ML20073H789

Application for Amend to License DPR-16,revising Tech Spec Table 4.15.2,Items 2.a & 3.a to More Accurately Reflect Requirements of Presently Installed Instrumentation

ML20073H789
Person / Time
Site:	Oyster Creek
Issue date:	04/25/1991
From:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20073H755	List: ML20073H750 ML20073H789 ML20073H808
References
NUDOCS 9105070264
Download: ML20073H789 (4)

Text

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GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 l-l Technical Specification Change Request No. 197

' Docket No. 50-219 Applicant submits, by this Technical Specification Change Request No. 197, to the Oyster Creek. Nuclear Generating Station Technical Specifications, a change to pageo'4.15-4, 4.15-5.

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[ . Barton tir, Oyster Creek Sworn'and subscribed to before me this 25th- day og. April 1993,

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NtfMRY PUBLIC OF NEW JERSEY JUDTTH M. CROWE r -

Notary Putdio of New My Commiselon Egiros // d /4 (

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t i OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCl'ET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST Applicant hereby requests the commission to change Appendix A to the above captioned license an indicated below. Pursuant to 10CFR50.91, an analysis concerning the determination of no significant hazards considerations is also presented:

1. Sectionn to be Chanood 4.15

2. Extent of Chance o

Modify channel Functional Test requirements for the Main Stack Monitoring System (Stack RAGEMS) and Turbine Building Ventilation Monitoring System (Turbine RAGEMS) radioactive noble gas monitors currently existing in the Technical Specificatione. Theco two (2) systems are installed to comply with NUREG 0737,Section II.F.1, Items 1 and 2 to addrene the equipment which was installed prior to operating cycle 12.

3. Chances Recuested These changes are indicated on the attached revised Technical Specification Table 4.15.2 and Table 4.15.2 Notations.

4. Discussions NUREG 0737,Section II.F.1., Items 1 and 2 require each nuclear generating station to have the capability to detect and measure concentrationa of radioactive noble gas fission producto from the plant's gaseous effluent releases during and following an accident.

Two Radioactive Gaseous Effluent Monitoring Systems (RAGEMS) have recently been fully placed into service at Oyster Creek to perform this function; one to monitor releases at the Main Stack (RAGEMS I) and the other to monitor the Turbine Building vents (RAGEMS II). Both of these monitoring systems are comprised of new state-of-the-art equipment for the radioactive noble gas monitors, which are housed in their own racka.

The noble gas monitors in RAGEMS I contain many vernier devices allowing for periodic instrument adjustments used to maintain that instrument within acceptable limita throughout its life. This new instrument with its vernier devices allows for much greater accuracy and-flexibility for its specific functione, i.e. measuring, counting, amplification, etc, throughout the instrument's life.

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Upon fully placing the RAGEMS I system into service prior to Oyster Creek's Operating Cycle 12, the positions of these vernier devices were approximated. Approximately one (1) year was required with the systems in operation for their proper positions to be established during various modes of plant operation. Prior to placing RAGEMS I into service, covers were installed over the instrument racks with alarms to the Control Room when the covers were opened. GPU Nuclear Administrative Procedures controlled the various switch positions of the instrument while data was collected on precise vernier positions. This is the operating procedure currently used.

However, the increased complexity of the RAGEMS I system with this ability to change / finely adjust switch positions does not lend itself to the simplistic operate / test conditions utilized by th9 previous system. The replaced system utilized more simplistic enep actica switches. Therefore, the :xisting iechnical Specification (note "e.3") is no longer appropriate for the new upgraded RAGEMS I system. _

GPU Nuclear is proposing to add a new notation "h" in Table 4.15.2 for the radioactive noble gas monitor in RAGEMS I. Currently in the RAGEMS I System, alarms for measured levels above alarm setpoint and low countrate/ monitor failure are hardwired to the control room. A more specific channel Functional Test Item which shall verify Control Room  ;

annunciation of the switch cover alarms after the face plate switches are verified in their correct positions is being requested as item h.3.

