NRC 2007-0052, Technical Specification Bases Change Summary

Technical Specification Bases Change Summary

ML071830085
Person / Time
Site:	Point Beach
Issue date:	06/29/2007
From:	Koehl D Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2007-0052, TS 5.5.13
Download: ML071830085 (3)

Text

Committed to Nuclear ExceIIence Point Beach Nuclear Plant Operated by Nuclear Management Company, LLC June 29,2007 NRC 2007-0052 TS 5.5.1 3 10 CFR 50.71(e)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Technical Specification Bases Chanqe Summary In accordance with the requirements of Technical Specification 5.5.13 and 10 CFR 50.71(e),

Nuclear Management Company, LLC (NMC), is submitting changes made to the Point Beach Nuclear Plant (PBNP) Technical Specification Bases. contains the Technical Specification (TS) Bases change summary from June 11,2004, through December 31,2006.

This letter contains no new commitments and no revisions to existing commitments.

I Dennis L. Koehl Site Vice-President, Point Beach Nuclear Plant Nuclear Management Company, LLC Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW 6610 Nuclear Road Two Rivers, Wisconsin 54241-9516 Telephone: 920.755.2321

ENCLOSURE 1 TECHNICAL SPECIFICATIONS BASES CHANGE

SUMMARY

Date of Affected Summary Chanae Section In the last sentence of the Applicable Safety Analyses section, "Criterion 3 of the NRC Policy Statement" was changed to "Criterion 3 of 10 CFR 50.36(c)(2)(ii)

The containment purge system description was changed for Unit 2.

The outside containment valves were replaced with blind flanges.

In the last sentence of the Applicable Safety Analyses section, "Criterion 3 of the NRC Policy Statement" was changed to "Criterion 3 of 10 CFR 50.36(c)(2)(ii).

Added a sentence to E.l as follows: "This Note does not prohibit voluntary MODE changes that may be prudent for safe operation."

Under SR 3.7.2.3, deleted "Section XI" after ASME Code.

In the last sentence of the Applicable Safety Analyses section, "Criterion 2 of the NRC Policy Statement" was changed to "Criterion 2 of 10 CFR 50e36(c)(2)(ii). In Action B.l changed MODE 2 to MODE 3 to correct an administrative error.

In the last sentence of the Applicable Safety Analyses section, "Criterion 2 of the NRC Policy Statement" was changed to "Criterion 2 of 10 CFR 50.36(c)(2)(ii). Corrected Action A.2 from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to reflect correct Technical Specification (TS)

Completion Time.

Added the alarm window title for the boron dilution alarm to the Background section. In the Applicable Safety Analysis, added the specific valve name and number which actuates the alarm.

In the last sentence of the Applicable Safety Analyses section, "Criterion 3 of the NRC Policy Statement" was changed to "Criterion 3 of 10 CFR 50.36(c)(2)(ii). Changed the definition of operability to be two fans from one fan in the LC0 section.

Added a third paragraph to the LC0 section to indicate the plant process computer system (PPCS) is not used to meet operability requirements and is not safety-related Added 38% as the limit value to SR 3.4.5.2. The value includes instrument uncertainty.

Added 38% as the limit value to SR 3.4.6.2. The value includes instrument uncertainty.

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Date of Affected Summarv Chanqe Section Added 48% and 92%, respectively, as the limit values for meeting the LC0 to include instrument uncertainty.

Added a paragraph for SR 3.5.1.2 and 3.5.1.3 to include levels (volumes) and pressures as the limit values which include instrument uncertainty.

Added a paragraph for SR 3.5.4.1 and 3.5.4.2 to include levels (volumes) and pressures as the limit values which include instrument uncertainty.

Added pressures in the LC0 as the limit values which include instrument uncertainty. For SR 3.6.4.1 added pressures as the limit values which include instrument uncertainty.

For SR 3.6.5.1, added a temperature limit value that includes instrument uncertainty. Added temperature limit value which includes instrument uncertainty to LC0 section.

Added volume value and level percent value to SR 3.6.7.2 that includes instrument uncertainty.

For SR 3.7.6.1, added a sentence which explains the level differences acceptable with tanks either cross-connected or separate from each other.

For SR 3.8.3 added volume value and level percent limit value which includes instrument uncertainty. For SR 3.8.3.3, added pressures and limit values which include instrument uncertainty.

In the Actions section, first paragraph section sentence and eleventh sentence, the word "door" was changed to "bulkhead door" to clearly distinguish between the two different mechanical devices.

The containment purge system description was changed to eliminate the differences between Unit 1 and Unit 2 configurations because the modifications to both units were completed.

In the last sentence of the LCO, changed temperature from 110°F to 112.5"F to address instrument uncertainties.

In the last sentence of the Applicable Safety Analyses section, "Criterion 2 of the NRC Policy Statement" was changed to "Criterion 2 of 10 CFR 50.36(c)(2)(ii). The numerical identifiers for the incore thimbles were removed. A descriptive paragraph regarding flux map development was deleted because it provided an unnecessary level of detail.

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