ML20116M409
| ML20116M409 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/12/1992 |
| From: | Dyer E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116M412 | List: |
| References | |
| NUDOCS 9211200259 | |
| Download: ML20116M409 (13) | |
Text
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UNITED STATES-NUCLEAR REGULATORY COMMISSION 7,;
WASHINoToN, D.C. 20 lie 6 -
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COMMONWEALTH EDISON COMPANY-8!iQ 10WA-IlllN0lS GAS AND ELECTRIC COMPANY DOCKET NO. 50-2 M -
OVAD CITIES NUCLEAR POWER STATION. UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment _No. 140 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company-(the licensee) dated April 20, 1992, complies with the standards.
and requirements of the Atomic Energy Act of.1954, as-amended-(the-
'3 Act) and the Commission's.rtles and regulations set forth in 10 CFR 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; a
C.
Ti.ere is reasonable assurance:(i) that-the activities authorized -
il by this amendment can be conducted without-endangering the health and safety of the pub _lic, 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 l 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;1icense amendment, and_ paragraph 3.B. of-facility Operating License No.'DPR-29 is hereby-amended to read as follows:
9211200259:921112 i
PDR -ADOCK 05000254-1 P
PDR j
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, B.
Ischnical SDecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
140, 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 W
J es E. Dyer, rector F oject Directorate 111-2 ivision of Reactor Projects - lil/IV/V.
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 12, 1992
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ATTACHMENT TO LICENSE AMENDMENT NO. 140 FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing _the pages identified below and 1.serting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.2/4.2-3 3.2/4.2-3 3.2/4.2-10 3.2/4.2-10 3.2/4.2-11 3.2/4.2-11 3.2/4.2-28 3.2/4.2-28 i
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QUAD-CITIES DPR-29 i
E..Postaccident-Instrumentation-E.
Postaccident Instrumentation The limiting conditions _for operation Postaccident instrumentation shall be.
for the instrumentation which is read functionally-tested and calibrated as:
out in the control room, required for indicated-in Table ~4.2-2.
~,
postaccident monitoring are given in Table 3.2-4.-
F.
Control Room Ventilation System F.
Control Room Ventitation System Iso-Isolation lation 1.
The control room ventilation 1.
Surveillance for instrumentation systems-are isolated from.
which. initiates. isolation of outside air on a signal of high control room ventilation shall-drywell pressure, icw water.
be as specified in Table 4.2-1, level, high main steamline flow, high toxic gas concentration,-
high radiatioh_in either of tht reactor building ventilation exhaust ducts, or manually.
Limiting conditions for operation shall be as indicated in Table 3.2-1.and Specification 3.2.H. and 3.2.F.2.
2.
The toxic gas detection 2.
Manual: isolation of the control.
. instrumentation shall cor.sist of room-ventilation system shall be l
an ammonia analyzer with a trip demonstrated once-every-setpoint set at < 50 ppmi refueling outage.
The provisions of Specification 3.0.A. are not applicable.
3.2/4.2 -Amendment'No.<140 h
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QUAD-CITIES DPR-29 Below 30% power, the worst case withdrawal of a single control rod without rod block action will not violate the fuel cladding integrity safety limit.
Thus the RBM rod block function is not required below this power level.
The IRM block function provides local as well as gross core protection.
The scaling arrangement is such that the trip setting is less than a factor of 10 above the indicated level.
Analysis of the worst-cuse accident results in rod block action before MCPR approaches the MCPR fuel cladding integrity safety limit.
A downscale indicatiori on an APRM is an indication the instrument has failed or is not sensitive enough.
In either case the instrument will not respond-to changes in control rod motion, and the control rod motion is thus prevented.
The downscale trips are set at 3/125 of full scale.
The SRM rod block with < 100 CPS and the detector not full inserted assures that the SRM's are not withdrawn from the core prior to commencing rod withdrawal for startup.
The scram discharge volume high water level block provide annunciation for operator action.
The alarm setpoint has been selected to provide adequate time to allow determination of the cause of level increase and corrective action prior to automatic scram initiation.
For effective emergency core cooling for small pipe breaks the HPCI system must function since reactor pressure does not decrease rapidly enough to allow 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 (reference UFSAR Section 7.3.1.4).
