ML13312A123

Selected Licensee Commitment Technical Specifications Bases (Tsb)

ML13312A123
Person / Time
Site:	Mcguire, McGuire
Issue date:	11/04/2013
From:	Beaver B Duke Energy Carolinas
To:	Office of Nuclear Reactor Regulation
References
DUK133080047
Download: ML13312A123 (8)

Text

DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS Date: 11104113 PRIORITY Normal OTHERWISE IDENTIFIED BELOW Document Transmittal #: DUK133080047

1) 02361 QATS-MG01MM

2) 02388 BOB SCHOMAKER LYNCHBG, VA Duke Energy QA CONDITION [ Yes

• No

3) 02532 RESIDENT NRC INSPECT MG01NRC OTHER ACKNOWLEDGEMENT REQUIRED 0 Yes DOCUMENT TRANSMITTAL FORM

4) 03044 MCG DOC CNTRL MISC MAN MG05DM IFQA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE

5) 03614 MCG OPS PROCEDURE GP MG01OP ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

REFERENCE

6) 03744 OPS TRNG MGR. MG03OT

7) 03759 U S NUC REG WASHINGTON, DC MCGUIRE NUCLEAR STATION Duke Energy

8) 03796 SCIENTECH CLEARWTR, FL McGuire

9) 04698 D E BORTZ EC07R DCRM MGO2DM TECHNICAL SPECIFICATIONS (TS)

10) 04809 MCG PLANT ENG. UBR. MG05SE 13225 Hagers Ferry Road TECHNICAL SPECIFICATIONS BASES Huntersville, N.C. 28078

11) 05262 J LFREEZE MG01IE

12) 05606 J C MORTON MG01EP (TSB)

13) 08103 WESTINGHOUSE ELECTRIC CO LLC

14) 09665 JON HTHOMPSON, USNRC RECORD RETENTION #421734 Rec'd By Page 2 of 2 Date DOCUMENT NO QACOND REV #/ DATE DISTR CODE 1 3 4 5 6 7 B8 99 10 110 11 11 12 12 I11313 14 14

'15 15 IUIAL 1TOTAL TSB 3.7.8 (ENTIRE SECTION) NA 128 10/14/13 tv MADM-04B V1 Vi x V1 V3 V1 V1 vi iV1 vi i 29 V1 V1 V1 29 REMARKS: PLEASE SEE MEMORANDUM DATED OCTOBER 14, 2013 & UPDATE TSB LOES S D CAPPS REVISION 117 VICE PRESIDENT MCGUIRE NUCLEAR STATION BY:

BC BEAVER MG01RC BCB/BRG

WOctober 14, 2013 MEMORANDUM To: All McGuire Nuclear Station Technical Specification (TS) and Tech Spec Bases (TSB) Manual Holders

Subject:

McGuire TSB Updates REMOVE INSERT TS Bases Manual TSB LOES (Entire Section) TSB LOES (Revision 117)

TSB 3.7.8 (Entire Section) TSB 3.7.8 (Entire Section) Rev 128 Revision numbers may skip numbers due to Regulatory Compliance Filing System.

Please call me if you have questions.

Bonnie Beaver Regulatory Compliance 875-4180

McGuire Nuclear Station Technical Specification Bases LOES TS Bases are revised by section Page Number Revision Revision Date BASES (Revised per section) i Revision 87 8/15/07 ii Revision 87 8/15/07 iii Revision 87 8/15/07 B 2.1.1 Revision 51 01/14/04 B 2.1.2 Revision 109 9/20/10 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 115 3/29/11 B 3.1.2 Revision 115 3/29/11 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 115 3/29/11 B 3.1.5 Revision 115 3/29/11 B 3.1.6 Revision 115 3/29/11 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 115 3/29/11 B 3.2.1 Revision 115 3/29/11 B 3.2.2 Revision 115 3/29/11 B 3.2.3 Revision 115 3/29/11 B 3.2.4 Revision 115 3/29/11 B 3.3.1 Revision 124 10/1/12 B 3.3.2 Revision 122 10/25/12 B 3.3.3 Revision 122 10/25/12 B 3.3.4 Revision 115 3/29/11 B 3.3.5 Revision 115 3/29/11 B 3.3.6 Not Used - Revision 87 6/29/06 B 3.4.1 Revision 115 3/29/11 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 115 3/29/11 B 3.4.4 Revision 115 3/29/11 B 3.4.5 Revision 115 3/29/11 McGuire Units I and 2 Page 1 Revisio n 117

