NL-07-0277, Technical Specifications Bases Changes for 2006

Technical Specifications Bases Changes for 2006

ML070510425
Person / Time
Site:	Hatch
Issue date:	02/19/2007
From:	George B Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-07-0277
Download: ML070510425 (4)

Text

Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERNI- \

COMPANY February 19, 2007 Energy to Serve Ybur WorldsM Docket Nos.: 50-321 50-366 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Technical SpecificationsBases Changes for 2006 Ladies and Gentlemen:

Attached please find summaries for the Technical Specifications Bases changes that were made at Plant Hatch for the year 2006. These summaries are being provided in accordance with the provisions of the Technical Specifications Bases Control Program, 5.5.1 1.d.

This letter contains no NRC commitments. If you have any questions, please advise.

Manager, Nuclear Licensing

Enclosure:

Technical Specifications Bases Changes for 2006 cc: Southern Nuclear Operating Companv Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President - Hatch Mr. D. H. Jones, Vice President - Engineering RTYPE: CHA02.004 U. S. Nuclear Regulatory Commission Dr. W. D. Travers, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Hatch Mr. D. S. Simpkins, Senior Resident Inspector - Hatch

Enclosure Edwin I. Hatch Nuclear Plant Technical Specifications Bases Changes for 2006

Edwin I. Hatch Nuclear Plant Technical Specifications Bases Changes for 2006 Licensing Document Change Request (LDCR) 2005-063 This LDCR implemented the Bases changes resulting from a revision of LC0 3.0.4 to the Technical Specifications (TS). The new LC0 3.0.4 was implemented at Plant Hatch Units 1 and 2 under Amendments 246 and 190, respectively. The changes are a part of the BWR industry Risk Informed TS initiatives; they revise the conditions under which mode changes may be made while relying on ACTION statements. The new LC0 provides for the performance of risk assessments to support such changes in modes. The corresponding Bases contains more detailed guidance on the performance of the actual risk assessments. These TS Bases changes were provided to the NRC as information with the TS submittal package and were then implemented under the provisions of 10 CFR 50.59.

LDCR 2005-064 This LDCR was implemented under the provisions of 10 CFR 50.59 and corrected a typographical error in Unit 1 Bases Section B 3.6.2.3, "Suppression Pool Cooling". A statement in the LC0 paragraph referred to a suppression pool "spray" subsystem. The word "spray" was changed to "cooling".

LDCR 2006-003 The "Applicable Safety Analysis" section of Units 1 and 2 Bases sections B 3.1.7 was revised to update the natural boron concentration that must be injected into the reactor core following an Anticipated Transient Without Scram. The value was changed from 660 ppb to 800 ppb. This resulted from a TS change to Standby Liquid Control Figure 3.1.7-1, "Sodium Pentaborate Solution Volume vs Concentration Requirements,"

implemented under Amendments 247 and 191 to the Hatch Units 1 and 2 TS, respectively. The change was made to accommodate new, higher energy, fuel designs for Plant Hatch. These Bases changes were provided to the NRC as part of the TS submittal package and were implemented at Plant Hatch under the provisions of 10 CFR 50.59.

LDCR 2006-005 The Units 1 and 2 TS were changed via Amendments 248 and 192 respectively to eliminate Unit 1 Surveillance Requirement (SR) 3.6.1.3.1 1 and Unit 2 SR 3.6.1.3.12.

These SRs dealt with primary containment isolation valves with resilient seats, and required replacing those seats every 24 months. The SRs were replaced with an Appendix J requirement to leak rate test the valves at a frequency of 30 months. The corresponding Bases changes eliminated the discussion of these SRs and were provided to the NRC in the TS revision request package as information. The changes were then implemented into the Hatch Bases via the provisions of 10 CFR 50.59.

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Edwin I. Hatch Nuclear Plant Technical Specifications Bases Changes for 2006 LDCR 2006-062 A section was added to the Units 1 and 2 TS Bases to support new TS LC0 3.0.8. This L C 0 was added to Section 3.0 of the Units 1 and 2 TS under Amendments 250 and 194, respectively, and provided an allowance for systems with non-functional snubbers. The changes are part of the BWR Industry Risk Informed TS initiatives. The LC0 allows a delay time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for snubbers associated with single subsystem components, and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for snubbers associated with dual subsystem components, prior to having to declare the associated L C 0 not met. This delay time is allowed only if "risk is assessed and managed." The LC0 3.0.8 Bases provides additional information on the performance of the risk evaluation, as well as information on the functional types of snubbers which are applicable to the LC0 guidance. The corresponding Bases were provided to the NRC with the original submittal package and implemented at the plant under the provisions of 10 CFR 50.59.

LDCR 2006-067 This LDCR was implemented under the provisions of 10 CFR 50.59 and clarified the Standby Gas Treatment System (SBGT) drawdown requirements for the secondary containment. SR 3.6.4.1.3 requires the SBGT system to drawdown the secondary containment to 2.20 inches of water vacuum gauge in 5 120 seconds. This change was made to the above listed SR Bases section to clarify that 13 seconds of diesel generator startup and breaker closing time is included in that 120 seconds.

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