Text

Technical Specifications Bases
	ML080500142
Person / Time
Site:	McGuire, Mcguire
Issue date:	01/30/2008
From:	Beaver B; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	DUK080300030
	Download: ML080500142 (74)
	v • d • e

PRIORITY Normal DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW

1) 01623 G L MONTGOMERY MG01WC

2) 01749 L C GIBBY - MG01VP

3) 02049NGO PRA MANAGER EC08I

4) 02388 DAVID DZIADOSZ LYNCHBG. VA

5) 02532 MCG NRC INSP MG-ADMIN MAIL RM

6) 02546 WC LIBRARY - MG01WC

7) 03044 MCG DOC CNTRL MISC MAN MGO5DM

8) 03283 PR TUCKER MG01RP

9) 03614 MCG OPS PROCEDURE GP MG01OP

10) 03743 MCG QA TEC SUP MNT QC MG01MM

11) 03744 OPS TRNG MGR. MG03OT

12) 03759 U S NUC REG WASHINGTON, DC

6.

13) 03796 SCIENTECH DUNEDIN, FL

14) 04698 D EBORTZ EC08G

15) 04809 MCG PLANT ENG. LIBR. MG05SE Duke Energy DOCUMENT TRANSMITTAL FORM REFERENCE MCGUIRE NUCLEAR STATION RECORD RETENTION # 005893 Date:

01/30/08 Document Transmittal #:

DUK080300030 OA CONDITION

[] Yes

No OTHER ACKNOWLEDGEMENT REOUIRED N Yes IF GA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

Duke Energy McGuire DCRM MGO2DM 13225 Hagers Ferry Road Huntersville, NC.

28078 Rec'd By Date TECHI TECHI (TSB)

NICAL SPECIFICATIONS (TS)

AND NICAL SPECIFICATIONS BASES Page 2 of 3 DOCUMENT NO QA COND REV #/DATE DISTR CODE 1

ý2 3

4 5

6 7

8 9

10 11 12 13 14 115 TOTAL TSB LIST OF EFFECTIVE SECTIONS TSB 3.9.3 NA NA 088 01/23/08 091 11/07/07 MADM-04B V1 V1 V1 vi Vl Vl Vl Vl Vl V3 V8 Vl V1 V2 48

- _____________ 4 ____________________ 4 ______________________ ~

_____ 4. _____ L _____ 4 _____.J ______ L...............

.1.4...L.......L.........:

_____ I _____ A REMARKS: PLEASE UPDATE ACCORDINGLY RECIPIENT # 00422 PREVIOUSLY COMPLETED G R PETERSON VICE PRESIDENT MCGUIRE NUCLEAR STATION BY:

BCBEAVER MGO1RC 0

0 BCB/CMK

January 23, 2008 MEMORANDUM To: All McGuire Nuclear Station Technical Specification, and Technical Specification Bases (TSB)

Manual Holders

Subject:

McGuire Technical Specifications Bases REMOVE INSERT Technical Specification Bases Manual:

TS Bases List of Effected Sections Rev 87 TS Bases List of Effected Sections Rev 88 Tech Spec Bases: 3.9.3 Rev 41 (Entire Bases)

Tech Spec Bases 3.9.3 Rev 91 (Entire Bases)

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 63 4/4/05 ii Revision 63 4/4/05 iii Revision 63 5/25/05 B 2.1.1 Revision 51 1/14/04 B 2.1.2 Revision 0 9/30/98 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 73 3/6/06 B 3.1.2 Revision 10 9/22/00 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 0 9/30/98 B 3.1.5 Revision 19 1/10/02 B 3.1.6 Revision 0 9/30/98 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 0 9/30/98 B 3.2.1 Revision 74 5/3/06 B 3.2.2 Revision 10 9/22/00 B 3.2.3 Revision 34 10/1/02 B 3.2.4 Revision 10 9/22/00 B 3.3.1 Revision 90 10/30/07 B 3.3.2 Revision 62 1/27/05 B 3.3.3 Revision 71 10/12/05 B 3.3.4 Revision 57 4/29/04 B 3.3.5 Revision 11 9/18/00 B 3.3.6 Not Used - Revision 87 6/29/06 B 3.4.1 Revision 51 1/14/04 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 44 7/3/03 B 3.4.4 Revision 86 6/25/07 B 3.4.5 Revision 86 6/25/07 McGuire Units 1 and 2 Page I Revision 88

Page Number B 3.4.6 B 3.4.7 B 3.4.8 B 3.4.9 B 3.4.10 B 3.4.11 B 3.4.12 B 3.4.13 B 3.4.14 B 3.4.14-2 B 3.4.14-6 B 3.4.15 B 3.4.16 B 3.4.17 B 3.4.18 B 3.5.1 B 3.5.2 B 3.5.3 B 3.5.4 B 3.5.5 B 3.6.1 B 3.6.2 B 3.6.3 B 3.6.4 B 3.6.5 B 3.6.5-2 B 3.6.6 B 3.6.7 B 3.6.8 B 3.6.9 B 3.6.10 B 3.6.11 B 3.6.12 B 3.6.13 B 3.6.14 Amendment Revision Date Revision 86 Revision 86 Revision 41 Revision 0 Revision 0 Revision 57 Revision 57 Revision 86 Revision 0 Revision 5 Revision 5 Revision 82 Revision 57 Revision 0 Revision 86 Revision 70 Revision 45 Revision 57 Revision 70 Revision 0 Revision 53 Revision 32 Revision 87 Revision 0 Revision 0 Revision 6 Revision 93 Not Used - Revision 63 Revision 63 Revision 63 Revision 43 Revision 78 Revision 53 Revision 83 Revision 64 6/25/07 6/25/07 7/29/03 9/30/98 9/30/98 4/29/04 4/29/04 6/25/07 9/30/98 8/3/99 8/3/99 9/30/06 4/29/04 9/30/98 6/25/07 10/5/05 8/20/03 4/29/04 10/5/04 9/30/98 2/17/04 10/4/02 6/29/06 9/30/98 9/30/98 10/6/99 04/30/07 4/4/05 4/4/05 4/4/05 5/28/03 9/25/06 2/17/04 12/04/06 4/23/05 McGuire Units 1 and 2 Page 2 Revision 88

Page Number Amendment Revision Date B 3.6.15 Revision 0 9/30/98 B 3.6.16 Revision 40 5/8/03 B 3.7.1 Revision 0 9/30/98 B 3.7.2 Revision 79 10/17/06 B 3.7.3 Revision 0 9/30/98 B 3.7.4 Revision 57 4/29/04 B 3.7.5 Revision 60 10/12/04 B 3.7.6 Revision 0 9/30/98 B 3.7.7 Revision 0 9/30/98 B 3;7.8 Revision 0 9/30/98 B 3.7.9 Revision 43 5/28/03 B 3.7.10 Revision 75 6/12/06 B 3.7.11 Revision 65 6/2/05 B 3.7.12 Revision 28 5/17/02 B 3.7.13 Revision 85 2/26/07 B 3.7.14 Revision 66 6/30/05 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 0 9/30/98 B 3.8.1 Revision 80 6/25/07 B 3.8.2 Revision 49 10/22/03 B 3.8.3 Revision 53 2/17/04 B 3.8.4 Revision 36 12/17/02 B 3.8.5 Revision 41 7/29/03 B 3.8.6 Revision 0 9/30/98 B 3.8.7 Revision 20 1/10/02 B 3.8.8 Revision 41 7/29/03 B 3.8.9 Revision 24 2/4/02 B 3.8.10 Revision 41 7/29/03 B 3.9.1 Revision 68 9/1/05 B 3.9.2 Revision 41 7/29/03 B 3.9.3 Revision 91 11/7/07 B 3.9.4 Revision 84 2/20/07 B 3.9.5 Revision 59 7/29/04 McGuire Units 1 and 2 Page 3 Revision 88

Page Number B 3.9.6 B 3.9.7 Amendment Revision 41 Revision 88 Revision Date 7/29/03 9/5/07 McGuire Units 1 and 2 Pg eiin8 Page 4 Revision 88

Nuclear Instrumentation B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Nuclear Instrumentation BASES BACKGROUND The source range neutron flux monitors are used during refueling operations to monitor the core reactivity condition. The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS) while the Wide Range Neutron Flux Monitoring System (Gamma-Metrics) are not. Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to the reactor vessel. These detectors monitor neutrons leaking from the core. Neutron flux indication for these monitors are provided in counts per second.

The NIS Source Range Channels are BF3 detectors with a range of 1 to 1 E6 cps. The Wide Range (Gamma-Metrics) channels are fission chambers with a range of 0.1 to 1E5 cps (in the startup range). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the control room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions. Since TS 3.9.2 requires isolation of unborated water sources, the shutdown monitors (Gamma-Metrics) audible alarm, NIS source range audible indication and audible alarm are not required for OPERABILITY in Mode 6.

The NIS source range detectors and the Gamma-Metrics are designed in accordance with the criteria presented in Reference 1.

I APPLICABLE Two OPERABLE source range neutron flux monitor(any combination of SAFETY ANALYSES the two NIS source range monitors and the two Gamma-Metrics wide range monitors) are required to provide an indication to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref. 2) or an improperly loaded fuel assembly.

The source range neutron flux monitors satisfy Criterion 3 of 10 CFR 50.36 (Ref. 3).

LCO This LCO requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity. To be operable, each monitor must provide a visual indication in the Control Room. The visual indication can be, but not limited to, either a gauge, chart recorder, CRT, or some other, recording device McGuire Units 1 and 2 B 3.9.3-1 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES LCO (continued)

The two required source range neutron flux monitors may consist of any combination of the two NIS source range monitors and the two Gamma-Metrics wide range shutdown monitors.

As required by LCO 3.9.2, "Unborated water source isolation valves", all isolation valves for reactor makeup water sources containing unborated water that are connected to the Reactor Coolant System (RCS) must be closed to prevent unplanned boron dilution of the reactor coolant during MODE 6 and thus avoid a reduction in shutdown margin. As such, the required source range monitors OPERABILITY includes only a visual monitoring function. A high flux alarm is not a required function for OPERABILITY.

APPLICABILITY In MODE 6, the source range neutron flux monitors must be OPERABLE to determine changes in core reactivity. There are no other direct means available to check core reactivity levels. In MODES 2, 3, 4, and 5, the NIS source range detectors and circuitry are also required to be OPERABLE by LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation."

The Gamma-Metrics wide range shutdown monitors do not provide an automatic reactor trip protective function.

