ML20084V177
| ML20084V177 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 05/22/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20084V181 | List: |
| References | |
| NUDOCS 9106040374 | |
| Download: ML20084V177 (11) | |
Text
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- -1 UNITED STATES lj NUCLEAR REGULATORY COMMISSION
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WASHINGTON D.C. 20Z5 c;
NEBRASKA FJBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.141 License No. OPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by N?braska Public Power District (the licensee) dated August 31, 1989, and amended by letters datCJ March 22, and April 19, 1991, complies with tne 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 C~R Chapter I; 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 heulth and safety of the public, al.u (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 j
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.
910604037f[')S-h$9s l
. 2.
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:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.141, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is ef fective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Nn $..- o cy Theodore R. Quay, Director ProjectDirectorateIV-1 Division of Reactor Projects III, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to tne Technical Specifications Date of Issuance: May 22, 1991 e
-w
ATTACHMENT TO LICENSE AMENDMENT NO.141 FACILIlY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 53 53 54 54 59 59 76 76 85 85 165 165 165a 165a 180 180 l
l l
l l
a A
i t$g COOPER tJUCLEAR STATioil g
TA BLE 3. 2. B ( PAGE 1 )
3 CIRCUITRY REQUIREMENTS CORE SPRAY SYSTH1 6
M i n iinism fJiimber of A.- t i.., 1:.-.pi r e..I tilm n Instrument t)perab]c Cmnpo s ic e t t -
Ci inposi ist op. t,abi lit y G
Ins t t y.nent I.D. fio.
Settinn Liriit Per Trin_s_/scem is r1.. e Ar. si e r e.! _U)
Reactor Lov Water NBI-LIS-72 A, B, C, 2-145.5 of Indicated 2
A Level
&D Level e
f
~
Reactor Low Pressure' NBI-PS-52 A2 & C2, 5450 psig 2
A NBI-PIS-52 B & D (Switch #2)
Drywell liigh Pressure PC-PS-101, A, B, s2 psig 2
A C&D Core Spray Pump CS-PS-44, A & B 2
A u
Disch. Pressure CS-PS-37, A & B 100 5 P s 165 psig Y
Core Spray Pump CS-TDR-K16 9sTsll seconds I
n Time Delay A&B Low Voltage Relay 27X1 - IF 6 IG Loss of Voltage 1
n Emerg. Bus 27X2 - IF 6 1C Aux. Bus Low 27X3 - IA 6 IB Loss of Voltage I
n Voltage Relay l
Pump Discharge Line CM-PS-73, A 6 B 210 psig (3)
D Low Pressure
____.________J i!
i
COOPER fiUCLEAR STATION 5
TABLE 3.2.B (PAGE'2) j RESIDUAL llEAT REMOVAL SYSTEM (LPCI HODE) CIRCUITRY ELQUIREMENTS ar+
m Minimurn Number of tion ite.pii e ist Vhen
?
Instrument Operable Compatients t :ompone n t opet.511ity Instrument I.D. No.
Settine Limit Per Trip System (I) _ is Not Assn.41 I"
Drywell High Pressure PC-PS-101 A.B.C. 6 D 52 psig 2
A 7
D I*
Reactor Low Water NBI-LIS-72, A,B,C, 2-145.5" Indicated 2
A g
Level 6 D #1 Level Reactor Vessel Shroud NBI-LITS-73, A 6 B 2-39 Indicated 1
B Level' Below Low
- 1 Level Level Trip Reactor Low Pressure RR-PS-128, A 6 B 575 psig i
B h.
Reactor Low Pressure NBI-PS-52A2 6 C2 5450 psig i
A (Injection Valve NBI-PIS-52B 6 D Permissive)
(Switch #2)
Drywell Pressure PC-PS-Il9, A,B,C, 52 psig 2
- 6D R11R "ttp Discharge RilR-PS-120 A.B.C,6D 100 s P 5 165 psig 2
A R11R-PS-105, A,B,C,6D 100 $ P s 165 psig 2
A Reactor Low Pressure NBI-PS-52A1 6 Cl 185 s P s 235 psig 1
A l
(Recire. Discharge NBI-PIS-52B 6 D I
Permissive)
(Switch #1)
N cus COOPER NUCLEAR STATION ct
.g TABLE 3.2.B (Page 7) j AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) CIRCUITRY REQUliti.f1E'iTS me z
?
