ML20070D832
| ML20070D832 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 02/25/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070D836 | List: |
| References | |
| NUDOCS 9103010255 | |
| Download: ML20070D832 (8) | |
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UNITED 8TATES NUCLEAR REGULATORY COMMISSION ti f
wAsmotow, c. c. som NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50 298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.136 License No. OPR 46 1.
The Nuclear Regulatory Commission (the Commissia) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated December 8, 1989, complies with the standards and requirements of the Atomic Energy Act of 1964, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter it 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 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 license 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 j
of the Commission's regulations and all applicable _ requirements have j
been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of facility Operating License No. DPR-46 is hereby amended to read as follows:
1 2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.136, are hereby incorporated in the license, j
The licensee shall operate the facility in accordance with the Technical Specifications.
i 3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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GA f vey gn Theodore R. Quay, Director Project Directorate IV 1 Division of Reactor Projects Ill, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 25, 1991
ATTACHMENT TO LICENSE AMENOMENT NO 136
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FACILITY OPERATING LICENSE NO. OPR-46 DOCKET NO.60-298 e
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 PAGES INSERT PAGES 78 78 165 165 183 183 215 215 215e 215e
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COOPFR NUCLEAR STATION TABLE 4.2.D MINIMUM TEST AND CALIBRATION FREQUENCIES FUR RADIATION MONITORING STSTEMS Instrument Instrument System I.D. No.
Functlanal Test Fr e<s.
Calibration Freo-Check Instrument Channels Steam Jet Air Ejector Of f-cas System RMP-RM-150 A & B (12)
(12)
(12)
Peactor Building Isolation and RMP-PJi-452 A & B (12)
(12)
(12)
Standby Cas Treatment Initiation Liquid Radwaste Discharge Isolation RMP-RM-1 (11)
(11)
(11)
' Main Control Room Ventilation RMV-RM-1 Once/ Month (1)
Once/3 Months once/ Day Isolation 5
Mechanical Vactuam Pump Isolation PJIP-RM-251. A-D See Tables 4.1.1 & 4.1.2 Loric Systems SJAE Off-Cas Isolation Once/18 Months l
f Eg Standby Cas Treatment Initiation Once/18 Months E
i Reactor Building Isolation Once/18 Months Liquid Radwaste Disch. Isolation Once/6 Months 4
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Main Control Room Vent Isolation Once/6 Months 5
Machanical Vacuum Pump Isolation Once/Gperating J
Cycle
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LIMITING CONDITIONS FOR OPEMTION -
I SURVEILIANCE REOlQlTMENTS 3.7 feent'd.)
4.7 (cont'd.)
B, St andbv CAg_lrf gttient System B-f.landby Cas TreatttenL9ystem 1.
Except as specified in 3.7,B.3 below, 1.
At least once per operating cycle both standby gas treatment systems the following conditions shall be shall be operable at all times when demonstrated.
secondary containment integrity is
- a. Pressure drop across the combined
" 9" " d '
HEPA filters and charcoal adsor'ser a
s an incW d 2.a. The results of the in. place cold D0p water at the system design now Icak tests on the HETA filters shall
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show 299% DOP removal. The results of the halogenated hydrocarbon leak b Inlet heater input is capable of tests on the charcoal adsorbers reducing R.H. from 100 to 70% R.H, shall ebow 299% halogenated hydrocarbon removal.
The DOP and 2.a. The tests and sample a.Talysis of halogenated hydrocarben tests shall Specification 3.7.B 2 shall be be performed at a Standby Gas performed at least once every Tre a ttre n t flowrate of $1780 CFM and 18 rnenths for f tandby service or at a Reactor Building pressure of after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system s 2:" Vg.
operation and following significant paintin6, fire or chemical release b.
The results of laboratory carbon in any venttistion zone communicating sample analysis shall show 2991 with the system.
radioactive methyl iodide removal b Cold DOP testing shall be performed with inlet conditions of: velocity af ter each complete ar partial l
227 FPM. 21.75 mg/m inlet methy.
replacement of t'..J HETA filter iodide concentration, 270% R.H.
bank or after any structural and $30 L maintenance on the system housing.
