ML20210U773
| ML20210U773 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  (DPR-29-A-189, DPR-30-A-186) |
| Issue date: | 08/04/1999 |
| From: | Anthony Mendiola NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210U779 | List: |
| References | |
| NUDOCS 9908200209 | |
| Download: ML20210U773 (7) | |
Text
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. m mi COMMONWEALTH EDISON COMPANY dLNQ MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.189 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 March 30,1999, as supplemented on June 30,1999, complies with the 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 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; j
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 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 29 is hereby amended to read as follows:
9908200209 990004 PDR ADOCK 05000254 p
PDR L
1 B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.189, 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 and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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. q c &.'r hony J. Mendiola, Chief, Section 2
' Project Directorate !!!
Aivision of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance: August 4,1999
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3068H001 o%4 s,.....,/
C.OMMONWEALTH EDISON COMPANY ANQ M!I.DAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.186 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 March 30,1999, as supplemented on June 30,1999, complies with the 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 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.
There is rerssonable 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 5ealth 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:
If:
2-B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.186, 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 and shall be implemented within 60 days.
FOR THE NUCLEAR REGUI.ATORY COMMISSION g lsk A
hony J. Mendiola, Chief, Section 2 roject Directorate 111 ivision of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 4, 1999 s
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ATTACHMENT TO LICENSE AMENDMENT NOS.189 AND 186 FACILITY OPERATING LICENSE NOS. DPR 29 AND DPl3-2Q DOCKET NOS. 50-254 AND 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 marginallines indicating the area of change.
REMOVE INSERT 3/4.6 10 3/4.6.10 B 3/4.6-4 B 3/4.6-4 t
PRIMARY SYSTEM BOUNDARY Loakage Detection 3/4.6.G 3.6 LIMITING CONDITIONS FOR OPERATION 4.11 SURVEILLANCE REQUIREMENTS G. Leakage Detection Systems G. Leakage Detection Systems The following reactor coolant system The reactor coolant system leakage leakage detection systems shall be detection systems shall be demonstrated OPERABLE:
OPERABLE by:
1 1.
The primary containment atmosphere 1.
Performing the leakage determinations particulate radioactivity sampling of Specification 4.6.H.
system, and 2.
Performing a CHANNEL CAllBRATION 2.
The drywell floor drain sump monitoring of required leakage detection system.
instrumentaion at least once per 18 months.
APPLICABILITY:
OPERATIONAL MODE (s) 1,2 and 3.
ACTION:
,L 1.
With the primary containment atmosphere particulate radioactivity sampling system inoperable, restore the inoperable leak detection radioactivity sampling system to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; otherwise, be in HOT SHUTDOWN 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 drywell floor drain sump monitoring system inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> establish an alternate manual method of determining drywell floor drain sump flow rates by calculating flow rates using sump pump run times, AND witMn 30 days restore the drywell floor drain sump monitoring system to cn OPERABLE status; otherwise, be in at least HOT SHUTDOWN 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 />.
QUAD CITIES - UNITS 1 & 2 3/4.6-10 Amendment No. 189 & 186 l
PRIMARY SYSTEM BOUNDARY B 3/4.6 l
BASES I
l Leakage from the reactor coolant pressure boundary inside the drywell is detected by at least one or two independently monitored variables, such as sump level changes and drywell atmosphere i
radioactivity levels. The means of quantifying leakage in the drywell is the drywell floor drain i
sump pumps. With the drywell floor drain sump pump monitoring system inoperable, an alternate method using measured sump run-times for quantifying leakage can be employed for up to 30 days under administrative controls. Primary containment atmosphere sampling for radioactivity can provide indication of changes in leakage rates.
t 3/4.6.H Operational Leakaoe The allowable leakage rates from the reactor coolant system have been based on the predicted and experimentally observed behavior of cracks in pipes. The normally expected background leakage due to equipment design and the detection capability of the instrumentation for determ:ning system leakage was also considered. The evidence obtained from experiments suggests that for leakage somewhat greater than that specified for UNIDENTIFIED LEAKAGE the probab.lity is small that the imperfection or crack associated with such leakage would grow rapidly. However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor will be shutdown to allow further investigation and corrective action.
An UNIDENTIFIED LEAKAGE increase of more than 2 gpm within a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period is an indication of a potential flaw in the reactor coolant pressure boundary and must be quickly evaluated.
Although the increase does not necessarily violate the absolute UNIDENTIFIED LEAKAGE limit, IGSCC susceptible components must be determined not to be the source of the leakage within the required completion time.
3/4.6.1 This Section intentionally Left Blank QUAD CITIES - UNITS 1 & 2 B 3/4.6-4 Amendment Nos. 189 & 186