%m Minimu:n Nurnber A. tion ite.pii reit when en Instrurnent of Operable Co npone nts t 'owpone n t operability Instrument I.D. No.
Settine Limit Pe r Trim;2s t em (1)
.I_ 3 tio n A gni e.f
'sa i
Reactor Low Water NBI-LIS-83, A & B 2 +12.5" Indicated 1
P,
"=
Level Level NBI-LIS-72, A,B,C & D E -145.5" Indicated 2
A Level ADS Timer MS-TDR-KS, A & B
$ 120 sec.
I B
i M
I N
t i
i 1
5
n, COOPER tJUCl.1:AR STATinti 5
TAllt.E 4. 2. It (Pary 7)
M ADS SYSTEM AND IDW-LOW SET TEST & t: Alt l\\l!ATI Ut1 1/R EQUlitit:! ES an y
l tis L 1 time rit.
en Item Item I.D.,No.
Fnnetlonal Test Freet.
Calibration 1...,
e:hect-w w
~
Instruments b
t 1.
ADS Inhibit Swit'ch MS-SW-53A 6 B Once/ Month (1)
N.A.
fJone
[
2.
Reactor Low Water Level NBI-LIS-83, A 6 B Once/ Month (1)
Once/3 Months once/luy l
NBI-LIS-72, A.P.C, 6 D Once/ Month (1)
Once/3 Months once/D..y 3.
ADS Timer MS-TDR-K5 A 6 B Once/ Month (1) once/Oper. Cvele tJ.ne 4.
Low-Low Set (LLS)
NBI-PS-51, A,B,C, 6 D Once/ Month (1)
Once/Oper Cvele tio ne 1.o ei c (4)(6) j h
1.
I ADS Control Power Monitor Once/6 Months f1 A.
j 2.
ADS Actuation Once/6 Months tJ. A.
l
=
l 3.
Low-Low Set Logic Once/6 Months tJ. A.
l i
I t
t I
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3.2 LaSLS (cent'd) 5.
-. gz3 g -
,-- cn e-+
7;;
!be ins tramentat.on whlch initia:es Core Star.dby Cool r.g System (CSCS) act.:-
it ;: i :+; ir a daal rus system.
As for otte: / ital ratrunenta:icn acre.;
in : Mis :ashion, the Specification preserves the effectiveness of the system even during perieds when maintenance er testing is being performed. An e:<ce; ic r to this is when logic functional testing is being performed.
a break in the HFCI steam piping including the RHR Cor.densing Mode Steam.
Tripping of this instrumentation results in actuation of HPCI isolation valves.
Tripping logic for -he high flow is a 1 out of 2 logic.
Temperature is monitored at' twelve (12) locations with four (4) temperature sensors at each location.
Two (2) sensors at each location are powered by "A" direct current control bus and two (2) by "B"' direct current control bus.
Each pair of sensors, e.g.,
"A" or "B", at each location are physically separated and the tripping of either "A" or "B" bus sensor will actuate HPCI isolation valves.
The trip settings of s 300% of design flow for hfgh flow and s 200'T for high temperature are such that core uncovery is prevented and fission product releare is within limits.
RCIC The RCIC high flow and temperature instrumentation are arranged the same as that for the HPCI.
The trip setting of s 300% for high flow and 5 200'F-for temperature are based on the same criteria as the HPCI, ADS The effective emergency core cooling for small pipe breaks, the HPCI system, function since reactor pressure does not decrease rapid enough to allow must either core spray or LPCI to operate in time.
The automatic pressure relief function is provided as a backup to the HPCI in the event the HPCI does not operate. The arrangement of the tripping contacts is such as to provide this function when necessary and minimize spurious operation.
The trip settings given in the specification are adequate to assure the above criteria are met.
-The specification preserves the effectiveness of the system during periods of maintenance, testing, or calibration, and also minimizes the risk of inadver-tent operation;- i.e., only one instrument channel out of service.
Amendment No. 46,83,141 85-
_ _ - _ -..=. _ _. _.
11$1110 CONDlIEGILOfffbTION EUPVfAldELPf0VIEfffMI 3.7 A (cont'd.)
4.7.A (cont'd.)
6.
1,nw Low Set ILelirf Function 6.
law-Low Set Pelie# Funttion 2
- a. The low-low set function of the
- a. The low low set safety / relief valves safety-relief valves shall be shall be tested and calibrated as operable when there is irradiated specified in Table 4.2.B.
fuel in the reactor vessel and the icactor coolant temperature is
- 212*F, except as specified in 3.7.A.6.a.1 and 2 below.