The specification l
preserves the effectiveness of the system during periodt of maintenance, testing or calibration and also minimizes the risk of inadvertent opention, i.e., only one instrument channel out of service.
Two radiation monitors are provided on the refueling floor which initiate isolation of the reactor building and operatic.1 of the standby gas treatment systems.
The trip logic is one out of two.
Trip settings of ( 100 mR/hr for the monitors on the refueling floor are based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the reactor building via the normal ventilation stack but that all the activity is processed by the standby gas trectment system.
3.2/4.2*10 Amendment No. 140
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QUAD-CITIES DPR-29 The instrumentation which is provided to monitor the postaccident condition is listed in Tabla 3.2-4.
The instrumentation listed and the limiting conditions for operation on these systems ensure adequate monitoring of the containment following a loss-of-coolant accident.
Information from this instrumentation will provide the operator with a detailed knowledge of the conditions resulting from the accident; based on this information he can make logical decir. ions regarding postaccident recovery.
The specifications allow for postaccident instrumentation to be out of service for a period of 7 days.
This period is basud on the fact that saveral diverse instruments are available for guiding the operatur should an accident occur, on the low probability of an instrument being out of service and an accident occurring in the 7-day period, and on engineering jud(1ent.
The normal supply of air for the control room ventilation fystem Trains "A" and "B" is outside the service building.
In the event of an accident, this source of air may be required t.o be shut cown to prevent high doses of radiation in the control room.
Rather than provide this isolation function on a radiation monitor installed in the intake air duct, signals which indicate an accident, i.e., high drywell pressure, low water level, main steamline high flow, or high radiation in the reactor building ventilation duct, will ccuse isolation of the intake air to the control room.
The above trip signals result in imn4diate isolation of the control room ventilation system and thus minimize any radiation dose.
Manual isolation capability is alsc provided.
Isolation from high toxic chemical concentration has been added as a result of the " Control Room Habitability Study" submitted to the NRC in December 1981 in response to NUREG-0737 Item III 0.3.4.
- Ammonia, chlorine and sulphur dioxide detection capability was added to the plant in response to the referenced study.
an a report generated by Sargent and Lundy in April 1991 justification was pros ' ed to delete the chlorine and sulphur dioxide detectors from the cfant ihe setpoints chosen for the control room ventilation isolatior n 2 tr.e1 on ca. v detection in the outside air supply at the odor thre. held, so tha, t
'nxic chemical will not achiew toxicity limit concentrat'ons in the t
/ Room,.
The radioactive liquid and gaseous effluent instrumentation is provided to monitor the release of radioactive materials in liquid and gaseous effluents during releases.
The alarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the limits of 10 CFR 20.
3.2/4.E-11 Amendment No. 140
QUAD-CITIES DPR-29 TABLE 4.2-1 (Cont'd)
Instrument Instrument functional Instrument I2)
Channel Test [2]
Calibration Chuck [2]
RCIC Isolation 1.
Steamline high flow Once/3 months [9] Once/3 months [9]
None 2.
Turbine area high temperature Refueling outage Refueling outage None 3.
Low reactor pressure Once/3 months Once/3 months None HPCI Isolation 1.
Steamline high flow
[1]
[9][10]
[9][10)
None 2.
Steamline area high Refueling outage Refueling outage Hone temperature 3.
Low reactor pressure
[1]
[10]
[10)
None Reactor Building Ventilation System Isolation and Standby uns Treatment System Initiation 1.
Refueling floor radiation
[1]
Once/3 months Once/ day monitors Steam Jet Air Ejector Off-Gas Isolation 1.
Off pas radiation monitors
[1] [4]
Refueling outage Once/ day Control Room Ventilation System 1301ation 1.
Reactor low water level
[1]
-Once/3 months Once/ day 2.
Drywell high pressure
[1]
Once/3 months None 3.
Main steamline high flow
[1]
Once/3 months Once/ day 4.
Toxic gas analyzer Once/ month Once/18 months Once/ day (ammonia)
Notes
[1] InitiallyonSepermnthuntilexposurehours(MasdefinedonFigure4.1-1) are 2.0 X 10 ; thereafter, according to Figure 4.1-1 with an interval not less than 1 month nor more than 3 months.
1he compilation of instrument failure rate data may include data obtained from other boiling water reactors for which the same design instrument operates in an environment similar to that of Quad Cities Units 1 and 2.
