ML19339B151
| ML19339B151 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 10/14/1980 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19339B145 | List: |
| References | |
| NUDOCS 8011060375 | |
| Download: ML19339B151 (11) | |
Text
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e' iINiil()51A1IS NUCLE AR Rt GULATORY COMMISSION E ',
.., / ' ',E i c,k' f?/ E WASHINGT ON, D. C. 20555
\\W OMAHA PUBLIC POWER DISTRICT DOCKET tl0. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. OPR-40 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Omaha Public Power District (the licensee) dated March 14, 1978, (as supplemented May 1. 26, 1978, March 6 and May 24,1979) and August 5, 1980, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and
.egulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, 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 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.
1 i
i l
80110 s.03'f5
. 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 facility Operating License No. DPR-40 is hereby amended to read es follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
52, 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
%[
C e G~
1-A L L.
beYt( E T ark, Chief Q
Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 14, 1980-
ATTACHMENT TO LICENSE AMENDMENT T40. 52 FACILITY OPERATlflG LICENS5 NO. DPR-40 DOCKET NO. 50-285 Replace the following pages of the Appendix "A" and "B" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Appendix "A" Pages i
5 2-0 (added) 2-0a (added) 2-Ob (added) l 3-20b i
3-20c Appendix "B" Page 1.1-2 l
' -~
TECFilrAL PPEr!PICATIOKS C. -
TABL,3 OF CO:' TENTS
.Pa._.e e 1
DEFI N I T I O:!S...........................................................
1.0 SAFETY LI!!ITS AND LIMITING SAFETY SYSTEM..........................
1-1 1-1 1.1 Safety Limits - Reacter Core 1.2 Safety Limit, Reacter Coolant System Pressu.e..............
1 h
- 1. 3 Limiting Safety System Settings, Reacter Protection System.. 1-6 2.0 LIMITING CONDITIONS FOR OPERATION.................................
2-0 2.0.I General Requirements............................... 2-0 2-3
~
2.1 henctor Coolant, Syr. tem 2-1 2.1.1 Oper: ble Component:
2-3 2.1.2 lleatup and Cooldown Rate 2.1. 3 Maximum Reactor Coolant Radioactivity....
2-8 2.1.4 Reactor Coolant System Leakage Limits.............
2-11 2.1.5 Maxinun Reactor Coolant Oxygen and Halogens Concentrations.................................
2-13 2.1.6 Pressurizer and Steam System Safety Valves........
2-15 2-16a 2
2.1.7 DNB Margin.........................................
2.2 Chemical and Volume Control Systen.......................... 2-17 2.3 Emergency Core Cooling System.............................
2-20 2.h Containment Cooling........................................
2-2h 2.5 Steam and Feedvater Systemc................................
2-28
- 2. 6 Containment System.........................................
2-30 2-32 2.7 Electrical Systems
- 2. 8 Refueling Operations..........
2-37 2.9 Radioactive Materints Release...........................
. 2 h0 2-h8 2.10 Reactor Core.............................
2.10.1 Minimum Conditionc for Criticality......
2-h8 2.10.2 CEA and Power Dirtribution Limits..............
2-50 2.10.3 In-Core Instrunentation....
2-Sh 2.10.h Moderator Tempernture Coefficient of Reactivity...
2-56 2.11 Containment Building and Fuel Storage Building Crane 2-58 2.12 Control Room Cystens.......................................
2-59 2.13 Nuclear Detector Cooling System..................
2-60 2.14 Engineered Safety Features System Initiatien 2-61 Instrumentation Settincs 2.15 Instrumentation and Control Systems........................
2-65 2.16 R i ve r Le v e l................................................
2-71 2.17 Miscellaneous Radicactive !*aterial Sources................
2-72 2.18 Shock Suppressors (Snubbers ).............................
2-73 2.10 Fire Protecticn Syntem.......................
