ML20100Q185
| ML20100Q185 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 11/27/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Northern States Power Co |
| Shared Package | |
| ML20100Q187 | List: |
| References | |
| DPR-22-A-031 NUDOCS 8412170036 | |
| Download: ML20100Q185 (6) | |
Text
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UNITED STATES
["
. NUCLEAR REGULATORY COMMISSION
- 3
,j WASHINGTON, D. C. 20555 -
f NORTHERN STATES POWER COMPANY DOCKET NO.'50-263 MONTICELLO NUCLEAR GENERATING PLANT
^
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. DPR-22
'1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northern States Power Company (the licensee) dated July 27, 1984 as clarified by letters dated September 25, 1984 and October 25, 1984, 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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the c^,mmon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, tha 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-22 is hereby amended to read as follows:
8412170036 841127 PDR ADOCK 05000263 P
. 2 Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 31, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
- n., P <.,.
a-e,<;. -
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 27, 1984
ATTACHMENT TO LICENSE AMENDPENT NO. 31 FACILITY OPERATING LICENSE NO. DPR-22 i
DOCKET NO. 50-263 Replace the following pages of the Appendix "A" Technical Specifications with
' the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 60A 60a 69 69 71 71 1
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Table 3.2.6 Instrumentation for Safeguards Rus Degraded Voltage and 1.oss of Voltage Protection Minimum Ho. of Hinlanse No. of Oper-Operable or Total No. of able or Operating operating Trip Instrument Channels Channels Per Required Function Trip Setting Systems 11)
Per Trip System Trip System (1)
Conditions
- 1.
Ilegraded Voltage 3915 + 18 volta 1/hus 3
3 A
Protection (3) 9.+ g,ec, 2.
Ioss of Volta e 2625 + 175 volta 2/ bus 2
2 A
Protection (2 y,g,ptentional delay NOTE:
1.
Upon discovery that misilmum requiremesets for the number of operable or operating trip systems or instrument channels are not satisfied, action shall be initiated tot a.
Sa t isf y the requirements by placing the appropriate channels or systems in the tripped condition, or b.
Place the plant under the specified required conditions using normal operating procedures.
2.
One out of two twice logic.
3.
Two out of three logic.
0 Required conditions when sluimum conditions for operation are emot satisfied:
A.
Cold shutdouse within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
O e
8-an
.O
- y 3.2/4.2 Min
- e. A t
a Bases Continued:
increases core voiding, a negative reactivity feedback. liigh pressure sensors initiate the pump trip in the event of an isolation transient.
Low level sensors initiate the trip on loss of feed-water (and the resulting MSIV closure). The recirculation pump trip is only required at high reactor power levels, where the safety / relief valves have insufficient capacity to relieve the steam which continues to be generated after reactor isolation in this unlikely postulated event, requiring the trip to be operable only when in the RUN mode is therefore conservative.
Voltage sensing relays are provided on the safeguards bus to transfer the bus to an alternate source when a loss of voltage condition or a degraded voltage condition is, sensed.
Du loss of voltage this transfer occurs immediately. The transfer on degraded voltage has a time delay to prevent transfer during the starting of large loads. The degraded voltage setpoint corresponds to the minimum acceptable safeguards bus voltage for starting and running Joads during a loss of coolant accident. An allowance for relay tolerance is included.
Although the operator will set the set points within the trip settings specifed in Tables 3.2.1 through 3.2.6, the actual values of the various set points can differ appreciably from tie value the operator is attempting to set.
The deviations could be caused by inherent instrument error, drif t of the set point, ect.
Therefore, these deviations have been ' accounted for in the various transient analyses and the actual trip settings may vary by the following amounts.
s e
2 8e Q
N 3.2 IIASES 69 I
-9.
t Trip funiction Deviation Instrumentation That Initlates Emergency Low-1.ow llenctor Water Level
-3 Inches Core Cooling Systems Table 3.2.2 Neactor I.ow Pressure (Pump
-10 ps!
Start) Permissive liigh lirywell Pressure
+1 pel Low Reactor Pressure (Valve
-10 pet Permissive)
Instrumentation That Inittstes IRH ikiwnscale
-2/125 of Scale Itod Block IMH lipscale
+2/125 of Scale Table 3.2.3
~ l april Ikiunseala
-2/125 of Seale ~
APlut lipscale See Basta 2.3 Nhlt Iksunseale
-2/125 of Scale RMI lipscale Same as APilH tipscale Scram Illscharge Volume-liigh
+ 1 gallon Level Ins t rumenta t ion Tha t Initiates liigh Neactor Pressure
+ 12 pai Recirculat tosi Pump Trip I.ow Reactor Water Level
-3 Inches Instrumentation for Safeguards Degraded Voltage 23897 volta (trip)
Bus l*rotection
$3975 volts (reset) 25 sec g10 see (delay) l.oss of Voltage
<.3000 volts >2000 volta aa i
j A violation of this specification is assumed ta occur only when a device is knowingly set outside of the limiting trip settings, or, when a suf ficient number of devices have been af fected by any means sisch that the automatic function is incapahle of operating within the allowable deviation wiille in a reactor mode in
=
C) which the especified function emist ho operable or when actions specified are not initiated as specified.
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3.2 BASES 71
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