ML20150D225
| ML20150D225 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/30/1988 |
| From: | Norrholm L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20150D227 | List: |
| References | |
| NUDOCS 8807130369 | |
| Download: ML20150D225 (12) | |
Text
cl7Euq
~k UNITED STATES
'8 NUCLEAR REGULATORY COMMISSION o
E p
WASHINGTON, D, C. 20555
\\...../
COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. DPR-29 1.
The Nuclear Regulatory Comission ('qe Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 22, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, ae amended (the Act) and the Comission'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 Comission; 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 Comission'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 Comission's regulaticns 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 cmendment, and paragraph 3.B of Facility Operating License No. DPR-29 is hereby amended to read as follows:
lll7130369880630 p
ADOCK 05000254 PNV l
~
B.
Technical Specifications The Technical Specifications contained in Appendix A and B, as revised thtough Amendment No.110, 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 NUCLE EGULATORY COMMISSION O
f L
' No
,At P ject Directorate III-2 Division of Reactor Projects - III, IV, V and Special Profacts
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 30, 1988
ATTACHMENT TO LICENSE AMENDMENT N0. 110 FACILITY OPERATING LICENSE N0. DPR-29 DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.2/4.2-2 3.2/4.2-2 3.2/4.2-7 3.2/4.2-7 6.2.1 6.2.1
QUAD-CITIES OPR-29 D.
Refueling Floor Radiation Monitors D.
Refueling Floor Radiation Monitors 1.
Except as specified in Specifi-The two refueling floor radiatior) cation 3.2.D.2, the two refuel-monitors shall be functionally tested ing floor radiation monitors
'and calibrated as indicated in Table shall be operable whenever irra-4.2-1.
Reactor building ventilation diated fuel or components are isolation and standby gas treatment present in the fuel storage pool system initiation shall be performed and during refueling or fuel at least each operating cycle, movement operations.
2.
One of the two refueling floor radiation monitors may be inop-erable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the inoperable monitor is not re-stored to service in this time, the reactor building ventilation system shall be isolated and the standby gas treatment operated until repairs are complete.
3.
The trip setting for the refuel-ing floor radiation monitors shall be set at a value of l
1 100 mR/hr.
4.
Upon loss of both refueling floor radiation monitors while in use, the reactor building ventilation system shall be iso-lated and the standby gas treat-ment operated.
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 toe control room, required for indicated in Table 4.2-2.
postaccident monitoring are given in Table 3.2-4.
0723B 3.2/4.2-2 f.mendment No.110
QUAD-CITIES DPR-29 The APRM rod block function is flow biased and prevents a significant reduction in MCPR especially during operation at reduced flow. The APRM provides gross core protection.
i.e.. limits the gross withdrawal of control rods in the normal withdrawal sequence.
In the refuel and startup/ hot standby modes the APRM rod block function is set at 12% of rated power. This control rod block provides the sane type of protection in the Refuel and Startup/ Hot Standby modes as the APRM flow-biased rod block does in the Ran mode, i.e.. prevents control rod withdrawal before a scram is reached.
The RBM rod block function provides local protection of the core, i.e., the prevention of transition boiling in a local region of the core for a single rod withdrawal error from a limiting control rod pattern. The trip point is flow biased. The worst-case single control rod withdrawal error is analyzed for each reload to assure that, with the 'pecific trip settings, rod withdrawal is blocked before the MCPR reaches the fuel cladding integrity safety limit.
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 t'ovides local as well as gross core protection. The scaling arrangement is sucn that the trip setting is less than a factor of 10 above the indicated level. Analysis of the worst-case accident results in rod block action before MCPR approaches the MCPR fuel cladding integrity safety limit.
A downscale indication on an APRM is an indication the instrument has f ailed 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 1100 CP5 and the detector not full inserted assures that the SRM's are not withdrawn f rom the core prior to corriencing rod withd'awal 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 saall pipe breaks the HPCI system sust 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 HFCI 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 SAR Section 6.2.6.3).
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 i 100 set /hr l
for the monitors on the refueling floor are based upon initiating normal ventilation isolation and standby gas treatment system operation 07238 3.2/4.2 7 Amentment No. 110
QUAD-C! TIES OPR W29 6.2 PLANT OPERATING PROCEDURES Detailed written procedures, including applicable checkoff lists A.
covering items listed below shall be prepared. approved, and adhered to:
Normal startup. operation, and shutdown of the reactor, and other 1.
1 systems and' components involving nuclear saf ety of the f acility.
2.
Refueling operations.
3.
Actions to be taken to correct specific and forseen potential rulfunctions of systems or components 4 including responses to alarms, suspec'.ed primary system leaks. and abnormal radtoactivity changes.