2-69 I
i i
A.cr.dr ent :!c. Jg, g. g ;, 52 i
1
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DEFINIT 20NS mo o
g
" 3' L@
- -N.k\\ 3' MISCELLANEOUS DEFINITIOF wo o
Ooerable - Overability A system, subsystem, train, component or device shall be OPERABLE or have OPEP>3ILITY vhen it is capable of performing its specified function (s).
Implicit in this definition shall be the assumptica that all necessary
- attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, conponent or device-to perform itn function (c) nre nlro enpnble or performing, their rc3stteil support function ( s).
In Ooeration A system or component is in operation if it is performing its design function.
CEA's All full length shutdown and regulating control rods.
Pert LenE h CEA'n t
CF.A'c which contain neutron absorbing material caly in the lower quarter er their length.
Containment Integrity Containment integrity is defined to exist vben all of the following are met:
(1) All nonautomatic containment isolation valves which are not required to be open during accident conditions and blind flanges are closed.
(2) The equipment batch is properly closed and sealed.
(3) At least one door in the personnel air lock is properly closed and scaled.
(h) All automatic containment isolation valves are operable er locked closed (or isolated by locked closed valves or blind flanges as permitted by limiting condition for operation).
(5) The uncontrolled containment leakage satisfies Specification 3.5 5
Amendment No. 52
0 rF P e O y n
f 2.0 LIII.ITING CONDITIONS FOR OPERATIO" So
- churn,
'.0.1 Genern! Reouirements Atml i e nbi J i t,v, Applies to the opernble stnt.us of all synteta, subsystems, traint, components, or devices covered by the Limiting Conditions for Oper-ation.
Objective To specify corrective measures to be er: ployed for system conditions not covered by or in excess of the Limiting Conditions for Operation.
Specification (1)
In the event a Limiting Condition for Operation and/or associated action requirements cannot be satisfied because of circu= stances in excess of those addressed in the specification, the unit shall be placed in at least HOT SHUTDOWU vithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at lenst suberitical and < 300 F vithin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least COLD f;HUTDOWN within the foljoving 30 houru, un3csr. corrective mennuren are completed that permit operation under the permissible action requirement: for the npecified time interval an meesured from initial discovery c.
until the renetor is placed in an Operating Mode in which the specification is not applicable.
Ex-ceptions to these requirements shall be stated in the individual specifications.
(2)
When a system, subsyster, train, component, or device is deter-mined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements bf iTs applicable Limiting Condition for Operation, provided:
(1) its corresponding normal or emergency power source is OPERABLE; an<i (2) rJ.1 of its re-dundant system (s), subsystem (s). train (s), component (s), and device (s) nre OPERAltLE, or likewise satisfy the requirements of this specifiention.
Un]ent, both conditions (1) and (?)
nre satisfied, the unit. shull be pinced in nt least HOT SilVT-DOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least suberitical 4.nd + 3000F vtthin the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at lenst COLD Sl!VfDOWN vithin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This specification is not applict ble in Operating Modes 4 or 5 Basis (1)
T' specification delineates corrective measures to be taken f..
- .rcunstances not direct 13 provided for in the system specific specifice' ions and vbose occurrence vould violate the intent of the.pecification.
For example, Specification 2.3 requiies each Low Pressure Safety Injection (LPSI) pump to be operable and r.79vides explicit corrective mecsures to 2-0 Amendment No. 52
D
' RD *DlT A
u g j\\\\
w j jd h, ".b 2.0 LIMITING COUDITIONS F_0R _Ori: RATION _
2.0.3 General Recuirements (Cont inued) be followed if one pump is inoperable.
Under the terms of Specification 2.0.1(1), if more than one LPSI pump is in-operable, the unit must be placed in at Icast HOT SEUTD0'n'N within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, in at least suberitical and < 300 F vithin 0
the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least CCLD SEUTD0'a'E vithin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, unless at least one LPSI purp were restored to operability.
It is assumed that the unit is brought to the required mode within the required tires by promptly initiating and carrying out the appropriate measures required by the specification.
(2)
This specification delineates what additional conditions must be satisfied to permit operation to continue, consistent with the syntem specific crecifications for power sources, when a normal or emergency power source is not OPERABLE.
is It specifically prohibits operation when one divisf or inoperable because its normal or emergency power source it-inoperable and a system, subsystem, train, component, or device in another division is inoperable for another reason.
