ML19332G077
| ML19332G077 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/11/1989 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19332G074 | List: |
| References | |
| NUDOCS 8912200132 | |
| Download: ML19332G077 (6) | |
Text
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"#jp ttog'o UNITED STATES T-NUCLEAR REGULATORY COMMISSION s
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1 NORTHEAST NUCLEAR ENERGY COMPANY DOCKET NO. 50-245
' MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 m
License No. DPR-21 1.
The Nuclear Regulatory C, mission (the Comission) has found that:
A.
The application for amendment b) Northeast Nuclear Energy Company (the licensee), dated August 17, 1987 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 Comission; C.
There'isreasonableassurance(i)thattheactivitiesauthorizedby 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 Comission's regulations; L
D.
The issuance.of this amendment will not be inimical to the comon 1
defense and security or to the health.and safety of the public; and j
E.
The issuence of this amendment is in accordance with 10 CFR Part 51 of the Corvr.ission's regulations and all applicable requirements have been satisfied.
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8912200132 891211 PDR ADOCK 05000245 p
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2-2.
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. DPR-21 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised i
through Amendment No. 41, are hereby. incorporated in the license.
The licensee shall operate the facility in accordance with the-Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be
-implemented-within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION c
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oh'n' F. Sto'12, Director S,cject Directorate I A Pr 1 vision of. Reactor Projects - 1/11 Office of Nuclear Reactor Regulatior.
Attachnient:
. Changes to the Technical
- Specifications Date of Issuance: December 11, 1989 t
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 41
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FACILITY OPERATING LICENSE NO. OPR-21 DOCKET NO. 50-245 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number end contain vertical lines indicating the areas of change.
Remove Insert 2-3 2-3 B2-8 B2-8 3/4 1-4 3/4 1-4 S
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SAFETY LIMITS fI 2.1.1 FUEL CLADDING INTEGRITY B.
When the reactor pressure is less than or equal to 800 psia or reactor flow-is less than 10% of design, the reactor thermal power transferred to
- the coolant shall not exceed 25% of rated.
C.
1.
To assure that the Limiting Safety System Settings established in Specificiations 2.1.2A and 2.1.2B are not' exceeded, each required scram shall be initiated by its primary source signal. The Safety Limit shall be' assumed to be exceeded when scram is accomplished by a means other than the Primary Source Signal.
2.
When the process computer is out of service, this safety limit shall be assumed to be exceeded if the neutron flux exceeds the scram setting established by Specificiation 2.1.2A and a control rod scram does not occur.
D.
Whenever the reactor is in the cold shutdown condition with irradiated fuel in the reactor vessel, the water level shall not be less than that corresponding to 12 inches above the top of the active fuel when it is seated in the core. This level shall be continuously monitored.
LIMITING SAFETY SYSTEM SETTINGS 2.1.2.A.1.a.
where:
S: Setting in percent of rated thermal power (2011 MWt)
W=
Total recirculation flow in percent of design. See Note (1)
The trip setting shall not exceed 90 percent of rated power i
dt.aing generator load rejections from an initial reactor thermal I'
power greater than 50% of rated. The APRM scram setdown shall be 90% of rated within 30 seconds after initiation of full load rejection.
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b.
In the event' of operation with a maximum fraction of limiting ll power density (MFLPD) greater than the fraction of rated power (FRP), the setting shall be modified as follows:
- where, FRP = fraction of rated thermal power (2011 MWt)
Nota (1) Design flog to be defined as the recirculation flow (not to exceed 33.48 x 10 lbs/hr.) needed to achieve 1005 core flow.
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Millstone Unit 1 2-3 Amendment No. 41 l
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'2.1.2 FUEL CLADDING 1NTEGRITY l
SASIS The design of the ECCS components to meet the above criteria was depen -
dent on three previously set parameters: the maximum break size,'the low water level scram setpoint, and the ECCS initiation setpoint. To lower the setpoint for initiation of the ECCS would prevent the ECCS components from meeting their design criteria. To raise the ECCs initiation setpoint would be in a safe direction, but it would reduce the margin established to prevent actuation of the ICC$'during normal operation or during normally expected transients.
f.
Turbine Sten Valve Scram s
The turbine stop valve scram, like the load rejection scram, anticipates the pressure, neutron flux, and heat flux increase caused by the rapid closure of the turbine stop valves and failure of the bypass. With a scram setting of < 10% of valve closure, the resultant increase in surf ace heat flux *is limited such that MCPR remains above 1.04 even during the worst case transient that a:sumes the turbine byoass is closed. This scram is bypassed when reactor thermal power is less than 50% of rated.
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F.
Turnine Control Valve Fast Closure The turbine control valve fast closure scram is provided to anticipate the rapid increase in pressure and neutron flux resulting from fast closure cf the turbine control valves due to a lead rejection and subse-quent failure-of the bypass; i.e., it prevents MCPR from becoming less than 1.04 for' this transient.
For the load rejection from 100% power with operable bypass valves, the heat flux inectases to only 106.5% of its rated power value, which results in only a small decrease in MCPR.
This trip is bypassed below a reictor thermal power of 50% of rated because, below this power level, the MCPR is greater than 1.04 throughout the transient without the scram.
In order to accommodate the full load rejection capability, this scram trip must be bypassed because it would be actuated and would scram the reactor during load rejections. This trip is automatically bypassed for a maximue of 280 millise following initiation of Icad rejection. After 280 millisec, the trip is bypassed providing the bypass valves have opened.
If.the bypass valves have not opened after 280 millisec, the
.bypa'ss is removed and the trip is returned to the active condition.
This bypass does not adversely affect plant safety because the primary system pressure is within limits and MCPR remains above 1.04 during the worst transient even if the trip fails.
There are many other trip functions which protect the system during such transients.
G.
Main Steam Line Isolation Valve Closure Scram The low pressure isolation of the main steam lines at 825 psig was provided to give protection against rapid reactor depressurization and the resulting rapid cooldown of the vessel. Advantage was taken of the scram feature which occurs when the main steam line isolation valves are
- closed, 1
Millstone Unit 1 B 2-8 Amendeent No. 1, 2,0, 41 1
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