[2] Functional tests, calibraticns, and instrument checks are not required when these instruments are not required to be operable or tripped.
3.2/4.2-28 Amendment No. 140
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- z UNITED STATES n
E i
NUCLEAR REGULATORY COMMISSION f
WASHINoToN, D C. 70%5 c,
[QHt10NWEALULEDISON COMPANY AHQ J.QWA-ILLINDIS GAS AND ELECTRIC _ COMPANY QQfKET NO. 50-265 OVAD CITIES NUCLEAR POWER STATION. UNIT 2 6HWQ!!ENT TO FAGITY. 0f[ RATING UCENSE Amendment No. 135 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated April 20, 1992, complies with the standards and requi*ements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR 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.
1here 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.
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-30 is hereby amended to read as follows:
.. B.
Technical Epecifications The Technical Specifications contained in Apaendices A and B, as revised througn Amendment No. 135, are heresy incorporated in the 1
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 0
sf M
Cl' J mes E. Dyer, irector Project Directorate 111-2 Division of Reactor Projects - Ill/lV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: November 12, 1.992
ATTACHMfNT TO LICEffSE AMENDMENT NO. 135 fjCILITY OPERATING LICENSE NO. OPR-30 00CKE*. NO. 50-265 Revise the Appendix A Technical Specifications by removing the pages identified below and ins;rting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REH0VE JJ{SIRI 3.2/4.2-3 3.2/4.2-3 3.2/4.2-0 3.2/4.2-8 3.2/4.2-17 3.2/4.2-17 l
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QUAD-CITIE5 DPR-30 F.
Control Room Ventilation System F.
Control Room Ventilation. System !$c-
! solation lation 1.
The control room ventilation 1.
Surveillance for-instrumentation systems are isolated from which initiates isolation of-outside air on a signal of high control room ventilation shall drywell pressure, Ic'w water be as specified in Table 4.2-1.-
i level, high main steamline flow, high toxic gas concentration, high radiation in either of the reactor building ventilation exhaust ducts, or manually.
Limiting conditions for operation shall be as indicated in Table 3.2-1 and Specification 3.2.H. and 3.2.F.2.
2.
The toxic gas detection 2.
Manual isolation of-the control instrumentation shall consist of room ventilation system shall an amonia analyzer with a trip demonstratsd once every setpoint set at 150 ppm.
refueling outage.
The proviAlons of Specification 3.0.A. are not applicable.
G.
Radioactive Liquid Effluent Instru-G.
Radioactive Liquid Effluent'Instru-mentatien mentation The effluent monitoring instrumenta-Each radioactive 11guld effluent mon-tion shown in Table 3.2-5 shall be Itoring instrument shown in Table operable with alarm setpoints set to 4.2-3 shall be demonstrated operable
- ensure that the limits of Specift-by performance of the given source _
cation 3.8.8 are not exceeded.
The check, instrument check, calibration, alarm setpoints shall be determined and functional test operations at the-in accordance with the ODCH.
frequencies shown in Table 4.2-3.
1.
With a radioactive liquid ef-fluent'monttoring instrument-alarm / trip setpoint less con-servative than required, without delay suspend the release of ra-dioactive Ilquid effluents mont-tored by the affected instru-u ment or declare the-instrument inoperable.-or change the set-1 point so it is acceptably con-servative.
L i.
3.2/4.2-3 Amendment No.J 135 l
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OUAD CITIES DPR 30 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 l
adequate to assure the above criteria are met (reference UFSAR Section 7.3.1.4).
The specification preserves the effectiveness of the system during periods of maintenance, testing or calibration and also minimizes the risk of inadvertent operation, i.e., only one instrument channel out of service.
Two radiation monitors are provided on the refueling floor which initiate isolation of the reactor building and operation of the standby gas treatment systems. The trip logic is one out of two. Trip settings of s 100 mR/br for the monitors on the refueling floor are based upon init ating normal ventilation isolation and clandby gas treatment system operation so that none of the activity released during the refueling accident leaves the reactor building via the normal ventilation stack but that all the activity is processed by the standby gas treatment system.
The inskumentation which is provided to monitor the postaccident condition is listed in Tab'e 3.2 4. The instrumentation listed and the limiting conditions for operation on these systems ensure adequate monitoring of the containment following a loss of coolant accident. Information from this instrumentation will provide the operator with a detailed knowledge of the conditions resulting from the accident; based on this information he can make logical decisions regarding postaccident recovery.