ACTIONS A.1 and A.2 With only one required source range neutron flux monitor OPERABLE, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS and introduction of coolant into the RCS with boron concentration less than required to meet the minimum boron concentration of LCO 3.9.1 must be suspended immediately. Suspending positive reactivity additions that could result in failure to meet the minimum boron concentration limit is required to assure continued safe operation. Introduction of coolant inventory must be from sources that have a boron concentration greater than that which would be required in the RCS for minimum refueling boron concentration. This may result in an overall reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical operation. Performance of Required Action A.1 shall not preclude completion of movement of a component to a safe position.

B.1 With no required source range neutron flux monitor OPERABLE, action to restore a monitor to OPERABLE status shall be initiated immediately.

Once initiated, action shall be continued until a source range neutron flux monitor is restored to OPERABLE status.

McGuire Units 1 and 2 B 3.9.3-2

. Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES B.2 With no required source range neutron flux monitor OPERABLE, there are no direct means of detecting changes in core reactivity. However, since CORE ALTERATIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE. This stabilized condition is determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists.

The Completion Time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient to obtain and analyze a reactor coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, considering the low probability of a change in core reactivity during this time period.

McGuire Units 1 and 2 B 3.9.3-3 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES SURVEILLANCE SR 3.9.3.1 REQUIREMENTS SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that the two indication channels should be consistent with core conditions. Changes in fuel loading and core geometry can result in significant differences between source range channels, but each channel should be consistent with its local conditions.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is consistent with the CHANNEL CHECK Frequency specified similarly for the same instruments in LCO 3.3.1.

SR 3.9.3.2 SR 3.9.3.2 is the performance of a CHANNEL CALIBRATION every 18 months. The CHANNEL CALIBRATION ensures that the monitors are calibrated. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage. Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 13, GDC 26, GDC 28, and GDC 29.

2.

UFSAR, Sections 4.2, 15.4.6.

3.

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

McGuire Units 1 and 2 B 3.9.3-4 Revision No. 9.1

January 23, 2008 MEMORANDUM To: All McGuire Nuclear Station Technical Specification, and Technical Specification Bases (TSB)

Manual Holders

Subject:

McGuire Technical Specifications Bases REMOVE INSERT Technical Specification Bases Manual:

TS Bases List of Effected Sections Rev 87 Tech Spec Bases: 3.9.3 Rev 41 (Entire-Bases)

TS Bases List of Effected Sections Rev 88 Tech Spec Bases 3.9.3 Rev 91 (Entire Bases)

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)

Revision 63 4/4/05 iiRevision 63 4/4/05 iiiRevision 63 5/25/05 B 2.1.1 Revision 51 1/14/04 B 2.1.2 Revision 0 9/30/98 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 73 3/6/06 B 3.1.2 Revision 10 9/22/00 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 0

-9/30/98 B 3.1.5 Revision 19 1/10/02 B 3.1.6 Revision 0 9/30/98 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 0 9/30/98 B 3.2.1 Revision 74 5/3/06 B 3.2.2 Revision 10 9/22/00 B 3.2.3 Revision 34 10/1/02 B 3.2.4 Revision 10 9/22/00 B 3.3.1 Revision 90 10/30/07 B 3.3.2 Revision 62 1/27/05 B 3.3.3 Revision 71 10/12/05 B 3.3.4 Revision 57 4/29/04 B 3.3.5 Revision 11 9/18/00 B 3.3.6 Not Used - Revision 87 6/29/06 B 3.4.1 Revision 51 1/14/04 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 44 7/3/03 B 3.4.4 Revision 86 6/25/07 B 3.4.5 Revision 86 6/25/07 McGuire Units 1 and 2 Pg eiin8 Page I Revision 88

.Page Number

ýB 3.4.6 B3 3.4.7 B 3.4.8 B 3.4.9 B 3.4.10 B 3.4.11 B 3.4.12 B 3.4.13 B 3.4.14 B 3.4.14-2 B 3.4.14-6 B 3.4.15 B 3.4.16 B 3.4.17 B 3.4.18 B 3.5.1 B 3.5.2 B 3.5.3 B 3.5.4 B 3.5.5 B. 3.6.1 B 3.6.2 B 3.6.3 B 3.6.4 B 3.6.5 B 3.6.5-2 B 3.6.6 B 3.6.7 B 3.6.8 B 3.6.9 B 3.6.10 B 3.6.11 B 3.6.12 B 3.6.13 B 3.6.14 McGuire Units I and 2 Amendment Revision 86 Revision 86 Revision 41 Revision 0 Revision 0 Revision 57 Revision 57 Revision 86 Revision 0 Revision 5 Revision 5 Revision 82 Revision 57 Revision 0 Revision 86 Revision 70 Revision 45 Revision 57 Revision 70 Revision 0 Revision 53 Revision 32 Revision 87 Revision 0 Revision 0 Revision 6 Revision 93 Not Used - Revision 63 Revision 63 Revision 63 Revision 43 Revision 78 Revision 53 Revision 83 Revision 64 Revision Date 6/25/07 6/25/07 7/29/03 9/30/98 9/30/98 4/29/04 4/29/04 6/25/07 9/30/98 8/3/99 8/3/99 9/30/06 4/29/04 9/30/98 6/25/07 110/5/05 8/20/03 4/29/04 10/5/04 9/30/98 2/17/04 10/4/02 6/29/06 9/30/98 9/30/98 10/6/99 04/30/07 4/4/05 4/4/05 4/4/05 5/28/03 9/25/06 2/17/04 12/04/06 4/23/05 Page 2 Page 2Revision 88

.Page Number B 3.6.15 B 3.6.16 B 3.7.1 B 3.7.2 B 3.7.3 B 3.7.4 B 3.7.5 B 3.7.6 B 3.7.7 B 3.7.8 B63.7.9 B 3.7.10 B 3.7.11 B 3.7.12 B 3.7.13 B 3.7.14 B 3.7.15 B 3.7.16 B 3.8.1 B 3.8.2 B 3.8.3 B 3.8.4 B 3.8.5 B 3.8.6 B 3.8.7 B 3.8.8 B 3.8.9 B 3.8.10 B 3.9.1 B 3.9.2 B 3.9.3 B 3.9.4 B 3.9.5 Amendment Revision 0 Revision 40 Revision 0 Revision 79 Revision 0 Revision 57 Revision 60 Revision 0 Revision 0 Revision 0 Revision 43 Revision 75 Revision 65 Revision 28 Revision 85 Revision 66 Revision 66 Revision 0 Revision 80 Revision 49 Revision 53 Revision 36 Revision 41 Revision 0 Revision 20 Revision 41 Revision 24 Revision 41 Revision 68 Revision 41 Revision 91 Revision 84 Revision 59 Revision Date 9/30/98 5/8/03 9/30/98 10/17/06 9/30/98 4/29/04 10/12/04 9/30/98 9/30/98 9/30/98 5/28/03 6/12/06 6/2/05 5/17/02 2/26/07 6/30/05 6/30/05 9/30/98 6/25/07

.10/22/03 2/17/04 12/17/02 7/29/03 9/30/98 1/10/02

,7/29/03 2/4/02 7/29/03 9/1/05 7/29/03 11/7/07 2/20/07 7/29/04 McGuire Units 1 and 2 Pg eiin8 Page 3 Revision 88

Page Number B 3.9.6 B 3.9.7 Amendment Revision 41 Revision 88 Revision Date 7/29/03 9/5/07 McGuire Units 1 and 2 Pg eiin8 Page 4 Revision 88

Nuclear Instrumentation B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Nuclear Instrumentation BASES BACKG ROUND The source range neutron flux monitors are used during refueling operations to monitor the core reactivity condition. The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS) while the Wide Range Neutron Flux Monitoring System (Gamma-Metrics) are not. Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to the reactor vessel. These detectors monitor neutrons leaking from the core. Neutron flux indication for these monitors are provided in counts per second.

The NIS Source Range Channels are BF3 detectors with a range of 1 to 1 E6 cps. The Wide Range (Gamma-Metrics) channels are fission chambers with a range of 0.1 to 1 E5 cps (in the startup range). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the control room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions. Since TS 3.9.2 requires isolation of unborated water sources, the shutdown monitors (Gamma-Metrics) audible alarm, NIS source range audible indication and audible alarm'are not required for OPERABILITY in Mode 6.

The NIS source range detectors and the Gamma-Metrics are designed 'in accordance with the criteria presented in Reference 1.

APPLICABLE Two OPERABLE source range neutron flux monitor,(any combination of SAFETY ANALYSES the two NIS source range monitors and the two Gamma-Metrics wide range monitors) are required to provide an indication to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref. 2) or an improperly loaded fuel assembly.

The source range neutron flux monitors satisfy Criterion 3 of 10 CFR 50.36 (Ref. 3).

LCO This LCO requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity. To be operable, each monitor must provide a visual indication in the Control Room. The visual indication can be, but not limited to, either a gauge, chart recorder, CRT, or some other recording device McGuire Units 1 and 2 B 3.9.3-1 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES LCO (continued)

The two required source range neutron flux monitors may consist of any combination of the two NIS source range monitors and the two Gamma-Metrics wide range shutdown monitors.

As required by LCO 3.9.2, "Unborated water source isolation valves", all isolation valves for reactor makeup water sources containing unborated water that are connected to the Reactor Coolant System (RCS) must be closed to prevent unplanned boron dilution of the reactor coolant during MODE 6 and thus avoid a reduction in shutdown margin. As such, the required source range monitors OPERABILITY includes only a visual monitoring function. A high flux alarm is not a required function for OPERABILITY.

APPLICABILITY In MODE 6, the source range neutron flux monitors must be OPERABLE to determine changes in core reactivity. There are no other direct means available to check core reactivity levels. In MODES 2, 3, 4, and 5, the NIS source range detectors and circuitry are also required to be OPERABLE by LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation."

The Gamma-Metrics wide range shutdown monitors do not provide an automatic reactor trip protective function.

ACTIONS A.1 and A.2 With only one required source range neutron flux monitor OPERABLE, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS and introduction of coolant into the RCS with boron concentration less than required to meet the minimum boron concentration of LCO 3.9.1 must be suspended immediately. Suspending positive reactivity additions that could result in failure to meet the minimum boron concentration limit is required to assure continued safe operation. Introduction of coolant inventory must be from sources that have a boron concentration greater than that which would be required in the RCS for minimum refueling boron concentration. This may result in an overall reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical operation. Performance of Required Action A.1 shall not preclude completion of movement of a component to a safe position.

B.1 With no required source range neutron flux monitor OPERABLE, action to restore a monitor to OPERABLE status shall be initiated immediately.

Once initiated, action shall be continued until a source range neutron flux monitor is restored to OPERABLE status.

McGuire Units 1 and 2 B 3.9.3-2 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES B.2 With no required source range neutron flux monitor OPERABLE, there are no direct means of detecting changes in core reactivity. However, since CORE ALTERATIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE. This stabilized condition is determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists.