The provisions of this specification permit the requirements associated with individual syste=s, subsystems, trains, com-ponents, or devices to be consistent with the specification of the associated electrical power source.
It allows oper-ation to be governed by the time limits of the requirements associated with the Limiting Condition for operation for the normal or emergency power source, not the individual requirements for each system, subsystem, train, component, or device that is determined to be inoperable solely be-cause of the inoperability of its normal or emergency power source.
For example, Specification 2.7 requires in part that two emergency diesel generators be OPERABLE. The specifica-tion provides for 7 days per month out-of-service time when one emergency diesel generator is not OPERABLE.
If the definition of OPERABLE vere applied without consider-ation of Specification 2.0.1(2), all systems, subsystecs, trains, components, and devices supplied by the inopereble emergency power source vould also be inoperable.
This vould di'etate invoking the applicable corrective measures for each of the applicable Limiting Conditions for Oper-ation.
However, the provisions of Specification 2.0.1(2) permit the time limits for continued operation to be coa-sistent with the requirements for the inoperable e=ergency dietel generatur instead, provided the other specified conditions are satisfied.
In this case, this would mean that the corresponding normal power source cust be OPERABLE, and all redundant systems, subsystems, trains, cospenents,
and cevices must be OPERABLE, or othervice satisfy Specifi-ention 2.0,1(2) (i.e., be ecpable of performing their design
^. - Ou Ar,c adme n t No.62
2.0 LIMITING CONDITIONS FOR OPERATION 2.0.1 General Requirements (Continued) function and have at least one normal and one emergency power source OPERABLE).
If they are not satisfied, shutdown is re-quired in accordance with this specification.
As a further example, Specification 2.7 requires in part that two physically independent cf.cuits between the offsite trans-mission network and the onsite Class IE distribution system be OPERABLE. The specification prevides a 24-hour out-of-service time when both required offsite circuits are not OPERABLE.
If the definition of OPERABLE vere applied with-out consideration of Specification 2.0.1(2), all systems, subsystems, trains, components, and devices supplied by the inoperable normal power sources, both of the offsite circuits, would also be inoperable. This vould dictate invoking the How-applicable measures for each of the applicable LCO's.
ever, the provisions of Specification 2.0.1(2) per=it the time limits for continued operation to be consistent with the corrective measures for the inoperable normal power sources instead, provided the other specified conditions are satisfied.
In this case, this vould mean that for one divi-sion the emergency power source must be OPERA 3LS (as must be the components supplied by the emergency power source) and all redundant systems, subsystems, trains, components, and devices in the other division must be OPERABLE, or likewise satisfy Specification 2.0.1(2) (i.e., be capable of performing their design functions and have an emergency power source OPERABLE). In other vords, both emergency power sources must be OPERABLE and all redundant systems, subsystems, trains, components, and devices in both divi-sions must also be OPERABLE.
If these conditions are not satisfied, shutdown is required in accordance with thir specificntion.
In Operating Modes 4 or 5, Upecification 2.0.1(2) is not applicable, and thus the individual requirements for each applicable Limiting Condition for Operation in these modes must be adhered to.
I 2-Oh Amendment No. 52
I-TABLE 3-5 (Continued)
FSAB Eecti:-
referen:e Test Frequency 10b.
Ok.ar:oal Adsorberr 1.
In-Place Testing **
Each refueling shutdown nct to exceed 18 6.2 fcr Jpent Fuel Charccal adrorbers shall be r.:. hs :r af ter every 720 Scurs of system 9 1' i
Stcrr.ge Pool Area leak tested and shall show cperstien, or af ter each ecmplete or par-
>99% Freon (R-11 or R-112) tial replacement of,the charecal adsorber bank, cr after any major structural mainte-C9@3]
rencval.
nance en the system housing and following Gjggg significant painting, fire er chemical re-g_; )
lease in a ventilation cne ccmmunicating b342Y with the system.
