NL-04-0233, Technical Specifications Bases Revisions for 2003

Technical Specifications Bases Revisions for 2003

ML040620280
Person / Time
Site:	Hatch
Issue date:	02/24/2004
From:	Sumner H Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-04-0233
Download: ML040620280 (4)

Text

H.L Sumner, Jr. Southern Nuclear Vice President Operating Company. Inc.

Hatch Project Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7279 SOUTHERNAE February 24, 2004 COMPANY Energy to Serve YourWorld' Docket Nos.: 50-321 NL-04-0233 50-366 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Edwin 1.Hatch Nuclear Plant Technical Specifications Bases Revisions for 2003 Ladies and Gentlemen:

Enclosed is a summary of the Plant Hatch Technical Specifications (TS) Bases changes made under 10 CFR 50.59 for the year 2003. This summary is provided under the provisions of the Bases Control Program TS Section 5.5.11.

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

Sincerely, H. L. Sumner, Jr.

HLS/OCV/sdl

Enclosures:

Bases Revisions for 2003 cc: Southern Nuclear Operating Company Mr. J. B. Beasley, Jr., Executive Vice President Mr. G. R. Frederick, General Manager - Plant Hatch Document Services RTYPE: CHAO2.004 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. C. Gratton, NRR Project Manager - Hatch Mr. D. S. Simpkins, Senior Resident Inspector - Hatch oD (

Enclosure Edwin 1. Hatch Technical Specifications Bases Changes under 10 CFR 50.59 Licensing Document Change Request (LDCR) 2002-081 Units I and 2. Section B 3.8.1 This Bases change was made to provide the following clarifications on use of the diesel generator 14 day Technical Specifications (TS) Allowed Out of Service time (AOT):

• The 14 day AOT may only be used once per diesel generator per operating cycle for the purpose of performing a planned major overhaul of the diesel generator.

• The 14 day AOT may be used as needed to complete unplanned maintenance, although, that time should be minimized.

• An additional statement was added to indicate that, for the swing diesel generator, the 14 day AOT may be used when it is inhibited from automatically aligning to either unit I or unit 2.

The above clarifications are consistent with the probabilistic analysis done in support of the diesel generator TS AOT extension to 14 days, granted to Plant Hatch Units I and 2 under TS amendments 231 and 172, respectively.

LDCR 2002-091 Unit 1. Section B 3.6.3.1 This Bases change was made to clarify the conditions for leaving a Containment Atmosphere Dilution (CAD) valve in the non-accident position.

SR 3.6.3.1.2 of the Unit I TS requires verification that the CAD system valves be aligned correctly. The SR is to be performed every 31 days. Prior to the change, the Bases section for the SR stated that a CAD system valve could be left in the non-accident position provided it could be re-aligned to the accident position within the time assumed in the accident analysis.

This Bases change was made to specifically identify that time as nine hours. The nine hours is based on the Unit I FSAR analysis for combustible gas control.

LDCR 2003-001 Units I and 2. Section B 3.1.8 This Bases change adds an opening time acceptance criterion for the Scram Discharge Volume (SDV) vent and drain valves. TS Surveillance Requirement (SR) 3.1.8.3 E-I

Enclosure Edwin 1.Hatch Nuclear Plant Technical Specifications Bases Changes under 10 CFR 50.59 requires that the SDV vent and drain valves be verified to close on a scram signal and to open upon the scram reset. The TS contains an explicit requirement for the valves to close in 60 seconds. However, no explicit criterion exists in the TS for valve opening.

This Bases change was made to state that the valves must open prior to receipt of the control rod block on high water level in the discharge volume. This requirement ensures that the valves can open in time to preclude a scram on high level and maintain sufficient volume to contain the water discharged by the control rod drives during a scram.

LDCR 2003-003 Units I and 2. Section B 3.3.3.1 This Bases change was made to item #2 of Section B 3.3.3.1, "Reactor Vessel Water Level," to reflect a design change which eliminated some fuel zone level indicators and routed their input to a fuel zone recorder. Also, a description of the temperature compensation for the fuel zone recorder was added to the Bases.

LDCR 2003-005 Units I and 2, Section B 3.3.1.1 This Bases change was made to accurately reflect the Technical Specifications (TS)

Operability requirements for Intermediate Range Monitors (IRMs).

Specifically, earlier TS amendments (233 and 175 for Units I and 2) revised the Operability requirements for the IRMs from three per channel to two per channel. Of course, the corresponding Bases were changed with that TS change. However, a statement concerning an old analysis which assumed three IRMs operable was left in the Bases. This resulted in confusion with some plant operators and consequently, a change was made to the Bases under LDCR 2003-005 to clarify that statement.

The analysis performed with three IRMs operable is still referenced in the Bases for historical purposes. However, it is now clear that the analysis of record assumes two IRMs operable per channel.

LDCR 2003-070 Units I and 2 Sections B 3.3.1. B 3.3.2. B 3.3.1.1. B 3.3.2.2. B 3.3.4.1. B 3.3.6.1. B 3.7.6, and B 3.7.7 Revisions were made to several sections of the Unit I and 2 Bases to support implementation of the thermal power uncertainty TS change, granted to Hatch Units I E-2

Enclosure Edwin 1. Hatch Technical Specifications Bases Changes under 10 CFR 50.59 and 2 via amendments 238 and 180, respectively. The Bases were changed to reflect the change in the power distribution limits TS applicability from 25% to 24% thermal power and to reflect the change in the turbine stop and control valve closure Reactor Protection System bypass from 28% to 27.6% power. Also, references to the old licensed thermal power level were changed from 2763 CMWt to 2804 CMWt.

E-3