ML20137T158
| ML20137T158 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/07/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137T163 | List: |
| References | |
| NUDOCS 8602180256 | |
| Download: ML20137T158 (10) | |
Text
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o UNITED STATES
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8 NUCLEAR REGULATORY COMMISSION n
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WASHINGTON, D. C. 20555
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COMMONWEALTH EDIS0N COMPANY AND TOWA-ILLIN0IS GAS AN5 ELECTRIC COMPANY DOCKET NO. 50-254 QUA0 CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING ~ LICENSE Amendment No. 92 License No. DPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated May 2,1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth i
in 10 CFR Chapter I; I
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the j
Comission; l
C.
There is reasonable assurance (i) that the activities authorized
-l by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
i conducted in compliance with the Commission's regulations; i
The issuance of this amendment will not be inimical to the l
D.
i common defense and security or to the health and safety of the l
public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable require.nents have been satisfied.
2.
Accordingly, the license is amended 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-29 is hereby amended to read as follows:
860218025o 860207 PDR AETK 05000254 P
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. (2) Technical Specifications The Technical Specifications contained in-Appendices A and B, as revised through Amendment No. 92, 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.
FORTHENUCLEARREGULATORYC0gISSION
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Joh A. Zwolinski, Director BWR oject Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 7, 1986.
ATTACHMENT TO LICENSE AMENDMENT NO. 92 FACILITY OPERATING LICENSE NO OPR-29 DOCKET NO. 50-254 Replace the following paa of the Appendix A Technical Specifications with the enclosed pages. The cised areas are indicated by marginal lines.
Pages 3.3/4.3-4
- 3.3/4.3-10 F
t t
i
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QUAD.CITir.S
- NH-29 the operating power level shall be c.
(
linited no that the MCPR will re -
nain above the MOPR fuel cladding integrity oafety lirait assursing a sin-gle error that results in entnplete withdrawal o any Single opersNe r
control rost.
C. Scrum Insertion Timn C Scram Issertion Times I. The averJEe veram inscraint' time. ha.
1.
After refueling outage and prfor to scJ on the dernerg.2Jtinn og the stram operation above 304 power, with pilot valve sc!cnnids at time tero. of all reactor pressure above 800 psig, all control rods'shall be suy ect operab!c centrol rods in the reactor to scram-time measarements from Powet oP'rJtion condiuna shJll be no the fully withdrawn position.
greater than-The scram times for single rod scram testing shall be measured without reliance on the control Attrage Scram rod drive pumps.
s inse-rtd from in 'i**
Fuly Wal.dramn Toasts fneel '
S 0.375 20 0.930 SO 2.00 90 3.50 The average of the scram insertion times for the three fastest controi rod-of all groups of four control tr$ in a two by tuo art.ty shall tn no greater than-e
% inserted from herege Scenm fsfly Hitledramn Tunes (ser) 3 0.39N 30 0.954 30 2.12 90 3.80 2.
All control rod drives shall have experienced scram test measure-
- 2. The maaimum ser.im irnertion time ments each year. Also, 50% of for 90*4insertsun e f en) oper.ibic wn-the control rod drives in each quadrant of the reactor core trol rods sh.ill nnt catml 7 setonds.
shall be seasured for the seras times specified in Specification
- 3. If SpecifirJt on 3.3.C.I cannot be net.
3.3.c daring the interval not the reactor shall not he niJde super.
more frequently than 16 weeks critical. if cI#ratmg. the reattor shall nor less frequently than 32 weeks. These tests shall be be shut down imme diairly upan deter.
performed with a reactor pres-gninstion that ag er.spe wram time t*
sure above 80U psig and may be alcfnient measured during a reactor scram. Wnenever all of the 4.
lf $petinrainin 31C 2 6.inmit be met.
control rod drive seamm tames the def.oene tonerol roJ Sh.ill be son.
have been measured, an evalu-ation shall be made to 3.3/41 4 Anendment flo. f,7, 92
QUAD CITIES brR-29 C.
Scram Insertion Times The control rod system is analyzed to bring the reactor suberitical at a rate fast enough to prevent fuel-damage, i.e.,
to prevent the HOPR from becoming less than the fuel cladding integrity safety limit.
lnalysis E thelimitin9 Power.
transient sheks that the negative reactivity rates resulting from the scram with the average response of all the drives as given in the above specification, provide the required protection, and NOPR remains greater than the fuel cladding inteErity safety limit. It is necessary to raise the NCPR operating limit (per Specification 3 5.K) when the average 20% scram insertion time reaches 0.73 seconds on a cycle cumulative basis (overall average of surveillance data to date) in order to comply with assumptions in.the implementation procedure for the ODYN transient analysis computer code.