- c. Each fan shall be shovn to provide
- c. Halogenated hydrocarbon testing 1 80 CFM MO.,
shall be performed after each c mNe e or padal nNacement 3.
From and after the date that one t
c an al adsoder bank standby gas treatment system is made I # "# #"7 * "" "##
or found to be inopetable for any
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E' reason, reactor operatien is permissible only durin6 the a, y pm gi 9 gg succeeding seven days unless such with the heaters on at least system is sooner made operable, gg provided that during such seven days all active components of the
- e. Test sealing of gaskets for housing other standby gas treatment system, doors downstream of the HEPA and its associated diesel generator' filters and charcoal adsorbers
-shall be operable, shall be performed at, and in conformance with, each test Fuel handling requirements are per rmed for compliance with specified in Specification 3.10.E.
Specification 4.7.B,2.a and Specification 3,7,B.2.a.
3.
System drains where present shall be inspected quarterly fer adequate water level in loop-seals.
165 Amendment No. 58,77,80,87,88, 97,102, 136
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t 4.7.B 6 4.7.0 PASES f
vith an adsorbene qualified according to Table 5.1 of ANSI N5091980. The replacement tray for the adsorber tray removed for the test should mest 1
the same adsorbent quality.
Tests of the HEPA filters with DOP aerosol shall be performed in accordance to ANSI N5101900.
Any filters found defective shall be replaced with filters qualified pursuant to Regulatory i
Position C.3.d. of Regulatory Guide 1.52, Revision 2, March,1978.
All elements of the heater should be demonstrated to be functional and i
operable during the test of heater capacity, Operation of the heaters vill i
prevent moisture buildup in the filters and adsorber system.
Vith doors closed and fan in operation, DOP aerosol shall be sprayed externally along the full linear periphery of each respective door to check the gasket seal.
Any detection of DOP in the fan exhaust shall be j
considered an unacceptable test result and the gaskets repaired and test repeated.
i If syt. tem drains are present in the filter /edserber bar.kr, loep.seak 1
be used with adequate water level to prevent by pass leakage f bcnks.
l If significant painting. fire or chemical release occurs such that t.
filter or charcoal adsorber could become contaminated f rort the 1%.
j cheettals or foreign naterial, the same tests and sample analysis shall l
be performed as required for operational use.
The determination of significance shall be made by the operator en duty at the time of t'e incident. Knowledgeable taff members should be consulted prior to mak j
this detersination.
Demonstration of the autematic initiation cap.sbility and operability of i
filter cooling is necessary to assure system performance capabilit-If ena standby gas treatitent system is inoperabic, the other system n..
t be tested daily. This substantiates the availability of the operable system and thus reactor operation or refueling operation can continue for a limited period of time.
3.7.D 6 4.7.D EASES Primary Containment I.-olation Valves Double isolation valves are provided on lines penetrating the primary contaiteent and open to the free space of the containment. Closure of one of the valves in each line vould be sufficient to maintain the integrity of the pressure suppression system.
Automatic initiation is required to sinimize the potential leakage paths from the containment in the event of a loss.of. coolant accident, The maximum closure times for the automatic isolation valves of the primary contain: tent and reactor vessel isolation control system have been selected in consideration of the design intent to prevent core uncovering-following-pipe breaks outside the primary containment and the need to contain released fission products following pipe breaks inside -the prima ry containment.
These valves are highly reliabic, have a lov service requirem)nt, and most are norna11y closed. The initiating sensors and associated trip channels are also checked to de.onstrate the capability for autorratit isolation.
~he test interval of once per operating cycle for autornatic initiation i
Amendment No. P2,102,13f; 163
1.1MITING CONDITIONS FOR OPERATION Sl'RVEILIANCE REQUIREMENTS
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3.12 Additional safety Related Plant 4.12 Additional Safety Relaled Plartt
{Acabilities Carabilities Arrlicabilig:
Apelicability:
Applies to the operating status of the Applies to the surveillance main control rnom ventilation system, requirements for the main contro.
the reactor building closed cooling room ventilation system, the reactor water system and the service water buildin" closed cooling water system sy s t e rt.
and the service water system which are required by the corresponding Obiective:
Limiting Conditions for Operation.
