ML20086R300

Rev to LAR 250 to License DPR-50,clarifying Section III, SE Justifying Change for source-range Nuclear Instrumentation SRs

ML20086R300
Person / Time
Site:	Three Mile Island
Issue date:	07/24/1995
From:	Broughton T GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20086R297	List: ML20086R295 ML20086R300
References
NUDOCS 9507310090
Download: ML20086R300 (4)

Text

.,

. METROPOLITAN EDISON COMPANY

, JERSEY CENTRAL POWER AND LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -

Operating License No. DPR-50 Docket No. 50-289 Facility Operating License Amendment Request No. 250 - Revision THE STATE OF PENNSYLVANIA )

) SS:

COUNTY OF DAUPHIN )

This Facility Operating License Amendment Request is submitted in support of Licensee's request to amend the Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1.

GPU NUCLEAR CORPORATION BY:

Vice President and Director, TMI Swo and subsc before me this S #/ day of 1/ //>> . ,1995.

V9 l ll tan YW Notary Public Notars) Seal Debra S. Khck, Notary Pub!ic fi Cor ~

xpres J */ 98

,wnew-mns 9507310090 950724 PDR P ADOCK 05000289 PDR

t 4 $

. UNITED STATES OF AMERICA  !

NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 ,

GPU NUCIEAR CORPORATION LICENSE NO. DPR-50 ,

CEKliFICATE OF SERVICE l This is to certify that a copy of the License Amendment Request No. 250 - Revision is submitted in support of Licensee's request to change the Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1, has, on the date given below, been filed with -  ;

executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:

Mr. Jay H. Kopp, Chairman Mr. Russell L. Sheaffer, Chairman Board Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse  ;

Middletown, PA 17057 Harrisburg, PA 17120 Director, Bureau of Radiation Protection  ;

PA Dept. of Environmental Resources ,

P.O. Box 2063 Harrisburg, PA 17120 t Att: Mr. Robert Barkanic l

GPU NUCLEAR CORPORATION l BY: M b*

Vice President add Director, TMI .j DATE: July 24,1995 l

l

, , ENCLOSURE  !

i Three Mile Island Nuclear Plant, Unit 1 (TMI-1)

Operating License No. DPR-50 I Docket No. 50-289 '

Facility Operating License Amendment Request No. 250 - Revision III. SAFETY EVALUATION JUSTIFYING CHANGE The safety functions and requirements for Nuclear Instrumentation are specified in the TMI-1 i

Technical Specificat ons: (a) Section 3.5.1 " Operational Safety Instrumentation"; (b) Section '

3.5.5, " Accident M( nitoring Instrumentation"; and, (c) Section 3.8, " Fuel Imading and -

Refueling; (d) Table 4.1-1, " Instrument Surveillance Requimments," Items 5. and 6. for Intennediate and Source Range channels, respectively; and, (e) Table 4.1-4, ." Post Accident Monitoring Instrumentation," Item 10. Wide Range Neutron Flux. This Tech. Spec. Change Request affects only Item 6. of (d) above, and does not impact upon any other requirement. l (a) Tech. Spec. 3.5.1.5 requires that, "During STARTUP when the intermediate range instruments come on scale, the overlap between intermediate range and source range shall not '

be less than one decade." The Nuclear Instrumentation source-range instnaments provide i indication of reactor power during reactor startup until reactor power has increased to the t point where the intennediate-range nuclear instruments are on scale. This TSCR does not change requirements for checking that the overlap between intennediate range and source .

mnge be not less than one decade, during STARTUP.

(b) Tech. Spec. 3.5.5 Bases states: "The operability of design basis accident monitoring instrumentation as identified in Table 3.5-3, ensures that sufficient information is available on selected plant pammeters to monitor and assess the variables following an accident." The  :

wide-range nuclear instruments channels pmvide post-accident monitoring of reactor power.

The current surveillance requirements are that a channel check be performed weekly and a '

calibration be performed on an interval not to exceed 24 months. This TSCR does not change surveillance requirements for the wide-range nuclear instrument channels, as found in (e) '

above.

(c) Tech. Spec. 3.8 Bases, states that, " Continuous monitoring of radiation levels and neutron h

flux provides immediate indication of an unsafe condition during refueling and fuel loading activities." Testing of the souree-range channels six (6) months prior to a reactor restart is acceptable based on the 0.5 % drift specified by the manufacturer, GAMMA-METRICS, Inc.

and will have no impact upon continuous monitoring capability, nor will it impact the ability to provide immediate indication of an unsafe condition during refueling.

T

. Three Mile Island Nuclear Plant, Unit 1 (TMI-1)

- Operating License No. DPR-50

. Docket No. 50-289

, Facility Operating License Amendment Request No. 250 - Revision (d) This TSCR serves only to replace the seven-day test requirement for the source-range nuclear instmmentation with a requirement to test these NI channels within six (6) months prior to each reactor startup, as indicated on Tech. Spec. Table 4.1-1, Item 6; based on the manufacturer GAMMA-METRICS, Inc. specification that this equipment exhibits a maximum drift rate of i0.5% of span over six months. The source range NI test verifies the operation and accuracy of the electronics, excluding the detector, and includes: (i) Power supply voltages; (ii) Built-in test features, which are used to simulate counts and count rates and to check the accuracy of the electronics, panel meters, and the computer; and, (iii) Bistable setpoints and their outputs are tested. This TMI channel test for the source-range NI is equivalent to the calibration test (with the application of the Note that excludes the detectors) of the Standardized Technical Specifications (STS)', except that the TMI-l Tech. Specs.

presently requires this " test" to be done 7-days prior to reactor staitup, whereas the STS would only require a calibration to be done on a refueling interval. Therefore, performance of this test in accordance with the proposed 6-month interval in this TSCR is still more conservative than the calibration interval of the new STS.

Further, GPUN has determined that the small incremental drift between conducting the Test and STARTUP will have no impact upon nuclear safety, based on the manufacturer's data.

Generic Ixtter 91-04 provides for the use of manufacturer's data in lieu of statistical observation pursuant to Enclosure 2. GPUN's experience based on observed operation of these instruments (NI-l1/12), following connection and turnover to operations during the 9R refueling outage, found that instmment drift was minimal; however, it is not statistically valid based upon limited amount of plant specific data. This change will have no impact on any Technical Specification governing the safety functions and requirements for the source range instmmentation; and, in particular, Tech. Specs. 3.5.1.5 and 3.5.5 ensure that these instruments are operable prior to STARTUP and that the equipment is functional with respect to its safety requirements.

' NUREG-1430, Revision 1