ML20073L036
| ML20073L036 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/08/1991 |
| From: | Samworth R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073L040 | List: |
| References | |
| NUDOCS 9105130173 | |
| Download: ML20073L036 (8) | |
Text
_
4 8
p* *t om 1
+5 0
3 J UC)n',
3 UNITED STATES l
) i NUCLEAR REGULATORY COMMISSION y'/
t WASHINGTON. D C 2M65 o
9.,.....#
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PL ANT, l' NIT NO.1 AMENDMENT TO FACILITY OPERAT.NG LICEN51 Amendment No.127 License No. DPR-24 1.
The Nuclear Regulatory Connission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated October 30, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conmission's rules and regulations set forth in 10 CFR Chapter I; B.
The f acility 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 connon 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.
910513017? *10500 POR ALOCK 0500C Q's p
PDn
2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No.
DPR-24 is hereby amended to read as folicws:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.127, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issu3nce.
The Technical Specifications are to be implemented within 20 days from the date of issuance.
FOR THE tlVCLEAR REGUl.ATORY COMMISSION vA Robert B. Samworth, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Cnanges to the Technical Specifications Date of issuance: May 8, 1991
j e atov
[E
, J, %
UNITED STATES
~p /p'i 5-NUCLEAR REGULATORY COMMISSION WASWNoTON, D.C. 2055s
+.....-
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No.131 License No. DPR f7 1.
The Nuclear Regulatory Commission (the Cornission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated October 30, 1990, 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; 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.
e
-2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license t.mendment, and paragraph 3.B of Facility Operating License No.
DPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No,131, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately upon issuance.
The Technical Specifications are to be implemented within 20 days from the date of issuance, FOR THE NUCLEAR REGULATORY COMMISSION hf W5 Robert B. Samworth, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/IV/V Office of Huclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
May 8, 1991
.~.
9 ATTACHMENT TO ' LICENSE AMENDMENT NOS.127 AND 131 TO FACILITY 0PERATING LICENSE N05. DPR-24 AND DPR-27 DOCKET N05. 50-266 AND 50-301 l
Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT P
15.3.1-17 15.3.1-17 i
15.3.1-18 1 5.3.1 '
15.5.3-2 15.5.3-2 l-
F.
MINIMUM CONDITIONS FOR CRITICALITY Specification:
1.
Except during low power physics tests, the reactor shall not be made critical when the moderator temperature coefficient is more positive than 5 pcm/'F.
2.
Reactor power shall not exceed 70 percent of Rated Power if the moderator -
temperature coefficient is positive.
i-3.
During an approach to criticality, at least one (1) count per second, attributable to neutrons, shall register on a narrow range source range nuclear instrument.
4.
In no case shall the reactor be made critical (other than for the purpose l
of low level physics tests) to the left of the reactor core criticality l
i l
curve presented in Figure 15.3.1-1.
5.
The reactor shall be maintained subcritical by at least 1%
until l
l normal water len, is established in the pressurizer.
i l
Basis:
During the early part of the fuel cycle, the moderator temperature coefficient is calculated to be sli htly positive at coolant temperatures below 70 percent of rated thermal power. I)I2) The moderator coefficient at low temperatures will be most positive at the beginning of life of the fuel cycle, when the boron concentration in the coolant is the greatest.
Later in the; life of the fuel cycle, the boron concentrations in the coolant will be lower and the l
moderator coefficients will be either less positive or will be negative.
At all ' times, the moderator coefficient is negative when 1 70 percent of I
rated thEPT3l power.
Suitable physics measurements of moderator coefficient of reactivity will be made as part of the startup program to verify analytic predictions.
l l
l Unit 1 - Amendment No. E7,RE,725,127 Unit 2 - Amendment No. E7,99,729,131 15.3.1-17
=-
Y
The limitations of the moderator temperature coefficient are provided to ensure that the assumptions used in the accident and transient analyses remain valid through each fuel cycle. This requirement is waived curing low power physics tests to permit measurement of reactor moderator coefficient and other physics design parameters of interest.
During physics tests, special operating pre-cautions will be taken.
In addition, the stror,g negative Doppler coefficient (3) and the small integrated ak/k would limit the magnitude of a power excursion resulting from a reduction of moderator density.
Requiring that the source range instrumentation is registering a count rate attributable to neutro'ns of at least one (1) count per second insures that the source range instrumentation is fonctioning properly.
A functional source range instrument permits the operator to monitor neutron flux levels and to observe the subtritical neutron multiplicatior, during the positive reactivity addition of the reactor startup.
The requirement that the reactor is not to be made critical below the Reactor Core Criticality Curve provides assurance that a proper relationship between reactor coolant pressure and temperature will be maintained during syste, aeatup and pressurization.
Heatup to this temperature will be accomplished by operating the reactor coolant pumps.
However, as provided in 10 CFR Part 50 Appendix G, Section IV. A 3, the reactor core may be taken critical below this curve for the purpose of low level physics tests.
If the specified shutdown margin is maintained (Section 15.3.10), there is no possibility of an accidental criticality as a result of an increase of moderator temperature or a decrease of coolant pressure.(I)
The requirement for bubble formation in the pressurizer when the reactor has passed the threshold of 1% subtriticality will M sure that the Reactor Coolant System will not be solid when criticality is achieved.
References:
(1) FSAR Table 3.2.1-1 (2)
FSAR Figure 3.2.1-9 (3) FSAR Figure 3.2.1-10 Unit 1 - Amendment No. EE, J2E,127 Unit 2 - Amendmtrt No. 90, M 8,131 15.3.1-18
s :. :-
3.
__ Burnable absorber and/or water displacer rods are incorporated for reactivity and/or power distribution control, The burnable absorber I4) rods consist of borated pyrex glass clad with stainless st I
i The water displacer rods are empty burnable absorber rods r.ontaining no pyrex glass.
Another type of burnable absorber may consist of a thin coating of zirconium diboride on the radial surface of selected fuel rod pellets.
4.
There are 33 full-length RCC assemblies in the reactor core.
The full-length RCC assemblies contain a 142-inch length of silver-indium-cadmium alloy clad with the stainless steel.
5.
Neutron source assemblies may be used to provide a required minimum cour.t rate during startup operations. A source assembly, if used, would typically consist of four source rodlets comprised of a mixture of antimony and beryllium.
6.
Peripheral power suppression assemblies (tlJA) are used to reduce neutron fluence at the welds in the beltline region of the reactor vessel.
Peripheral fuel assemblies may contain PPSAs, which utilize part-length hafnium absorber rods in the assembly guide tubes.
B.
The design of the Reactor Coolant System complies with the code requirements.I6) 2.
All high pressure piping, components of the Reactor Coolant System and their supporting structures are designed to Class I requirements, and-have been designed to withstand:
a.
The design seismic ground acceleration 0.069, acting in the horizontal and 0.04g acting in the vertical planes simultaneously, with stresses maintained within code
-allowable working stresses.
Unit l'- Amendment No. 22,26,E6,JJJ,128,127 Unit 2 - Amendment No. 22,70,JJA,J22,131 15.5.3-2 1
-