ML20057C180
| ML20057C180 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/21/1993 |
| From: | Bill Dean Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057C181 | List: |
| References | |
| NUDOCS 9309280043 | |
| Download: ML20057C180 (7) | |
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TJI[ E UNITED STATES 5{h i NUCLEAR REGULATORY COMMISSION g,
8 WASHINGTON, D.C. 20555-0001 CONSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.159 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated September, 3, 1993, 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; 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 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; 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license amendment and Paragraph 2.C.(2) of facility Operating License No. DPR-20 is hereby amended to read as follows:
9309280043 930921 PDR ADDCK 0S000255 P
I Technical Specifications t he Technical Specifications contained in Appendix A, as revised ough Amendment No.159, and the Environmental Protection Plan
. atained in Appendix B are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
FOR T 1UCLEAR REGULATORY COMMISSION h
for William M. Dean, Acting Director Project Directorate 111-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: Septsber 21, 1993
4 ATTACHMENT TO LICENSE AMENDMENT NO.199 FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT B 2-5 B 2-5 3-3 3-3 3-67 3-67 3-107 3-107 1
d t
F
2.0 BASIS - Safety Limits and limitino Safety System Settinos 2.3 Basis - Limitino Safety System Settinos (continued) 5.
Low Steam Generator Water level - The low steam generator water level reactor trip protects against the loss of feed-water flow accidents and assures that the design pressure of the primary coolant system will not be exceeded. The specified set point assures that there will be sufficient water inventory in the steam generator at the time of trip to allow a safe and orderly plant shutdown and to prevent steam generator dryout assuming minimum auxiliary feedwater capacity.'"
The setting listed in Table 2.3.1 assures that the heat transfer surface (tubes) is covered with water when the r.eactor is critical.
6.
Low Steam Generator Pressure - A reactor trip on low steam generator secondary pressure is provided to protect against an excessive rate.of heat extraction from the steam generators and subsequent cooldown of the primary coolant. The setting of 500 psia is sufficiently below the rated load operating point of 739 psia so as not to interfere with normal operation, but still high enough to provide the required protection in the event of excessivel was used in the accident analysis.'" y high steam flow.
This setting 7.
Containment Hiah Pressure - A reactor trip on containment high pressureisprovidedtoassurethatthereactorisshutdownbeforgthe initiation of the safety injection system and containment spray.'
t References (1)
EMF-92-178, Revision 1, Table 15.0.7-1
[
(2)
Updated FSAR, Section 7.2.3.3.
(3)
EMF-92-178, Revision 1, Section 15.0.7-1 l
1 (4)
XN-NF-86-91(P)
(5)
ANF-90-078, Section 15.1.5 (6)
ANF-87-150(NP), Volume 2, Section 15.2.7 (7)
Updated FSAR, Section 7.2.3.9.
(8)
ANF-90-078, Section 15.2.1 Amendment No M, B2, 448. H7, MO, 4M,159 B 2-5
4 3.1 PRIMARY COOLANT SYSTEM (Cont'd)
Basis (Cont'd) measurement; 10.06 for ASI measurement; 150 psi for pressurizer pressure; 17'F for inlet temperature; and 3% measurement and 3% bypass for core flow.
In addition, transient biases were included in the derivation of the following equation for limiting reactor inlet temperature:
Tg,, s 542.99 +.0580(P-2060) + 0.00001(P-2060)**2 + 1.125(W-138) -
.0205(W-138)**2 The limits of validity of this equation are:
1800spregsures2200 psia 100.0 x 10 s Vessel Flow s 150 x 10' lb/h ASI as shown in Figure 3.0 With measured primary coolant system flow rates > 150 M lbm/hr, limiting the maximum allowed inlet temperature to the T LCO at 150 M lbm/hr increases the margin to DNB for hIg$,er PCS flow ratesW The Axial Shape Index alarm channel is being used to monitor the ASI to ensure that the assumed axial power profiles used in the development of the inlet temperature LC0 bound measured axial power profiles. The signal representing core power (Q) is the auctioneered higher of the neutron flux power and the Delta-T power. The measured ASI calculated from the excore detector signals and adjusted for shape annealing (Y,) and the core power constitute an ordered pair (Q,Y ).
An alarm signal is activated before i
the ordered pair exceed the boundaries specified in Figure 3.0.
The requirement that the steam generator temperature be s the PCS temperature when forced circulation is initiated in the PCS ensures that an energy addition caused by heat transferred from the secondary system to the PCS will not occur. This requirement applies only to the initiation of forced circulation (the start of the first primary coolant pump) when the PCS cold leg temperature is < 430*F.
However, analysis (Reference 6) shows that under limited conditions when the Shutdown Cooling System is isolated from the PCS, forced circulation may be initiated when the steam generator temperature is higher than the PCS cold leg temperature.
References (1)
Updated FSAR, Section 14.3.2.
(2)
Updated FSAR, Section 4.3.7.
(3)
Deleted (4)
EMF-92-178, Revision 1, Section 15.0.7.1 l
(5)
ANF-90-078 (6)
Consumers Power Company Engineering Analysis EA-A-NL-89-14-1 3-3 Amendment No. M, H, W, MB, 4M, M4, W, M3, M6 159
. =.
3.12 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY
.j Acolicability i
Applies to the moderator temperature coefficient of reactivity for'the
]
core.
l Ob.iective To specify a limit for the positive moderator c1 efficient.
Specifications The moderator. temperature coefficient (MTC) shall be less positive than +0.5 x 10"' Ap/*F at s 2% of rated power.
i Bases The limitations on moderator temperature coefficient s'HTC)'are provided to ensure that the assumptions used in the safety analysis")-
-l remain valid.
j l
Reference l
(1)
EMF-92-178, Revision 1, Section 15.0.5 l
i 1
t i
i I
3-67 l
. Amendment No. 448, 4M, 443, 4M,159 '
l (next page is 3-69) j e
I TABLE 3.23-1 i
LINEAR HEAT RATE LIMIT Peak Rod 15.28 kW/ft TABLE 3.23 I RADIAL PEAKING FACTOR LIMITS, Ft Peaking Factor Reload L & M Reload N Reload 0 l
Assembly Fj 1.57 l'.66 1.76 PeakRodF[
1.92 1.92 2.04 r,
TABLE 3.23-3 POWER DISTRIBUTION MEASUREMENT UNCERTAINTY FACTORS LHR/ Peaking Factor Measurement Heasurement Measurement Parameter Uncertainty
- Uncertainty
- Uncertainty
- LHR 0.0623 0.0664 0.0795 i
\\
Fj 0.0401 0.0490 0.0695 F{
0.0455 0.0526 0.0722 i
(a)
Measurement uncertainty for reload cores using all fresh incore detectors.
i (b)
Measurement uncertainty for reload cores using a mixture of fresh and i
once-burned incere detectors.
(c)
Measurement uncertainty when quadrant power tilt, as determined using
?
incore measurements and an incore analysis computer program *, exceeds 2.8% but is less than or equal to 5%.
j i
3-107 Amendment No. 68, 446, M3, 444, 4%,159 l
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