The Completion Time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient to obtain and analyze a reactor coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, considering the low probability of a change in core reactivity during this time period.

McGuire Units 1 and 2 B 3.9.3-3 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES SURVEILLANCE SR 3.9.3.1 REQUIREMENTS SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that the two indication channels should be consistent with core conditions. Changes in fuel loading and core geometry can result in significant differences between source range channels, but each channel should be consistent with its local conditions.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is consistent with the CHANNEL CHECK Frequency specified similarly for the same instruments in LCO 3.3.1.

SR 3.9.3.2 SR 3.9.3.2 is the performance of a CHANNEL CALIBRATION every 18 months. The CHANNEL CALIBRATION ensures that the monitors are calibrated. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage. Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 13, GDC 26, GDC 28, and GDC 29.

2.

UFSAR, Sections 4.2, 15.4.6.

3.

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

McGuire Units 1 and 2 B 3.9.3-4 Revision No. 9.1

January 23, 2008 MEMORANDUM To: All McGuire Nuclear Station Technical Specification, and Technical Specification Bases (TSB)

Manual Holders

Subject:

McGuire Technical Specifications Bases REMOVE INSERT Technical Specification Bases Manual:

TS Bases List of Effected Sections Rev 87 Tech Spec Bases: 3.9.3 Rev 41 (Entire Bases)

TS Bases List of Effected Sections Rev 88 Tech Spec Bases 3.9.3 Rev 91 (Entire Bases)

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 p er section)

SRevision 63 4/4/05 HI Revision 63 4/4/05 iiiRevision 63 5/25/05 B 2.1.1 Revision 51 1/14/04 B 2.1.2 Revision 0 9/30/98 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 73 3/6/06 B 3.1.2 Revision 10 9/22/00 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 0 9/30/98 B 3.1.5 Revision 19 1/10/02 B 3.1.6 Revision 0 9/30/98 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 0 9/30/98 B 3.2.1 Revision 74 5/3/06 B 3.2.2.

Revision 10 9/22/00 B 3.2.3 Revision 34 10/1/02 B 3.2.4 Revision 10 9/22/00 B 3.3.1 Revision 90 1.0/30/07 B 3.3.2 Revision 62 1/27/05 B 3.3.3 Revision 71 10/12/05 B63.3.4 Revision 57 4/29/04 B 3.3.5 Revision 11 9/18/00 B 3.3.6 Not Used - Revision 87 6/29/06 B 3.4.1 Revision 51 1/14/04 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 44 7/3/03 B 3.4.4 Revision 86 6/25/07 B 3.4.5 Revision 86 6/25/07 McGuire Units 1 and 2 Pg eiin8 Page I Revision 88

Page Number B 3.4.6 B33.4.7 B 3.4.8 B 3.4.9 B 3.4.10 B 3.4.11.

B 3.4.12 B 3.4.13 B 3.4.14 B 3.4.14-2 B 3.4.14-6 B 3.4.15 B 3.4.16 B 3.4.17 B 3.4.18 B 3.5.1 B 3.5.2 B 3.5.3 B 3.5.4 B 3.5.5 B 3.6.1 B 3.6.2 B 3.6.3 B 3.6.4 B 3.6.5 B 3.6.5-2 B 3.6.6 B 3.6.7 B 3.6.8 B 3.6.9 B 3.6.10 B 3.6.11 B 3.6.12 B 3.6.13 B 3.6.14 Amendment AmenmentRevision Date Revision 86 Revision 86 Revision-41 Revision 0 Revision 0 Revision 57 Revision 57 Revision 86 Revision 0 Revision 5 Revision 5 Revision 82 Revision 57 Revision 0 Revision 86 Revision 70 Revision 45 Revision 57 Revision 70 Revision 0 Revision 53 Revision 32 Revision 87 Revision 0 Revision 0 Revision 6 Revision 93 Not Used - Revision 63 Revision 63 Revision 63 Revision 43 Revision 78 Revision 53 Revision 83 Revision 64 6/25/07 6/25/07 7/29/03 9/30/98 9/30/98 4/29/04 4/29/04 6/25/07 9/30/98 8/3/99 8/3/99 9/30/ 06 4/29/04 9/30/98 6/25/07 10/5/05 8/20/03 4/29/04 10/5/04 9/30/98 2/17/04 10/4/02 6/29/06 9/30/98 9/30/98 10/6/99 04/30/07 4/4/05 4/4/05 4/4/05 5/28/03.

9/2 5/0 6 2/17/04 12/04/06 4/23/05 McGuire Units I and 2PaeRvsin8 Page 2 Revision 88

Page Number Amendment Revision Date B 3.6.15 Revision 0 9/30/98 B 3.6.16 Revision 40 5/8/03 B 3.7.1 Revision 0 9/30/98 B 3.7.2 Revision 79 10/17/06 B 3.7.3 Revision 0 9/30/98 B 3.7.4 Revision 57 4/29/04 B 3.7.5 Revision 60 10/12/04 B 3.7.6 Revision 0 9/30/98 B 3.7.7 Revision 0 9/30/98 B 3.7.8 Revision 0 9/30/98 B 3.7.9 Revision 43 5/28/03 B 3.7.10 Revision 75 6/12/06 B 3.7.11 Revision 65 6/2/05 B 3.7.12 Revision 28 5/17/02 B 3.7.13 Revision 85 2/26/07 B 3.7.14 Revision 66 6/30/05 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 0 9/30/98 B 3.8.1 Revision 80 6/25/07 B 3.8.2 Revision 49 10/22/03 B 3.8.3 Revision 53 2/17/04 B 3.8.4 Revision 36 12/17/02 B 3.8.5 Revision 41 7/29/03 B 3.8.6 Revision 0 9/30/98 B 3.8.7 Revision 20 1/10/02 B 3.8.8 Revision 41 7/29/03 B 3.8.9' Revision 24 2/4/02 B 3.8.10 Revision 41 7/29/03 B 3.9.1 Revision 68 9/1/05 B 3.9.2 Revision 41 7/29/03 B 3.9.3 Revision 91 11/7/07 B 3.9.4 Revision 84 2/20/07 B 3.9.5 Revision 59 7/29/04 McGuire Units 1 and 2 Page 3 Revision 88

Page Number B 3.9.6 B 3.9.7 Amendment Revision 41 Revision 88 Revision Date 7/29/03 9/5/07 McGuire Units I and 2 Pg eiin8 Page, 4 Revision 88

Nuclear Instrumentation B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Nuclear Instrumentation BASES BACKGROUND The source range neutron flux monitors are used during refueling operations to monitor the core reactivity condition. The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS) while the Wide Range Neutron Flux Monitoring System (Gamma-Metrics) are not. Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to the reactor vessel. These detectors monitor neutrons leaking from the core. Neutron flux indication for these monitors are provided in counts per second.

The NIS Source Range Channels are BF3 detectors with a range of 1 to 1 E6 cps. The Wide Range (Gamma-Metrics) channelsare fission chambers with a range of 0.1 to 1 E5 cps (in the startup range). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the control room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions. Since TS 3.9.2 requires isolation of unborated water sources, the shutdown monitors (Gamma-Metrics) audible alarm, NIS source range audible indication and audible alarm are not required for OPERABILITY in Mode 6.

The NIS source range detectors and the Gamma-Metrics are designed in accordance with the criteria presented in Reference 1.

APPLICABLE Two OPERABLE source range neutron flux monitor,(any combination of SAFETY ANALYSES the two NIS source range monitors and the two Gamma-Metrics wide range monitors) are required to provide an indication to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref. 2) or an improperly loaded fuel assembly.

The source range neutron flux monitors satisfy Criterion 3 of 10 CFR 50.36 (Ref. 3).

LCO This LCO requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity. To be operable, each monitor must provide, a visual indication in the Control Room. The visual indication can be, but not limited to, either a gauge, chart recorder, CRT, or some other recording device I'

McGuire Units 1 and 2 B 3.9.3-1 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES LCO (continued)

The two required source range neutron flux monitors may consist of any combination of the two NIS source range monitors and the two Gamma-Metrics wide range shutdown monitors.

As required by LCO 3.9.2, "Unborated water source isolation valves", all isolation valves for reactor makeup water sources containing unborated water that are connected to the Reactor CoolantSystem (RCS) must be closed to prevent unplanned boron dilution of the reactor coolant during MODE 6 and thus avoid a reduction in shutdown margin. As such, the required source range monitors OPERABILITY includes only a visual monitoring function. A high flux alarm is not a required function for OPERABILITY.

APPLICABILITY In MODE 6, the source range neutron flux monitors must be OPERABLE to determine changes in core reactivity. There are no other direct means available to check core reactivity levels. In MODES 2, 3, 4, and 5, the NIS source range detectors and circuitry are also required to be OPERABLE by LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation."

The Gamma-Metrics wide range shutdown monitors do not provide an automatic reactor trip protective function.

ACTIONS A.1 and A.2 With only one required source range neutron flux monitor OPERABLE, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS and introduction of coolant into the RCS with boron concentration less than required to meet the minimum boron concentration of LCO 3.9.1 must be suspended immediately. Suspending positive reactivity additions that could result in failure to meet the minimum boron concentration limit is required to assure continued safe operation. Introduction of coolant inventory must be from sources that have a boron concentration greater than that which would be required in the RCS for minimum refueling boron concentration. This may result in an overall reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical operation. Performance of Required Action A.1 shall not preclude completion of movement of a component to a safe position.

B.1 With no required source range neutron flux monitor OPERABLE, action to restore a monitor to OPERABLE status shall be initiated immediately.

Once initiated, action shall be continued until a source range neutron flux monitor is restored to OPERABLE status.

McGuire Units 1 and 2 B 3.9.3-2 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES B.2 With no required source range neutron flux monitor OPERABLE, there are no direct means of detecting changes in core reactivity. However, since CORE ALTERATIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE. This stabilized condition is determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists.

The Completion Time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient to obtain and analyze a reactor coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, considering the low probability of a change in core reactivity during this time period.

McGuire Units 1 and 2 B 3.9.3-3 Revision No. 91

Nuclear Instrumentation:

B 3.9.3 BASES SURVEILLANCE SR 3.9.3.1 REQUIREMENTS SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that the two indication channels should be consistent with core conditions. Changes in fuel loading and core geometry can result in significant differences between source range channels, but each channel should be consistent with its local conditions.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is consistent with the CHANNEL CHECK Frequency specified similarly for the same instruments in LCO 3.3.1.

SR 3.9.3.2 SR 3.9.3.2 is the performance of a CHANNEL CALIBRATION every 18 months. The CHANNEL CALIBRATION ensures that the monitors are calibrated. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage. Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 13, GDC 26, GDC 28, and GDC 29.