The basis for choosing 0.73 seconds is discussed furtner in the bases for. Specification 3 5.K.
In the analytical treatment of the transients, 290 milliseconds are allowed between a neutron sensor reaching the scram point and the start of motion of the control rods.
This is adequate and conservative when compared to the typically observed time delay of about 210 milliseconds.
Approximately'90 milliseconds after neutron flux reaches the trip point, the pilot scram valve solenoid deenergizes and 120 milliseconds later the control rod motion is estimated to actually begin.
Ecwever, 200' milliseconds rather than 120 milliseconds is conservatively assumed for this time interval in the transient analyses and is also included in the allow-able scram insertion times specified in Specification 3 3.C.
The scram times for all control rods will be determined at the time of each refueling outage. A representative sample of control rods will be scram tested during the interval of greater than 16 weeks but not more than 32 weeks Scram times of new drives are approximately 2 5 to 3 seconds; lower raies of change in scram times folleming initial pf4nt operatien at power are expreted.
The test schedule i
provides reason bre ciur.nce ordeieedon orslow drives belbre system deierioration be3ond the limits of Specificai,or,3.3.C.The pregram was developed on the basis of the stadsiieal appreach outlined below ar.d judgment.
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,i The histnry of drive perfntmance arrumulated to date indicates that the 90% insertion dmes of new and overhauled driges approxim ie a antmal distribution about the mean which tends lo become skewed loward longer scram times as operating time is aceumi. lated.The probability of a drive not eaceeding the mean 90% insertion time by 0.75 seconds is greater than 0.999 for a normal distribution. The i
measurement of the scram perfnimance of the drises surtnunding a drive enceeding the especied range of scram perfortnance wi!! derret loca! varia or.s and also provide assurance that local scram time limiu i
are not carreded. Continued monitoring of other drives cacceding the espected range of scram times provides survei!!ance of possible anomalous performance.
The numerical values attigned to the predicted scram performance are based on the analpis of the Dresden 2 stariup Na and of dain from other NWR's such as Nine Mile Point and Oyster Creek.
The occurrence o' 4.... r ' within the limits, het signir.rantly longer than averate, shnufd b: viewed as an indication.
- a s....ie problem with conisol soJ Jrives. especially if sl.e number of drives sahibiting such scram iimes stereds eight. the allowahle number ofinoperah!c rods.
3.3 / 4 3 -10 l
Amendment No. 67 A3,92
Leruq' c
e UNITED STATES 8'
t NUCLEAR REGULATORY COMMISSION h
WASHINGTON. D. C,20555
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COMMONWEALTH EDISON COMPANY AND
-TOWA-ILLIN0IS GAS ARIf ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated May 2,1983, complies with the standards and requireraents of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I;
'f B.
The facility will operate in conformity with the application,
[
the provisions of the Act, and the rules and regulations of the i
Comission; i
l C.
There is reasonable assurance (i) that the activities authorized i
and safety of the public, and (ii) that such activities will be
{
conducted in compliance with the Comission's regulations; i
D.
The issuance of this anendment will not be inimical to the common defense and security or to the health and safety of the public; and I
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 i
8 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended 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. DPR-30 is hereby amended to read as follows:
. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendmant No. 89, are hereby incorporated in the license. The licensee shall operate the facility in acenrdance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMLSSION b
John A. Zwolinski, Director BWR Project Directorate #1 Division of BWR Licensine
Attachment:
Changes to the Technical Specifications Date of Issuance: February 7, 1986.
i
ATTACHMENT TO LICENSE AMENDMENT NO. 89__
FACILITY OPERATING LICENSE NO. OPR-30 DOCKET NO. 50-265 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Pages 3.3/4.3-4
, 3.3/4.3-10 i
QUAD-CITII7.S
- DPit-3J the operating power levc1 chall be
(
c.
lireiter'. so that the MCPR will re -
inain above the MCFR fuel cladding integrity safety 1 bit assuming a sin-gle error laat tesults in enmplete withdrawal. ora.1y single operable control rod C. Sersm insertion Times C. Scram insertion Times
- 1. The average wram inwrtion time.ha-1.
After refueling outage and prfor to operation above 30s power, with sed on the dcenergitation of the scram reactor pressure above 800 psig, I ot valve solenoids at timc zero. of all all control rods snall be subject il operable control tods a.n the reactor to scram-time messarements from the fully withdrawn position.
power operation condition thJil be no The scram times f r single rod greater than.
scram testing shall be measured without r eliance on the control rod drive pumps.
