ML17216A376
| ML17216A376 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/12/1985 |
| From: | Thadani A Office of Nuclear Reactor Regulation |
| To: | Florida Power & Light Co |
| Shared Package | |
| ML17216A377 | List: |
| References | |
| DPR-67-A-070 NUDOCS 8512230251 | |
| Download: ML17216A376 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION V/ASHINGTON, D. C. 20555 FLORIDA POISE'ER 8I LIGHT COMPANY DOCKET NO. 50-335 ST.
LUCIE PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
70 License No.
DPR-67 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power E Light Coripany, (the licensee) dated October 17, 1985 as supplemented by letter dated December 2,
- 1985, ccmplies 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; 8.
The facility will operate in conformity with the application, 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 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 Cormnission'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 have been satisfied.
8512230251 851212 PDR ADOCK 05000335 I
I ll P
PDR 2.
Accordingly, Facility Cperating License 1'o.
DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, by amending paragraph 2.C.(2),
and by adding a
new paragraph 2.C(5) to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A
and 8, as revised through Amendment No. 70, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
(5)
The licensee shall provide a supplement to XN-NF-85-117, "St. Lucie Unit 1 Revised LCOA-ECCS Analysis with 15/~ Steam Generator Tube Plugging", that will provide the complete large break LOCA spectrum results to demonstrate full compliance with the criteria of 10 CFR 50.46 and Appendix K to 10 CFR Part 50 for the Commission staff' review and approval.
3.
This license amendment is effective as of the date of its issuance.
Attachment:
Changes to the Technical Specifications FOR THr.<UCLEAR REGULATORY COt..t!ISSION S('&6~3o-Ashok C. Thadani, Director PllR P object Directorate
-.',8 Division of PWR Licensing-B Date of Issuance:
December 12, 1985
ATTACHf'.EffT TO LICENSE AffEt'Of'!""flTffO. 70 TO FACILITY OPERATING LICENSE NO.
DPR-67 OOCKET NO. 50-335 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 overleaf pages are also provided to maintain document completeness.
Remove Paaes 3/4 2-2 3/4 2-3 3/4 2-4 8 3/4 2-1 Insert Paces 3/4 2-2 3/4 2-3 3/4 2-4 8 3/4 2-1
3/4. 2 POMER DISTRIBUTION LIMITS 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:
NODE l.
ACTION:
llith 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 corrective action to reduce the linear heat rate to within the limits and either:
a.
Restore the linear heat rate to within its limits within one hour, or b.
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 />.
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 Nonitorin S stem - The excore detector moni-toring system may be used for monitoring 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 limits shown on Figure 3.2-2.
ST.
LUC IE - UNIT 1
3/4 2-1 Amendment No. g7, 32
POWER DISTRIBUTION LIMITS BASES used in the analysis establishing the DNB Margin LCO, and Thermal Margin/Low Pressure LSSS setpoints remain valid during operation at the various allowable CEA group insertion limits. If FTy, F" or T exceed their basic limitations, operation may continue under tPe addition31 restrictions imposed by the ACTION statements since these additional restrictions provide adequate provisions to assure that the assumptions used in establishing the Linear Heat Rate, Thermal Margin/Low Pressure and Local Power Density - High LCOs and LSSS setpoints remain valid.
An AZIMUTHAL 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 ( 1+Tq) be multiplied by the calculated values of Fr and Fxy to determine FT is applicable only when Fr and Fxy are calculated with a non-full core power distribution analysis.
With a full core power distribution analysis code the azimuthal tilt is explicitly accounted for as part of the radial power distribution used to calculate Fxy and Fr.
The surveillance requi rements for verifying that FT FT and T
are within their limits provide assurance that the actual values of FTy",
FT and T do not exceed the assumed values.
Verifying F/v and FT after each fuel 7oading prior to exceeding 75/ of PATED THERMAL PQWER 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 opera-tion assumed in the transient and accident analyses.
The limits are consis-tent with the safety analyses assumptions and have been analytically demon-strated adequate to maintain a minimum DNBR of > 1.22 throughout each analyzed transient.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their 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 wi 11 provide sufficient verification of flow rate on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis.
ST.
LUCIE - UNIT 1
B 3/4 2-2 Amendment No. 27, 8H
~>~
65
UNACCEPTABLE OPERATION Gl 15 O
PQ +
aM l3 X O
+
Ck FQ foal 0
(0.6, 15.0)
(0.81, 13.4)
ACCEPTABLE OPERATION (l.oi 10.07) 0.0 0.5 1.0 FRACTION OF CORE HEIGHT FIGURE 3.2-1 ALLOWABLE PEAK'LINEAR HEAT RATE VERSUS FRACTION OF CORE HEIGHT ST.
LUCRE - Ut<IT 1
3/4 2-3 Amendment Ho. g7, PZ RS 7o
1.2 1.0 Or Q,9 3
Q.8 0.7 0
0.6 0
O 0.5 REGION OF UNACCEPTABLE OPERATION (0
0 g
0 82)
REGION OF ACCEPTABLE OPERATION (0.15, 0.82)
REGION OF UNACCEPTABLE OP ERATION (0.3r 0.58)
(-0.3r0.45)
Q ~ 4
-0.6
-0.4
-0.2 0.0 0.2 0.4 0.6 PERIPHERAL AXIAL SHAPE INDEX FIGURE 3.2-2 AXIAL SHAPE INDEX vs.
MAXIMUMALLOWABLE POWER LEVEL PER SPECIFICATION 4.2.1.3 ST.
LUCIE - UNIT t
3/4 2-4 Amendment No. 27~88.Q~70
3/4.2 POMER DISTRIBUTION LINITS BASES 3/4.2.1 LINEAR HEAT PATE 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 tlonitoring System and the Incore Detector Monitoring System, provides adequate monitoring of the core power distribution and is-capable of verifying that the linear heat rate does not exceed its limits.
The Excore Detector Nonitoring 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 assump-tions are made; 1) the CEA insertion limits of Specifications 3,1.3.5 and 3.1.3.6 are satisfied,
- 2) the A2It~iUTHAL POh'ER TILT restrictions of Specifica-tion 3.2.4 are satisfied, and 3) the TOTAL PLANAR RADIAL PEAKING FACTOR does not exceed the limits of Specifica=ion 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 i ncore detector segments ensure that the peak linear heat rates will be maintained within the allowable limits of Figure 3.2-1.
The setpoints
'.r these alarms include allowan es, set in the conservative directions, for')
a meas!
ement-calculational uncertainty factor of 1.07,
- 2) an engineering uncertainty factor of 1.03, 3) a THERt1AL POh'ER 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 F AND AZIMUTHAL POldER TILT - T The limitations on F
and T
are provided to ensure that the assump-
. T xy q
tions 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
are provided to ensure that the assumptions r
q ST.
LUCIE - UNIT 1
B 3/4 2-1 Amendment No. )7/,)),p,]f, 70
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 100 percent of maximum allowable power represents the maximum THERMAL POWER allowed by the following expression:
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 monitor-ing system may be used for monitoring 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 appropriat:ly included in the setting of these alarms:
l.
A measurement-calculational uncertainty factor of 1.07, 2.
3 ~
An engineering uncertainty factor of 1.03, F
A THERMAL POWER measurement uncertainty factor of 1.02.
PIf the core 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 4.2.1.
ST.
LUCIE - UNIT 1
3/4 2-2 Amendment No. f7, g?, gg,g8&. 70