L-MT-04-047, Technical Specification Bases Change 138a

Technical Specification Bases Change 138a

ML042080511
Person / Time
Site:	Monticello
Issue date:	07/26/2004
From:	Thomas J. Palmisano Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-04-047
Download: ML042080511 (4)

Text

Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC July 26, 2004 L-MT-04-047 Technical Specification 6.8.K U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 Technical Specification Bases Change 138a Using the Monticello Technical Specification Bases Control Program, one Monticello Technical Specification Bases page has been changed. The affected page is designated with the amendment applicable at the time and the suffix a. The change is summarized in Enclosure 1. A final typed copy of the changed page that is applicable, for entry into the NRC authority copy, is provided in Enclosure 2.

This letter makes no new commitments or changes to any existing commitments.

If you have any questions please contact John Fields, Senior Regulatory Affairs Engineer (763-295-1663).

Thomas J. Palmisano Site Vice President, Monticello Nuclear Power Plant Nuclear Management Company, LLC Enclosures (2) cc: Administrator, Region III, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC 2807 West County Road 75

• Monticello, Minnesota 55362-9637 Telephone: 763.295.5151

• Fax: 763.295.1454

ENCLOSURE 1

SUMMARY

OF TECHNICAL SPECIFICATION BASES CHANGE (TSBC)

Following is a summary of the bases changes forwarded herein. The changes have been processed in accordance with the Monticello Technical Specification Bases Control Program described in Technical Specification 6.8.K.

TSBC-138a Technical Specification (TS) Involved - TS Table 4.1.1 Pages affected - 42 Summary of Change: Added clarifying statements to identify that testing of both the Automatic and Manual Scram Channel Logic needs to be performed. Provided a basis for the testing along with the method for testing.

Page 1 of 1

ENCLOSURE 2 REVISED MONTICELLO TECHNICAL SPECIFICATION BASES PAGES This enclosure consists of the revised Monticello Technical Specification Bases page that incorporates the change. This page should be entered into the NRC Authority copies of Technical Specifications. The page included is listed below:

Page 42 1 page follows

Bases 4.1:

The instrumentation in this section will be functionally tested and calibrated at regularly scheduled intervals. Specific surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30851P, Technical Specification Improvement Analysis for BWR Reactor Protection System, as approved by the NRC and documented in the SER dated July 15, 1987 (letter to T A Pickens from A Thadani).

Table 4.1.1 INSTRUMENTATION CHANNEL Manual Scram refers to a manually initiated trip of both the MANUAL and AUTO Scram Channel Logic in accordance with GE Topical Report NEDC-30851P. The topical report permitted relaxation of instrument channel testing provided manual testing of the auto scram channels was performed on a weekly basis. Weekly testing of the auto scram contactors is performed by tripping each channel through actuation of that channels test switch (manually initiated scram).

Calibration frequency of the instrument channel is divided into two groups as defined on Table 4.1.2.

Experience with passive type instruments indicates that a yearly calibration is adequate. Where possible, however, quarterly calibration is performed. For those devices which employ amplifiers etc., drift specifications call for drift to be less than 0.5%/month; i.e., in the period of a month a drift of 0.5% would occur and thus provide for adequate margin. For the APRM system, drift of electronic apparatus is not the only consideration in determining a calibration frequency. Change in power distribution and loss of chamber sensitivity dictate a calibration every three days. Calibration on this frequency assures plant operation at or below thermal limits.

4.1 BASES NEXT PAGE IS 45 42 06/10/04 Amendment No. 63, 81, 103, 138a