LIC-02-0073, Closure of NRC TAC Issues for Fort Calhoun Station
| ML021710030 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/05/2002 |
| From: | Ridenoure R Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LIC-02-0073 | |
| Download: ML021710030 (2) | |
Text
Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 June 5, 2002 LIC-02-0073 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Reference:
- 1.
2.
Docket No. 50-285 Letter from OPPD (R. L. Phelps) to NRC (Document Control Desk), dated April 27, 1999, "Closure of NRC TAC Issues for Fort Calhoun Station" (LIC-99-0041)
SUBJECT:
Closure of NRC TAC Issues for Fort Calhoun Station Omaha Public Power District has implemented the necessary actions associated with the open TAC issues listed in the Attachment. Subject to agreement by the NRC/NRR Project Manager, these items are considered ready to close. These actions have been taken since the last TAC Closure letter, Reference 2.
Please contact me if you have any questions.
Sincerely, rnj c:
E. W. Merschoff, NRC Regional Administrator, Region IV A. B. Wang, NRC Project Manager J. G. Kramer, NRC Senior Resident Inspector Winston & Strawn AYIA Employment with Equal Opportunity 4171
"LIC-02-0073 Attachment Page 1 Table of Implemented TAC Actions Fort Calhoun Station AmenmentTACFCS Amendment Description Number Implementation Number NDate 190 Change Title of Shift Supervisor to Shift MA1276 4/15/99 Manager Unreviewed Safety Question on Overriding 191 The Containment Isolation Actuation Signal MA3400 8/20/99 Closure Signal 192 Core Operating Limits Report (COLR)
MA4651 8/26/99 Revision 193 Reactor Coolant System Flow Rate MA5318 11/5/99 Limiting Condition for Operation for an 194 Inoperable Engineered Safety Features MA0610 9/21/00 Logic Subsystem.
195 The Use of Steam Generator Tube Leak MA9653 3/30/01 Tight Sleeves Siemens Power Corporation (SPC) 196 Methodologies for Determining MB0083 4/10/01 Reactor Core Operating Limits 197 Extending Pressure - Temperature (P-T)
MB0322 4/11/01 Limits 198 Ventilation System Charcoal Adsorbers MA6892 4/25/01 199 Pressurized Thermal Shock (PTS)
MA9690 7/3/01 200 Elimination of Post Accident Sampling MB2274 12/7/01 Requirements 201 Accident Source Term Analyses for Control MB1221 1/25/02 Room Habitability 202 Administrative Changes MB2063 2/7/02 203 Framatome Methodology Changes MB3449 4/16/02 204 Containment Penetrations MB3651 5/3/02 205 Emergency Power Sources MB3652 4/16/02 206 Recirculation Actuation Logic Channel MB4664 4/19/02 Functional Test 207 P-T Curve Changes for Cooldown & Code MB3654 &
4/25/02 Case N640 Exemption MB3606 208 Alternate Shutdown Panel Requirements MB3448 5/24/02 209 Minimum RCS Flow Rate MB3653 5/24/02 210 High Power Trip Setpoint MB4657 5/30/02 Mechanical Nozzle Seal Assembly (Cycles MB0802 &
4/29/01 & 6/2/02 20&21)
MB3581 Reactor Vessel Surveillance Capsule MB3422 5/29/02 Removal Schedule Change MB3422 5/29/02