Emergency conditions involving potenttal or actual release of 4.
radioactivity "Generating Station Emergency Plan
- and station emergency and abnorwal procedures.
5.
Instrumentation operation which could have an effect on the safety of the facility.
6.
Preventive and corrective maintenance operations which could have an affect on the safety of the facility.
7.
Surveillance and testing requirenents.
8.
Tests and experiments.
9.
Procedure to ensure safe shutdown of the plant 10.
Station Security Plan and implementation procedures.
11.
Fire Protection Progrun irglecentation.
- 12. 00CM impleeentation.
- 13. PCP implementation.
Working hours of the Shtft Engineer. Station Control Room 14 Engineer. Shif t Forerun and the Nuclear Station Operator job classifications such that the heavy use of overtime is not routinely required.
Radiation control procedures shall be maintained, made available to all S.
station personnel, and adhered to. The procedures small snow permissible radiation esposure and shall be consistent with the requirerents of 10 CFR 20.
This radiation protection program shall be organized to meet the req.irenents of 10 CFR 20.
Procedures for items identified in Specification 6.2. A and 6.2.8 C.
1.
and any changes to such procedures shall be reviewed and approved by the Technical Staff Supervisor, the Assistant Superintendent, At and department head responsible for the activity performed.
least one person approving each of the above procedures shall hold a valid senior operator's license. In addition, these procedures and changes thereto must have authorization by a Station
/
Superintendent before being implemented.
Work and instruction type procedures which implement approved 2.
maintenance or modification procedures shall be approved and authorized by the Alst. Sust. Maintenance where the writtenThe authority has been provided by a Station Superintendent.
- Maintenance Modification Procedure
- utilized for safety related work shall be so approved only if procedures referenced in the
- Maintenance Modification Procedure
- have been approved as Procedures which do not fall within the required by 6.2.A.
requirenent of 6.2. A or 6.2.5 may be approved by the Oepartment Heads.
Temporary changes to procedures 6.2.A and 6.2.5 above may be made D.
provided:
1.
The intent of the original proccdure is not altered.
The change is approved by two members of the plant management 2.
staf f. at least one of wnom holds a Senior Reactor Operator's license on the unit affected.
Amenorent No.110 6.2-1 0726B
pien
'o,,
UNITED STATES NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D. C. 20555
\\...../
COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CliidS NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 106 License No. DPR-30 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated December 22, 1987, comp 1fes with the standards and requirements of the Atomic Energy Act of 1954, as amen'Jed (the Act) and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable recuirements 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:
-2 B.
Technical Specifications The Technical Specifications contained in Appendix A and B, as revised through Amendment No.106, are hereby incorporated in this 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 3s t 4 Leif J N holm, Acting Director Project D ectorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 3D, 1988 l
l l
l
e ATTACHMENT TO LICENSE AMENDMENT N0.106 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET N0. 50-265 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.2/4.2-2 3.2/4.2-2 3.2/4.2-7 3.2/4.2-7 6.2.1 6.2.1
QUAD-CfTIES DPR-30 D.
Refueling Floor Radiation Monitors 1.
Except as specified in Specift-cation 3.2.0.2, the two refuel-ing floor radiation monitors shall be operable whenever irra-diated fuel or components are present in the fuel storage pool and durMg refueling or fuel movement operations.
2.
One of the two refueling ficnr radiation monitors may be inop-D.
Refueling Floor Radiation Monitors erable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the inoperable monitor is not re-The two refueling floor radiation stored to service in this time, monitors shall be functionally tested the reactor building ventilation and calibrated as indicated in Table system shall be isolated and the 4.2-1.
Reactor building ventilation standby gas treatment operated isolation and standby gas treatment until repairs are complete, system initiation shall de performed at least each operating cycle.
3.
The trip setting for the refuel-ing floor radiation monitors shall be set at a value of l
3,100 mR/hr.
4.
Upon loss of both refueling floor radiation monitors while in use, the reactor building ventilation system shall be iso-lated and the standby gas treat-ment operated.
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.
07248 3.2/4.2-2 Amendment No. 106
\\
QUAO-CITIES DPR-30 The APRM rod block function is flow biased and prevents a significant redu tion in MCPR. especially during operation at reduced flow. The APRM provides gross core protection.
i.e.. Itmits the gross withdrawal of control rods in the normal withdrawal sequence.
In the refuel and startup/ hot standby modes, the APRM rod block function is set at 12% of rated power. This control rod block provides the same type of i
protection in the Refuel and Startup/ Hot Standby modes as the APRM flow-biased rod block does in the Run mode, i.e., prevents control rod withdrawal before a scram is reached.