In the RAGEMS II system, each mode of operation is controlled by an Allen-Bradley Programmable Controller which provides a Control Room trouble alarm via computer for measured levels above alarm setpoint, and low countrate/ monitor failure. GPU Nuclear is proposing to add a new notation "i" in Table 4.15.1 for the noble gas monitor in RAGEMS II, which addresses testing necessary to demonstrate RAGEMS II functional capability.

Both RAGEMS systems' alarms continue to be checked during each Channel Functional Test per the Technical Specifications.

5. potermination GPU Nuclear has determined that operation of the Oyster Creek Nuclear Generating Station in accordance with the proposed Technical Specifications does not involve a significant hazards consideration. The changes do not:

A. Involve a significant increase in the probability or the consequences of an accident previously evaluated. The radioactive noble gas monitors are installed to provide the plant operators with information on noble gas effluent releases during and following an accident as required by NUREG 0737, Section !I.F.1, Items 1 and 2. This modification to the specifications of this accident monitoring equipment does not af fect plant operations during normal operating conditions, and thus does not involve an increase in the probability of i an accident, and thus does not involve an increase in the consequences of an accident previously evaluated. .

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Upon fully placing the RAGEMS I system into service prior to-Oyster Creek's Operating Cycle 12, the positions of these vernier devices were approximated. 'Approximately one (1) year was required with the systems in operation for their proper positions to be established during various modes of plant operation. Prior to placing RAGEMS I into service, covers wero installed over-the instrument. racks with alarms to the Control Room when the covers were opened. GPU Nuclear Administrative Procedures controlled the various switch positions of the instrument while data was collected on precise vernier positions. This is the opeaating procedure currently usad.

However,_the increased complexity of the RAGEMS I system with this ability to change / finely adjust switch positions does not lend itself to the simplistic operate / test conditions utilized by the previous system. The replaced system utilized more simplistic anap action switches. Therefore, the existing Technical Specification (note "e.3") is no longer appropriate for the new upgraded RAGEMS I system.

-GPU Nuclear is proposing to' add a new notation "h" in Table 4.15.2 for the radioactive noble gas monitor in RAGEMS I. Currently in the RAGEMS I System, alarms for measured levels above alarm setpoint and low countrate/ monitor failure are hardwired to the control room. A more

-specific Channel' Functional Test Item which shall verify Control Room annunciation-of the switch cover alarms after the face plate switches are verified in their correct positions is being requested as item h.3.

-In the.RAGEMS II-system, each mode of operation is controlled by an Allen-Bradley. Programmable controller which provides a control Room trouble alarm via-computer for measured levels above alarm setpoint, and low

-countrate/ monitor-failure. GPU Nuclear is proposing to add a new notation "1" in Table 4.15.1 for the. noble gas monitor in RAGEMS II, which addresses testing necessary to demonstrate RAGEMS II functional capability.

Both RAGEMS sy' stems' alarms continue to be checked during each Channel Functional Test per the Technical Specifications.-

5. Determination GPU Nuclear has determined that operation of the Oyster Creek Nuclear

Generating Station in accordance with the proposed Technical Specifications does not-involve a significant hazards consideration. The changes do not A. Involve a significant increase in the probability or the consequences

-of an accident previously evaluated. The radioactive noble gas monitors are-installed-to provide the plant operators with information on noble gas effluent releases during and following an accident as required-by NUREG.0737,Section II.F.1, Items 1 and 2. This

modification to the_ specifications of this accident monitering equipment does'not affect plant operations-during normal operating ,

conditions, and' thus does not involve an increase in the probability of '

.an -accident', and thus_does not involve an increase in the consequences J

of an accident previously evaluated.

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I B . =- Create the' possibility'of a now:or different. kind of accident from any previously evaluated. . The RAGEMS' systema do not interface with any -

- nuclear = plant.' systems, and thus cannot initiate a new or dif ferent type of' accident.-

C. --- Involve a significant reduction in a margin.of safety. The proposed I changes'shall provide assurance that the operability of the radioactive

' noble gas monitors -and associated electronics' will be maintained within acceptable limits. Therefore this ' change does not reduce the margin of safety.-

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