ML20211N813
| ML20211N813 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/03/1999 |
| From: | Craig C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211N819 | List: |
| References | |
| NUDOCS 9909130081 | |
| Download: ML20211N813 (5) | |
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2 WASHINGTON, D.C. 300SH001 CONSUMERS ENERGY COMPANY DOCKET NO. 50-255 PALISADES PLANT-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.187 License No. DPR 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Energy Company (the licensee) dated June 17,1998, as supplemented by letters dated June 23 and December 2,1998, and March 18,1999, 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:
The Technical Specifications contained in Appendix A, as revised through Amendment No. 187
,' and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license. Consumers Energy Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
9909130081 990903 l
PDR ADOCK 05000255 P
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3.
This license amendment is effective as of the date of issuance and shall be
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implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION QV
' c',
Claudia M. Craig, Chief, Section 1 Project Directorate lil Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
- Changes to the Technical Specifications Date of issuance:
September 3, 1999 l
ATTACHMENT TO LICENSE AMENDMENT NO.187 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 verticallines indicating the areas of change.
EgMOVE INSERT 3-1 b 3-1 b 3-2 3-2 3-3 3-3 i
3.1 PRIMARY COOLANT SYSTEM Acolicab111tv Applies to the operable status of the primary coolant system.
Qb.iective To specify certain conditions of the primary coolant system which must be met to assure safe reactor operation.
Specifications 3.1.1 Operable Comoonents a.
At least one primary coolant pump or one shutdown cooling pump with a flow rate greater than or equal to 2810 gpm shall be in operation whenever a change is being made in the boron concentration of the primary coolant and the plant is operating in cold shutdown or above, except during an emergency loss of coolant flow situation. Under these circumstances, the boron concentration may be increased with no primary coolant pumps or shutdown cooling pumps running.
b.
Four primary coolant aumps shall be in operation whenever the reactor is operated a)ove hot shutdown, with the following exception:
Before removing a pump from service, thermal power shall be reduced as specified in Table 2.3.1 and appropriate corrective action implemented. With one pump out of service, return the pump to service within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (return to four pump operation) or be in hot shutdown (or below) with the reactor tripped (from the C 06 panel, opening the 42 01 and 42 02 circuit breakers) within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Start up (above hot shutdown) with less than four pumps is not permitted and power operation with less than three pumps is not permitted.
c.
The measured four arimary coolant pumps operating reactor vessel flow shall ae > 352,000 gpm.
I d.
Both steam generators shall be ca>able of performing their heat transfer function whenever tie average temperature of the primary coolant is above 300*F.
e.
The AXIAL SHAPE INDEX (ASI) shall be maintained within the limits specified in the COLR.
(1)
When the ASI exceeds the limits specified in the COLR, within 15 minutes initiate corrective actions to restore the ASI to the acceptable region. Restore the ASI to acceptable values within one hour or be at less than 70%
of rated power within the following two hours.
3 lb Amendment No. M, 85 HB, H9, H4, B7, M1, %9, 187
3.1 PRIMARY COOLANT SYSTEM 3.1.1 Ooerable comoonents (continued)
Basis When primary coolant boron concentration is being changed, the process must be unifom throughout the primary coolant system volume to prevent stratification of primary coolant at lower boron concentration which could result in a reactivity insertion. Sufficient mixing of the primary coolant is assured is in operation."jf one shutdown cooling or one 1rimary coolant pum)
The shutdown cooling pump will circulate the prtmary system volume in less than 60 minutes when operated at rated capacity. By imposing a minimum shutdown cooling pump flow rate of 2810 gpm, sufficient time is provided for the(gperator to teminate the boron dilution under asymmetric flow conditions.
The pressurizer volume is relatively inactive, therefore it will tend to have a boron concentration higher than the rest of the primary coolant system during a dilution operation. Administrative procedures will )rovide for use of pressurizer sprays to maintain a nominal snraad between t1e boron concentratig in the pressurizer and the primary system during the addition of boron.
The 57% pressurizer level, in section 3.1.1h(4), is not an analytical result, but simply a decision )oint between having and not having a bubble.
It was chosen to agree with t1e maximum programmed level during power operation.
The limitation, in section 3.1.11, on operating P-50A and P-50B together with T, below 300*F allows the pressure Temperature limits of Figures 3-1 and 3-2 to be higher than they would be without this limit.
The FSAR safety analysis was perfomed assuming four primary coolant pumps were operating for accidents that occur during reactor operation. Therefore, reactor startup above hot shutdown is not )ermitted unless all four primary coolant pumps are operating. Operation wit 1 three primary coolant pumps is pemitted for a limited time to allow the restart of a stopped pump or for reactor internals vibration monitoring and testing.
Requiring the plant to be in hot shutdown with the reactor tripped from the 0-06 panel, opening the 42-01 and 42-02 circuit breakers, assures an inadvertent rod bank withdrawal will not b3 initiated by the control room operator. Both steam generators are required to be operable whenever the temperature of the primary coolant is greater than the design temperature of the shutdown cooling system to assure a redundant heat removal system for the reactor.
The transient analyses which require a minimum vessel flow rate assumption were perfomed assuming a vessel volumetric flow rate of 352,000 gpm, which corresponds to an analytical limit of 341,400 g>m when adjusted for 3% flow measurement uncertainty. For calculations whic1 require a core flow rate, the analyticg limit is further reduced by 3% to account for core bypass, to 331,200 gpa A DNS analysis was performed for the limiting A00 which is not protected by a reactor trip, in a parametric fashion to determine the core inlet temperature as a function of pressure and flow for which the minimum DNBR is equal to the l
DNB correlation safety limit. Subsequent conftming analyses include the
.fcilowing uncertainties and allowances: 2% of rated power for power measurement; 0.06 for ASI measurement; 22 psi for pressurizer pressure; N.
- 7'F for inlet temperature; and 3% measurement and 3% bypass for core flow In addition, transient biases were included in the determination of the allowable reactor inlet temperature.
3-2 Amendment No. 67, BS, H 7, HB, tM, H7, MS M9. -H+,
187
3.1 -PRIMARY COOLANT SYSTEM BA111 (continued)
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-_The limits of validity of the T, _ equation are:
1800 s pressure s 2200 psia-l 100.0 x 10' s Vessel Flow s 150 x 10' lb/h ASI as shown in the COLR.
With measured primary coolant system flow rates > 150 M lbm/hr, limiting the i
maximum allowed inlet temperature to thgI., LCO at 150 M lbm/hr increases the T
1 margin to.DNB for higher PCS flow rates l
The Axial Shase'Index alam channel is being used to monitor the ASI to ensure that tie' assumed axial power profiles used in the development of the
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inlet temperature LCO 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 ordered pair exceed the boundark)e. An alam signal ls activated before constitute an ordered pair (Q Y s specified in the COLR.
The requirement that the steam !enerator temperature be s the PCS temperature when forced circula ion 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 f
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) EMF 97-051, Revision 1.-Table 2.1.
l (4) EMF-98-013. Revision 0. Section 15.0.7.1 l
L I
(5) ANF-90-078 (6) Consumers Power Company Engineering Analysis EA-A-NL-89-14-1 9
4 3-3 Amendment No. M. H. W. H6, Mt. H4, W. H3, M6, M9, M9, H+,187
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