ML15268A486
| ML15268A486 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, Quad Cities  |
| Issue date: | 10/06/2015 |
| From: | Blake Purnell Plant Licensing Branch III |
| To: | Bryan Hanson Exelon Generation Co |
| Blake Purnell, NRR/DORL | |
| References | |
| TAC MF4436, TAC MF4437, TAC MF4438, TAC MF4439, TAC MF4440, TAC MF4441, TAC MF4442, TAC MF4443, TAC MF4444, TAC MF4445, TAC MF4446 | |
| Download: ML15268A486 (11) | |
Text
Mr. Bryan C. Hanson Senior Vice President UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 6, 2015 Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2; BYRON STATION, UNIT NOS. 1 AND 2; AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 -
CORRECTION OF AMENDMENTS ADOPTING TECHNICAL SPECIFICATION TASK FORCE TRAVELER TSTF-523 (TAC NOS. MF4436-MF4446)
Dear Mr. Hanson:
The U.S. Nuclear Regulatory Commission (NRC) issued the following amendments on June 19, 2015 (Agencywide Documents Access and Management System Accession No. ML15114A188):
- 1. Amendment No. 183 to Facility Operating License No. NPF-72 and Amendment No. 183 to Facility Operating License No. NPF 77 for the Braidwood Station, Units 1 and 2, respectively;
- 2. Amendment No. 189 to Facility Operating License No. NPF-37 and Amendment No. 189 to Facility Operating License No. NPF-66 for the Byron Station, Unit Nos. 1 and 2, respectively; and
- 3. Amendment No. 257 to Renewed Facility Operating License No. DPR 29 and Amendment No. 252 to Renewed Facility Operating License No. DPR-30 for the Quad Cities Nuclear Power Station, Units 1 and 2, respectively.
The amendments revised the technical specifications (TSs) to adopt Technical Specification Task Force (TSTF) Traveler TSTF-523, Revision 2, "Generic Letter 2008-01, Managing Gas Accumulation," dated February 21, 2013. The revised TS pages were provided when the amendments were issued, except as follows:
- 1. TS page 3.4. 7-3 for Braidwood Station, Units 1 and 2,
- 2. TS pages 3.4.7-3, 3.6.6-3, and 3.9.6-2 for Byron Station, Unit Nos. 1 and 2, and
- 3. TS page 3.4.8-2 for Quad Cities Nuclear Power Station, Units 1 and 2.
The NRC staff has determined that these pages were erroneously omitted and should have been issued with the amendments. The omitted TS pages are enclosed.
If you have any questions, please contact me at 301-415-1380.
Docket Nos. STN 50-456, STN 50-457, STN 50-454,STN 50-455, 50-254, and 50-265
Enclosure:
- 1. Braidwood Station, Units 1 and 2, Replacement TS Pages
- 2. Byron Station, Unit Nos. 1 and 2, Replacement TS Pages Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- 3. Quad Cities Nuclear Power Station, Units 1 and 2, Replacement TS Pages cc w/encls: Listserv
BRAIDWOOD STATION, UNITS 1 AND 2 REPLACEMENT TECHNICAL SPEFICATION PAGES LICENSE AMENDMENT NOS. 183 AND 183 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the technical specifications with the attached revised pages.
The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove TS Page 3.4.7-3 Insert TS Page 3.4.7-3
RCS Loops-MODE 5, Loops Filled 3.4. 7 ACTIONS (continued)
CONDITION REQUIRED ACTION D.
Two required RHR loops D.1 Suspend all inoperable.
operations involving a reduction of RCS OR boron concentration.
Required RHR loop AND inoperable and one or both required SG D.2.1 Initiate action to secondary side water restore one RHR loop level Cs) not within to OPERABLE status.
limits.
OR D.2.2 Initiate action to restore required SG secondary side water level Cs) to within limits.
SURVEILLANCE REQUIREMENTS SR 3.4.7.1 SR 3.4. 7.2 SR 3.4.7.3 SURVEILLANCE Verify required RHR loop is in operation.
Verify SG secondary side narrow range water level is ~ 18% in required SGs.
Verify correct breaker alignment and indicated power are available to each required RHR pump that is not in operation.
BRAIDWOOD - UNITS 1 & 2 3.4.7 - 3 COMPLETION TIME Immediately Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Amendment No. 183
BYRON STATION, UNIT NOS. 1 AND 2 REPLACEMENT TECHNICAL SPEFICATION PAGES LICENSE AMENDMENT NOS. 189 AND 189 FACILITY OPERATING LICENSE NOS. NPF-37 AND NPF-66 DOCKET NOS. STN 50-454 AND STN 50-455 Replace the following pages of the technical specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove TS Page 3.4.7-3 3.6.6-3 3.9.6-2 Insert TS Page 3.4.7-3 3.6.6-3 3.9.6-2
RCS Loops-MODE 5, Loops Filled 3.4. 7 ACTIONS (continued)
CONDITION REQUIRED ACTION D.
Two required RHR loops D.1 Suspend all inoperable.
operations involving a reduction of RCS OR boron concentration.