To assure the availability of the cain Obiective:
control room ventilation system, the reacter building closed cooling water To verify that operability or system and the service water system availability under conditions for upen the conditions for which the which these capabilities are an capability is sa essential response essential response to station to statien abnermalitier.
abnormalities.
A.
tidn Cf.rtrol_ Room Ventilation A.
Main Control Root Ventilation 1.
Except as specified in Specification 1.
At least once per operating cycle, 3.l?.A.e below, the control room the pressure drop across the combined air treatrrent system, the diesel HEPA filters and charcoal ebsorber generators required for operation of banks shall be demonstratei to be this system and the main control less than 6 inchos of kster at system t oort. air radiation tronitor shall be design flow rate.
operable at all times when containment integrity is required.
2.a. The tests and sample analysis of Specification 3.12.A.2 shall be 2.a. The results of the in. place cold performed at least once every DOP leak tests on the HEPA filters 18 months for standby service or shall show 2 99% DOP removal. The af ter every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />' of system results of the halogenated operation and following significant hydr 9 carbon leak tests on the painting, fire or chemical release in cha ;oal adsorbers shall show 299%
any ventilation zone communicating halogenated hydrocarbon removal, with the system.
The DOP and halogenated hydrocarbon tests shall be performed at a
af ter each cortplete or partial replacement of the HEPA filter bank b The results of laboratory carbon or after any structural staintenance sample analysis shall show 299%.
on the system housing.
radioactive methyl iodide removal with inlet conditions of: velocity
- c. Halogenated hydrocarbon testing 222 FPM, 21.75 w6/m inlet irsdide shall be performed after each concentration 2 95: R h. and coceplete or partial replacement of
$30*C.
the charcoal absorber bank or af ter any structural maintenance on the
- c. Each fan shall be shown to provide sy's t e rt housing.
3 1 CTM 210%.
I
-215-Amendment No. 82J8,102,136
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3,M BAS E S,,ig qntip}
heat exchanger.
Valves are included in the common discharge header to pe rmit the Seismic Class I service water system to be operated as two independent loops.
The heat exchangers are valved such that they can be individually backwashed without interrupting system operation, i
During normal operation two or three pumps will be required. Three pumps are used for a normal shutdown.
The loss of all a.c power vill trip all operating service water pumps.
3 The automatic etne rgency diesel generator start system and emergency equipment starting sequence vill then start one selected service water pump i
in 30 40 seconds.
In the t:2e a nt i me, the drop in service water header l
pressure vill close the turbine building cooling water isolation valve guaranteeing supply to the reactor building, the control room baserment, and the diesel generators from the one service water pump.
Due to the redundance of pumps and the requirement of only ont to meet the accident requirements, the 30 day repair time is justified.
D.
f.rter~ P m Ventilation i
The temperature rise and hydrogen buildup in the battery rooms without adequate ventilation is such that continuous safe operation of equipment in these rooms cannot be assured.
4.12 PASES A.
Main Control Roer Ventilatien System Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 6 inches of water at the system design flow rate vill indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once per operating cycle to show system performance capability.
Tests of the charcoal adsorbers with halogenated hydrocarbon refrigerant should be performed in accordance with ANSI N510 1980.
The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated.
The test canisters that are installed with the adsorber trays should be used for the charceal adscrber efficiency test. Each sample should be at least two inchas in diameter and a length equal to the thickness of the bed. If test results are unacceptable, all adsorbent in the system shall be replaced with an adsorbent qualified according to Table 5.1 of ANSI N509 1980.
l The replacement tray for the absorber tray removed for the test should meet the same adsorbent quality.
Tests of the HEPA filters with DOP aerosol shall be performed in accordance to ANSI N5101980. Any HEPA filters found defective shall be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide 1.52.
Operation of the system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month will dettons t ra t e l
operability of the filters and adsorber system and remove excessive I
moisture built up en the adsorber.
l Amendment No. P2,136
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