1.
With the low low function of one safety /rolief valve (S/kV) inoperable, restore the inoperable LLS S/RV to OPERABLE within 14 days or be in the HOT STANDBY mode within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
With the low low set function of both S/RVs inoperable, be in at least HOT STANDBY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- h. The pressure switches which contre,1 the low-low set safety / relief valves shall have the following settings.
NCI Pri 51A Open Low Valve 1015 20 psig (Increasing)
NBI-PS 51B Close Low Valve 875 1 20 psig (Decreasing)
NPd PS-Sic Open High Valve 10?5 ! 20 psig (Increasing) un1.PS,51D Close High Valve 8'/5 1 ?O psig (Decreasing) 1.
At least once per operating cycle the following conditions shall be y,,
- randbv cc Treatment Svstem demonstrated.
1 P.::c e p t as specified in 3.7.B.3 beinw, both standby gas treatment
. Pressure drop across the combined HEPA filters and charcoal adsorber svntems shall be operable at all banks is less than 6 inches of water
.t iu e s when secondary containment h v d % n flow m.
inregri.v is required.
2.a.
The resul tu of the in place cold DOP b.
Inlet beater input is capable of Icak tem nn the HEPA filters shall reducing R.H.
from 100 to 0% R. :1.
.how 2997 DOP removal. Ine results of rho halogenated hydrocarbon leak 2.a. The tests and sample analvsic of tesrs on the charcoal adsorbers Specification 3.7 B.2 shall he shall' show
'c99%
halogenated performed at least once every hydrncarbon remnval.
The DOP and 18 months for standby s e rt ic e or ha inernated hydrocarbon tests shall after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> nf snrem be pe r fo rrre d at a
Standbv Cas operation and followine s tralficant wa we n : fin e rn nf st7an "rt,nl nain-inn, fire or c h e n i c a ', ra i m a ac,.. w r soituing pressure of in an-
,,ntitation
-one
. ? ..N',
communicaripg with ::he lystem.
Amendment No. 58 M,80,82,88,97, 102,136,141
m m !e c^':D.lr "* 10R OPEffJION E'RVEILLWE REQUIP FME!:*
- 3.
- + 34
~.P icent-d) 4
- b. The results of laboratory carbon
- b. Cold DOP testing snall be perforced sar:le u i.esis shall abov a99; after each complete or part;al rac...;:. e e:Lc1 aadice removal replacement of the HEPA filter with ir;et conditions of:
velocity bank or after any structural 3
a42 rrM, 21.75.ag/m inlet methyl maintenance on the system housing iodide me e n: r at io:
270% R.H.
and 13.
c, Halogenated hydrocarbon testirg shall be performed after each
- c. Each fan shall be shown to provide complete or partial replacenen:
!?SO CMT clot.
of the charcoal adsorber bank or after any structural maintenance 3.
Trom and after the date that one on the system housing.
standby gas treatment system is made or found to be inoperable for any
- d. Each system shall be operated reason, reactor operation is with the heat 2rs on at least permirsible only during the 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month, succeeding seven days unless such
doors downstream of the HEPA provided that during such seven ters and charcoal adsorbers days all active components of the other se.andby gas treatment system, shall be performed ct, and in and its associated diesel generator, ce fromance with, each test shall be operable.
Performed for compliance with Specification u.7.B.2.4 and S '"ifi***i#" 3'7'0'2'#'
P Tuel handling requirements are specified in Specification 3.10.E.
3.
System drains whare present shall 4
If these conditions cannot be met, be inspected quarterly for adequate procedures shall be initiated water level in loop seals, immediately to establish reactor conditions for which the standby 4.a. At least ence per operating cycle automatic initiation of each branch of gas treatment system is not required.
the standby gas treatment system'shall be demonstrated, b.
At least once per operating cycle manual operability of the bypass valve for filter cooling shall be demonstrated.
c.
When one standby gas treatment system bacomes inoperable the other standby gas treatment system shall be demonstrated to be operable.
immediately and daily thereafter.
A demonstration of diesel generator operability is not required by this specification.
C.
Secondary containment integrity 1.
Secondary containment surveillance shall be maintained during all shall be performed as indicated below:
modes of plant operation except when all of the following conditions are met.
