.
Overpower AT 4.6 2.02 0.14 See Note 3 See Note 4 g
h 9.
Pressurizer Pressure-Low 3.7 0.71 2.49 21940 psig 219'1 pais l
a?
16.
Pressurizer Pressure-High 7.5 0.71 2.49 s2385 psig s2400 psig S
b 11.
Pressurizer Water Level-High 8.0 2.18 1.96 s92% of instrument s93.9% of instrument f
span span S
- j
- RTP - RATED THERMAL POWER
- Loop design flow - 90,324 gpm l
.ms i
i m
{
2 POWER DISTRIBUTION LIMITS 314.2.5 DNB PARAMETERS 1
i LIMITINC, CONDITION FOR OPERATION ACTION:
(Continued)
I j
4.
Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION 1.b and/or 3, above; subsequent j
POWER OPERATION may proceed provided that the. indicated.RCS l
total flow rate is demonstrated to be within the region of acceptable operation prior to exceeding the following THERMAL 1
POWER 1evels:
A r.ominal 50% of RATED THERMAL POWER, a.
l b.
- f. a9minal 75% of RATED THERMAL POWER, and l
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 95%
c.
of RATED THERMAL POWER.
SURVEILLANCE REDUIREMENTS 4.2.5.1.The provisions of Specification 4.0.4 are not applicable to,
Specification'3.2.5.c.
i 4.2.5.2 their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.Each of the parameters of Table 7.M l
4.2.5.3 CALIBRATION at least once per 18 months.The RCS total flow rate indic i
4.2.5.4 The RCS total flow rate shall be detemined by precision heat balance measurement at least once per 18 months.
i the precision heat balance, the instramentation used for determination ofWit i
steam pressure, feedwater pressure, feedwater temperature, and feedwater j
venturi AP in the calorimetric calculations tha11 be calibrated, c
4.2.5.5 The feeihialer~ venturi shall be inspected ir,r fouling and cleaned as i
necessary at least once per 18 months.
WOLF CREEK - UNIT 1 3/4 2-15 Amendment No. 61
TABLE 3.2-1 DNB PARAMETERS LIMITS Four Loops in PARAMETER Ooeration 1.
Indicated Reactor Coolant System T,
5590.5'F 2.
Indicated Pressurizer Pressure 22220 psig*
3.
Reactor Coolant System Flow Rate 237.1 x 10' GPM l
l l
- Limit not applicabit during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.
WOLF CREEK - UNIT 1 3/4 2-16 Amendment No. 51,5^,72,99 l
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