ML20128N235
| ML20128N235 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/10/1996 |
| From: | Robert Schaaf NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20128N240 | List: |
| References | |
| NUDOCS 9610160329 | |
| Download: ML20128N235 (5) | |
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y UNITED STATES 3
,g NUCLEAR REGULATORY COMM!SRON WASHINGTON, D.C. 20666 4 001 O
49.....,o CONSUMERS POWER COMPANY DOCKET NO. 50-255 Pall 5ADES PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.173 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 January 5,1996, as supplemented July 12, 1996, 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:
9610160329 961010 PDR ADOCK 05000255 P
The Technical Specifications contained in Appendix A, as revised through Amendment No.173, and the Environmental Protection Plan contained 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 THE NUCLEAR REGULATORY COMMISSION Robert G. Schaaf, Project Manager Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 10, 1996
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ATTAPllMENT TO LICENSE AMENDMENT NO.173 FACILITY OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 i
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.
j REMOVE INSERT l
3-25j 3-25j 3-25k 3-25k i
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i 3.1.9 SHUTDOWN COOLING (SDC)
Snecification 3.1.9.3 One SDC train shall be in operation providing 21000 gpm flow through the reactor core listedbelowshallbeOPERA8LE:and at least two of the means of decay heat removal i
1.
SDC train A consisting of an OPERABLE SDC. pump and an OPERABLE heat flow path to Lake Michigan.
t 2.
SDC train 8 consisting of an OPERABLE SDC pump and an OPERABLE heat flow path to Lake Michigan.
l 3.
The refueling cavity with water level 2 647'.
Anolicability Specification 3.1.9.3 ap with PCS Temperature is < plies when there is fuel in the reactor, 200*F and the PCS loops E I filled.
Exceptions 1.
All flow through the reactor core may be intentionally stopped for up to I hour provided:
a.
No operations are permitted that would cause reduction of the PCS boron concentration or PCS inventory, and b.
Core outlet temperature stays s 200*F, and c.
l 2.
One or both required SDC trains may be intentionally rendered inoperable for testing or maintenance for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided:
a.
One SDC train is providing flow through the reactor core, and b.
Core outlet temperature stays s 200*F, and c.
The refueling cavity water level is 2 647'.
Action 1.
With fewer OPERABLE means of decay heat removal than required:
a.
Immediately initiate corrective action to return a second train to OPERABLE status, and Maintain PCS temperature as low as practical with e.
available equipment.
2.
With less flow through the core than required:
a.
Immediately suspend all operations involving a reduction in PCS boron concentration, and b.
Immediately initiate corrective action to return a train to operation providing flow through the core.
3-25j Amendment No. M1,173
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-3.1 PRIMARY COOLANT SYSTEM (FLS) 3.1.9 SHUTDOWN COOLING 4
Basis The Shutdown Cooling (SDC) specifications require a minimum flow be
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maintained through the reactor core and two methods of decay heat removal to be OPEAABLE, in each of three situations PCS temperature 200*F to 300*F, PCS temperature below 200*F with the loops fl11ed,d" means the PCS loops ar and PCS temperature below 200 F with the loops not filled.
" Loops Fille intact, not blocked by dams, and totally filled with coolant.
The requirement to maintain 2810 gpa flow through the reactor core when the 3
PCS loops are filled is based on an analysis of potential dilution events.
Maintenance of this flow assures that indication of increasing count rate will be available to warn the operator and allow compensating action. The requirement to maintain 1000 gpa flow through the reactor core when the loops are not filled assures mixing of the PCS while allowing flow to be reduced to avoid vortexing in the SDC suction piping. The 1000 gpa is based on rather on analysis. With flow less than 2810 gpe, operating experience, imposes additional requirements for Shutdown Margin and Specification 3.10.1 limits charging pump operability. Maintaining flow through the reactor core also allows use of the SDC temperature indication to determine core outlet i
temperature when the core outlet thermocouples are not in service.
Natural circulation is adequate for decay heat removal however it may not provideadequatemixingofthePCScoolantduringPCSboronconcentration changes or inadvertent dilution events. Therefore, forced circulation is required axcept during short intervals when the required loops or trains m g i
be intentionally stopped provided additional constraints are followed.
4 The reactor cavity filled to 2 647' elevation provides backup decay heat removal capability. Decay heat is moved by natural circulation to the large mass of water in the refueling cavity. The heat storage capacity of the filled reactor cavity provides a temporary method of decay heat removal which l
provides time to restore the required train of SDC.
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An OPERABLE steam generator, for the purposes of this specification must i
have both its primary and secondary sides intact, its tubes filled with primary coolant, and a secondary water level of at least -84% on the wide range level channels. The specified steam generator secondary water level of q
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-84% ensures that at least one-third of the effective steam generator heat transferareaiscoverg8and is therefore sufficient to sup') ort natural circulation in the PCS In addition, there must be avai able a method of feedwater addition and a controllable path for steam release.
i A heat flow path to the lake may vary in actual component configuration, method of operation and control, but it shall always accomplish the objective 1
i of transferring decay heat from the reactor to Lake Michigan. As a minimum, i
a heat flow path requires: a shutdown cooling pump, a shutdown cooling heat exchanger, a component cooling water pump, a component cooling heat exchanger, a service water pump, and appropriate piping, valves and controls for the equipment to perform its function. All of this equipment must be j
OPERABLE and must have adequate, but not necessarily redundant, electrical power.
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3-25k Amendment No. M+,173 1