ML20080F136
| ML20080F136 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 01/23/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Northern States Power Co |
| Shared Package | |
| ML20080F138 | List: |
| References | |
| DPR-22-A-021 NUDOCS 8402100346 | |
| Download: ML20080F136 (5) | |
Text
_ _,
=.
ps n or,,
g UNITED STATES
[ f. c. f i NUCLEAR REGULATORY COMMISSION g#
s,s A/gj WASWNGTON. D. C. 20555 gw NORTHERil STATES POWER COMPANY DOCKET N0. 50-263 fTitTICELLO t;UCLEAR GENEPATING PLAflT AMENDriErlT TO FACILITY OPERATING LICENSE Amendment No. 21 License flo. DPR-22 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by florthern States Pcwer Company (the
. licensee) dated May 15, 1980, complies with the standards and requirenents 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 regulatibns of the l
Commissien; C.
There is reasonable assurance (1) 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 Conmission's regulations; 4
D.
The issuance of this amendment will not be inimical to the comnon 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 reouirements have been satisfied.
2.
Accordingly, the license is anended 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. OPR-22 is hereby amended to read as follows:
2 Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 21 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
P 8402100346 840123 9
PDR ADOCK 05000263 P
PDN e
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEsR REGULATORY COMMISSI0t<
W
. s **
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Chenges to the Technical Specifications Date of Issuance:
January 23, 1984
ATTACHMENT TO LICENSE At12NDMENT fl0. 21 FACILITY OPERATING LICENSE N0. OPR_22 DOCKET N0. 50-263 1
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 lires indicating the area of change.
Remove Insert 2
2 3
3 e
O e
t
D..I=mediata - Immediate means cost the requ.
tction will be initiated as soca as practictb1 i
considering the safe cparation cf the unit end the importance of the required action.
E.
Instrueent Functional Test - An instrument functional test means the injection of a simulated signal into the primary sensor to verify the proper instrueent channet response, alarm, and/or initiating action.
i F.
Ir.struser.t Calibration - An instrunent calibration neans the adjustment of an instrument j
signal output so that it corresponds, within acceptabic range, accuracy, and respor.se tire to a kncwn value (s) of the parameter which the ins. rument monitors. Calibration shall encompass the entite instrurent including actuation, alarm or trip.
Response time is not part of the I
rou t ine '. ins trume nt calibration but wi,11 be checked once per cycle.
G.
J. nitinn Conditient or Operatfor. (LCO) - The liniting onditions for eperation specify the j
f ntnizuo acciptahic Icvels of system performance necessary to auscre safe startup and operation of the fa' ility. When these conditions are met, the plant can be operated safely and abnormal c
(
situations can be safety controlled.
H.
"Liciting Safety System Setting (LSSS) - The 'liatting safety systen settings are nettings on instrumsntation which initiate the automatic protective. action at a level such that the safety.
limits will not be exceeded. The region between the safety limit and these settings represents cargin with normal operation lying below these settinCs. The margin has been established so that with proper operation c( the ins trumentation,, the safety linits will never be exceeded.
i 1.
Pia s inua Fraction of Limi t t un Power Density (NFLpp)' -, The m.3xim im f raction at limiting poear density is the highest value in the core of the ratio of the existing to the design linear heat generation rate.
4
\\
J.
Hinicum Critical Power Ratio (HCPR) - The minimum critical power ratio is the value of critical peset ratio asscclated with the must limiting assembly in the reactor core. Crit (cal pouct l
ratio (CPR) is the ratio of that. power in a fuel asucubly which. is calculated by the GEyL i
correistion to cause some point in the assembly to experience boiling transition to the actual assen'aly operating power.
K.
Mode - The teactor mode is that which is established by the mode-selector switch.
L.
Operable - A system, subsystem, t rain, component or device shall be Operable or have Operabilit y when it is ce pahle of performing its specified funct ion (s).
Implicit in this definition I
shall_be the assumption that all necessary attendant instrumentation, controls, normal and emergency ele ctrical power sources, cooling or seal water, tuhrication or other auxiliary equi pme nt thet are required for the system, subsystem, t rain, compo ient or device to perform it s functionis) nre also capable of performing their related support funct ion ( s ).
2 0
When a oystcs, subsystem, train, composant or d2vice io leterabc to be annperable soley brecu se it o e me rgsncy powe r ccur ce 10 inopercble, or coley beceuce ito normal power cource is inrperable, it acy be considered oporchte for the purpose of natiofying the requirement s of it s applicable Limiting Condition for Operation provided:
(1) its corresponding normal or emergency powe r source is operable; and (2) all of its redundant system (s), subsystem (s), trains (s),
c an-ponent(s) and device (s) are Operable, or likewise satisfy the requirements of this paragraph.
M.
Operat ing - ( perating means that a system or compqnent is pe r forming i t s specified functions.
l N.
sheratine Cvele - Interval between the en6 -3f nne ref ueling ou: age and the end of the r. ext l
du5s eq uent refueling outcge.
i C.
Po.cr Operation - Power Operation is any operation with the node switch in the " Start-Up" or "l:un" position with the reactor critical and above 1% rated thermal power.
7.
Primary Containment Integrity - Primary Containment Integrity means that the drywell and pressure suppress 16a chamber are intact and all of the following conditions are satisfied.
1.
All nanual containoent isolation valves on lines connecting to the reactor coolant system or containment which are not required to be open during accident conditions are closed.
2.
At least one door in the airlock is closed and sealed.
f 3.
All automatic containment isolation valves are operable or are deactivated in the closed pcsition or at least one valve in each line having an inoperable valve is closed i
4.
All blind flanges and manways are closed..
Q~
Protective Instrunentation Lealc Definitions 1.
Instrument Channel - An instrument channel means an arrangement of a sensor and auxiliary equipment required to generate and transmit to a trip system, a single trip signal related to the plant parameter monitored by that in's trume nt channel.
2.
Trip Systee ; A trip system means an arrangement of instrument channel trip signals and y
aux 111ery equipment required to initiate a protection action. A trip system may require one or more instrument channel trip signals related to one or more plant parameters to initiate trip system action.
Initiation of the protective function may require tripping of a singic trip system (e.g., llPCI systen isolation, of f-gas system isolation, reactor '
building isolation and standby gas treatment initiation, and rod block), or the coincident
@f t ripping of two t rip systems (e.g., initiation' of sc ran, reactor isolation, and prLsary containment isolattun).
2 3
. Protective Action - An action initiated by the protection system when a limit is.exce eded.
A protective a'ction can be at channel or system level.
3