CNS-15-021, Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program.

Technical Specification Bases Changes Made According to the Provisions of Technical Specification 5.5.14, Technical Specifications (TS) Bases Control Program.

ML15070A533
Person / Time
Site:	Catawba
Issue date:	03/09/2015
From:	Henderson K Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNS-15-021
Download: ML15070A533 (13)

Text

Kelvin Henderson u

4n DUKE ENERGY.

Vice President

,~, ero Catawba Nuclear Station Duke Energy CNOIVP 1 4800 Concord Road York, SC 29745 o: 803.701.4251 CNS-15-021 f: 803.701.3221 March 9, 2015 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Technical Specification Bases Changes Pursuant to 10CFR 50.4, please find attached changes to the Catawba Nuclear Station Technical Specification Bases. These Bases changes were made according to the provisions of Technical Specification 5.5.14, "Technical Specifications (TS) Bases Control Program."

Any questions regarding this information should be directed to Larry Rudy, Regulatory Affairs, at (803) 701-3084.

I certify that I am a duly authorized officer of Duke Energy Carolinas, LLC, and that the information contained herein accurately represents changes made to the Technical Specification Bases since the previous submittal.

Kelvin Henderson Vice President, Catawba Nuclear Station Attachment www.duke-energy.com

U.S. Nuclear Regulatory Commission March 9, 2015 Page 2 xc: V. M. McCree, Regional Administrator U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Mr. G.E. Miller NRC Project Manager (CNS)

U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop O-8G9A 11555 Rockville Pike Rockville, MD 20852-2746 G. A. Hutto, Senior Resident Inspector Catawba Nuclear Station

Catawba Nuclear Station

~ENERGY, Duke Energy CNO1VP 1 4800 Concord Road York, SC 29745 March 9, 2015 Re: Catawba Nuclear Station Technical Specifications Bases Please replace the corresponding pages in your copy of the Catawba Technical Specifications Manual as follows:

REMOVE THESE PAGES INSERT THESE PAGES LIST OF EFFECTIVE PAGES Entire Bases Section (pages 13 - 19) Entire Bases Section (pages 13 - 19)

TAB 3.4.7 B 3.4.7-1 thru B 3.4.7-5 B 3.4.7-1 thru B 3.4.7-5 Revision 5 Revision 6 If you have any questions concerning the contents of this Technical Specification update, contact Kristi Byers at (803)701-3758.

Interim Regulatory Affairs Manager www.duke-energy.com

BASES Revision 1 4/08/99 ii Revision 2 3/01/05 iii Revision 1 6/21/04 B 2.1.1-1 Revision 0 9/30/98 B 2.1.1-2 Revision 1 12/19/03 B 2.1.1-3 Revision 1 12/19/03 B 2.1.2-1 Revision 0 9/30/98 B 2.1.2-2 Revision 0 9/30/98 B 2.1.2-3 Revision 0 9/30/98 B 3.0-1 Revision 1 3/19/07 B 3.0-2 Revision 1 3/19/07 B 3.0-3 Revision 2 3/19/07 B 3.0-4 Revision 3 3/19/07 B 3.0-5 Revision 3 3/19/07 B 3.0-6 Revision 2 3/19/07 B 3.0-7 Revision 2 3/19/07 B 3.0-8 Revision 3 3/19/07 B 3.0-9 Revision 2 3/19/07 B 3.0-10 Revision 3 3/19/07 B 3.0-11 Revision 3 3/19/07 B 3.0-12 Revision 3 3/19/07 B 3.0-13 Revision 3 3/19/07 B 3.0-14 Revision 3 3/19/07 B 3.0-15 Revision 1 3/19/07 B 3.0-16 Revision 1 3/19/07 B 3.0-17 Revision 0 3/19/07 B 3.0-18 Revision 0 3/19/07 B 3.0-19 Revision 0 3/19/07 B 3.1.1-1 thru Revision 3 5/05/11 B 3.1.1-6 Catawba Units 1 and 2 Page 13 02/26/15