Ant ap Scram
% inserted from interrion fully Watindrawn Times (sec) 5 0.375 20 0.900 50 2.00 90 3.50 The average of the scram insertion times for the three fastest control tod.
of all groups of four contro! rods in a two by two array shall tx no greater than:
% inserted from Averup Scram fu!Iy Wisisdrawn Times (see) 5 0.39K 20 0.954 50 2.12 90 3.80 2.
All control rod drives shall have experienced scram test measure-
"t* ***h Y'*'*
^18 50' f
- 2. The masimum serem insertion time the control rod drives'in each for 90'4 inertion of any oper.ihle svn.
quadrant of the reactor core t
shall be measured for the seram trol rodt th.ill not estved 7 Sceonds, times specified in Specification 3.3.C during the interval not i
- 3. If $pecification 3.3.C.I cannot be met.
more requently than 16 weeks the reactor shall not be mJde super-nor less frequently than 32 weeks. These tests shall be critical; if operating. the reactor shall r
periormed with a reactor pres-be shut down immedsately upon deter.
sure above 800 psig and may be mination that averJfe skram time is measured during a reactor scram. Whenever all of the deficient.
control rod drive scram times have been measured, an evalu-
- 4. If Specification 310.2 tannot be met, ation shall be made to I
the deficient tonlini rek! bliall be con.
3.3 / 4.3-4 Amendment No.
M. 89
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DPR-30 C.
Scram Inse tion Times The control rod sy' stem is analyzed to bring the reactor suberitical et a rate fast enough to prevent fuel damage, i.e.,
to prevent the HOPR from becoming less than the fuel cladding integrity safety limit.
"Xnalysis lil'the limitin9 Power.
transient sheks thet the negative
~
reactivity rates resulting from the scram with the average response of all the drives as given in the above specification, provide the required protection, and MOPR recains greater than the fuel cladding integrity safety limit..
It is necessary to raise the MCPR operating limit
-(per Specification 3 5.K) when the average 20% scram insertion time reaches 0 73 seconds on a cycle-cumulative basis. (overall average of surveillance data to date) in order to comply with assumptions in the implementation procedure for the ODYN transient analysis computer code.
in the bases for Specification 3.5.K.The basis for choosing 0.73 seconds is disc In the 'onelytical trea tment of the transients, 290 milliseconds are allowed between a neutron sensor reaching the scram point and the start of motion of the cor. trol rods.
This is adequate and conservative when campared to the typically observed time delay of about 210 milliseconds.
milliseconds af ter neutron flux reaches the trip point,Approximately 90 the pilot scram valve solenoid deenergizes avid 120 milliseconds later the control rod motion is estimated to actually begin.
However 200 milliseconds rather than 120 milliseconds is conservatively assum,ed for this time interval in the transient analyses and is also included in the allow able scram insertion times specified in Specification 3-3.c.
l refueling outage.The scram times for all control rods will be determined at the time of each during the interval of greater than 16 weeks but not more than 32 weeksA representat
{
Scram times of new drives are approximately 2.5 to 3 seconds; lower raies of chante in scram ti j
folinwing initial pfant operatica at power are capected.
The test schedule i
provides renonable enarance of deiection of slow drives belbre system deierioration beyond the lim
{
of Specification 3.3.C.The program was developed on the bois of the statistical app each outlined be ar.d bd; ment.
i The history ofdrive performance areumufased to daic indicates that the 90% intenien times of new and overhauled drives approximate a normal distribution about the mean which tends to become sLemed l
toward longer scram times as op rating timeis accuinut.ited.The probability of a drive not eseceding the mean 90% insenion time by 0.75 seconds is greater than 0.999 for a nortnal distribution. The measurement of:he scram perfortnance of the drises surtnunding, a drive eseceding the espected range of scram performance will delen local varinier.s and also provicie assurance thai local scram time limits are not caereded. Continued monitoring of other drives cacceding the espected range of scram times provides surveillance of possible anomalous performance.
The numerical values assigned to the predicted scram performance are bned on the analpis of the Dresden 2 stanup data and of Jara from other NWR's such as Nine Mile Point and Oyster Creek.
The cecurrence of scram times within the limits. hus signir.can Iy longer than average, should b: viewed as an Indication of a spiematic problem with contml roJ Jrnes ciperially if the number of drives cahibiting such scram times cacceds eight. the allowahle number of inopCrJhlC rods.
3.314.3-10 M.endment No. ff, $9,89 I
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