ML15264A448

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Forwards Request for Addl Info Re 860813 Amend Request to Raise Reactor Trip Setpoint from 2,300 to 2,355 Psig. Response Requested within 45 Days of Ltr Date
ML15264A448
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 03/31/1987
From: Stolz J
Office of Nuclear Reactor Regulation
To: Tucker H
DUKE POWER CO.
References
NUDOCS 8704070055
Download: ML15264A448 (2)


Text

March 31, 1987 Docket Nos.

50-269, 50-270 and 50-287 Mr. Hal B. Tucker Vice President - Nuclear Production Duke Power Company P. 0. Box 33189 422 South Church Street Charlotte, North Carolina 28242

Dear Mr. Tucker:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION-PPOPOSED AMENDMENT ON HIGH PRESSURE REACTOR TRIP SETPOINT RE:

Oconee Nuclear Station, Units 1, 2 and 3 We have been reviewing your August 13, 1986 amendment request to raise the reactor trip setpoint from 2300 to 2355 psig. Our consultant, EG&G Idaho, has been reviewing your submittal and has determined that we need the additional information, identified in the enclosure, to complete the review.

We request that you respond to this request for additional information forty-five days of the date of this letter.

The reporting and recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under Public Law 96-511.

Sincerely,

/S/

John F. Stolz, Director PWR Project Directorate No. 6 Division of PWR Licensing-B

Enclosure:

As stated cc w/enclosure See next page Distribution:

Docket File GEdison JPartlow NRC & L PDRs EJordon BGrimes ACRS(10)

HPastis JStolz OGCA-ethesda PBD Rdg Ha s:bd 10 n t

/50/87 8

//7 5/5b/87 89704070055 870331 PDR ADOCK 05000269 P

PDR

REQUEST FOR ADDITIONAL INFORMATION

1. Considering the turbine bypass capabilities and other plant specific features for Oconee Units 1, 2, and 3, will raising the reactor trip on high pressure to 2355 psig while keeping the Power Operated Relief Valve (PORV) setpoint at 2450 psig result in more frequent liftina of the first bank or additional banks of the main steam safety valves (MSSVs)? Also, will the proposed Technical Specification change result in more frequent lifting of MSSVs than for the original plant design (i.e., 2355 psig high pressure trip, 2255 psig PORV set point and no anticipatory reactor trip on turbine trip). Provide the bases for your response.
2. If the proposed change will result in more frequent lifting of the MSSVs than for the current conditions or the original design, then state why the proposed change is acceptable.