Required RHR loop inoperable and one or AND both required SG D.2.1 Initiate action to secondary side water restore one RHR loop level Cs) not within to OPERABLE status.
limits.
OR D.2.2 Initiate action to restore required SG secondary side water level(s) to within limits.
SURVEILLANCE REQUIREMENTS SR 3.4.7.1 SR 3.4.7.2 SR 3.4. 7.3 SURVEILLANCE Verify required RHR loop is in operation.
Verify SG secondary side narrow range water level is~ 18% in required SGs.
Verify correct breaker alignment and indicated power are available to each required RHR pump that is not in operation.
BYRON - UNITS 1 & 2 3.4.7-3 COMPLETION TIME Immediately Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Amendment No. 189
Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.6.3 Verify each containment cooling train In accordance cooling water flow rate is~ 2660 gpm to with the each cooler.
Surveillance Frequency Control Program SR 3.6.6.4 Verify each containment spray pump's In accordance developed head at the flow test point is with the greater than or equal to the required Inservice developed head.
Testing Program SR 3.6.6.5 Verify each automatic containment spray In accordance valve in the flow path that is not locked, with the sealed, or otherwise secured in position, Surveillance actuates to the correct position on an Frequency actual or simulated actuation signal.
Control Program SR 3.6.6.6 Verify each containment spray pump starts In accordance automatically on an actual or simulated with the actuation signal.
Surveillance Frequency Control Program SR 3.6.6.7 Verify each containment cooling train In accordance starts automatically on an actual or with the simulated actuation signal.
Surveillance Frequency Control Program SR 3.6.6.8 Verify each spray nozzle is unobstructed.
Foll owing maintenance that could result in nozzle blockage OR Following fluid fl ow through the nozzles (cont rnued) I BYRON - UNITS 1 & 2 3.6.6 - 3 Amendment No. 189
RHR and Coolant Circulation-Low Water Level 3.9.6 ACTIONS (continued)
CONDITION REQUIRED ACTION B.
No RHR loop in operation.
B.1 Suspend operations involving a reduction in reactor coolant boron concentration.
AND B.2 Initiate action to restore one RHR loop to operation.
AND B.3 Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.
SURVEILLANCE REQUIREMENTS SR 3.9.6.1 SR 3.9.6.2 SURVEILLANCE Verify one RHR loop is in operation and circulating reactor coolant at a flow rate of ~ 1000 gpm.
Verify correct breaker alignment and indicated power available to the required RHR pump that is not in operation.
BYRON - UNITS 1 & 2 3.9.6 - 2 COMPLETION TIME Immediately Immediately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Amendment No. 189
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 REPLACEMENT TECHNICAL SPEFICATION PAGES LICENSE AMENDMENT NOS. 257 AND 252 RENEWED FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the technical specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove TS Page 3.4.8-2 Insert TS Page 3.4.8-2
RHR Shutdown Cooling System-Cold Shutdown 3.4.8 ACTIONS CONDITION REQUIRED ACTION A.
(continued)
A.2
NOTE--------
Onl y appl i cable if both RHR shutdown cooling subsystems are inoperable.
Verify reactor coolant circulating by an alternate method.
A.3
NOTE--------
Only applicable if both RHR shutdown cooling subsystems are inoperable.
Monitor reactor coolant temperature and pressure.
SURVEILLANCE REQUIREMENTS SR 3.4.8.1 SURVEILLANCE Verify each RHR shutdown cooling subsystem manual and power operated valve in the flow path, that is not locked, sealed or otherwise secured in position, is in the correct position or can be aligned to the correct position.
Quad Cities 1 and 2 3.4.8-2 COMPLETION TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter Once per hour FREQUENCY In accordance with the Surveillance Frequency Control Program (continued) I Amendment No. 257/252
If you have any questions, please contact me at 301-415-1380.
Docket Nos. STN 50-456, STN 50-457, STN 50-454,STN 50-455, 50-254, and 50-265
Enclosure:
- 1. Braidwood Station, Units 1 and 2, Replacement TS Pages
- 2. Byron Station, Unit Nos. 1 and 2, Replacement TS Pages Sincerely, IRA!
Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
- 3. Quad Cities Nuclear Power Station, Units 1 and 2, Replacement TS Pages cc w/encls: Listserv DISTRIBUTION:
PUBLIC RidsNrrDorllp13-2 Resource RidsNrrLASRohrer Resource RidsNrrDorlDpr Resource RidsNrrPMExelon Resource RidsAcrsAcnw_MailCTR Resource Accession No. ML15268A486 OFFICE LPL3-2/PM LPL3-2/LA NAME BPurnell SRohrer DATE 10/5/15 9/28/15 LPL3-2 R/F RidsNrrPMBraidwood Resource RidsNrrPMByron Resource RidsNrrPMQuadCities Resource RidsRgn3MailCenter Resource RecordsAmend Resource LPL3-2/BC LPL3-2/PM TTate BPurnell 10/5/15 10/6/15 OFFICIAL RECORD COPY