ML20248A849
| ML20248A849 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 05/31/1989 |
| From: | Yandell L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248A853 | List: |
| References | |
| NUDOCS 8906080212 | |
| Download: ML20248A849 (6) | |
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'4 uq'o UNiiED STATES
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NUCLEAR REGULATORY COMMISSION n
g WASHINGTON, D. C. 20555 f
CONSUMERS POWER COMPANY PALISADES PLANT DOCKET NO. 50-255 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.124 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 February 25, 1987, 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;
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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.
I 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.
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. 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 Provisional Operating License No. DPR-20 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.124, 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 its issuance and shall be implemented not later than July 15, 1989.
FOR THE NUCLEAR REGULATORY' COMMISSION M1Q4QQ Lawrence A. Yandell, Acting Director Project Directorate III-I Division of Reactor Projects - III, IV, V
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& Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical e
Specifications i
i Date of Issuance: May 31, 1989 I
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ATTACHMENT TO LICENSE AMENDMENT NO.124 PROVISIONAL 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 the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 1-3 1-3 3-77 3-77
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3-81 3-81
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.4 1.2 PROTECTIVE SYSTEMS Instrument Channels One of four independent measurement channels, complete with the sensors, sensor power supply units, amplifiers and bistable modules provided for each safety parameter.
Reactor Trip The de-energizing of the control rod drive mechanisms (CRDM) magnetic clutch holding coils which releases the control rods and allows them to drop into the core.
Reactor Protective System Logic This system utilizes relay contact outputs from individual instrument channels to provide the reactor trip signal for de-energizing the magnetic clutch power supplies. The logic system is wired to provide a reactor trip on 2-of-4 or 2-of-3 basis for any given input parameter.
Degree of Redundancy The difference between the number of operable channels and the number of channels which, when tripped, will cause an automatic system trip. This defini, tion does not apply to the 1 out of 2 taken twice logic scheme used to initiate the Recirculation Actuation System.
Engineered Safety Features System Logic
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This system utilizes relay contact outputs from individual instrument channels to provide a dual channel (right and left) signal to initiate independently the actuation of engineered safety feature equipment connected to diesel generator.1-2 (right channel) and diesel generator 1-1 (left channel). The logic system is wired to provide appropriate signal for the actuation of the engineered safety feature equipment on a
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2-of 4 basis for any given input parameter. The Recirculation Actuation System is initiated by a 1 out of 2 taken twice logic.
1.3 INSTRUMENTATION SURVEILLANCE Channel Check A qualitative determination of acceptable operability by observation of channel behavior during normal plant operation. This determination shall, where feasible, include comparison of the channel with other independent channels measuring the same variable.
Channel Functional Test Injection of a simulated signal into the channel to verify that it is operable, including any alarm and/or trip initiating system.
Channel Calibration Adjustment of channel output such that it responds with acceptable range and accuracy, to known values of the parameter which the channel Calibration shall encompass the entire channel, including measures.
equipment action, alarm, interlocks or trip and shall be deemed to include the channel functional test.
1-3 Amendment No. 43, 57,124 l
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.3.17 INSTRi? MENTATION AND CONTROL SYSTEMS (Contd)
If the bypass is'not effected, the out-of-service channel (Power Removed)assumesatrippedcondition(excepthighrate-of-gnge power, variable high power and high pressurizer pressure),
which results in a one-out-of-three channel. logic.
If, in the 2 of 4 logic system of either the reactor protective system or the engineered safeguards system, one channel is bypassed and a second channel manually.placed in a tripped condition, the.resulting logic is 1 of 2.
At rated power, the minimum operable variable high power level channels is 3 in order to provide adequate flux tilt detection.
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'If only 2 channels are operable, the reactor power level is reduced to 70% rated power which protects the reactor from possibly exceeding design peaking factors due to undetected flux tilts.
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The engineered safeguards system provides a 2 out of 4 logic on the signal used to actuate the equipment connected to each of the 2 emergency diesel generator units.
Two start-up channels are available any time reactivity changes are deliberately being introduced into the reactor and the neutron power is,not visible on the log-range nuclear instrumentation pr above 10 4% of rated power. This ensteres that redundant start-up a-instrumentation is available to operators to monitor effects of reactivity changes when neutron power levels are only visible on the start-up channels.
In the event only one start-up range channel-is available and the neutron power level is sufficiently high that it is being monitored by both channels of log-range instrumentation, a startup can be performed in accordance with footnote (d) of Table 3.17.4.
The Recirculation Actuation System (RAS) initiates on a 1 out of 2 taken twice logic scheme. Any one channel declared inoperable shall be placed in a bypass condition to ensure protection from an inadvertent RAS actuation. Since the bypassing of a channel intro-duces the possibility for a failure to receive an automatic RAS actuation signal, the time period in the bypassed condition is limited.
The Zero Power Mode Bypass can be used to byp g the low flow, steam generator low pressure, and TM/LP trips for all four Reactor Protective system channels to perform control rod testing or to perform low power physics testing below normal operating temperatures. The requirement to maintain cold shutdown boron concentration when in the bypass condition provides additional assurance that an accidental criticality will not occur. To allow low power physics testing at reduced temperature and pressure, the requirement for cold shutdown boron concentration is not required I
and the allowed power is increased to 10 1%.
References i
(1) Updated FSAR, Section 7.2.7.
(2) Updated TSAR, Section 7.2.5.2 3-77 Amendment No. 1 4.124
l Table 3.17.4 l
1 Instrumentation Operating Requirements for Other Safety Feature Functions i
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l Minimum Minimum Permissible l
Operable Degree of Bypass
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l No Functional Unit Channels Redundancy Conditions i
1 SIRh7 Low-Level 4
NA(b)
One channel may be i
l Switches inoperable for a period of 7 days (b) i 2
AT - Power 3(C) 1 None Comparator l
3 (Deleted) 4 Air Cooler Service 1
None None k'ater Flow Instruments 5
Primary and Secondary 1
None NA Rod, Insertion and Out-of-Sequence Monitors 6
Fuel Pool Building 1
None As Requested Under Crane Interlocks Administgive Controls 7
Start-Up Channels 2
1(d)
Not Required Above 4
10 % of Rated Power I
(a) Crane shall not be used to move material past the fuel storage pool j
unless the interlocks are available.
(b) If a channel is declared inoperable, it shall be placed in a bypass 4
condition. Minimum degree of redundancy is not applicable to the SIRbT low-level switches.
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(c) If only two channels are operable, load shall be reduced to 70% or less i
of rated power.
(d) Minimum operable channels shall be one (1) and minimum degree of redundancy is rero (0) if shutdown neutron power levels indicated on the log range channels are greater than three times the lowest decade in which neutron visibility can be confirmed. Neutron visibility will I
be confirmed through observation of reactivity changes on neutron power level (including a 1/M plot during reactor start-up) and comparing the observed changes to the changes noted on previous similar start-ups.
Instrumentation operability will also be verified by comparison among the three operable channels to ensure their individual responses are in agreement.
i 3-31 O//fd/Kp//3 Amendment No. JJJ,124
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