ML20205F469
| ML20205F469 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  (DPR-29-A-187, DPR-30-A-184) |
| Issue date: | 03/31/1999 |
| From: | Anthony Mendiola NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205F477 | List: |
| References | |
| NUDOCS 9904060272 | |
| Download: ML20205F469 (11) | |
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 3088H001 COMMONWEALTH EDISON COMPANY ANQ MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.187 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commony.ealth Edison Company (the licensee) dated January 21,1999, 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 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:
9904060272 990331 PDR ADOCK 05000254 P
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B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised l
through Amendment No.187, 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 30 days.
FOP. THE NUCLEAR REGULATORY COMMISSION I
/
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hony Mendiola, Section Chief
/ Project Directorate 111-2
// Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 31, 1999
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UNITED STATES j ~
WASHINGTON, D.C. 30006-0001 NUCLEAR REGULATORY COMMISSION s.,...../
l COMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 l
QUAD CITIES NUCLEAR POWER STATION. UNIT 2 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.184 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the l
licensee) dated January 21,1999, complies with the standards and requirements i
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; 8.
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 health and safety of the j
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:
a
t 2-l B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 184, 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 30 days.
1 FOR THE NUCLEAR REGULATORY COMMISSION Anthony Mendiola, Section Chief
'f Project Directorate 111-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
March 31, 1999 l
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l ATTACHMENT TO LICENSE AMENDMENT NOS.187 AND 184 l
FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 l
Revise the Appendix A Technical Specifications by removing the pages identified below and l
inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginallines indicating the area of change.
i REMOVE INSERT Vill Vill XXI XXI 3/4.6-13 3/4.6-13 3/4.6-14 3/4.6-14 3/4.6-15 3/4.6-15 B 3/4.6-4 8 3/4.6-4 I
TABLE OF CONTENTS TOC LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 PRIMARY SYSTEM BOUNDARY
{
3/4.6.A Recirculation Loops...................................
3/4.6 1 i
l 3/4.6.B Je t Pu m p s.........................................
3/4.6-3 3/4.6.C Recirculatien Pumps 3/4.6 5 3/4.6.D Idle Recirculation Loop Startup...........................
3/4.6 6 3/4.6.E S a f ety Valves.......................................
3/4.6 7 3/4.6.F Relief Valves 3/4.6-8 3/4.6.G Leakage Detection Systems.............................
3/4.6-10 3/4.6 11 l
3/4.6.H Operational Leakage l
3/4.6.1 DELETED.....
3/4.6 13 3/4.6.J Specific Activity.....................................
3/4.6-16 l
I 3/4.6.K Pressure / Temperature Limits.............................
3/4.6-19 l
l Figure 3.6.K-1, Pressure Temperature Limits for Pressure Testing - Valid to 18 EFPY l
Figure 3.6.K-2, Pressure-Temperature Limits for Pressure Testing - Valid to 20 EFPY i
Figure 3.6.K-3, Pressure-Temperature Limits for Pressure Testing - Valid to 22 EFPY l
Figure 3.6.K-4, Pressure-Temperature' Limits for Non-Nuclear Heatup/Cooldown - Valid to 22 EFPY Figure 3.6.K-5, Pressure Temperature Limits for Critical Core Operations - Valid to 22 EFPY f
3/4.6.L Reactor Steam Dome Pressure 3/4.6 22 3/4.6.M Main Steam Line isolation Valves 3/4.6 23 3/4.6.N Structural Integrity 3/4.6-24 i
3/4.6.0 Residual Heat Removal - HOT SHUTDOWN...................
3/4.6-25 i
3/4.6.P Residual Heat Removal - COLD SHUTDOWN..................
3/4.6-27 QUAD CITIES - UNITS 1 & 2 vill Amendment Nos.187 and 184 i-
1
. TABLE OF CONTENTS B TOC
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BASES SECTION PAGE 3/4,6 PRIMARY SYSTEM BOUNDARY 3/4.6.A Recircu!ation Loops B 3/4.6-1 3/4.6.B JetPumps...........................................
B 3/4.6-1 3/4.6.C Recirculation Pumps....................................
B 3/4.6-1 3/4.6.D Idle Recirculation Loop Startup B 3/4.6-1 3/4.6.E S a f e ty Val ve s........................................
B 3/4.6 3 3/4.6.F R e li e f V a l v e s.........................................
B 3/4.6-3 3/4.6.G Leakage Detection Systems B 3/4.6-3 3/4.6.H Operational Le akage....................................
B 3/4.6-4 3/4.6.1 DELETED B 3/4.6-4 3/4.6.J Specific Activity B 3/4.6 5 l
3/4.6.K Pressure / Temperature Limits..............................
B 3/4.6-5 3/4.6.L Reactor Steam Dome Pressure.............................
B 3/4.6-8 i
3/4.6.M Main Steam Line isolation Valves...........................
B 3/4.6-8 3/4.6.N Stru ctural Int eg rity.....................................
B 3/4.6-8 3/4.6.0 Residual Heat Removal - HOT SHUTDOWN...................
B 3/4.6-8 3/4.6.P Residual Heat Removal - COLD SHUTDOWN...................
B 3/4.6-8 l
l QUAD CITIES - UNITS 1 & 2 XXI Amendment Nos.187 and 184 1.
PRIMARY SYSTEM BOUNDARY 3/4.6-1 THIS PAGE INTENTIONALLY LEFT BLANK.
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QUAD 6l TIES - UNITS 1 & 2 3/4.6-13 Amendment Nos.187 and 184 i
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PRIMARY SYSTEM BOUNDARY 3/4.6-1 t'
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i THIS PAGE INTENTIONALLY LEFT BLANK.
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OUAO CITIES - UNITS 1 & 2 3/4.6-14 Amendment Nos.187 and 184
PRIMARY SYSTEM BOUNDARY 3/4.6-1 E
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THIS PAGE INTENTIONALLY LEFT BLANK.
l QUAD CITIES - UNITS 1 & 2 3/4.6-15 Amendment Nos.187 and 184 L-
PRIMARY SYSTEM BOUNDARY B 3/4.6 BASES Leakage from the reactor coolant pressure boundary inside the drywell is detected by at least oile or two independently monitored variables, such as sump level changes and drywell atmosphere radioactivity levels. The means of qucntifying leakage in the drywell is the drywell floor drain sump pumps. With the drywell floor drain sump pump system inoperable, no other form of monitoring can provide the equivalent ir. formation. However, primary containment atmosphere sampling for radioactivity can provide indication of changes in leakage rates.
3/4.6.H Ooerational Leakaae 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 fer determining system leakage was also considered. The evidence obtained from experiments suggests that for leakage somewhat greater than that specified for UNIDENTIFIED LEAKAGE the probability is small that the imperfection or crack associated with such leakage would grow rapidly. However, in all t *.es, if the leakage rates exceed the values specified or the leakage is l' cated and known L RESSURE BOUNDARY LEAKAGE, the reactor will be shutdown to allow further investigation
. corrective action.
An UNIDENTIFIED LEAKAGE increase of more than 2 gpra 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 pc,tential 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-co.mpletion time.
3/4 6.I This Section Intentionally Left Blank i
QUAD CITIES - UNITS 1 & 2 0 3/4.6 4 Amendment Nos.187 and 184 u