B 3.1.2-1 thru Revision 2 5/05/11 B 3.1.2-5 B 3.1.3-1 Revision 4/26/00 B 3.1.3-2 Revision 4/26/00 B 3.1.3-3 Revision 4/26/00 B 3.1.3-4 Revision 4/26/00 B 3.1.3-5 Revision 4/26/00 B 3.1.3-6 Revision 4/26/00 B 3.1.4-1 thru Revision 5/05/11 B 3.1.4-9 B 3.1.5-1 thru Revision 2 5/05/11 B 3.1.5-4 B 3.1.6-1 thru Revision 1 5/05/11 B 3.1.6-6 B 3.1.7-1 Revision 0 9/30/98 B 3.1.7-2 Revision 2 1/08/04 B 3.1.7-3 Revision 2 1/08/04 B 3.1.7-4 Revision 2 1/08/04 B 3.1.7-5 Revision 2 1/08/04 B 3.1.7-6 Revision 2 1/08/04 B 3.1.8-1 thru Revision 2 5/05/11 B 3.1.8-6 B 3.2.1-1 thru Revision 4 5/05/11 B 3.2.1.-11 B 3.2.2-1 thru Revision 3 5/05/11 B 3.2.2-10 B 3.2.3-1 thru Revision 2 5/05/11 B 3.2.3-4 B 3.2.4-1 thru Revision 2 5/05/11 B 3.2.4-7 B 3.3.1-1 thru Revision 7 11/15/11 B.3.3.1-55 B 3.3.2-1 thru Revision 10 5/05/11 B 3.3.2-49 B 3.3.3-1 thru Revision 6 4/11/14 B.3.3.3-16 B 3.3.4-1 thru Revision 2 5/05/11 B 3.3.4-5 Catawba Units 1 and 2 Page 14 02/26/15

B 3.3.5-1 thru Revision 2 5/05/11 B 3.3.5-6 B 3.3.6-1 thru Revision 6 08/02/12 B 3.3.6-5 B 3.3.9-1 thru Revision 3 06/02/14 B 3.3.9-5 B 3.4.1-1 thru Revision 3 5/05/11 B 3.4.1-5 B 3.4.2-1 Revision 0 9/30/98 B 3.4.2-2 Revision 0 9/30/98 B 3.4.2-3 Revision 0 9/30/98 B 3.4.3-1 thru Revision 2 5/05/11 B 3.4.3-6 B 3.4.4-1 thru Revision 2 5/05/11 B 3.4.4-3 B 3.4.5-1 thru Revision 3 5/05/11 B 3.4.5-6 B 3.4.6-1 thru Revision 4 5/05/11 B 3.4.6-5 B 3.4.7-1 thru Revision 6 2/10/15 B 3.4.7-5 B 3.4.8-1 thru Revision 3 5/05/11 B 3.4.8-3 B 3.4.9-1 thru Revision 3 08/02/12 B 3.4.9-5 B 3.4.10-1 Revision 1 3/4/04 B 3.4.10-2 Revision 0 9/30/98 B 3.4.10-3 Revision 1 3/4/04 B 3.4.10-4 Revision 2 10/30/09 B 3.4.11-1 thru Revision 4 5/05/11 B 3.4.11-7 B 3.4.12-1 thru Revision 4 5/05/11 B 3.4.12-13 B 3.4.13-1 thru Revision 7 3/15/12 B 3.4.13-7 B 3.4.14-1 thru Revision 3 5/05/11 B 3.4.14-6 B 3.4.15-1 thru Revision 6 5/05/11 B 3.4.15-10 Catawba Units 1 and 2 Page v

