ML17219A418
| ML17219A418 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/05/1987 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | City of Orlando, FL, Florida Municipal Power Agency, Florida Power & Light Co, Orlando Utilities Commission |
| Shared Package | |
| ML17219A419 | List: |
| References | |
| NPF-16-A-017 NUDOCS 8703120391 | |
| Download: ML17219A418 (11) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER 8( LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST.
LUCIE PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
17 License No.
NPF-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power 8 Light Company, et al. (the licensee),
dated November 7, 1986, 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, the provisions of the Act, and the rules and regulations of the Commission; CD 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 Commission's regulations; D.
The issuance of this 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
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have been satisfied.
87031203'Pi 870305 PDR ADOCK 05000389 P
2.
Accordingly, Facility Operating License No.
NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C;2 to read as follows:
2, Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
17
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 5, 1987 FOR THE N CLEAR REGULATORY COMMISSION
\\
Ashok
. Thadani, Director PWR Project Directorate ¹8 Division of PWR Licensing-B
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ATTACHMENT TO LICENSE AMENDMENT NO. 17 TO FACILITY OPERATING LICENSE NO.
NPF-16 DOCKET NO. 50-389 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding over leaf pages are also provided to maintain document completeness.
Remove Pa es 3/4 2-2 3/4 2-6 8 3/4 2-1 Insert Pa es 3/4 2-2 3/4 2-6 B 3/4 2-1
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3/4. 2 POWER DISTRIBUTION LIMITS 3/4 2.1 LINEAR HEAT RATE LIMITING CONDITION FOR OPERATION 3.2.
1 The linear heat rate shall not exceed the limits shown on Figure 3.2-1.
APPLICABILITY:
MODE 1.
ACTION:
With the linear heat rate exceeding its 'limits, as indicated by four or more coincident incore channels or by the AXIAL SHAPE INDEX outside of the power dependent control limits of Figure 3.2-2, within 15 minutes initiate cor-rective action to reduce the linear heat rate to within the limits and either:
a.
Restore the linear heat rate to within its limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or b.
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 />.
SURVEILLANCE RE UIREMENTS 4.2.1.1 The provisions of Specification 4.0.4 are not applicable.
4.2. 1.2 The linear heat rate shall be determined to be within its limits by continuously monitoring the core power distribution with either the excore detector monitoring system or with the incore detector monitoring system.
4.2. 1.3 Excore Detector Honitorin S stem - The excore detector monitoring system may be used for mon>.tor>ng the core power distribution by:
a.
Verifying at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that the full-length CEAs are withdrawn to and maintained at or beyond the Long Term Steady State Insertion Limit of Specification
- 3. 1.3.6.
b.
Verifying at least once per 31 days that the AXIAL SHAPE INDEX alarm setpoints are adjusted to within the limit shown on Figure 3.2-2.
ST.
LUCIE - UNIT 2 3/4 2-1
POWER DISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS Continued C.
Verifying that the AXIAL SHAPE INDEX is maintained within the allowable limits of Figure 3.2-2, where 100K of maximum allowable power represents the maximum THERMAL POWER allowed by the following expression:
MxN where:
1.
M is the maximum allowable THERMAL POWER level for the existing Reactor Coolant Pump combination.
2.
N is the maximum allowable fraction of RATED THERMAL POWER as determined by the F
curve of Figure 3.2-3.
xy 4.2.1.4 Incore Detector Monitorin S stem
- The incore detector monitoring system may be used for mon)torlng the core power distribution by verifying that the incore detector Local Power Density alarms:
a.
Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days of accumulated operation in MODE l.
b.
Have their alarm setpoint adjusted to less than or equal to the limits shown on Figure 3.2-1 when the following factors are appropriately.inc'luded in the setting of these alarms:
A measurement-calculational uncertainty factor of 1.062, I
2 An engineering uncertainty factor of 1.03, 3.
A linear heat rate uncertainty factor of 1.01 due to axial fuel densification and thermal expansion, and 4.
A THERMAL POWER measurement uncertainty factor of 1.02.
If incore system becomes inoperable, reduce power to M x N within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and monitor linear heat rate in accordance with Specification 4.2. l.3.
ST.
LUCIE " UNIT 2 3/4 2"2 Amendment No.
17
FIGURE 3.2-3 ALLOWABLE COMBINATIONS OF THERtgL POWER AND F Fr'y 1.2 j
I UNA CEPTABLE I N.
l REMI N
C) 1.0 C) 0 ~ 8 C)
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L T 0 EG ON
.75, (1-'
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3
.85).