The RDM cod block function provides local protection of the core i.e., the prevention of transition boiling in a local region of the core for a single l
rod withdrawal error from a limiting control rod patt?rn. The trip point is flow biased. The worst-case single control rod withdrawal error is analyzed for each reload to assure that, with the specific trip settings, rod withdrawal is blocked before the MCPR reaches the fuel cladding integrity safety limit.
Below 30% power the worst-case withdrawal of a single control rod without rod block action will not violate tha fuel cladding integrity safety limit.
Thus the RSM 'od block function is act 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 f actor of 10 above the indicated level. Analysis of the worst-case accident results in rod block action before MCPR approaches the MCPR fuel cladding integrity safety limit.
A downstale indication on an APRM is an indication the instrument has f ailed or *$ not sensitive enough. In either case the instrument will not respond to changes in control rod rction and the control rod motion is thus prevented. The downscale trips are set at 3/125 of full scale.
The SRM rod block with 1100 CPS and the detector not full inserted ascures that the SeM's are not withdrawn from the core prior to coprencing rod withdrawal for startup. The scram discharge volume high water level block provide annunciation for operator action. The alarm setpoint has beer, selected to provida adequate time to allow determination of the cause of level increase and corrective action prior to automatic scron initiation.
For ef fective emergency core cooling for small pipe breaks the HPCI system pust function since reactor press 6te does not decrease rapidly enough to allow either core spray or LPCI to operate in time. The automatic pressurc 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 SAR 5ection 6.2.6.3).
The specification preserves the ef fectiveness of the system during periods of maintenance, testing or calib'
'n and also minimizes the risk of inadvertent operation.
i.e., only one 1. :yent 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 cas treatmeet systems. The trip logic is one out of two. Trip settings of i 100 mR/hr l
for the monitors on the refueling floor are based upon initiating normal ventilation isolation and standby gas treatment system cperation 0724B 3.2/4.2-7 knenament No. 106
~
OVAD-CITIES OPR-30 6.2 PLANT OPERATING PROCEDURES Detailed written procedures. including applicable checkof f lists A.
covering items listed below shall be prepared, approved, and adhered to:
Normal startup, operation, and shutdown of the reactor. and other 1.
systems and' components involving nuclear saf ety of the f acility.
2.
Refueling operations.
Actions to be taken to correct specific and forseen potential 3.
sulfunctions of systems or cewgonents. including responses to alarms, suspected primary system leaks and abnormal radioactivity changes.
Emergency conditions involving potential or actual release of 4.
radioactivity "Generating Station Emergency Plan
- and station emergency and abnormal procedures.
5.
Instrumentation operation which could have an effect en the safety of the facility.
Prevent 1.e and corrective mairtenance op* stie.1s which could have 6.
an affect on the safety of the facility.
7.
Surveillance and testing requirements.
8.
Tests and experiments.
9.
Procedure to ensure safe shutdown of the plant 10.
Station Security Plan and implementation procedures.
- 11. Fire Protection Progrun implementation.
12.
00CM implementation.
13.
PCP implementation.
Working hours of the Shift Engineer. Station Contrn1 Roan 14 Engineer. Shift Foreman and the Nuclear Station Operator Job classifications such that the heavy use of overtime is not routinely required.
Radiation control procedures shall be rutntained, pude available to all 8.
station personnel. and adhered to. The procedures shall show permissible radiation exposure and shall be conststent with the requirements of 10 CFR 20.
This radiation protection program shall be organized to meet the requirements of 10 CFA 20.
Procedures for items identified in Specification 6.2. A and 6.2.B C.
1.
and any changes to such procedures shall be reviewed and approved by the Technical Staff Supervisor. the Assistant Superintendent, At and department head responsible for the activity performed.
least one person approving each of the above procedures shall hold a valid sentor operator's license. In addition, these procedures and changes thereto must have authorization by a Station Superintendent before being implemented.
Work and instruction type procedures which implement approved 2.
maintenance or modification procedures shall be approved and authorteed by the Asst. Supt. Maintenance where the writtenThe authority has been provided by a Station Superintendent.
'Matatenance Modification Procedure" utilized for safety related work sha11 be so approved only if procedures referenced in the
' Maintenance Modification Procedure
- have been approved as Procedures which do not f all within the required by 6.2.A.
requirerent of 6.2.A or 6.2.8 may be approved by the Department Heads.
Temporary changes to procedures 6.2.A and 6.2.B above may be made D.
provided:
The intent of the original procedure is not altered.
1.
The change is approved by two members of ta. witnt management 2.
staf f, at least one of whom holds a Senior Reactor Operator's license on the unit affected.
Amensment No. 106 6.2 1 07268
.. _. _