2.
Labcratory Testing a.
Initial batch tests of all Pricr to initial loading in the filter unit.
e---)
M charecal adsorbers shall
.M chow >99% elemental iodine NU3 d V'
removal when tested under Ej conditions of 295% R.H.,
Cb;. g e
>1250F, 5 to 10 mg/m3 inlet
.D P
ele.. ental iodine concentra-tien and at the face velocity vithin +20% of system design. Each refueling shutdown not to exceed 18 b.
The carbon sample test re-salts shall shov >90% ele-men-h er af ter every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system mental iodine removal, under operation, and followinc significant paint-
- enditions of >95% R.H.,
ing, fire or chemical release in any venti-3 in-1cti:. =cne communicating with the system.
>125CF, 5 to 10 mg/m let elemental concentration and within 20% of design face velocity.
3 Overall system oneration Operation of each circuit Ten hcurs every month.
a.
shall be demonstrated.
b.
Volume flow rate through At least once per plant crerating cycle.
cnarcoal filter shall be shown to be between 9000 l
and 12,000 cfm.
h.
Manual initiation of the nystem At least once per plant operating cycle.
shall te demonstrated.
Tests shall be per formed in acccrdance ith applicable section(s) Of ANSI N510-1975.
s, 52 AmendentNo.)T,
TRBLE 3-5 (Continued)
TE A? Sectio:.
eference Test Frecuency 00.
Charcoal Adnorbers 1.
In-Flace Testing **
Each refueling shutdown not to exceed 18 3 13 for 3.I. Pump Room Thir: cal adsorbers shall be nonths or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system 6.2 lea'r. :ested and shall show c;eration or after each complete or partial 3.99% Freon (R-ll or R-112) replacement of the charcoal adsorber bank, re-eval, or after any major structural maintenance on the system housing and following si6ni-ficant painting, fire or chemical release in any ventilation zone communicating with the system.
2.
Laboratory Testing
- nitial batch tests of all Frior to initial loading in the filter unit.
a.
charcoal adsorbers shall shev >99% elemental iodine remo'7al when tested under el conditions of >95% R.H.,
a
?
>1250F, 5 to 10 mg/m3 in-let elemental, iodine con-centration ahd at a face velocity within +20% of system design.
b.
The carbon sample test Each refueling shutdown not to exceed 18 results for.the S.I. Pump conths or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system Poom cha' coal filters shall creration and following significant paint-r show no less than 90% ele-ir.g, fire or chemical release in any venti-nental iodine removal, lation zone communicating with the syster.
under conditions of 3.95%
at >125 F, 5 to 10 F.H.b nlet elemental mg/m i iodine concentration and within +20% of design face velocity.
3 1cersil System Operation Operation of each circuit Ten hours every month.
a.
shall be demonstrated.
b.
Volume flow rate shall be At least once per plnnt operating cycle.
shown to be between 3000 and 6000 cfm.
- Tests shall be performed in acecrdance with applicable section(s) of ANSI N510-1975 Amandment rio. J'/, [, 52
Basis The once-through condenser cooling system will increase the temperature of the river water pumped through the system during the full-load opera-tion by approximately 25 F.
On the average, the area of the river heated 5 F or more above ambient will be within a zone 2000 ft. long by 250 ft.
wide.
During the winter months when the river temperature is 55 F or less, it may be planned to overhaul the circulators one at a time or perform other maintenance that may require reduced circulating water flow. Normally one to two weeks will be required to overhaul each circulator.
It is expected that during this period of time the number of circulators will be cut from three to two and that the rise across the condenser could increase to 35 F at the full-load operation. During these periods when a circulator is out of operation, recirculation flow for ice control and/
or load will be limited such that the total rise will not exceed 35 F.
The position of the 5 F isotherm will move downstream to about 5,000 to 6,000 ft. for these flow ranges.
The limit of 7,000 cfs river flow, under which such operation could result in undesirabic temperatures across the river, is the low flow expected for a seven-day period once in 10 years under 1970 development conditions.
J G
I.1-2 Amendment No.
52