ML16299A350

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Forwards Reactor Physics Section Evaluation of Util Application to Reload for Cycle 6.Proposed Changes in LOCA-related Requirements Are Acceptable
ML16299A350
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 01/13/1981
From: Johnston W
Office of Nuclear Reactor Regulation
To: Reid R
Office of Nuclear Reactor Regulation
References
NUDOCS 8101270444
Download: ML16299A350 (3)


Text

JAN 1 3 1981 REGUIWORY 0 7 1 C~

MEMORANDUM FOR: Robert W. Reid, Chief Operating Reactors Branch #4, DL FROM-W. V. Johnston, Chief Core Performance Branch, DSI

SUBJECT:

OCONEE UNIT 3, RELOAD FOR CYCLE 6 (TACS 42%16)

Plant Name:

Oconee NuclearStation, Unit No. 3 Docket No.:

50-287 Originating Branch:

Operating Reactors Branch No. 4 and Project Manager:

M. Fairtile Review Branch:

Reactor Physics Section, Core Performance Branch and Reviewer:

W. L. Brooks Status:

Complete The Reactor Physics Section of the Core Performance Branch has reviewed the application of Duke Power Company to reload the Oconee Unit 3 reactor and operate it for Cycle 6. Our review was concerned with changes in Technical Specifications brought about by changes in the LOCA-related requirements on the linear heat >rate as a function of core elevation.

We find the proposed changes acceptable. Our evaluation is enilosed.

DISTRIBUTION Docket File 50-287 TERA NRC PDR W. V. Johnston, Chief Local PDR Core Performance Branch CPB Reading Division of Systems Integration WVJohnston

Enclosure:

As Stated cc: D. F. Ross T. Novak L. Rubenstein M. Fairtile D. Fieno W. Brooks 0060C1 ?4L

  • See previous record copy for concurrences OFFICE)

DSI:CPB DSI:CPB 4

DI SURNAMEO k

DFieno*

IWVJohns on DATE) 01/09/81 01/12/81 01/

/81 NRC

.FR 3810 0NR.20F C O PY

..USGPO:1980.-329-8 NRC FORM 318 10/80) NRCM 0240 OFFICIAL RECORD COPY

-USGPO:

1980-329-82 4

MEMORANDUM FOR: Robert W. Reid, Chief Operating Reactors Brach #4, DL FROM:

W. V. Johnston, Chief Core Performance Branch, DSI SUBJECT'\\

OCONEE UNIT 3, RELOAD FOR CYCLE 6 (TACS 42816)

Plant Name:

Oconee Nuclear Station, Unit No. 3 Docket No.:

50287 Originating Branch:

Operating Reactors Branch No. 4 and Project Manager:

M. Fairtile Review Branch:

Reactor Physics Section, Core Performance Branch and Reviewer:

W. L. Brooks Status:

Complete The Reactor Physics Section of the Core Performance Branch has reviewed the application of Duke Power Company to reload the Oconee Unit 3 reactor and operate it for CycleN6. Our review was concerned with changes in Technical Specification'sqbrought about by changes in the LOCA-related requirements on the linear heat rate as a function of core elevation.

We find the proposed changes acceptable. Our evaluation is enclosed.

W. V. John on, Chief Core Perform'bnce, Branch D

.ivision of S~stems Integration DISTRIBUTION

Enclosure:

Encloure:Docket File %OX50-287 As Stated TERA cc:

D. F. Ross Loc PR T. Novak T. NovakCPB Reading L. Rubenstein WVohnston M. Fairtile D. Fieno W. BrooksVo 1Cor Perfomhnc Branchd'7 OFFICEO DSI:CPB,0 DSI:CPB ZSI DSI:CPB SURNAMED WBrooks:jb DFieno WVJohnstnn

..... /..................

NRC FORM 318 (10/80) NRCM 0240 OFFICIAL RECORD COPY

,USGP: 1980-329824

Enclosure EVALUATION OF OCONEE 3 CYCLE 6 RELOAD The Reactor Physics Section of the Core Performance Branch has reviewed the effect on the rod insertion limit and axial imbalance limiting con ditions of operation caused by the reduction in allowable heat generation rate at the bottom of the core due to the TAFY-TACO conversion. In order to meet the reduced limit on the power in the lower half of the core during the first 50 effective full power days of the cycle the allowable negative imbalance has been reduced, the amount of control rod insertion allowed at full power has been decreased and the amount of permitted withdrawal of the axial power shaping rods has been reduced.

All of these actions are in a direction to reduce the power at the bottom of the core. The techniques used to obtain the revised limiting conditions of operation are the same as have been previously used to obtain limiting operating conditions. On the basis of our review, which is discussed above, we conclude that the revised Technical Specifications are acceptable.

A further Technical Specification (3.5.2.9) specifies that the curves shown in the various Specifications shall be valid only to the end of the nominal cycle length (in spite of the open ended nature, e.g.,

Figure 3.5.2-1C3 which is designated for use after 200 + 10 EFPD).

However., use of these curves would be permitted after the end of the nominal cycle if analyses are performed which confirm their suitability.

Such use would not, therefore, involve a Technical Specification change.

If analyses failed to confirm the suitability of the curves, a Technical Specification change would have to be obtained to continue operation beyond the nominal cycle length. We find this approach to be acceptable.