ML20043B115
| ML20043B115 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 05/21/1990 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043B116 | List: |
| References | |
| NUDOCS 9005240207 | |
| Download: ML20043B115 (7) | |
Text
.s.
r
?*
(('
0,,
UNITED STATES g
NUCLEAR REGULATORY COMMISSION a'
7, E
WASHINGTON, D. C. 20bb5 8
4
%, *.. * /
FLO,RIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNEl.L CITY OF GAINE5VL LLE CITY OF KISSIMM EE CITY OF LEE 5 BURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMI5SION, CITY OF NEW SMYRNA BEACN r
CITY OF OCALA ORLANDO UTILITIES M RTETf5N IND CITY OF ORLANDO SEBRING UTILITIES COMISSION SEMIl4 OLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMEN 0 MENT TO FACILITY OPERATING LICENSE l
Amendment No.129 License No. OPR-72 l.
I i
L 1.
The Nuclear Regulatory Comission (the Comission) has found that:
).
A.
The application for amendment by Florida Power Corporation, et al.
(the licensees) dated March 15, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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; 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 amendment will not be inimical to the comon 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 i
been satisfied.
$$$k $$gf2.1 Nse'
4 9
7 2-F 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. OPR-72 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.129, are hereby incorporated in the license.
Florida Power Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION He bert N. Berkow, Director i
Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
i Changes to the Technical l
Specifications Date of Issuance: May 21, 1990 i
l c
i L
1 e-
C...
t v.
u; ' r. :
r
- l in ATTACHMENT TO LICENSE AMENDMENT NO.129
)
i C
FACILITY OPEF.ATING LICENSE NO. DPR-72 I
i e
i DOCKET NO. 50-302' i
t
. Replace:the following pages of the Appendix "A" Technical Specifications with the.atteched pages.
The revised pages are identified by amendment number and
.i contain vertical. lines indicating the area of change.
The corresponding
'. l t-overleaf pages are also provided to maintain document completeness.
[
Remove Insert 3/4 2-5 3/4 2-5 I
r-B 3/4 2-2 B 3/4 2-2 L
)
e I
i p
A
)
i
?
b h
(
k i
i J'
l i
4 9
i
- rs, < <
-i
I 3/4,2 POWER DISTDIBUTION tlMITS l
BASES i
The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and 11 (Incidents of Moderate Frequency) events by:
(a) maintaining the minimum DNBR in the core within the limit during L
normal operation and during short term transients, (b) maintaining the peak linear power density s 18.0 kw/ft during normal operation, and (c) maintaining the peak power density 1 20.5 kw/ft during short term transients.
In i
addition, the above criteria must be met in orcer to meet the a,,$umptions used for the loss of coolant accidents.
The power imbalance envelope and the insertion limit curves, defined in the CORE OPERATING LIMITS REPORT (COLR), are based on LOCA analyses which have defined the maximum linear heat rate such that the maximum clad temperature will not exceed the Final Acceptance Criteria of 2200'F following a LOCA.
Operation outside of the power imtalance envelope alone does not constitute a situation that would cause the Final Acceptance Criteria to be exceeded should a LOCA occur.
The power imbalance envelope represents the boundary of operation limited by the Final Acceptance Criteria only if the control rods are at the insertion limits, as defined in the COLR and if the steady state l
limit QUADRANT POWER TILT exists. Additional conservatism is introduced by application of:
a.
Nuclear uncertainty factors, b.
Thermal calibration uncertainty.
c.
Fuel densification effects, i
d.
Hot rod manufacturing tolerance factors.
The conservative application of the above peaking augmentation factors considers the potential peaking penalty due to fuel rod blow.
The ACTION statements which permit limited variations from the basic requirernents are accompanied by additional restrictions which ensure that the original criteria are met.
The definitions of the oesign limit nuclear power peaking factors as used in these specifications are as follows:
FQ Nuclear Heat Flux Hot Channel Factor, is defined as the maximum local fuel rod linear power density divided by the average fuel rod linear power density, assuming nominal fuel pellet and rod dimensions, i
l I
CRYSTAL RIVER - UNIT 3 8 3/4 2-1 Amendment No. 76.77,703, 125 l
JAfi 31 E
7-d i
POWER DISTRIBUTION LIMITS BASES FN Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of LH the integral of linear power along the rod on which minimum DNBR occurs to the average rod power.
