ML20079R982
| ML20079R982 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 01/16/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Northern States Power Co |
| Shared Package | |
| ML20079R984 | List: |
| References | |
| DPR-22-A-020 NUDOCS 8402030116 | |
| Download: ML20079R982 (5) | |
Text
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NUCLEAR REGULATOR CCM."RS$iO.'1
'3 fl3 UNITED STATES 5. k. d, l' i l~
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20 License No. DPR-22 1.
The Nuclear Regulatory. Commission (the Commission) has found that:
A.
The application for amendmer,t by Northern States Power Company (the licensee) dated September 30, 1982, as supplemented on
' November 4, 1983, complies with the standards and requirements of the Atonic Energy Act of 1354, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulatiens 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 reauirements have been satisfied.
2.
Accordingly, the license is amended by charges to the Technical Specifications as indicated in the attachment to this license amendment.
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. 20 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
84CGbD30116 840116 PDR ADOCK 05000263 P
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. 3.
This license amendment is effective as of the da. of issuance.
FOR THE NUCLEAR REGU' ATORY COMMISSION 7
Domenic B. Vassallo, Chie' Operatina Reactors Branch #2 Division of licensina Attachtrent:
Chances to the Technical Specifications Date of Issuance:
January 16, 1984 l
ATTACHMENT TO LICENSE AMENDMENT NO. 20 FACILITY OPERATING LICENSE N0. DPR-22 DOCKET N0. 50-263 Replace the following paget 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 207 207 209 209 S
I
t 3.0 LillITIlAl CO!3DIT10l'S FOli OPERATIOli 1.0 tRNIVEILIANCE REQUIRINDIT3 6
B.
Core Monitoring B.
Core Monitoring l
During core alterations two SfH's she.Il be Prior to sekire egy alterations to the operable, one in and one ad,lecent to es;y cc.re core, the BIH's shall be functionally g.sadrant where fuel or control rods are being teuied and checked for neutron response.
moved. For an BIH to be considered operable, thereafter, the BIH's will be checked the following conditions shall be satinfiedi daily for response.
i 1.
%e BIH shall be inserted to the normal operating level. (Useof j
specisi moveable, dunking type detectors during inittel ibel loading and major ecre alterations is per-missible es long as the detector is connected into thn nonnel BiH circuit.)
t 2.
%e BIN shall have a minimum of 3 CPS with all rods fully inserted in the core I
except when both of the following conditions are fulfilled
- a. No re. ore than two fuel assemblies are a
present in the core quadrant assoc-1sted with the SR)f,
- b. While in core, these fuel assemblies
)
are in locations adjacent to the SRM.
C.
Fuel Blorage Pool Water level 0.
Ibel. Storage Pool Water level E
Whenever irradiated fuel is stored Whenoter irradiated ibel is stored in in the fuel storage pool, the pool the fuel storage pool the pool level water level shall be maintained at shall be recorded daily.
a level of greater or er:uel to 33 feet.
y L.
'Ibe reactor shall be shutdown for a l
l ministan of E s hours prior to movement j
g of Ibel within the reactor.
l 207 s
3.lb/ls.lc
no w :
4
'A.
Ilofbeling Intarlocks Ibring refueling operationer, the reactivity potential of the core is being sitered. It is neces-sary to require certain interlocks en1 restrict certain reibeling procedures auch that there is assurance that inadvertent criticality does not occur.
1b minimize the possibility of loading fuel into e cell containing no control rod, it is required that all control rods are hally inserted when fuet'is being loaded into the reactor core.
21s requirement assures that during refbeling the reDieling interlocha, es designed, will prevent inadvertent criticality. '%e core resotivity' limitation of Specification 3 3 limits the core alterations to assure that the resulting core loading con be controlled with the reactivity centrol system and interlocks et, any time during shutdown or the following operating cycle..
l Addition of Israe amounts of reactivity to the core is prevented by operating procedures,.which are in turn backed up by renseling interlocks on rod withdrawal and movement of,th,rehieling plat-9 form.
When the mode switch is in the "Refbel" pos!Llon, interlocks prevent the refueling plattdra frcus being moved over the core if a control rod is withdrawn and ibel is on a hoist. 1.1k.ewlae, if the refueling platforin is over the core with fuel on a hoist, control rod motion is blocked by the interlocks. With the mode switch in the rensel position only one control rod can be withdrawn.
For a new core the dropping of a fuel assesably into a vacant fuel tocation adjacent to a withdrawn contrcl rod does not result, in an excursion or a critical configuration, thus adequate margin la provided.
B.
Core Monitoring
%e DIH's are provided to monitor the core during periods of station shutdown and to guide the operator during renseling operations and station startup, Requiring two operable 8.W s, one in and one adjacent to any core quadrant where ibel or control rods are being moved, assures ode-quate m.mitoring of that quadrant during such alterations.
Requiring a ministen of 3 counta per second whenever criticality is possible provides assurance that neutron flux is being monitored.
Criticality is considered to be impossible if there are no more than two assemblies in a quadrant and if these are in locations adjacent to the SRM, In :his case only, the SRH or dunking type detector count rate is permitted to be less than 3 coints per second.
I C.
Fuel Storage pool Water level i
1b assure that there is a4:quate water to shield and cool the irradiated fuel asseublies stored g
in the pool, a a:Ar.1 stas rool water level la estehtished. De ministas veter level of 33 feet is g
established because it would be a significent, change fram the normal level (3189")
and well above a level to espure adequate cooling.
o 209 3.10/4.10 Imam m
ca
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