2.

UFSAR, Sections 4.2, 15.4.6.

3.

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

McGuire Units 1 and 2 B 3.9.3-4 Revision No. 91

January 23, 2009 MEMORANDUM To: All McGuire Nuclear Station Technical Specification, and Technical Specification Bases (TSB)

Manual Holders

Subject:

McGuire Technical Specifications Bases REMOVE INSERT Technical Specification Bases Manual:

TS Bases List of Effected Sections Rev 87 Tech Spec Bases: 3.9.3 Rev 41 (Entire Bases)

TS Bases List of Effected Sections Rev 88 Tech Spec Bases 3.9.3 Rev 91 (Entire Bases)

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 63 4/4/05 ii Revision 63 4/4/05 iii Revision 63 5/25/05 B 2.1.1 Revision 51 1/14/04 B 2.1.2 Revision 0 9/30/98 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 73 3/6/06 B 3.1.2 Revision 10 9/22/00 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 0 9/30/98 B 3.1.5 Revision 19 1/10/02 B 3.1.6 Revision 0 9/30/98 B 3'.1.7 Revision 58 06/23/04 B 3.1.8 Revision 0 9/30/98 B 3.2.1 Revision 74 5/3/06 B 3.2.2 Revision 10 9/22/00 B 3.2.3 Revision 34 10/1/02 B 3.2.4 Revision 10 9/22/00 B 3.3.1 Revision 90 10/30/07 B 3.3.2 Revision 62 1/27/05 B 3.3.3 Revision 71 10/12/05 B 3.3.4 Revision 57 4/29/04 B 3.3.5 Revision 11 9/18/00 B 3.3.6 Not Used - Revision 87 6/29/06 B 3.4.1 Revision 51 1/14/04 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 44 7/3/03 B 3.4.4 Revision 86 6/25/07 B 3.4.5 Revision 86 6/25/07 McGuire Units 1 and 2 Page I Revision 88.

Page Number B 3.4.6 B 3.4.7 B 3.4.8 B 3.4.9 B 3.4.10 B 3.4.11 B 3.4.12 B 3.4.13 B 3.4.14 B 3.4.14-2 B 3.4.14-6 B 3.4.15 B 3.4.16 B 3.4.17 B 3.4.18 B 3.5.1 B 3.5.2 B 3.5.3 B 3.5.4 B 3.5.5 B 3.6.1 B 3.6.2 B 3.6.3 B 3.6.4 B 3.6.5 B 3.6.5-2 B 3.6.6 B 3.6.7 B 3.6.8 B 3.6.9 B 3.6.10 B 3.6.11 B 3.6.12 B 3.6.13 B 3.6.14 Amendment Revision Date Revision 86 Revision 86 Revision 41 Revision 0 Revision 0 Revision 57 Revision 57 Revision 86 Revision 0 Revision 5 Revision 5 Revision 82 Revision 57 Revision 0 Revision 86 Revision 70 Revision 45 Revision 57 Revision 70 Revision 0 Revision 53 Revision 32 Revision 87 Revision 0 Revision 0 Revision 6 Revision 93 Not Used - Revision 63 Revision 63 Revision 63 Revision 43 Revision 78 Revision 53 Revision 83 Revision 64 6/25/07 6/25/07 7/29/03 9/30/98 9/30/98 4/29/04 4/29/04 6/25/07 9/30/98 8/3/99 8/3/99 9/30/06 4/29/04 9/30/98 6/25/07 10/5/05 8/20/03 4/29/04 10/5/04 9/30/98 2/17/04 10/4/02 6/29/06 9/30/98 9/30/98 10/6/99 04/30/07 4/4/05 4/4/05 4/4/05 5/28/03 9/25/06 2/17/04 12/04/06

.4/23/05 McGuire Units I and 2 Page 2 Revision 88

.Page Number B 3.6.15 B 3.6.16

,B 3.7.1 B 3.7.2 B 3.7.3 B 3.7.4 B 3.7.5 B 3.7.6 B 3.7.7 B 3.7.8 B 3.7.9 B 3.7.10 B 3.7.11 B 3.7.12 B 3.7.13 B 3.7.14 B 3.7.15 B 3.7.16 B 3.8.1 B 3.8.2 B 3.8.3 B 3.8.4 B 3.8.5 B 3.8.6 B 3.8.7 B 3.8.8 B 3.8.9 B 3.8.10 B 3.9.1 B 3.9.2 B 3.9.3 B 3.9.4 B 3.9.5 Amendment Revision 0 Revision 40 Revision 0 Revision 79 Revision 0 Revision 57 Revision 60 Revision 0 Revision 0 Revision 0 Revision 43 Revision 75 Revision 65 Revision 28 Revision 85 Revision 66 Revision 66 Revision 0 Revision 80 Revision 49 Revision 53 Revision 36 Revision 41 Revision 0 Revision 20 Revision 41 Revision 24 Revision 41 Revision 68 Revision 41 Revision 91 Revision 84 Revision 59 Revision Date 9/30/98 5/8/03 9/30/98 10/17/06 9/30/98 4/29/04 10/12/04 9/30/98 9/30/98 9/30/98 5/28/03 6/12/06 6/2/05 5/17/02 2/26/07 6/30/05 6/30/05 9/30/98 6/25/07 10/22/03

.2/17/04 12/17/02 7/29/03 9/30/98 1/10/02 7/29/03 2/4/02 7/29/03 9/1/05 7/29/03 11/7/07 2/20/07 7/29/04 McGuire Units 1 and 2 Pg eiin8 Page 3 Revision 88

Page NumberA Amendment Revision Date B 3.9.6 Revision 41 7/29/03 B 3.9.7 Revision 88 9/5/07 McGuire Units 1 and 2 Page 4 Revision 88

Nuclear Instrumentation B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Nuclear Instrumentation BASES BACKGROUND The source range neutron flux monitors are used during refueling operations to monitor the core reactivity condition. The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS) while the Wide Range Neutron Flux Monitoring System (Gamma-Metrics) are not. Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to the reactor vessel. These detectors monitor neutrons leaking from the core. Neutron flux indication for these monitors are provided in counts per second.

The NIS Source Range Channels are BF3 detectors with a range of 1 to 1 E6 cps. The Wide Range (Gamma-Metrics) channels are fission chambers with a range of 0.1 to 1 E5 cps (in the startup range). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the control room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions. Since TS 3.9.2 requires isolation of unborated water sources, the shutdown monitors (Gamma-Metrics) audible alarm, NIS source range audible indication and audible alarm are not required for OPERABILITY in Mode 6.

The NIS source range detectors and the Gamma-Metrics are designed in accordance with the criteria presented in Reference 1.

I APPLICABLE Two OPERABLE source range neutron flux monitor,(any combination of SAFETY ANALYSES the two NIS source range monitors and the two Gamma-Metrics wide range monitors) are required to provide an indication to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref..2) or an improperly loaded fuel assembly.

The source range neutron flux monitors satisfy Criterion 3 of 10 CFR 50.36 (Ref. 3).

LCO This LCO requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity. To be operable, each monitor must provide a visual indication in the Control Room. The visual indication can be, but not limited to, either a gauge, chart recorder, CRT, or some other recording device McGuire Units 1 and 2 B 3.9.3-1 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES LCO (continued)

The two required source range neutron flux monitors may consist of any combination of the two NIS source range monitors and the two Gamma-Metrics wide range shutdown monitors.

As required by LCO 3.9.2, "Unborated water source isolation valves", all isolation valves for reactor makeup water sources containing unborated water that are connected to the Reactor Coolant System (RCS) must be closed to prevent unplanned boron dilution of the reactor coolant during MODE 6 and thus avoid a reduction in shutdown margin. As such, the required source range monitors OPERABILITY includes only a visual monitoring function. A high flux alarm is not a required function for OPERABILITY.

APPLICABILITY In MODE 6, the source range neutron flux monitors must be OPERABLE to determine changes in core reactivity. There are no other direct means available to check core reactivity levels. In MODES 2, 3, 4, and 5, the NIS source range detectors and circuitry are also required to be OPERABLE by LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation."

The Gamma-Metrics wide range shutdown monitors do not provide an automatic reactor trip protective function.

ACTIONS A.1 and A.2 With only one required source range neutron flux monitor OPERABLE, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS and introduction of coolant into the RCS with boron concentration less than required to meet the minimum boron concentration of LCO 3.9.1 must be suspended immediately. Suspending positive reactivity additions that could result in failure to meet the minimum boron concentration limit is required to assure continued safe operation. Introduction of coolant inventory must be from sources that have a boron concentration greater than that which would be required in the RCS for minimum refueling boron concentration. This may result in an overall reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical operation. Performance of Required Action A.1 shall not preclude completion of movement of a component to a safe position.

B.1 With no required source range neutron flux monitor OPERABLE, action to restore a monitor to OPERABLE status shall be initiated immediately.

Once initiated, action shall be continued until a source range neutron flux monitor is restored to OPERABLE status.

McGuire Units 1 and 2 B 3.9.3-2 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES B.2 With no required source range neutron flux monitor OPERABLE, there are no direct means of detecting changes in core reactivity. However, since CORE ALTERATIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE. This stabilized condition is determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists.

The Completion Time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient to obtain and analyze a reactor coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, considering the low probability of a change in core reactivity during this time period.

McGuire Units 1 and 2 B 3.9.3-3 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES SURVEILLANCE SR 3.9.3.1 REQUIREMENTS SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that the two indication channels should be consistent with core conditions. Changes in fuel loading and core geometry can result in significant differences between source range channels, but each channel should be consistent with its local conditions.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is consistent with the CHANNEL CHECK Frequency specified similarly for the same instruments in LCO 3.3.1.

SR 3.9.3.2 SR 3.9.3.2 is the performance of a CHANNEL CALIBRATION every 18 months. The CHANNEL CALIBRATION ensures that the monitors are calibrated. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage. Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 13, GDC 26, GDC 28, and GDC 29.

2.

UFSAR, Sections 4.2, 15.4.6.

3.