Amendment No. 80,95,141 165a-
~
3.7 A 6 4. 7. A fAffl(cont'd)
The primary centainment is normally slightly pressuri:ed during periods of reactor operation.
Nitrogen used for inerting could leak out of the containment but air could not leak in :o increase oxygen concentration. Once the containment is filled with nitrogen to the required concentration, no monitoring of or.ygen concentratiwn is necessary.
However, at least twice a week the oxygen enneentration u111 be determined as added assurance.
t The 500 gallon conservative limi: on the nitrogen storage tank assures that adequate time is available to get the tank refilled assuming normal plant operation.
The estimated maximum makeup race is 1500 SCFD which would require about 160 gallons for a 10 day makeup requirement. The normal leak rate should be about 200 SCFD.
3.7 A.6 & 4.7.A.6 LOU LOU SET PELIEF FUNCTION The low low se: relief lo5 c is an automatic safety relief valve (SRV) control i
system designed to micigate the postulated thrust load conc e rn of subsequent actuations of SRV's during cer:ain transients (such as inadvertant MSIV closure) and small and inte rmediate break loss of coolant accident (LOCA) events.
The setpoin:s used in Section 3.7. A.6.b are based upon a minimum blowdown range to provide adequate time between valve actuations to allow the SRV discharge line high water leg to clear, coupled with consideration of instrument inaccuracy and the main steam isolation valve isolation setpoint.
The as found se: point for NBI-PS-SlA, the pressure switch controlling the opening of RV ?lD, mus: be s 1040 psig. The as-found closing setpoint for NBI PS-51B mus:
be at least 90 psig less than 51A, and must be 2 850 psig.
The as-found setpoint for NBI PS 51C, pressure switch controlling the opening of RV 71F must be
$ 1050 psig. The as-found closing setpoint for NBI PS-51D must be at least 90 psig below 51C, and mus: be 2 850 psig.
This ensures that the analytical upper limi for the openin5 se: point (1050 psig), the analytical lower limit on the closing se: point (850 psig) and the analytical limit on the blowdown range (2 90 psig) for
- he Low-Low Se: Relief Function are not exceeded. Although :he specified ins:rument se: point tolerance is : 20 psig, an instrument drift of : 25 psig was used in the analysis to ensure adequate margin in determinin5 the valve opening and closing se: points. The opening se: point is set such that, if both the lowest se t non LLS S/RV and the highes: set of the rvo LLS S/RVs drift 25 psig in the worst case directions, ;ne LLS S/RVs vill still control subsequent S/RV ac:uations. Likewise.
- he closin5 se: point is set to ensure the LLS S/RV closing setpoint remains above the MSIV low pressure : rip. The 90 psis blowdown provides adequate energy release from the vessel to ensure time for the water les to clear between subsequent S/RV ac:uations.
3.7.B & 3.7.C STA"0BY GAS *REA*' DENT SYSTEM AND SECONDARY CONTAINMEN*
The secondary containment is designed to =ini=1:e any ground level release of radioae:ive materials which m1 h: resul: from a serious acciden:.
The reactor 5
buildin5 provides secondart containment durin5 reac:or operation when :he dryvell is sealed anc in serrice. The reactor building provides primary con:ainmen: when the reac:or is shu: down and :he dryvell_ is open, as during refueling. Because the se::ndar7 c on:ainme r.: is an inte5:al par: of :he complete con:sinmen: system.
se:cndar :on:ainmen: is required at all times :ha: primary con:ainmen: is recuired as veli as durin5 refueling. Secondary containmen may be broken for snor: periods of :ime :o allow access to :he reac:or building roof :o perform necessarr inspec: ions anc =aintenance.
The s:anchy gas treatment system is designed to fil:er and exhaus: :he reae:or bui'.:ing a:mospnere to :he stack during secondary con:ainmen; isolation condi:Lons -
Bo:n standby gas trea: men: system fans are designed to automa:ically s:ar: 20cn can ainmen: iso'.a: ion and :o maintain :he reac or buildin5 pressure :o the des,ipp.
neca:ive pressure so :na: al. ' eakage shoulc be in-leakage. Shoul: one sys:em :a:.
- o 2:ar:. :ne recuncan: system is designec :s start au:oca:i:a;':.
Iach o:, One %o fans-has 100 per:en: :apaci:7 Amendment No. 38,80,91,141
.,3c.