ML072700458

Transmittal of Technical Specifications Bases Manual Revisions

ML072700458
Person / Time
Site:	McGuire, Mcguire
Issue date:	09/20/2007
From:	Beaver B Duke Energy Corp
To:	Office of Nuclear Reactor Regulation
References
DUK072630001
Download: ML072700458 (9)

Text

PRIORITY Normal DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW 1) 2)

3) 4)

5) 6)

7) 8)

9) 10) 11) 12) 13) 14) 15) 01623 G L MONTGOMERY MG01WC 01749 L C GIBBY - MG01VP 02049 NGO PRA MANAGER ECO81 02388 DAVID DZIADOSZ LYNCHBG, VA 02532 MCG NRC INSP MG-ADMIN MAIL RM 02546 WC LIBRARY-MG01WC 03044 MCG DOC CNTRL MISC MAN MGO5DM 03283 P R TUCKER MG01RP 03614 MCG OPS PROCEDURE GP MG01OP 03743 MCG OA TEC SUP MNT OC MG01MM 03744 OPS TRNG MGR. MG03OT 03759 U S NUC REG WASHINGTON, DC 03796 SCIENTECH DUNEDIN, FL 04698 D E BORTZ EC08G 04809 MCG PLANT ENG. LIBR. MG05SE Duke Energy DOCUMENT TRANSMITTAL FORM REFERENCE MCGUIRE NUCLEAR STATION RECORD RETENTION # 005893 TECHNICAL SPECIFICATIONS (TS)

AND TECHNICAL SPECIFICATIONS BASES (TSB)

Date:

09/20/07 Document Transmittal #:

DUK072630001 QA CONDITION

[- Yes

• No OTHER ACKNOWLEDGEMENT REQUIRED

• Yes IF OA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

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

28078 Rec'd By Page 2 of 3 Date DOCUMENT NO TS & TSB MEMORANDUM TSB LIST OF EFFECTIVE SECTIONS (4 PAGES)

TSB 3.9.7 (3 PAGES)

CA COND REV #/DATE DISTR CODE 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 TOTAL

-~

+

4 4

4

+

~

~

4

+

~

+

4-4-+-~

+

4

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NA NA NA

--- 09/17/07 086 09/17/07 088 09/05/07 MADM-04B V1 Vi vl V1 V1 Vl Vi V1 V1 V3 V8 V1 V1 V2 48 REMARKS: PLEASE UPDATE ACCORDINGLY RECIPIENT # 00422 PREVIOUSLY COMPLETED G R PETERSON VICE PRESIDENT MCGUIRE NUCLEAR STATION BY:

B C BEAVER MG01RC BCB/CMK

September 17, 2007 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 85 TS Bases List of Effected Sections Rev 86 Tech Spec Bases: 3.9.7 (Rev 0) (Entire Bases)

Tech Spec Bases 3.9.7 (Rev 88) (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 53 2/17/04 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 86

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 4/4/0 5 4/4/0 5

.4/4/05 5/28/03 9/2 5/0 6 2/17/04 12/04/06 4/23/05 McGuire Units 1 and 2 Pg eiin8 Page 2 Revision 86

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 41 7/29/03 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 Revision 86

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

McGuire Units 1 and 2 Page 4 Revision 86

Refueling Cavity Water Level B 3.9.7 B 3.9 REFUELING OPERATIONS B 3.9.7 Refueling Cavity Water Level BASES BACKGROUND The movement of irradiated fuel assemblies or performance of CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts, within containment requires a minimum water level of 23 ft above the top of the reactor vessel flange. During refueling, this maintains sufficient water level in the containment, refueling canal, fuel transfer canal, refueling cavity, and spent fuel pool. Sufficient water is necessary to retain iodine fission product activity in the water in the event of a fuel handling accident (Refs. 1 and 2). Sufficient iodine activity would be retained to limit offsite doses from the accident to within 10 CFR 50.67 (ref. 3) limits, as provided by the guidance of Reference 1.

APPLICABLE SAFETY ANALYSES During CORE ALTERATIONS and movement of irradiated fuel assemblies, the water level in the refueling canal and the refueling cavity is an initial condition design parameter in the analysis of a fuel handling accident in containment, as postulated by Regulatory Guide 1.183 (Ref. 1). Regulatory Guide 1.183 Appendix B provides the regulatory positions applicable to evaluating the radiological consequences of a fuel handling accident. The methodology stipulates a minimum water level of 23 feet to apply an effective iodine decontamination factor of 200 to the chemical forms of iodine given in Reference 1.

The fuel handling accident analysis inside containment is described in Reference 2. With a minimum water level of 23 ft and a minimum decay time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to fuel handling, the analysis and test programs demonstrate that the iodine release due to a postulated fuel handling accident is adequately captured by the water and offsite doses are maintained within allowable limits (Refs. 1 and 4).

Refueling cavity water level satisfies Criterion 2 of 10 CFR 50.36 (Ref. 5).

I LCO A minimum refueling cavity water level of 23 ft above the reactor vessel flange is required to ensure that the radiological consequences of a postulated fuel handling accident inside containment are within acceptable limits, as provided by the guidance of Reference 1.

McGuire Units 1 and 2 B 3.9.7-1 Revision No. 88

Refueling Cavity Water Level B 3.9.7 BASES APPLICABILITY LCO 3.9.7 is applicable during CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts, and is also applicable when moving irradiated fuel assemblies within containment. The LCO minimizes the possibility of a fuel handling accident in containment that is beyond the assumptions of the safety analysis. If irradiated fuel assemblies are not present in containment, there can be no significant radioactivity release as a result of a postulated fuel handling accident.

Requirements for fuel handling accidents in the spent fuel pool are covered by LCO 3.7.13, "Spent Fuel Pool Water Level."

ACTIONS A.1 and A.2 With a water level of < 23 ft above the top of the reactor vessel flange, all operations involving CORE ALTERATIONS or movement of irradiated fuel assemblies within the containment shall be suspended immediately to ensure that a fuel handling accident cannot occur.

The suspension of CORE ALTERATIONS and fuel movement shall not preclude completion of movement of a component to a safe position.

SURVEILLANCE SR 3.9.7.1 REQUIREMENTS Verification of a minimum water level of 23 ft above the top of the reactor vessel flange ensures that the design basis for the analysis of the postulated fuel handling accident during refueling operations is met.

Water at the required level above the top of the reactor vessel flange limits the consequences of damaged fuel rods that are postulated to result from a fuel handling accident inside containment (Ref. 2).

The Frequency of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is based on engineering judgment and is considered adequate in view of the large volume of water and the normal procedural controls of valve positions, which make significant unplanned level changes unlikely.

McGuire Units 1 and 2 B 3.9.7-2 Revision No. 88

RefuelingCavity Water Level B 3.9.7 BASES REFERENCES

1.

Regulatory Guide 1.183, Rev. 0.

2.

UFSAR, Section 15.7.4.

3.

10 CFR 50.67, Accident Source Term.

4.

Malinowski, D. D., Bell, M. J., Duhn, E., and Locante, J., WCAP-7828, Radiological Consequences of a Fuel Handling Accident, December 1971.

5.

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

I McGuire Units 1 and 2 B 3.9.7-3 Revision No. 88