ML20217K799

Amend 116 to License NPF-42,revising TS 3.2.4 & Associated Bases Re Quadrant Power Tilt Ratio

ML20217K799
Person / Time
Site:	Wolf Creek
Issue date:	04/27/1998
From:	Thomas K NRC (Affiliation Not Assigned)
To:
Shared Package
ML20217K802	List: ML20217K799 ML20217K805
References
NUDOCS 9805040129
Download: ML20217K799 (8)

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UNITED STATES l

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'$9.....,o WOLF CREEK NUCLEAR OPERATING CORPORATION I

WOLF CREEK GENERATING STATIO_N DOCKET NO. 50-482

(

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 116 License No. NPF-42 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 February 4,1998, complies with the standards 1

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 provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance: (i) that the activities authorized by this smendment 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 common defense A

and security or to the health ar,d 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.

)

9805040129 980427 l

PDR ADOCK 05000482 P

PDR

4.

a 2.

Accordingly, the license is amended by changes to the Technical Specifications as j

indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility j

Operating License No. NPF-42 is hereby amended to read as follows:

j 2.

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.116, 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 to be implemented within 60 days from the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION M

Kristine M. Thomas, Project Manager Project Directorate IV-2 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

April 27, 1998 i

a l

ATTACHMENT TO LICENSE AMENDMENT NO.116 FACILITY OPERATING LICENSE NO. NPF-42 l

DOCKET NO. 50-482 i

Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginallines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT 3/4 2-11 3/4 2-11 3/4 2-12 3/4/2-12 3/4 2-13 3/4 2-14*

3/4 2-14*

B 3/4 2-3 8 3/4 2-3 l

1

• No changes were made to Page 3/4 2-14. Reissued to become one-sided page.

1 POWER DISTRIBUTION LIMITS 3/4.2.4 0UADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2.4 The OUADRANT POWER TILT RATIO shall not exceed 1.02.

APPLICABILITY:

MODE 1 above 50% of RATED THERMAL POWER *.

ACTION:

I a.

With the OUADRANT POWER TILT RATIO determined to exceed 1.02 l

1.

Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for l

each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1.00 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after each OUADRANT POWER TILT RATIO determination, and 2.

Determine the OUADRANT POWER TILT RATIO at least'once per 12 l

hours, and l

l 3.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilibrium conditions from a THERMAL POWER reduction required by ACTION a.1., and once per 7 days thereafter:

a)

Confirm that the Heat Flux Hot Channel Factor F (Z). is I

within its limit by performing Surveillance Req,uirement l

4.2.2.2, and l

b)

Confirm that Nuclear Enthalpy Rise Hot Channel Factor.

F",is within its limit by performing Surveillance Re,q,uirement 4.2.3.1, and l

l 4.

Reduce the Power Range Neutron Flux-High Trip Setpoints a 3%

for each 1% of OUADRANT POWER TILT RATIO > 1.00 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> I

after each OUADRANT POWER TILT RATIO determination, and 5.

Prior to increasing THERMAL POWER and Power Range Neutron Flux-i High Trip Setpoints above the limits of ACTION a.1. and a.4..

reevaluate the safety analyses and confirm that the results remain valid for the duration of operation under this condition, and 6.

Prior to increasing THERMAL POWER above the limit of ACTION a.1.. normalize excore detectors to restore OUADRANT POWER TILT RATIO to within limit, and

• See Special Test Exception Specification 3.10.2.

4 WOLF CREEK - UNIT 1 3/4 2-11 Amendment No.116

POWER DTSTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) 7.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after achieving equilibrium conditions not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after increasing THERMAL POWER above the limit-of ACTION a.1.**:

a)

Confirm that the Heat Flux Hot Channel Factor F (Z) is within its limit by performing Surveillance Req,uirement 4.2.2.2, and b)

Confirm that Nuclear Enthalpy Rise Hot Channel Factor.

F" is within its limit by performing Surveillance ReYu,irement4.2.3.1.

b'.

If the requirements of a.1.. a.2.. a.3.. a.4.. a.5.. a.6.. or a.7.

above are not met. reduce THERMAL POWER to s 50% of RTP within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

c.

The provisions of Specification 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.2.4.1 The OUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a.

Calculating the ratio at least once per 7 days when the alarm is OPERABLE. and b.