15

B 3.4.16-1 thru Revision 4 10/23/12 B 3.4.16-5 B 3.4.17-1 thru Revision 2 5/05/11 B 3.4.17-3 B 3.4.18-1 Revision 0 1/13/05 B 3.4.18-2 Revision 0 1/13/05 B 3.4.18-3 Revision 1 3/18/08 B 3.4.18-4 Revision 0 1/13/05 B 3.4.18-5 Revision 0 1/13/05 B 3.4.18-6 Revision 0 1/13/05 B 3.4.18-7 Revision 0 1/13/05 B 3.4.18-8 Revision 1 3/18/08 B 3.5.1-1 thru Revision 3 5/05/11 B 3.5.1-8 B 3.5.2-1 thru Revision 3 5/05/11 B 3.5.2-10 B 3.5.3-1 Revision 0 9/30/98 B 3.5.3-2 Revision 5 4/29/04 B 3.5.3-3 Revision 1 4/29/04 B 3.5.4-1 thru Revision 5 4/11/14 B.3.5.4-5 B 3.5.5-1 thru Revision 1 5/05/11 B 3.5.5-4 B 3.6.1-1 Revision 1 7/31/01 B 3.6.1-2 Revision 1 7/31/01 B 3.6.1-3 Revision 1 7/31/01 B 3.6.1-4 Revision 1 7/31/01 B 3.6.1-5 Revision 1 7/31/01 B 3.6.2-1 thru Revision 2 5/05/11 B 3.6.2-8 B 3.6.3-1 thru Revision 4 5/05/11 B 3.6.3-14 B 3.6.4-1 thru Revision 2 5/05/11 B 3.6.4-4 B 3.6.5-1 thru Revision 3 07/27/13 B 3.6.5-4 Catawba Units 1 and 2 Page 16 02/26/15

B 3.6.6-1 thru Revision 6 5/05/11 B 3.6.6-7 B 3.6.8-1 thru Revision 3 5/05/11 B 3.6.8-5 B 3.6.9-1 thru Revision 6 5/05/11 B 3.6.9-5 B 3.6.10-1 thru Revision 2 5/05/11 B 3.6.10-6 B 3.6.11-1 thru Revision 5 5/05/11 B 3.6.11-6 B 3.6.12-1 thru Revision 5 5/05/11 B 3.6.12-11 B 3.6.13-1 thru Revision 4 5/05/11 B 3.6.13-9 B 3.6.14-1 thru Revision 2 4/11/14 B 3.6.14-5 B 3.6.15-1 thru Revision 1 5/05/11 B 3.6.15-4 B 3.6.16-1 thru Revision 3 5/05/11 B 3.6.16-4 B 3.6.17-1 Revision 1 3/13/08 B 3.6.17-2 Revision 0 9/30/98 B 3.6.17-3 Revision 0 9/30/98 B 3.6.17-4 Revision 0 9/30/98 B 3.6.17-5 Revision 1 3/13/08 B 3.7.1-1 Revision 0 9/30/98 B 3.7.1-2 Revision 0 9/30/98 B 3.7.1-3 Revision 0 9/30/98 B 3.7.1-4 Revision 1 10/30/09 B 3.7.1-5 Revision 1 10/30/09 B 3.7.2-1 Revision 0 9/30/98 B 3.7.2-2 Revision 0 9/30/98 B 3.7.2-3 Revision 2 6/23/10 B 3.7.2-4 Revision 1 9/08/08 B 3.7.2-5 Revision 3 10/30/09 B 3.7.3-1 Revision 0 9/30/98 B 3.7.3-2 Revision 0 9/30/98 Catawba Units 1 and 2 Page 17 02/26/15

B 3.7.3-3 Revision 0 9/30/98 B 3.7.3-4 Revision 0 9/30/98 B 3.7.3-5 Revision 1 9/08/08 B 3.7.3-6 Revision 2 10/30/09 B 3.7.4-1 thru Revision 2 5/05/11 B 3.7.4-4 B 3.7.5-1 thru Revision 3 5/05/11 B 3.7.5-9 B 3.7.6-1 thru Revision 4 08/02/12 B 3.7.6-3 B 3.7.7-1 thru Revision 2 5/05/11 B 3.7.7-5 B 3.7.8-1 thru Revision 5 08/09/13 B 3.7.8-8 B 3.7.9-1 thru Revision 3 5/05/11 B 3.7.9-4 B 3.7.10-1 thru Revision 10 10/24/11 B 3.7.10-9 B 3.7.11-1 thru Revision 3 10/24/11 B 3.7.11-4 B 3.7.12-1 thru Revision 6 1/09/13 B 3.7.12-7 B 3.7.13-1 thru Revision 4 5/05/11 B 3.7.13-5 B 3.7.14-1 thru Revision 2 5/05/11 B 3.7.14-3 B 3.7.15-1 thru Revision 2 5/05/11 B 3.7.15-4 B 3.7.16-1 Revision 2 9/27/06 B 3.7.16-2 Revision 2 9/27/06 B 3.7.16-3 Revision 2 9/27/06 B 3.7.16-4 Revision 0 9/27/06 B 3.7.17-1 thru Revision 2 5/05/11 B 3.7.17-3 B 3.8.1-1 thru Revision 5 07/27/13 B.3.8.1-29 B 3.8.2-1 Revision 0 9/30/98 B 3.8.2-2 Revision 0 9/30/98 Catawba Units 1 and 2 Page 18 02/26/15