IHI..C R.E...
0.6 1.65
- 1. 70
- 1. 75 HEASURED F, F 1.80
THIS PAGE INTENTIONALLYBLANK ST.
LUCIE - UNIT 2 3/4 2-6 Amendment No. 17
3/4. 2 POWER DISTRIBUTION LIMITS BASES 3 4.2.1 LINEAR HEAT RATE The limitation on linear heat rate ensures that in the event of a
- LOCA, the peak temperature of the fuel cladding will not exceed 2200'F.
Either of the two core power distribution monitoring systems, the Excore Detector Monitoring System and the Incore Detector Monitoring System, provides adequate monitoring of the core power distribution and are capable of verifying that the linear heat rate does not exceed its limits.
The Excore Detector Monitoring System performs this function by continuously monitoring the AXIAL SHAPE INDEX with the OPERABLE quadrant symmetric excore neutron flux detectors and verifying that the AXIAL SHAPE INDEX is maintained within the allowable limits of Figure 3.2-2.
In conjunction with the use of the excore monitoring system and in establishing the AXIAL SHAPE INDEX limits, the following assumptions are made:
(1) the CEA insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are satisfied, (2) the AZIMUTHAL POWER TILT restrictions of Soecification 3.2.4 are satisfied.
and (3) the TOTAL PLANAR RADIAL PEAKING FACTOR does not exceed the limits of Specification 3.2.2.
The Incore Detector Monitoring System continuously provides a direct measure of the peaking factors and the alarms which have been established for the individual incore detector segments ensure that the peak linear heat rates will be maintained within the allowable limits of Figure 3.2-1.
The setpoints for these alarms include allowances, set in the conservative directions, for (1) a measurement-calculational uncertainty factor of 1.062, (2) an engineering uncertainty factor of 1.03, (3) an allowance of 1.01 for axial fuel densificatio and thermal expansion, and (4) a THERMAL POWER measurement uncertainty factor of
- 1. 02 ~
3/4.2.2, 3 4.2.3 and 3 4.2
~ 4 TOTAL PLANAR AND INTEGRATED RADIAL PEAKING FACTORS -
F and Fr AND AZIMUTHAL POWER TILT - T The limitations on F
and T
are provided to ensure that the assumptions T
xy q
used in the analysis for establishing the Linear Heat Rate and Local Power Density - High LCOs and LSSS setpoints remain valid during operation at the various allowable CEA group insertion limits.
The limitations on F
and T
r q
are provided to ensure that the assumptions used in the analysis establishing the DNB Margin LCO, the Thermal Margin/Low Pressure LSSS setpoints remain valid during operation at the various allowable CEA group insertion limits.
If F F
or T exceed their basic limitations, operation may continue under the additional restrictions imposed by the ACTION statements since these additional restrictions provide adequate provisions to assure that the ST.
LUCIE - UNIT 2 B 3/4 2-1 Amendment No.
POWER DISTRIBUTION LIHITS BASES assumptions used in establishing the Linear Meat Rate, Thermal Hargin/Low Pressure and Local Power Density - High LCOs and LSSS setpoints remain valid.
An AEINUTHAL POWER TILT > 0. 10 is not expected and if it should occur, subsequent operation would be restricted to only those operations required to identify the cause of this unexpected tilt.
The requirement that the measured value of Tq be mutiplied by the calculated values of F
and F
to determine F
and F
is applicable only xy r
xy when F
and F
are calculated with a non-full core power distribution analysis xy code.
When monitoring a reactor core power distribution, F
or F
with a full r
xy core power distribution analysis code the azimuthal tilt is explicitly accounted for as part of the radial power distribution used to calculate Fx and F
r'heSurveillance Requirements for verifying that F
F and T
are xy r
within their limits provide assurance that the actual values of F F
and T
xy' q
do not exceed the assumed values.
Verifying F and F
after each fuel xy r
loading prior to exceeding 75K of RATED THERMAL POWER provides additional assurance that the core was properly loaded.
3/4.2.5 DNB PARAMETERS The limits on the DNB-related parameters assure that each of the parameters are maintained within the normal steady-state envelope of operation assumed in the transient and safety analyses.
The limits are consistent with the safety analyses assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR of > 1.28 throughout each analyzed transient.
1 The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within theit limits following load changes and other expected transient operation.
The 18-month periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure correlation of the flow indication channels with measured flow such that the indicated percent flow will provide sufficient verification of flow rate on a 12-hour basis.
ST.
LUCIE " UNIT 2 8 3/4 2-2 Amendment, No. 8