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

McGuire Units 1 and 2 B 3.9.3-4 Revision No. 91

January 23, 2008 MEMORANDUM To: All McGuire Nuclear Station Technical Specification, and Technical Specification Bases (TSB)

Manual Holders

Subject:

McGuire Technical Specifications Bases REMOVE INSERT Technical Specification Bases Manual:

TS Bases List of Effected Sections Rev 87 Tech Spec Bases: 3.9.3 Rev 41 (Entire Bases)

TS Bases List of Effected Sections Rev 88 Tech Spec Bases 3.9.3 Rev 91 (Entire Bases)

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)

Revision 63 4/4/05 iiRevision 63 4/4/05 iiiRevision 63 5/25/05 B 2. 1.1 Revision 51 1/14/04 B 2.1.2 Revision 0 9/30/98 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 73 3/6/06 B 3.1.2 Revision 10 9/22/00 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 0 9/30/98 B 3.1.5 Revision 19 1/10/02 B 3.1.6 Revision 0 9/30/98 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 0 9/30/98 B 3.2.1 Revision 74 5/3/06 B 3.2.2 Revision 10 9/22/00 B 3.2.3 Revision 34 10/1/02 B 3.2.4 Revision 10 9/22/00 B 3.3.1 Revision 90 10/30/07 B 3.3.2 Revision 62 1/27/05 B 3.3.3 Revision 71 10/12/05 B 3.3.4 Revision 57 4/29/04 B 3.3.5 Revision 11 9/18/00 B 3.3.6 Not Used - Revision 87 6/29/06 B 3.4.1 Revision 51 1/14/04 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 44 7/3/03 B 3.4.4 Revision 86 6/25/07 B 3.4.5, Revision 86 6/25/07 McGuire Units 1 and 2 Pg eiin8 Page 1 Revision 88

.Page Number IB 3.4.6 B33.4.7 B 3.4.8 B 3.4.9 B 3.4.10 B 3.4.11 B 3.4.12 B 3.4.13 B 3.4.14 B 3.4.14-2 B 3.4.14-6 B 3.4.15 B 3.4.16 B 3.4.17 B 3.4.18 B 3.5.1 B 3.5.2 B 3.5.3 B 3.5.4 B 3.5.5 B 3.6.1 B 3.6.2 B 3.6.3 B 3.6.4 B 3.6.5 B 3.6.5-2 B 3.6.6 B 3.6.7 B 3.6.8 B 3.6.9 B 3.6.10 B 3.6.11 B 3.6.12 B 3.6.13 B 3.6.14 Amendment Revision Date Revision 86 Revision 86 Revision 41 Revision 0 Revision 0 Revision 57 Revision 57 Revision 86 Revision 0 Revision 5 Revision 5 Revision 82 Revision 57 Revision 0 Revision 86 Revision 70 Revision 45 Revision 57 Revision 70 Revision 0 Revision 53 Revision 32 Revision 87 Revision 0 Revision 0 Revision 6 Revision 93 Not Used - Revision 63 Revision 63 Revision 63 Revision 43 Revision 78 Revision 53 Revision 83 Revision 64 6/25/07 6/25/07 7/29/03

.9/30/98 9/30/98 4/29/04 4/29/04 6/25/07 9/30/98 8/3/9 9

-8/3/99 9/30/06 4/29/04 9/30/98 6/25/07 10/5/05 8/20/03 4/29/04 10/5/04 9/30/98 2/17/04 10/4/02 6/2 9/0 6 9/30/98 9/30/98 10/6/99 04/30/07 4/4/05 4/4/05 4/4/05 5/28/03 9/25/06 2/17/04 12/04/06 4/23/05 McGuire Units I and 2 Pg eiin8 Page 2 Revision 88

Page Number Amendment PageNumer AendentRevision Date B 3.6.15 Revision 0 9/30/98 B 3.6.16 Revision 40 5/8/03

.B 3.7.1 Revision 0 9/30/98 B 3.7.2 Revision 79 10/17/06 B 3.7.3 Revision 0 9/30/98 B 3.7.4 Revision 57 4/29/04 B 3.7.5 Revision 60 10/12/04 B 3.7.6 Revision 0 9/30/98 B 3.7.7 Revision 0 9/30/98 B 3.7.8 Revision 0 9/30/98 B 3.7.9 Revision 43 5/28/03 B 3.7.10 Revision 75 6/12/06 B 3.7.11 Revision 65 6/2/05 B 3.7.12 Revision 28 5/17/02 B 3.7.13 Revision 85 2/26/07 B 3.7.14 Revision 66 6/30/05 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 0 9/30/98 B 3.8.1 Revision 80 6/25/07 B 3.8.2 Revision 49 10/22/03 B 3.8.3 Revision 53 2/17/04 B 3.8.4 Revision 36

.12/17/02 B 3.8.5 Revision 41 7/29/03 B 3.8.6 Revision 0 9/30/98 B 3.8.7 Revision 20 1/10/02 B 3.8.8 Revision 41 7/29/03 B 3.8.9 Revision 24 2/4/02 B 3.8.10 Revision 41 7/29/03 B83.9.1 Revision 68 9/1/05 B 3.9.2 Revision 41 7/29/03 B 3.9.3 Revision 91 11/7/07 B 3.9.4 Revision 84 2/20/07 B 3.9.5 Revision 59 7/29/04 McGuire Units I and 2 Pg eiin8 Page 3 Revision 88

Page Number Amendment PageNumer AendentRevision Date B 3.6.15 Revision 0 9/30/98 B 3.6.16 Rlevision 40 5/8/03

.B 3.7.1 Revision 0 9/30/98 B 3.7.2 Revision 79 10/17/06 B 3.7.3 Revision 0 9/30/98 B 3.7.4 Revision 57 4/29/04 B 3.7.5 Revision 60 10/12/04 B 3.7.6 Revision 0 9/30/98 B 3.7.7 Revision 0 9/30/98 B 3.7.8 Revision 0 9/30/98 B 3.7.9 Revision 43 5/28/03 B 3.7.10 Revision 75 6/12/06 B 3.7.11 Revision 65 6/2/05 B 3.7.12 Revision 28 5/17/02 B 3.7.13 Revision 85 2/26/07 B 3.7.14 Revision 66 6/30/05 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 0 9/30/98 B 3.8.1 Revision 80 6/25/07 B 3.8.2 Revision 49 10/22/03 B 3.8.3 Revision 53 2/17/04 B 3.8.4 Revision 36 12/17/02 B 3.8.5 Revision 41 7/29/03 B 3.8.6 Revision 0 9/30/98 B 3.8.7 Revision 20 1/10/02 B 3.8.8 Revision 41 7/29/03 B 3.8.9 Revision 24 2/4/02 B 3.8.10 Revision 41 7/29/03 B83.9.1 Revision 68 9/1/05 B 3.9.2 Revision 41 7/29/03 B 3.9.3 Revision 91 11/7/07 B 3.9.4 Revision 84 2/20/07 B 3.9.5 Revision 59 7/29/04 McGuire Units I and 2 Pg eiin8 Page 3 Revision 88

Page Number Amendment Revision Date B 3.9.6 Revision 41 7/29/03 B 3.9.7 Revision 88 9/5/07 McGuire Units 1 and 2 Page 4 Revision 88

Nuclear Instrumentation B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Nuclear Instrumentation BASES BACKG ROUND The source range neutron flux monitors are used during refueling operations to monitor the core reactivity condition. The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS) while the Wide Range Neutron Flux Monitoring System (Gamma-Metrics) are not. Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to the reactor vessel. These detectors monitor neutrons leaking from the core. Neutron flux indication for these monitors are provided in counts per second.

The NIS Source Range Channels are BF3 detectors with a range of 1 to 1 E6 cps. The Wide Range (Gamma-Metrics) channels are fission chambers with a range of 0.1 to 1 E5 cps (in the startup range). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the control room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions. Since TS 3.9.2 requires isolation of unborated water sources, the shutdown monitors (Gamma-Metrics) audible alarm, NIS source range audible indication and audible alarm are not required for OPERABILITY in Mode 6.

The NIS source range detectors and the Gamma-Metrics are designed in accordance with the criteria presented in Reference 1.

APPLICABLE Two OPERABLE source range neutron flux monitoro(any combination of SAFETY ANALYSES the two NIS source range monitors and the two Gamma-Metrics wide range monitors) are required to provide an indication to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref. 2) or an improperly loaded fuel assembly.

The source range neutron flux monitors satisfy Criterion 3 of 10 CFR 50.36 (Ref. 3).

LCO This LCO requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity. To be operable, each monitor must provide a visual indication in the Control Room. The visual indication can be, but not limited to, either a gauge, chart recorder, CRT, or some other recording device McGuire Units 1 and 2 B 3.9.3-1 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES LCO (continued)

The two required source range neutron flux monitors may consist of any combination of the two NIS source range monitors and the two Gamma-Metrics wide range shutdown monitors.

As required by LCO 3.9.2, "Unborated water source isolation valves", all isolation valves for reactor makeup water sources containing unborated water that are connected to the Reactor Coolant System (RCS) must be closed to prevent unplanned boron dilution of the reactor coolant during MODE 6 and thus avoid a reduction in shutdown margin. As such, the required source range monitors OPERABILITY includes only a visual monitoring function. A high flux alarm is not a required function for

-OPERABILITY.

APPLICABILITY In MODE 6, the source range neutron flux monitors must be OPERABLE to determine changes in core reactivity. There are no other direct means available to check core reactivity levels. In MODES 2, 3, 4, and 5, the NIS source range detectors and circuitry are also required to be OPERABLE by LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation."

The Gamma-Metrics wide range shutdown monitors do not provide an automatic reactor trip protective function.

ACTIONS A.1 and A.2 With only one required source range neutron flux monitor OPERABLE, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS and introduction of coolant into the RCS with boron concentration less than required to meet the minimum boron concentration of LCO 3.9.1 must be suspended immediately. Suspending positive reactivity additions that could result in failure to meet the minimum boron concentration limit is required to assure continued safe operation. Introduction of coolant inventory must be from sources that have a boron concentration greater than that which would be required in the RCS for minimum refueling boron concentration. This may result in an overall reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical operation. Performance of Required Action A.1 shall not preclude completion of movement of a component to a safe position.

B.1 With no required source range neutron flux monitor OPERABLE, action to restore a monitor to OPERABLE status shall be initiated immediately.

Once initiated, action shall be continued until a source range neutron flux monitor is restored to OPERABLE status.

McGuire Units 1 and 2 B 3.9.3-2 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES B.2 With no required source range neutron flux monitor OPERABLE, there are no direct means of detecting changes in core reactivity. However, since CORE ALTERATIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE. This stabilized condition is determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists.

The Completion Time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient to obtain and analyze a reactor coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, considering the low probability of a change in core reactivity during this time period.

McGuire Units 1 and 2 B 3.9.3-3 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES SURVEILLANCE SR 3.9.3.1, REQUIREMENTS SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that the two indication channels should be consistent with core conditions. Changes in fuel loading and core geometry can result in significant differences between source range channels, but each channel should be consistent with its local conditions.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is consistent with the CHANNEL CHECK Frequency specified similarly for the same instruments in LCO 3.3.1.

SR 3.9.3.2 SR 3.9.3.2 is the performance of a CHANNEL CALIBRATION every 18 months. The CHANNEL CALIBRATION ensures that the monitors are calibrated. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage. Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 13, GDC 26, GDC 28, and GDC 29.

