ML15268A486

Correction of Amendments Adopting Technical Specification Task Force Traveler TSTF-523 (TAC Nos. MF4436-MF4446)

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 6, 2015 Mr. Bryan C. Hanson Senior Vice President 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.

B. Hanson If you have any questions, please contact me at 301-415-1380.

Blake Purnell, Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 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

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 Insert TS Page 3.4.7-3 3.4.7-3 Enclosure 1

RCS Loops-MODE 5, Loops Filled 3.4. 7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two required RHR loops D.1 Suspend all Immediately 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 Immediately secondary side water restore one RHR loop level Cs) not within to OPERABLE status.

limits.

OR D.2.2 Initiate action to Immediately restore required SG secondary side water level Cs) to within limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required RHR loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4. 7.2 Verify SG secondary side narrow range water In accordance level is ~ 18% in required SGs. with the Surveillance Frequency Control Program SR 3.4.7.3 Verify correct breaker alignment and In accordance indicated power are available to each with the required RHR pump that is not in operation. Surveillance Frequency Control Program (continued)

BRAIDWOOD - UNITS 1 & 2 3.4.7 - 3 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 Insert TS Page 3.4.7-3 3.4.7-3 3.6.6-3 3.6.6-3 3.9.6-2 3.9.6-2 Enclosure 2

RCS Loops-MODE 5, Loops Filled 3.4. 7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two required RHR loops D.1 Suspend all Immediately 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 Immediately secondary side water restore one RHR loop level Cs) not within to OPERABLE status.

limits.

OR D.2.2 Initiate action to Immediately restore required SG secondary side water level(s) to within limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify required RHR loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.7.2 Verify SG secondary side narrow range water In accordance level is~ 18% in required SGs. with the Surveillance Frequency Control Program SR 3.4. 7 .3 Verify correct breaker alignment and In accordance indicated power are available to each with the required RHR pump that is not in operation. Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.4.7-3 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 COMPLETION TIME B. No RHR loop in B.1 Suspend operations Immediately operation. involving a reduction in reactor coolant boron concentration.

AND B.2 Initiate action to Immediately restore one RHR loop to operation.

AND B.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and In accordance circulating reactor coolant at a flow rate with the of ~ 1000 gpm. Surveillance Frequency Control Program SR 3.9.6.2 Verify correct breaker alignment and In accordance indicated power available to the required with the RHR pump that is not in operation. Surveillance Frequency Control Program (continued)

BYRON - UNITS 1 &2 3.9.6 - 2 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 Insert TS Page 3.4.8-2 3.4.8-2 Enclosure 3

RHR Shutdown Cooling System-Cold Shutdown 3.4.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ---------NOTE--------

Onl y appl i cable i f both RHR shutdown cooling subsystems are inoperable.

Verify reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> coolant circulating by an alternate method.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter A.3 ---------NOTE--------

Only applicable if both RHR shutdown cooling subsystems are inoperable.

Monitor reactor Once per hour coolant temperature and pressure.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify each RHR shutdown cooling subsystem In accordance manual and power operated valve in the flow with the path, that is not locked, sealed or Surveillance otherwise secured in position, is in the Frequency correct position or can be aligned to the Control Program correct position.

(continued) I Quad Cities 1 and 2 3.4.8-2 Amendment No. 257/252

B. Hanson If you have any questions, please contact me at 301-415-1380.

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 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

3. Quad Cities Nuclear Power Station, Units 1 and 2, Replacement TS Pages cc w/encls: Listserv DISTRIBUTION:

PUBLIC LPL3-2 R/F RidsNrrDorllp13-2 Resource RidsNrrPMBraidwood Resource RidsNrrLASRohrer Resource RidsNrrPMByron Resource RidsNrrDorlDpr Resource RidsNrrPMQuadCities Resource RidsNrrPMExelon Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR Resource RecordsAmend Resource Accession No. ML15268A486 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC LPL3-2/PM NAME BPurnell SRohrer TTate BPurnell DATE 10/5/15 9/28/15 10/5/15 10/6/15 OFFICIAL RECORD COPY