Page Number Amendment Revision Date B 3.4.6 Revision 115 3/29/11 B 3.4.7 Revision 115 3/29/11 B 3.4.8 Revision 115 3/29/11 B 3.4.9 Revision 115 3/29/11 B 3.4.10 Revision 102 8/17/09 B 3.4.11 Revision 115 3/29/11 B 3.4.12 Revision 115 3/29/11 B 3.4.13 Revision 126 5/1/13 B 3.4.14 Revision 115 3/29/11 B 3.4.15 Revision 115 3/29/11 B 3.4.16 Revision 121 8/5/09 B 3.4.17 Revision 115 3/29/11 B 3.4.18 Revision 86 6/25/07 B 3.5.1 Revision 115 3/29/11 B 3.5.2 Revision 116 8/18/11 B 3.5.3 Revision 57 4/29/04 B 3.5.4 Revision 122 10/25/12 B 3.5.5 Revision 115 3/29/11 B 3.6.1 Revision 53 2/17/04 B 3.6.2 Revision 115 3/29/11 B 3.6.3 Revision 115 3/29/11 B 3.6.4 Revision 115 3/29/11 B 3.6.5 Revision 115 3/29/11 B 3.6.6 Revision 122 10/25/12 B 3.6.7 Not Used - Revision 63 4/4/05 B 3.6.8 Revision 115 3/29/11 B 3.6.9 Revision 115 3/29/11 B 3.6.10 Revision 120 4/26/12 B 3.6.11 Revision 122 10/25/12 B 3.6.12 Revision 115 3/29/11 B 3.6.13 Revision 115 3/29/11 B 3.6.14 Revision 115 3/29/11 B 3.6.15 Revision 125 10/19/12 B 3.6.16 Revision 115 3/29/11 McGuire Units 1 and 2 Page 2 Revision 117

Page Number Amendment Revision Date B 3.7.1 Revision 102 8/17/09 B 3.7.2 Revision 105 2/22/10 B 3.7.3 Revision 102 8/17/09 B 3.7.4 Revision 115 3/29/11 B 3.7.5 Revision 115 3/29/11 B 3.7.6 Revision 127 8/2/13 B 3.7.7 Revision 115 3/29/11 B 3.7.8 Revision 128 10/2/13 B 3.7.9 Revision 120 4/26/12 B 3.7.10 Revision 115 3/29/11 B 3.7.11 Revision 115 3/29/11 B 3.7.12 Revision 115 3/29/11 B 3.7.13 Revision 115 3/29/11 B 3.7.14 Revision 115 3/29/11 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 115 3/29/11 B 3.8.1 Revision 115 3/29/11 B 3.8.2 Revision 92 1/28/08 B 3.8.3 Revision 123 9/29/12 B 3.8.4 Revision 115 3/29/11 B 3.8.5 Revision 41 7/29/03 B 3.8.6 Revision 115 3/29/11 B 3.8.7 Revision 115 3/29/11 B 3.8.8 Revision 115 3/29/11 B 3.8.9 Revision 115 3/29/11 B 3.8.10 Revision 115 3/29/11 B 3.9.1 Revision 115 3/29/11 B 3.9.2 Revision 115 3/29/11 B 3.9.3 Revision 115 3/29/11 B 3.9.4 Revision 115 3/29/11 B 3.9.5 Revision 115 3/29/11 B 3.9.6 Revision 115 3/29/11 B 3.9.7 Revision 115 3/29/11 McGuire Units 1 and 2 Page 3 Revision 117

SNSWP B 3.7.8 B 3.7 PLANT SYSTEMS B 3.7.8 Standby Nuclear Service Water Pond (SNSWP)

BASES BACKGROUND The SNSWP functions as the ultimate heat sink and performs two principal safety functions: (1) dissipation of residual heat after reactor shutdown and (2) dissipation of residual heat after an accident. This is done by utilizing the Nuclear Service Water System (NSWS) and the Component Cooling Water (CCW) System.