Calculatingtheratioatleastonceper12hoursduringsteady-state operation when the alarm is inoperabie.

4.2.4.2 The OUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range Channel inoperable by using the movaole incore detectors to confirm that the normalized symmetric power distribution, obtained from two sets of four symmetric thimble locations or a full-core flux map. is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• • ACTION a.7. must be completed when ACTION a.6. is performed.

l WOLF CREEK - UNIT 1 3/4 2-12 Amendment No.116 (Next page is 3/4 2-14) l

POWER DISTRIBUTION LIMITS 3/4.2.5 DNB PARAMETERS e

LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB related parameters shall be maintained within the limits shown on Table 3.2-1:

a.

Reactor Coolant System T b.

Pressurizer Pressure, and c.

Reactor Coolant System (RCS) Flow Rate APPLICABILITY: MODE 1.*

ACIION:

a.

With parameter 1 or 2 of Table 3.2-1 exceeding its limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b.

With the RCS total flow rate outside the region of acceptable operation shown on Table 3.2-1:

1.

Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:

a.

Restore the total flow rate to within the above limit, or b.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER.

2.

Within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either:

a.

Restore the total flow rate to within the above limit, or b.

Reduce the Power Range Neutron Flux - High Trip Setpoint to less than or equal to 55% of RATED THERMAL POWER.

3.

Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of initially being outside the above limit, verify that the RCS total flow rate is restored to within the above limit, or reduce THERMAL POWE3 to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; and o

• see special Test Exception Specification 3.10.4 for 3.2.5.c.

I WOLF CREEK - UNIT 1 3/4 2-14 Amendment No. 61

1 POWER DISTRIBUTION LIMITS BASES 4

OUADRANT POWER TILT RATIO (Continued)

With OPTR exceeding 1.02, reducing THERMAL POWER to greater than or equal to 3% below RTP for each 1% by which the OPTR exceeds 1.00 is a conservative tradeoff of total core power with peak linear power. The 2-hour time allowance after each OPTR determination allows sufficient time to identify the cause and correct the tilt, or reduce power as necessary. Any additional changes in the OPTR are detected by requiring a check of the OPTR once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> therafter.

For purposes of monitoring OUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the OUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles. The two sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8. E-5. E-11. H-3 H-13. L-5. L-11. N-8.

3/4.2.5 DNB PARAMETERS The limits on the Reactor Coolant System T and the pressurizer pressureassurethateachoftheparametersare,daintainedwithinthenormal steady-state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial USAR assumptions and have been analytically demonstrated adequate to maintain a DNBR above the safety analysis limit DNBR specified in the CORE OPERATING LIMITS REPORT (COLR) throughout each analyzed transient. The indicated T value of 590.5Fandtheindicatedpressurizerpressurevalueof222Ppsigcorrespond to analytical limits of 593.0"F and 2205 psig respectively, with allowance for measurement uncertainty.

The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their 1

limits following load changes and other expected transient operation.

Fuel rod bowing reduces the value of DNB ratio. Credit is available to offset this redudion in the generic margin. The generic margins completely offset any rod bow penalties. This is the margin between the correlation DNBR limit and the safety analysis limit DNBR. These limits are specified in the COLR.

The applicable values of rod bow penalties are referenced in the USAR.

l When RCS flow rate and F (X,Y). per Specification 3.2.3. are measured, no additional allowances are,n,ecessary prior to comparison with the limits in the COLR.

Measurement uncertainties of 2.5% for RCS total flow rate and 4%

for F,,(X,Y) have been allowed for in determination of the design DNBR value.

WOLF CREEK - UNIT 1 B 3/4 2-3 Amendment No. 51.51.59.72. 116 L

POWER DISTAfBt1Tf0N LIMITS BASES DNB PARAMETERS (Continued)

The measurement uncertainty for RCS total flow rate is based upon performing a precision heat balance and using the result to calibrate the RCS flow rate indicators.

not be detected could bias the result f:in the precision beat balance in a nonconservative manner.

Therefore, an inspection is performed of the feedwater venturi sach refueling outage.

The 12-hour periodic surveillance of indicated RCS flew is sufficient to detect only flow degradation which could lead to operation outside the acceptable region of operation specified in Table 3.2-1.

This surveillance also provides adequate monitoring to detect any core cred buildup.

WOl.F CREEK - UNIT 1 B 3/4 2-4 Amendment No. 61