ML20216H839

From kanterella
Jump to navigation Jump to search
Amends 190 & 187 to Licenses DPR-29 & DPR-30,respectively, Increasing Notch Testing Surveillance Interval of Partially Withdrawn Control Rods in TS SR 3/4.3.C from Interval of Once in 7 Days to Once in 31 Days
ML20216H839
Person / Time
Site: Quad Cities  
(DPR-29-A-190, DPR-30-A-187)
Issue date: 09/23/1999
From: Anthony Mendiola
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20216H845 List:
References
NUDOCS 9910040071
Download: ML20216H839 (6)


Text

f y

UNITED STATES E

NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066M001 COMMONWEALTH EDISON COMPANY bhD MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.190 License No. DPR-29 I

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated June 29,1999, 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; l

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 i

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:

9910040071 990923 PDR ADOCK 05000254 P

PDR

  • B.

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.190, 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

'g, 4-Anthony J. Mendiola, Chief, Section 2 Project Directorate til

/ Division of Licensing Project Management

./

Office of Nuclear Reactor Regulation j

Attachment:

Changes to the Technical Specifications i

Date of Issuance: September 23, 1999 o

l l

F o uey O

t UNITED STATES

. NUCLEAR REGULATORY COMMISSION i

o WASHINGTON, D.C. m =1

\\;'< f COMMONWEALTH EDISON COMPANY m

l MIDAMERICAN ENERGY COMPANY l

l DOCKET NO. 50-265 1

QUAD CITIES NUCLEAR POWER STATION. UNIT 2 i

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.187 License No. DPR-30 l

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated June 29,1999, 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 i

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 appiicable 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:

l

r B.

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised 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 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/

q c.~,

, Anthony J. Mendiola, Chief, Section 2 Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 23, 1999 4

I

\\.

ATTACHMENT TO LICENSE AMENDMENT NOS.190 AND 187 FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 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 3/4.3-3 3/4.3-3 l

l l

l l

l l

l l

l I

e

REACTIVITY CONTROL CR OPERABILITY 3/4.3.C 3.3 - LIMITING CONDITIONS FOR OPERATION 4.3 - SURVEILLANCE REQUIREMENTS C.

Control Rod OPERABILITY C.

Control Rod OPERABILITY All control rods shall be OPERABLE.

1.

When above the low power setpoint of the RWM, all withdrawn control rods APPLICABILITY:

not required to have their directional control valves disarmed electrically or OPERATIONAL MODE (s) 1 and 2.

hydraulically shall be demonstrated OPERABLt by moving each control rod at least one notch:

ACTION:

a.

At least once per 7 days'*' for each 1.

With one control rod inoperable due to fully withdrawn control rod, and at being immovable as a result of least once per 31 days'*) for each excessive friction or mechanical partially wbMrawn control rod, and interference, or known to be unscrammable:

b.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when any control rod is immovable as a result of a.

Within one hour:

excessive friction or mechanical interference, or known to be

1) Verify that the inoperable unscrammable, control rod, if withdrawn, is separated from all other 2.

All control rods shall be demonstrated inoperable withdrawn control OPFRABLE by performance of rods by at least two control Surveillance Requirements 4.3.D,4.3.F, cells in all directions.

4.3.G, 4.3.H and 4.3.1.

2) Disarm the associated directional control valves

either:

a) - Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves, b.

With the provisions of ACTION 1.a above not met, 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 />, May be rearmed intermittently, under administrative control, to permit testing associated with restoring the a

control rod to OPERABLE status.

b Not required to be performed until 7 days (for fully withdrawn) or 31 days (for partially withdrawn) after the control rod is withdrawn and above the Icw power setpoint of the RWM.

QUAD CITIES - UNITS 1 & 2 3/4.3-3 Amendment No. 190 & 187 l