2.

UFSAR, Sections 4.2,15.4.6.

3.

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

McGuire Units 1 and 2 B 3.9.3-4 Revision No. 91

January 23, 2008 MEMORANDUM To: All McGuire Nuclear Station Technical Specification, and Technical Specification Bases (TSB)

Manual Holders

Subject:

McGuire Technical Specifications Bases REMOVE INSERT Technical Specification Bases Manual:

TS Bases List of Effected Sections Rev 87 TS Bases List of Effected Sections Rev 88 Tech Spec Bases: 3.9.3 Rev 41 (Entire Bases)

Tech Spec Bases 3.9.3 Rev 91 (Entire Bases)

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)

SRevision 63 4/4/05 ii Revision 63 4/4/05 iii Revision 63 5/25/05 B 2.1.1 Revision 51 1/14/04 B 2.1.2 Revision 0 9/30/98 B 3.0 Revision 81 3/29/07 B 3. 1.1 Revision 73 3/6/06 B 3.1.2 Revision 10 9/22/00 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 0 9/30/98 B 3.1.5 Revision 19 1/10/02 B 3.1.6 Revision 0 9/30/98 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 0 9/30/98 B 3.2.1 Revision 74 5/3/06 B 3.2.2 Revision 10 9/22/00 B 3.2.3 Revision 34 10/1/02 B 3.2.4 Revision 10 9/22/00 B 3.3.1 Revision 90 10/30/07 B 3.3.2 Revision 62 1/27/05 B 3.3.3 Revision 71 10/12/05 B 3.3.4 Revision 57 4/29/04 B 3.3.5 Revision 11 9/18/00 B 3.3.6 Not Used - Revision 87 6/29/06 B 3.4.1 Revision 51 1/14/04 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 44 7/3/03 B 3.4.4 Revision 86 6/25/07 B 3.4.5 Revision 86 6/25/07 McGuire Units I and 2 Pg eiin8 Page I Revision 88

Page Number B 3.4.6 B 3.4.7 B 3.4.8 B 3.4.9 B 3.4.10 B 3.4.11 B 3.4.12 B 3.4.13 B 3.4.14 B 3.4.14-2 B 3.4.14-6 B 3.4.15 B 3.4.16 B 3.4.17 B 3.4.18 B 3.5.1 B 3.5.2 B 3.5.3 B 3.5.4 B 3.5.5 B 3.6.1 B 3.6.2 B 3.6.3 B 3.6.4 B 3.6.5 B 3.6.5-2 B 3.6.6 B 3.6.7 B 3.6.8 B 3.6.9 B 3.6.10 B 3.6.11 B 3.6.12 B 3.6.13 B 3.6.14 Amendment AmenmentRevision Date Revision 86 Revision 86 Revision 41 Revision 0 Revision 0 Revision 57 Revision 57 Revision 86 Revision. 0 Revision 5 Revision 5 Revision 82 Revision 57 Revision 0 Revision 86 Revision 70 Revision 45 Revision 57 Revision 70 Revision 0 Revision 53 Revision 32 Revision 87 Revision 0 Revision 0 Revision 6 Revision 93 Not Used - Revision 63 Revision 63 Revision 63 Revision 43 Revision 78 Revision 53 Revision 83 Revision 64 6/25/07 6/25/07 7/29/03 9/30/98 9/30/98 4/29/04 4/29/04 6/25/07 9/30/98 8/3/9 9 8/3/99 9/30/06 4/29/04 9/30/98 6/25/07 10/5/05 8/20/03 4/29/04 10/5/04 9/30/98 2/17/04 10/4/02 6/29/06 9/30/98 9/30/98 10/6/99 04/30/07 4/4/05 4/4/05 4/4/05 5/28/03 9/25/06 2/17/04 12/04/06 4/23/05 McGuire Units 1 and 2 Pg eiin8 Page 2 Revision 88

Page NumberAmnmnResinDt Amendment Revision Date B 3.6.15 Revision 0 9/30/98 B 3.6.16 Revision 40 5/8/03 B 3.7.1 Revision 0 9/30/98 B 3.7.2 Revision 79 10/17/06 B 3.7.3 Revision 0 9/30/98 B 3.7.4 Revision 57 4/29/04 B 3.7.5 Revision 60 10/12/04 B 3.7.6 Revision 0 9/30/98 B 3.7.7 Revision 0 9/30/98 B 3.7.8 Revision 0 9/30/98 B 3.7.9 Revision 43 5/28/03 B 3.7.10 Revision 75 6/12/06 B 3.7.11 Revision 65 6/2/05 B 3.7.12 Revision 28 5/17/02 B 3.7.13 Revision 85 2/26/07 B 3.7.14 Revision 66 6/30/05 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 0 9/30/98 B 3.8.1 Revision 80 6/25/07 B 3.8.2 Revision 49 10/22/03 B 3.8.3 Revision 53 2/17/04 B 3.8.4 Revision 36 12/17/02 B 3.8.5 Revision 41 7/29/03 B 3.8.6 Revision 0 9/30/98 B 3.8.7 Revision 20 1/10/02 B 3.8.8 Revision 41 7/29/03 B 3.8.9 Revision 24 2/4/02 B 3.8.10 Revision 41 7/29/03 B 3.9.1 Revision 68 9/1/05 B 3.9.2 Revision 41 7/29/03 B 3.9.3 Revision 91 11/7/07 B 3.9.4 Revision 84 2/20/07 B 3.9.5 Revision 59 7/29/04 McGuire Units 1 and 2 Pg eiin8 Page 3 Revision 88

Page Number B 3.9.6 B 3.9.7 Amendment Revision 41 Revision 88 Revision Date 7/29/03 9/5/07 McGuire Units 1 and 2 Page 4 Revision 88

Nuclear Instrumentation B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Nuclear Instrumentation BASES BACKGROUND The source range neutron flux monitors are used during refueling operations to monitor the core reactivity condition. The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS) while the Wide Range Neutron Flux Monitoring System (Gamma-Metrics) are not. Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to the reactor vessel. These detectors monitor neutrons leaking from the core. Neutron flux indication for these monitors are, provided in counts per second.

The NIS Source Range Channels are BF3 detectors with a range of 1 to 1 E6 cps. The Wide Range (Gamma-Metrics) channels are fission chambers with a range of 0.1 to 1 E5 cps (in the startup range). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the control room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions. Since TS 3.9.2 requires isolation of unborated water sources, the shutdown monitors (Gamma-Metrics) audible alarm, NIS source range audible indication and audible alarm are not required for OPERABILITY in Mode 6.

The NIS source range detectors and the Gamma-Metrics are designed in accordance with the criteria presented in Reference 1.

APPLICABLE Two OPERABLE source range neutron flux monitor,(any combination of SAFETY ANALYSES the two NIS source range monitors and the two Gamma-Metrics wide range monitors) are required to provide an indication to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref. 2) or an improperly loaded fuel assembly.

The source range neutron flux monitors satisfy Criterion 3 of 10 CFR 50.36 (Ref. 3).

LCO This LCO requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity. To be operable, each monitor must provide a visual indication in the Control Room. The visual indication can be, but not limited to, either a gauge, chart recorder, CRT, or some other recording device McGuire Units 1 and 2 B 3.9.a-1 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES LCO (continued)

The two required source range neutron flux monitors may consist of any combination of the two NIS source range monitors and the two Gamma-Metrics wide range shutdown monitors.

As required by LCO 3.9.2, "Unborated water source isolation valves", all isolation valves for reactor makeup water sources containing unborated water that are connected to the Reactor Coolant System (RCS) must be closed to prevent unplanned boron dilution of the reactor coolant during MODE 6 and thus avoid a reduction in shutdown margin. As such, the required source range monitors OPERABILITY includes only a visual monitoring function. A high flux alarm is not a required function for OPERABILITY.

APPLICABILITY In MODE 6, the source range neutron flux monitors must be OPERABLE to determine changes in core reactivity. There are no other direct means available to check core reactivity levels. In MODES 2, 3, 4, and 5, the NIS source range detectors and circuitry are also required to be OPERABLE by LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation."

The Gamma-Metrics wide range shutdown monitors do not provide an automatic reactor trip protective function.

ACTIONS A.1 and A.2 With only one required source range neutron flux monitor OPERABLE, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS and introduction of coolant into the RCS with boron concentration less than required to meet the minimum boron concentration of LCO 3.9.1 must be suspended immediately. Suspending positive reactivity additions that could result in failure to meet the minimum boron concentration limit is required to assure continued safe operation. Introduction of coolant inventory must be from sources that have a boron concentration greater than that which would be required in the RCS for minimum refueling boron concentration. This may result in an overall reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical operation. Performance of Required Action A.1 shall not preclude completion of movement of a component to a safe position.

B._ 1 With no required source range neutron flux monitor OPERABLE, action to restore a monitor to OPERABLE status shall be initiated immediately.

Once initiated, action shall be continued until a source range neutron flux monitor is restored to OPERABLE status.

McGuire Units 1 and 2 B 3.9.3-2 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES B.2 With no required source range neutron flux monitor OPERABLE, there are no direct means of detecting changes in core reactivity. However, since CORE ALTERATIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE. This stabilized condition is determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists.

The Completion Time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient to obtain and analyze a reactor coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, considering the low probability of a change in core reactivity during this time period.

McGuire Units 1 and 2 B 3.9.3-3 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES SURVEILLANCE SR 3.9.3.1 REQUIREMENTS SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that the two indication channels should be consistent with core conditions. Changes in fuel loading and core geometry can result in significant differences between source range channels, but each channel should be consistent with its local conditions.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is consistent with the CHANNEL CHECK Frequency specified similarly for the same instruments in LCO 3.3.1.-

SR 3.9.3.2 SR 3.9.3.2 is the performance of a CHANNEL CALIBRATION every 18 months. The CHANNEL CALIBRATION ensures that the monitors are calibrated. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage. Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 13, GDC 26, GDC 28, and GDC 29.

2.

UFSAR, Sections 4.2, 15.4.6.

3.