The specifications allow for postaccident instrumentation to be out of service for a period of 7 days. This period is based on the fact that several diverse instruments are available for guiding the operator should an accident occur, on the low probability of an instrument being out of service and an accident occurring in the 7 day period, and on engineering judgment.
The normal supply of air for the control room ventilation system Trains "A" and "B" is outside the service building. In the event of an accident, this source of air may bu required to be shut down to prevent high doses of radiation in the control room.
Rather than provide this isolation function on a radiation monitor installed in the intake air duct, signals which indicate an accident, i.e., high drywell pressure, low l
water level, main steamline high flow, or high radiation in the reactor building ventilation duct, will cause iso ation of the intake air to the control room. The above trip signals result in immediate isolation of the control room ventilation system and thus minimize any radiation dose. Manuallsolation capability is also provided.
Isolation from high toxic chemical concentration has been added as a result of the submitted to the NRC in December 1981 in
' Control Room Habitability Study"i D.3.4 Ammonia, chlorine and sulphur dioxide response to NUREG 0737 Item ll detection capability was added to the plant in response to the referenced study. In a report generated by Sargent and Lundy in April 1991, justification was provided to delete the chlorine and sulphur dioxide detectors from the plant. The setpoints chosen for the control room ventilation isolation are based on early detection in the outside air supply at the odor threshold, so that the toxic chemical will not achieve toxicity limit concentrations in the Control Room.
The radioactive liquid and gaseous effluent instrumentation is provided to monitor the release of radioactive materials in liquid and gaseous effluents during releases.
The alarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the limits of 10 CFR 20.
3.2/4.2 8 A,nendment No.135
QUAO-CiflC$
LPR-30 1ABLC 4.2 1 (Cont'd)
Instrument Instrument funct nel Instr 2$nt 3
Calnratind2)
Chui CbuneL Int HPCI 1 solation 1.
Steamline high flow (1) (9) (10)
(g) (10)
None 2.
Steamilne area high temperature Refueling outage Refueling outage None 3.
Los reactor pressure (1) (10)
(10)
None Reactor Building Ventilation $ystem Isolation and $tandby Treatment $ystem Initiation 1.
Refueling floor radiation (1)
Ontc/3 senths Once/ day monitors Steam Jet Air Ejector Off-Gas isolation 1.
Off-gas radiation monitors (1) (4)
Refueling outage Once/ day Control Room Ventilation System Isoistion 1.
Reactor low water level (1)
Once/3 months Once/ day 2.
Drywell high pressure (1)
Once/3 mnths None 3.
Main steamline high flow (1)
Onre/3 reonths Once/ day 4
Tonic gas analyrers (ammonia)
Once/ Month Once/18 months Once/ day l
!491tl Initiallyongepermonthunttiesposurehours(HasdefinedonFigure4.1-1) 1.
are 2.0 X 10 ; thereaf ter, according to Figure 4.1 1 with an interval not less than 1 month nor more than 3 months. The compilation of instrument failure rate data may include data obtained from other boiling water reactors for which the same design instrument operates in an environment stellar to that of Quad Cities Units 1 and 2.
2.
Functional tests, calibrations, and instrument checks are not required when these instruments are not required to be operable or tripped.
This instrumentation is excepted from the functional test definition. The 3.
func*len test shall consist of injecting a simulated electric signal into the measurement channel.
This instrument channel is excepted from the functional test definitions and 4
shall be calibrated using simulated electrical signals once every 3 months.
Functional tests shall be performed before each startup with a required 5.
frequency not to exceed once per week. Calibrations shall be performed during each startup or during controlled shutdowns with a required frequency not to exceed once per week.
6.
The positioning mechanism shall be calibrated every refueling outage.
Logic system functional tests are performed as specified in the applicable 7.
section for these systems.
Functional tests shall include verification of operation of the degraded 8.
voltage. $ minute timer and 7 second inherent timer.
Verification of the time delay setting of 3 i t i 9 seconds shall be 9.
performed during each refueling outage.
- 10. Trip units are functionally tested monthly. A calibration of the trip unit is to be performed concurrent with the functional testing. Transmitters are calibrated once per operating cycle.
3.2/4.2 17 Amendment No. 135