The ultimate heat sink (UHS) is comprised of cooling water from the SNSWP, necessary retaining structures, and the canals or conduits connecting the water sources with, but not including, the cooling water system intake structures as discussed in the UFSAR, Section 9.2 (Ref. 1).

For McGuire, the SNSWP is the only cooling water source qualified as the ultimate heat sink.

The SNSWP can be aligned to dissipate sensible heat during normal operation. The basic performance requirements are that a 30 day supply of water be available, and that the design basis temperatures of safety related equipment not be exceeded.

Additional information on the design and operation of the system, along with a list of components served, can be found in Reference 1.

APPLICABLE The SNSWP provides the Ultimate Heat Sink safety function to dissipate SAFETY ANALYSES residual heat from the reactor core following all accidents and anticipated operational occurrences in which the unit is cooled down and placed on residual heat removal (RHR) operation. The maximum post accident heat load occurs approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after a design basis loss of coolant accident (LOCA). Prior to this time, the unit switches from injection to recirculation and the containment cooling systems and RHR are required to remove the core decay heat.

The SNSWP is designed in accordance with Regulatory Guide 1.27 (Ref.

2), which requires a 30 day supply of cooling water in the SNSWP.

Reference 1 provides the details of the assumptions used in the analysis.

The SNSWP satisfies Criterion 3 of 10 CFR 50.36 (Ref. 3).

McGuire Units 1 and 2 B 3.7.8-1 Revision No. 128

SNSWP B 3.7.8 BASES LCO The SNSWP is required to be OPERABLE and is considered OPERABLE if it contains a sufficient volume of water at or below the maximum temperature that would allow the NSWS to operate for at least 30 days following the design basis LOCA without the loss of net positive suction head (NPSH), and without exceeding the maximum design temperature of the equipment served by the NSWS. To meet this condition, the SNSWP temperature should not exceed 82 0 F at 722 ft mean sea level and the level should not fall below 739.5 ft mean sea level during normal unit operation.

APPLICABILITY In MODES 1, 2, 3, and 4, the SNSWP is required to support the OPERABILITY of the equipment serviced by the SNSWP and required to be OPERABLE in these MODES.

In MODE 5 or 6, the requirements of the SNSWP are determined by the systems it supports.

ACTIONS A.1 If the SNSWP is inoperable the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

SURVEILLANCE SR 3.7.8.1 REQUIREMENTS This SR verifies that adequate long term (30 day) cooling can be maintained. The specified level also ensures that sufficient NPSH is available to operate the NSWS pumps. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. This SR verifies that the SNSWP water level is _>739.5 ft mean sea level.

McGuire Units 1 and 2 B 3.7.8-2 Revision No. 128

SNSWP B 3.7.8 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.7.8.2 This SR verifies that the NSWS is available to cool the CCW System to at least its maximum design temperature with the maximum accident or normal design heat loads for 30 days following a Design Basis Accident.

The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program. This SR verifies that the average water temperature of the SNSWP is < 82 0 F at an elevation of 722 ft. The SR is modified by a Note that states the Surveillance is only required to be performed during the months of July, August, and September. During other months, the ambient temperature is below the surveillance limit.

SR 3.7.8.3 This SR verifies dam integrity by inspection to detect degradation, erosion, or excessive seepage. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.

REFERENCES 1. UFSAR, Section 9.2.

2. Regulatory Guide 1.27.

3. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).

4. Regulatory Guide 1.127.

McGuire Units 1 and 2 B 3.7.8-3 Revision No. 128