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

McGuire Units 1 and 2 B 3.9.3-4 Revision No. 91

January 23, 2008 MEMORANDUM To: All McGuire Nuclear Station Technical Specification, and Technical Specification Bases (TSB)

Manual Holders

Subject:

McGuire Technical Specifications Bases REMOVE INSERT Technical Specification Bases Manual:

TS Bases List of Effected Sections Rev 87 TS Bases List of Effected Sections Rev 88 Tech Spec Bases: 3.9.3 Rev 41 (Entire Bases)

Tech Spec Bases 3.9.3 Rev 91 (Entire Bases)

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)

SRevision 63 4/4/05 iiRevision 63 4/4/05 iii Revision 63 5/25/05 B 2.1.1 Revision 51 1/14/04 B 2.1.2

-Revision 0 9/30/98 B 3.0 Revision 81 3/29/07 B 3.1.1 Revision 73 3/6/06 B 3.1.2 Revision 10 9/22/00 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 0 9/30/98 B 3.1.5 Revision 19 1/10/02 B 3.1.6 Revision 0 9/30/98 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 0 9/30/98 B 3.2.1 Revision 74 5/3/06 B 3.2.2 Revision 10 9/22/00

'B 3.2.3 Revision 34 10/1/02 B 3.2.4 Revision 10 9/22/00 B 3.3.1 Revision 90 10/30/07 B 3.3.2 Revision 62 1/27/05 B 3.3.3 Revision 71 10/12/05 B 3.3.4 Revision 57 4/29/04 B 3.3.5 Revision 11 9/18/00 B 3.3.6 Not Used - Revision 87 6/29/06 B 3.4.1 Revision 51 1/14/04 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 44 7/3/03 B 3.4.4 Revision 86 6/25/07 B 3.4.5 Revision 86 6/25/07 McGuire Units 1 and 2 Pg eiin8 Page I Revision 88

Page Number B 3.4.6 B 3.4.7 B 3.4.8 B 3.4.9 B 3.4.10 B 3.4.11 B 3.4.12 B 3.4.13 B 3.4.14 B 3.4.14-2 B 3.4.14-6 B 3.4.15 B 3.4.16 B 3.4.17 B 3.4.18 B 3.5.1 B 3.5.2 B 3.5.3 B 3.5.4 B 3.5.5 B 3.6.1 B 3.6.2 B 3.6.3 B 3.6.4 B 3.6.5 B 3.6.5-2 B 3.6.6 B 3.6.7 B 3.6.8 B 3.6.9 B 3.6.10 B 3.6.11 B 3.6.12 B 3.6.13 B 3.6.14 Amendment Revision Date Revision 86 Revision 86 Revision 41

Revision 0 Revision 0 Revision 57 Revision 57 Revision 86 Revision 0 Revision 5 Revision 5 Revision 82 Revision 57 Revision 0 Revision 86 Revision 70 Revision 45 Revision 57 Revision 70 Revision 0 Revision 53 Revision 32 Revision 87 Revision 0 Revision 0 Revision 6 Revision 93 Not Used - Revision 63 Revision 63 Revision 63 Revision 43 Revision 78 Revision 53 Revision 83 Revision 64 6/25/07 6/25/07 7/29/03 9/30/98 9/30/98 4/29/04 4/29/04 6/25/07 9/30/98 8/3/99 8/3/99 9/30/06 4/29/04 9/30/98 6/2 5/0 7 10/5/05 8/20/03 4/29/04 10/5/04 9/30/98 2/17/04 10/4/02 6/2 9/0 6 9/30/98 9/30/98 10/6/99 04/30/07 4/4/05 4/4/05 4/4/05 5/28/03 9/2 5/0 6 2/17/04 12/04/06 4/23/05 McGuire Units I and 2 Pg eiin8 Page 2 Revision 88

.Page Number Amendment PageNumer AendentRevision Date B 3.6.15 Revision 0 9/30/98 B 3.6.16

Revision 40 5/8/03 B 3.7.1 Revision 0 9/30/98 B 3.7.2 Revision 79 10/17/06 B 3.7.3 Revision 0 9/30/98 B 3.7.4 Revision 57 4/29/04 B 3.7.5 Revision 60 10/12/04 B 3.7.6 Revision 0 9/30/98 B 3.7.7 Revision 0 9/30/98 B 3.7.8 Revision 0 9/30/98 B 3.7.9 Revision 43 5/28/03 B 3.7.10 Revision 75 6/12/06 B 3.7.11 Revision 65 6/2/05 B 3.7.12 Revision 28 5/17/02 B 3.7.13 Revision 85 2/26/07 B 3.7.14 Revision 66 6/30/05 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 0 9/30/98 B 3.8.1 Revision 80 6/25/07 B 3.8.2 Revision 49 10/22/03 B 3.8.3 Revision 53 2/17/04 B 3.8.4 Revision 36 12/17/02 B 3.8.5 Revision 4.1 7/29/03 B 3.8.6 Revision 0 9/30/98 B 3.8.7 Revision 20 1/10/02 B 3.8.8 Revision 41 7/29/03 B 3.8.9 Revision 24 2/4/02 B 3.8.10 Revision 41 7/29/03 B 3.9.1 Revision 68 9/1/05 B 3.9.2 Revision 41 7/29/03 B 3.9.3 Revision 91 11/7/07 B 3.9.4 Revision 84 2/20/07 B 3.9.5 Revision 59 7/29/04 McGuire Units I and 2 Page 3 R(-vision 88

Page Number B 3.9.6 B 3.9.7 Amendment Revision 41 Revision 88 Revision Date 7/29/03 9/5/07 McGuire Units 1 and 2 Pg Page 4 Revision 88

Nuclear Instrumentation B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Nuclear Instrumentation BASES BACKGROUND The source range neutron flux monitors are used during refueling operations to monitor the core reactivity condition. The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS) while the Wide Range Neutron Flux Monitoring System (Gamma-Metrics) are not. Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to the reactor vessel. These detectors-.

monitor neutrons leaking from the core. Neutron flux indication for these monitors are provided in counts per second.

The NIS Source Range Channels are BF3 detectors with a range of 1 to 1 E6 cps. The Wide Range (Gamma-Metrics) channels are fission chambers with a range of 0.1 to 1 E5 cps (in the startup range). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the control room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions. Since TS 3.9.2 requires isolation of unborated water sources, the shutdown monitors (Gamma-Metrics) audible alarm, NIS source range audible indication and audible alarm are not required for OPERABILITY in Mode 6.

The NIS source range detectors and the Gamma-Metrics are designed in accordance with the criteria presented in Reference 1.

I APPLICABLE Two OPERABLE source range neutron flux monitor.o(any combination of SAFETY ANALYSES the two NIS source range monitors and the two Gamma-Metrics wide range monitors) are required to provide an indication to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref. 2) or an improperly loaded fuel assembly.

The source range neutron flux monitors satisfy Criterion 3 of 10 CFR 50.36 (Ref. 3).

LCO This LCO requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity. To be operable, each monitor must provide a visual indication in the Control Room. The visual indication can be, but not limited to, either a gauge, chart recorder, CRT, or some other recording device McGuire Units 1 and 2 B 3.9.3-1 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES LCO (continued)

The two required source range neutron flux monitors may consist of any combination of the two NIS source range monitors and the two Gamma-Metrics wide range shutdown monitors.

As required by LCO 3.9.2, "Unborated water source isolation valves", all isolation valves for reactor makeup water sources containing unborated water that are connected to the Reactor Coolant System (RCS) must be closed to prevent unplanned boron dilution of the reactor coolant during MODE 6 and thus avoid a reduction in shutdown margin. As such, the required source range monitors OPERABILITY includes only a visual monitoring function. A high flux alarm is not a required function for OPERABILITY.

APPLICABILITY In MODE 6, the source range neutron flux monitors must be OPERABLE to determine changes in core reactivity. There are no other direct means available to check core reactivity levels. In MODES 2, 3, 4, and 5, the NIS source range detectors and circuitry are also required to be OPERABLE by LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation."

The Gamma-Metrics wide range shutdown monitors do not provide an automatic reactor trip protective function.

ACTIONS A.1 and A.2 With only one required source range neutron flux monitor OPERABLE, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS and introduction of coolant into the RCS with boron concentration less than required to meet the minimum boron concentration of LCO 3.9.1 must be suspended immediately. Suspending positive reactivity additions that could result in failure to meet the minimum boron concentration limit is required to assure continued safe operation. Introduction of coolant inventory must be from sources that have a boron concentration greater than that which would be required in the RCS for minimum refueling boron concentration. This may result in an overall reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical operation. Performance of Required Action A.1 shall not preclude completion of movement of a component to a safe position.

B.1 With no required source range neutron flux monitor OPERABLE, action to restore a monitor to OPERABLE status shall be initiated immediately.

Once initiated, action shall be continued until a source range neutron flux monitor is restored to OPERABLE status.

McGuire Units 1 and 2 B 3.9.3-2 Revision No. 91

Nuclear Instrumentation B 3.9.3 P

BASES B.2 With no required source range neutron flux monitor OPERABLE, there are no direct means of detecting changes in core reactivity. However, since CORE ALTERATIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE. This stabilized condition is determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists.

The Completion Time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient to obtain and analyze a reactor, coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, considering the low probability of a change in core reactivity during this time period.

S 0

McGuire Units 1 and 2 B 3.9.3-3 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES SURVEILLANCE SR 3.9.3.1 REQUIREMENTS SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that the two indication channels should be consistent with core conditions. Changes in fuel loading and core geometry can result in significant differences between source range channels, but each channel should be consistent with its local conditions.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is consistent with the CHANNEL CHECK Frequency specified similarly for the same instruments in LCO 3.3.1.

SR 3.9.3.2 SR 3.9.3.2 is the performance of a CHANNEL CALIBRATION every 18 months. The CHANNEL CALIBRATION ensures that the monitors are calibrated. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage. Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 13, GDC 26, GDC 28, and GDC 29.

2.

UFSAR, Sections 4.2, 15.4.6.

3.

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

McGuire Units 1 and 2 B 3.9.3-4 Revision No. 91

January 23, 2008 MEMORANDUM To: All McGuire Nuclear Station Technical Specification, and Technical Specification Bases (TSB)

Manual Holders

Subject:

McGuire Technical Specifications Bases REMOVE INSERT Technical Specification Bases Manual:

TS Bases List of Effected Sections Rev 87 Tech Spec Bases: 3.9.3 Rev 41 (Entire Bases)

TS Bases List of Effected Sections Rev 88 Tech Spec Bases 3.9.3 Rev 91 (Entire Bases)

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)

SRevision 63 4/4/05 ii Revision 63 4/4/05 iii Revision 63 5/25/05 B 2. 1.1 Revision 51 1114104 B 2.1.2 Revision 0 9/30/98 B 3.0 Revision 81 3/29/07 B 3. 1.1 Revision 73 3/6/06 B 3.1.2 Revision 10 9/22/00 B 3.1.3 Revision 10 9/22/00 B 3.1.4 Revision 0 9/30/98 B 3.1.5 Revision 19 1/10/02 B 3.1.6 Revision 0 9/30/98 B 3.1.7 Revision 58 06/23/04 B 3.1.8 Revision 0 9/30/98 B 3.2.1 Revision 74 5/3/06 B 3.2.2 Revision 10 9/22/00 B 3.2.3 Revision 34 10/1/02 B 3.2.4 Revision 10 9/22/00 B 3.3.1 Revision 90 10/30/07 B 3.3.2 Revision 62 1/27/05 B 3.3.3 Revision 71 10/12/05 B 3.3.4 Revision 57 4/29/04 B 3.3.5 Revision 11 9/18/00 B 3.3.6 Not Used - Revision 87

.6/29/06 B 3.4.1 Revision 51 1/14/04 B 3.4.2 Revision 0 9/30/98 B 3.4.3 Revision 44 7/3/03 B 3.4.4 Revision 86 6/25/07 B 3.4.5 Revision 86 6/25/07 McGuire Units 1 and 2 Pg eiin8 Page I Revision 88

Page Number Amendment PageNumer AendentRevision Date IB 3.4.6 B 3.4.7 B3.4.8 B 3.4.9.