I B 3.8.2-3 Revision 0 9/30/98 B 3.8.2-4 Revision 1 5/10/05 B 3.8.2-5 Revision 2 5/10/05 B 3.8.2-6 Revision 1 5/10/05 B 3.8.3-1 thru Revision 4 5/05/11 B 3.8.3-8 B 3.8.4-1 thru Revision 10 5/05/11 B3.8.4.10 B 3.8.5-1 Revision 0 9/30/98 B 3.8.5-2 Revision 2 7/29/03 B 3.8.5-3 Revision 1 7/29/03 B 3.8.6-1 thru Revision 4 5/05/11 B 3.8.6-7 B 3.8.7-1 thru Revision 3 5/05/11 B 3.8.7-4 B 3.8.8-1 thru Revision 3 5/05/11 B 3.8.8-4 B 3.8.9-1 thru Revision 2 5/05/11 B 3.8.9-10 B 3.8.10-1 thru Revision 3 5/05/11 B 3.8.10-4 B 3.9.1-1 thru Revision 3 5/05/11 B 3.9.1-4 B 3.9.2-1 thru Revision 4 5/05/11 B 3.9.2.4 B 3.9.3-1 thru Revision 4 5/05/11 B 3.9.3-5 B 3.9.4-1 thru Revision 4 5/05/11 B 3.9.4-4 B 3.9.5-1 thru Revision 3 5/05/11 B 3.9.5-4 B 3.9.6-1 thru Revision 2 5/05/11 B 3.9.6-3 B 3.9.7-1 thru Revision 1 5/05/11 B 3.9.7-3 Catawba Units 1 and 2 Page 19 02/26/15

RCS Loops-MODE 5, Loops Filled B 3.4.7 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.7 RCS Loops-MODE 5, Loops Filled BASES BACKGROUND In MODE 5 with the RCS loops filled, the primary function of the reactor coolant is the removal of decay heat and transfer this heat either to the steam generator (SG) secondary side coolant or the component cooling water via the residual heat removal (RHR) heat exchangers. While the principal means for decay heat removal is via the RHR System, the SGs are specified as a backup means for redundancy. Even though the SGs cannot produce steam in this MODE, they are capable of being a heat sink due to their large contained volume of secondary water. As long as the SG secondary side water is at a lower temperature than the reactor coolant, heat transfer will occur. The rate of heat transfer is directly proportional to the temperature difference. The secondary function of the reactor coolant is to act as a carrier for soluble neutron poison, boric acid.

In MODE 5 with RCS loops filled, the reactor coolant is circulated by means of two RHR loops connected to the RCS, each loop containing an RHR heat exchanger, an RHR pump, and appropriate flow and temperature instrumentation for control, protection, and indication. One RHR pump circulates the water through the RCS at a sufficient rate to prevent boric acid stratification.

The number of loops in operation can vary to suit the operational needs.

The intent of this LCO is to provide forced flow from at least one RHR loop for decay heat removal and transport. The flow provided by one RHR loop is adequate for decay heat removal. The other intent of this LCO is to require that a second path be available to provide redundancy for heat removal.

The LCO provides for redundant paths of decay heat removal capability.

The first path can be an RHR loop that must be OPERABLE and in operation. The second path can be another OPERABLE RHR loop or maintaining two SGs with secondary side narrow range water levels >

12% to provide an alternate method for decay heat removal.

