ML060260407

Oyster Creek Generating Station - Facsimile Transmission, Draft Request for Additional Information to Be Discussed in an Upcoming Conference Call

ML060260407
Person / Time
Site:	Oyster Creek
Issue date:	02/01/2006
From:	Geoffrey Miller Plant Licensing Branch III-2
To:	Darrell Roberts Plant Licensing Branch III-2
Miller G, NRR/DLPM, 415-2481
References
%dam200604, TAC MC6046
Download: ML060260407 (3)

Text

February 1, 2006 MEMORANDUM TO: Darrell J. Roberts, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager /RA/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

OYSTER CREEK GENERATING STATION, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MC6046)

The enclosed draft RAI was transmitted by e-mail on January 25, 2006, to Mr. David Robillard, AmerGen Energy Company, LLC (AmerGen). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support an upcoming conference call with AmerGen in order to clarify certain items in the licensees submittal. The draft RAI is related to AmerGens submittal dated February 2, 2005, regarding revisions to the Oyster Creek Generating Station Technical Specifications to incorporate a Limiting Condition for Operation for the isolation trip setting and the instrumentation surveillance requirements of the reactor water cleanup system and high-energy line break detection and isolation equipment. Review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-219

Enclosure:

Draft RAI

February 1, 2006 MEMORANDUM TO: Darrell J. Roberts, Chief Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager /RA/

Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUBJECT:

OYSTER CREEK GENERATING STATION, FACSIMILE TRANSMISSION, DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI) TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MC6046)

The enclosed draft RAI was transmitted by e-mail on January 25, 2006, to Mr. David Robillard, AmerGen Energy Company, LLC (AmerGen). This draft RAI was transmitted to facilitate the technical review being conducted by the Nuclear Regulatory Commission (NRC) staff and to support an upcoming conference call with AmerGen in order to clarify certain items in the licensees submittal. The draft RAI is related to AmerGens submittal dated February 2, 2005, regarding revisions to the Oyster Creek Generating Station Technical Specifications to incorporate a Limiting Condition for Operation for the isolation trip setting and the instrumentation surveillance requirements of the reactor water cleanup system and high-energy line break detection and isolation equipment. Review of the draft RAI would allow AmerGen to determine and agree upon a schedule to respond to the RAI. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-219

Enclosure:

Draft RAI DISTRIBUTION:

Public NTrehan RidsNrrDeEicb LPL1-2 RidsNrrPMGMiller SMazumdar Accession No.: ML060260407 OFFICE NRR/LPL1-2/PM NRR/LPL1-2/LA NAME GEMiller CRaynor DATE 2/1/06 2/1/06 OFFICIAL RECORD COPY

DRAFT REQUEST FOR ADDITIONAL INFORMATION OYSTER CREEK GENERATING STATION RWCU HELB ISOLATION TAC NO. MC6046 These questions are being provided to support discussions relating to the subject license amendment request. They do not convey a formal NRC staff position.

1. The license amendment request (LAR) specifies in TS Table 3.1.1, for Function P, RWCU HELB Isolation, a "Trip Setting" of < 180 F. Explain the meaning of the terms, "Trip Setting," Check and Test used in TS Tables 3.1.1 and TS 4.1.1.

2. The GPU Nuclear Calculation. C-1302-215-E320-063 , RWCU HELB High Temperature Setpoint Error Calculation, has stated 180 F as the Process Safety Limit, 160 F as "Setpoint" and 172 F as "As-Found" values. Explain the meaning of the terms,Process Safety Limit, Setpoint" and "As-Found" used in the calculation.

3. The AmerGen Engineering Division Standard ES-002, Instrument Error Calculation and Setpoint Determination, refers to ISA-S67.04 (1982). Explain how the various tolerances, including Total Loop Uncertainty, specified in ISA-S67.04 for calculating Nominal Trip Setpoint, Acceptable As-Left, Acceptable As-Found, and Allowable Values have been accounted in the calculation of the Oyster Creek RWCU HELB Isolation tolerances and setpoints.

4. The Calc. No. C-1302-215-E320-063 states in clause 4.2 that all manufacturers data is assumed to have 3 sigma confidence level. Provide explanation for this assumption.

5. The Calc. No. C-1302-215-E320-063 states in clause 4.5 that since control logic has seal-in feature and since switch will actuate within 1 minute following RWCU HELB, error due to radiation and pressure is not considered in the calculation. Provide explanation for this conclusion.

6. The Calc. No. C-1302-215-E320-063 indicates in clause 7.6 that Test Equipment Error and Temperature Switch Error have been used twice to calculate Upper As-Found Limit.

Provide explanation why they have been used twice to calculate Upper As-Found Limit.

7. The Calc. No. C-1302-215-E320-063 indicates that drift has been positive between 05/21/91 and 01/02/93, low between 01/02/93 and 10/11/94, and mostly negative between 10/11/94 and 10/14/96. Provide explanation for using all the values except one outlier in drift evaluation of the RWCW HELB High Temperature Setpoint Error Calculation, and what investigation has been done on time dependency of this drift.

Enclosure