B 3.4.10 B 3.4.11 B 3.4.12 B 3.4.13 B 3.4.14 B 3.4.14-2 B 3.4.14-6 B 3.4.15 B 3.4.16 B 3.4.17 B 3.4.18 B 3.5.1 Bý 3.5.2 B 3.5.3 B 3.5.4 B 3.5.5 B 3.6.1 B 3.6.2 B 3.6.3 B 3.6.4 B 3.6.5 B 3.6.5-2 B 3.6.6 B 3.6.7 B 3.6.8 B 3.6.9 B 3.6.10 B 3.6.11 B 3.6.12 B 3.6.13 B 3.6.14 Revision 86 Revision 86 Revision 41 Revision 0 Revision 0 Revision 57 Revision 57 Revision 86 Revision 0 Revision 5 Revision 5 Revision 82 Revision 57 Revision 0 Revision 86 Revision 70 Revision 45 Revision 57 Revision 70 Revision 0 Revision 53 Revision 32 Revision 87 Revision 0 Revision 0 Revision 6 Revision 93 Not Used - Revision 63 Revision 63 Revision 63 Revision 43 Revision 78 Revision 53 Revision 83 Revision 64 6/25/07 6/25/07 7/29/03 9/30/98 9/3/98 4/29/04 4/29/04 6/25/07 9/30/98 8/3/99 8/3/9 9 9/30/06 4/29/04 9/30/98 6/25/07 10/5/05 8/20/03 4/29/04 10/5/04 9/30/98 2/17/04 10/4/02 6/29/06 9/30/98 9/30/9 8 10/6/99 04/30/07 4/4/05 4/4/05 4/4/05 5/28/03 9/25/06 2/17/04 12/04/06 4/23/05 McGuire Units I and 2 Pg eiin8 Page 2 Revision 88

Page Number Amendment PageNumer AendentRevision Date B 3.6.15 Revision 0 9/30/98 B 3.6.16 Revision 40 5/8/03 B 3.7.1 Revision 0 9/30/98 B 3.7.2 Revision 79 10/17/06 B 3.7.3 Revision 0 9/30/98 B 3.7.4 Revision 57 4/29/04 B 3.7.5 Revision 60 10/ 12/04 B 3.7.6 Revision 0 9/30/98 B 3.7.7 Revision 0 9/30/98 B 3.7.8 Revision 0 9/30/98 B 3.7.9 Revision 43 5/28/03 B 3.7.10 Revision 75 6/12/06 B 3.7.11 Revision 65 6/2/05 B 3.7.12 Revision 28 5/17/02 B 3.7.13 Revision 85 2/26/07 B 3.7.14 Revision 66 6/30/05 B 3.7.15 Revision 66 6/30/05 B 3.7.16 Revision 0 9/30/98 B 3.8.1 Revision 80 6/25/07 B 3.8.2 Revision 49 10/22/03 B 3.8.3 Revision 53 2/17/04 B 3.8.4 Revision 36 12/17/02 B 3.8.5 Revision 41 7/29/03 B 3.8.6 Revision 0 9/30/98 B 3.8.7 Revision 20 1/10/02 B 3.8.8 Revision 41 7/29/03 B 3.8.9 Revision 24 2/4/02 B 3.8.10 Revision 41 7/29/03 B 3.9.1 Revision 68 9/1/05 B 3.9.2 Revision 41 7/29/03 B 3.9.3 Revision 91 11/7/07 B 3.9.4 Revision 84 2/20/07 B 3.9.5 Revision 59 7/29/04 McGuire Units 1 and 2 Pg eiin8 Page 3 Revision 88

Page Number Amendment Revision Date B 3.9.6 Revision 41 7/29/03 B 3.9.7 Revision 88 9/5/07 McGuire Units I and2 Page 4 Revision 88

Nuclear Instrumentation B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Nuclear Instrumentation BASES BACKGROUND The source.range neutron flux monitors are used during refueling operations to monitor the core reactivity condition. The installed source range neutron flux monitors are part of the Nuclear Instrumentation System (NIS) while the Wide Range Neutron Flux Monitoring System (Gamma-Metrics) are not. Source range indication is provided via the NIS source range channels and the Gamma-Metrics shutdown monitors using detectors located external to.the reactor vessel. These detectors monitor neutrons leaking from the core. Neutron flux indication for these monitors are provided in counts per second.

The NIS Source Range Channels are BF3 detectors with a range of 1 to 1 E6 cps. The Wide Range (Gamma-Metrics) channels are fission chambers with a range of 0.1 to 1 E5 cps (in the startup range). The NIS source range channels and the Gamma-Metrics shutdown monitors provide continuous visible count rate indication in the control room and a high flux control room alarm to alert operators to any unexpected positive reactivity additions. Since TS 3.9.2 requires isolation of unborated water sources, the shutdown monitors (Gamma-Metrics) audible alarm, NIS source range audible indication and audible alarm are not required for OPERABILITY in Mode 6.

The NIS source range detectors and the Gamma-Metrics are designed in accordance with the criteria presented in Reference 1.

APPLICABLE Two OPERABLE source range neutron flux monitor,(any combination of SAFETY ANALYSES the two NIS source range monitors and the two Gamma-Metrics wide range monitors) are required to provide an indication to alert the operator to unexpected changes in core reactivity such as with a boron dilution accident (Ref. 2) or an improperly loaded fuel assembly.

The source range neutron flux monitors satisfy Criterion 3 of 10 CFR 50.36 (Ref. 3).

LCO This LCO requires that two source range neutron flux monitors be OPERABLE to ensure that redundant monitoring capability is available to detect changes in core reactivity. To be operable, each monitor must provide a visual indication in the Control Room. The visual indication can be, but not limited to, either a gauge, chart recorder, CRT, or some other recording device McGuire Units 1 and 2 B 3.9.3-1 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES LCO (continued)

The two required source range neutron flux monitors may consist of any combination of the two NIS source range monitors and the two Gamma-Metrics wide range shutdown monitors.

As required by LCO 3.9.2, "Unborated water source isolation valves", all isolation valves for reactor makeup water sources containing unborated water that are connected to the Reactor Coolant System (RCS) must be closed to prevent unplanned boron dilution of the reactor coolant during MODE 6 and thus avoid a reduction in shutdown margin. As such, the required source range monitors OPERABILITY includes only a visual monitoring function. A high flux alarm is not a required function for OPERABILITY.

APPLICABILITY In MODE 6, the source range neutron flux monitors must be OPERABLE to determine changes in core reactivity. There are no other direct means available to check core reactivity levels. In MODES 2, 3, 4, and 5, the NIS source range detectors and circuitry are also required to be OPERABLE by LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation."

The Gamma-Metrics wide range shutdown monitors do not provide an automatic reactor trip protective function.

ACTIONS A.1 and A.2 With only one required source range neutron flux monitor OPERABLE, redundancy has been lost. Since these instruments are the only direct means of monitoring core reactivity conditions, CORE ALTERATIONS and introduction of coolant into the RCS with boron concentration less than required to meet the minimum boron concentration of LCO 3.9.1 must be suspended immediately. Suspending positive reactivity additions that could result in failure to meet the minimum boron concentration limit is required to assure continued safe operation. Introduction of coolant inventory must be from sources that have a boron concentration greater than that which would be required in the RCS for minimum refueling boron concentration. This may result in an overall reduction in RCS boron concentration, but provides acceptable margin to maintaining subcritical operation. Performance of Required Action A.1 shall not preclude completion of movement of a component to a safe position.

B.1 With no required source range neutron flux monitor OPERABLE, action to restore a monitor to OPERABLE status shall be initiated immediately.

Once initiated, action shall be continued until a source range neutron flux monitor is restored to OPERABLE status.

McGuire Units 1 and 2 B 3.9.3-2 Revision No. 91

Nuclear Instrumentation B 3.9.3 S

BASES B.2 With no required source range neutron flux monitor OPERABLE, there are no direct means of detecting changes in core reactivity. However, since CORE ALTERATIONS and positive reactivity additions are not to be made, the core reactivity condition is stabilized until the source range neutron flux monitors are OPERABLE. This stabilized condition is determined by performing SR 3.9.1.1 to ensure that the required boron concentration exists.

The Completion Time of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is sufficient to obtain and analyze a reactor coolant sample for boron concentration and ensures that unplanned changes in boron concentration would be identified. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Frequency is reasonable, considering the low probability of a change in core reactivity during this time period.

0 McGuire Units 1 and 2 B 3.9.3-3 Revision No. 91

Nuclear Instrumentation B 3.9.3 BASES SURVEILLANCE SR 3.9.3.1 REQUIREMENTS SR 3.9.3.1 is the performance of a CHANNEL CHECK, which is a comparison of the parameter indicated on one channel to a similar parameter on other channels. It is based on the assumption that the two indication channels should be consistent with core conditions. Changes in fuel loading and core geometry can result in significant differences between source range channels, but each channel should be consistent with its local conditions.

The Frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is consistent with the CHANNEL CHECK Frequency specified similarly for the same instruments in LCO 3.3.1.

SR 3.9.3.2 SR 3.9.3.2 is the performance of a CHANNEL CALIBRATION every 18 months. The CHANNEL CALIBRATION ensures that the monitors are calibrated. This SR is modified by a Note stating that neutron detectors are excluded from the CHANNEL CALIBRATION. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage. Operating experience has' shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 13, GDC 26, GDC 28, and GDC 29.

2.

UFSAR, Sections 4.2, 15.4.6.

3.

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

McGuire Units 1 and 2 B 3.9.3-4 Revision No. 91

ML080500142

Contents

Text

Subject:

Subject:

Subject:

Subject:

Subject:

Subject:

Subject:

Subject:

Navigation menu

ML080500142

Text

Subject:

Subject:

Subject:

Subject:

Subject:

Subject:

Subject:

Subject:

Navigation menu

Search