APPLICABLE In MODE 5, RCS circulation is considered in the determination of the time SAFETY ANALYSES available for mitigation of the accidental boron dilution event. The RHR loops provide this circulation.

RCS Loops-MODE 5 (Loops Filled) satisfy Criterion 4 of 10 CFR 50.36 (Ref. 1 ).

Catawba Units 1 and 2 B 3.4.7-1 Revision No. 6

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RCS Loops - MODE 5, Loops Filled B 3.4.7 BASES LCO (continued) the test, and operating experience has shown that boron stratification is not likely during this short period with no forced flow.

Utilization of Note 1 is permitted provided the following conditions are met, along with any other conditions imposed by initial startup test procedures:

a. No operations are permitted that would dilute the RCS boron concentration with coolant with boron concentrations less than required to meet SDM of LCO 3.1.1, therefore maintaining an adequate margin to criticality. Boron reduction with coolant at boron concentrations less than required to assure SDM is maintained is prohibited because a uniform concentration distribution throughout the RCS cannot be ensured when in natural circulation; and

b. Core outlet temperature is maintained at least 10°F below saturation temperature, so that no vapor bubble may form and possibly cause a natural circulation flow obstruction.

Note 2 allows one RHR loop to be inoperable for a period of up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, provided that the other RHR loop is OPERABLE and in operation. This permits periodic surveillance tests to be performed on the inoperable loop during the only time when such testing is safe and possible.

Note 3 requires that the secondary side water temperature of each SG be

< 50°F above each of the RCS cold leg temperatures before the start of an RCP with an RCS cold leg temperature < 210°F. This restriction is to prevent a low temperature overpressure event due to a thermal transient when an RCP is started.

Note 4 provides for an orderly transition from MODE 5 to MODE 4 during a planned heatup by permitting removal of RHR loops from operation when at least one RCS loop is in operation. This Note provides for the transition to MODE 4 where an RCS loop is permitted to be in operation and replaces the RCS circulation function provided by the RHR loops.

An OPERABLE RHR loop is comprised of an OPERABLE RHR pump capable of providing forced flow to an OPERABLE RHR heat exchanger.

If not in its normal RHR alignment from the RCS hot leg and returning to the RCS cold legs, the required RHR loop is OPERABLE provided the system may be placed in service from the control room, or may be placed in service in a short period of time by actions outside the control room and there are no restraints to placing the equipment in service. RHR pumps are OPERABLE if they are capable of being powered and are able to provide flow if required. SGs A or D can perform as OPERABLE heat sinks with adequate water level; SGs B or C can perform as OPERABLE heat sinks with adequate water level and at least one RCP in operation.

Catawba Units 1 and 2 B 3.4.7-3 Revision No. 6

RCS Loops - MODE 5, Loops Filled B 3.4.7 BASES SURVEILLANCE SR 3.4.7.1 REQUIREMENTS This SR requires verification that the required loop is in operation.

Verification includes flow rate, temperature, or pump status monitoring, which help ensure that forced flow is providing heat removal. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.

SR 3.4.7.2 Verifying that at least two SGs are OPERABLE by ensuring their secondary side narrow range water levels are >Ž12% ensures an alternate decay heat removal method in the event that the second RHR loop is not OPERABLE. The A and D SGs are OPERABLE with > 12% narrow range level. The B and C SGs are OPERABLE if narrow range levels are > 12%

and at least one RCP is in operation. If both RHR loops are OPERABLE, this Surveillance is not needed. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.

SR 3.4.7.3 Verification that a second RHR pump is OPERABLE ensures that an additional pump can be placed in operation, if needed, to maintain decay heat removal and reactor coolant circulation. Verification is performed by verifying proper breaker alignment and power available to the RHR pump.

If secondary side narrow range water level is Ž_12% in at least two SGs, this Surveillance is not needed. The A and D SGs are OPERABLE with >

12% narrow range level. The B and C SGs are OPERABLE if narrow range levels are > 12% and at least one RCP is in operation. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).

2. Problem Investigation Process M-00-02276.

Catawba Units 1 and 2 B 3.4.7-5 Revision No. 6