It has been determined by extensive analysis of possible operating power shapes L
that the design limits on nuclear power peaking and on minimum DNBR at full power i
1 are met, provided:
Fg 1 3.13; FN g 1,7}
LH Power Peaking is_ not a directly observable quantity and therefore limits have been established on the bases of the AXIAL POWER IMBALANCE produced by the power peaking.
It has been determined that the above hot channel factor limits will be met provided the following conditions are maintained.
1.
Control rods in a single group move together with no individual rod insertion differing by more than 6.5% (indicated position) from the group average height.
(
2.
Regulating rod groups are sequenced with overlapping groups as required in
)
Specification 3.1.3.5.
3.
The regulating rod insertion limits of Specification 3.1.3.6 and the axial i
power shaping rod insertion limits of Specification 3.1.3.9 are maintained.
i 4.
AX1AL POWER IMBALANCE limits are maintained.
The AXIAL POWER IMBALANCE is a measure of the difference in power between the top and bottom halves of the core. Calculations of core average axial peaking factors for many plants and measurements from operating plants under a variety of operating conditions have been correlated with AXIAL POWER IMBALANCE. The correlation shows that the design power shape is not exceeded if' the AXIAL POWER IMBALANCE is maintained within the limits defined in the COLR.
L The design limit power peaking factors are the most restrictive calculated at full power for the range from all control rods fully withdrawn to minimum allowable control rod insertion and are the core DNBR design basis. Therefore, for operation at a fraction of RATED THERMAL POWER, the design limits are met.
When using incore detectors to make power distribution maps to determine Fg and N
F H:
b a.
The measurement of total peaking factor, FgMeas, shall be increased by 2.0 percent to account for manufacturing tolerances and further incre6 sed by 7.5 l
percent to account for measurement error.
l CRYSTAL RIVER - UNIT 3 B 3/4 2 2 Amendment No. 76,79,77,70),725,129
' POWER DISTRIBUTION LIMITS SURVEILLANCE RE0VIREMENTS (Continued) t a.
Prior to initial operation above 75 percent of RATED THERMAL POWER after each fuel loading, and b.
At least once per 31 Effective Full Power Days.
c.
The provisions of Specification 4.0.4 are not applicable.
4.2.2.2 The measured FQ of 4.2.2.1 above, shall be increased by 2.0% to account for manufacturing tolerances and further increased by 7.5% to account for measurement uncertainty.
l l
l L
CRYSTAL RIVER - UNIT 3 3/4 2 5 Amendment No. 129 l
i POWER DISTRIBUTION LIMITS NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F[g LIMITING CONDITION FOR OPERATION I
L N
3.2.3 Fb H, shill be limited by the following relationship:
' N
-)
-.!.71 1 + 0.3 (1-P) 4 Thermal Power p,
Rated Thermal Power and P ( l.0-APPLICABILITY:
MODE 1.
ACTION:
With F[g exceeding its limit:
Reduce THERMAL POWER at least 1% for each 1% that FA a.
exceeds the limit with n 15 minutes and similarly reduce the Nuclear i
vetpower Trip Setpoint and Nuclear Overpower based on RC5 Flow and the AX1AL POWER i
i IMBALANCE Trip Setpoint within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
N' b.
Demonstrate through in-core mapping that u is within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter exceeding the limit or reduce ERMAL POWER to less than 3% 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 />.
c.
Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by a or b, above; subsequent POWER OPERATION may proceed provided that Fly is demonstrated through in-core mapping to be witnin its limit at a nominal 50% of RATED THERMAL POWER prior to exceecing this THERMAL POWER, at a nominal 73% of RATED THERMAL POWER prior to exceeding this THERMAL POWER and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter attaining 95% or greater RATED THERMAL POWER.
l l
l CRYSTAL RIVER - UNIT 3 3/42-6 Amendment Np. 76,77 l
l 1