ML15264A550
| ML15264A550 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/23/1988 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8808260383 | |
| Download: ML15264A550 (6) | |
Text
August 23, 1988 Docket Nos.: 50-269 DISTRIBUTION 50-270 DocketiA NRC POR 50-287 Local PDR PDII-3 Reading OCONEE FILE Mr. H. B. Tucker, Vice President S. Varga 14-E-4 Nuclear Production Department G. Lainas 14-H-3 Duke Power Company D. Matthews 422 South Church Street M. Rood ACRS (10) H-1016 Charlotte, North Carolina 28242 H. Pastis OGC E. Jordan MNBB-3302
Dear Mr. Tucker:
B. Grimes 9-A-2
SUBJECT:
DELETION OF THE NUMERICAL VALUES OF CYCLE-DEPENDENT CORE OPERATING LIMITS FROM THE TECHNICAL SPECIFICATIONS Re:
Oconee Nuclear Station, Units 1, 2, and 3 We have reviewed your September 3, 1987, proposed amendment. The proposed revisions would delete the numerical values of certain cycle-dependent core operating limits and place them in a Core Operating Limits Report. Based on our review we have concluded that your proposed wording needs to be clarified as suggested in the enclosure. Please respond as soon as possible with a revised amendment.
Sincerely, Original Signed By:
David B. Matthews, Director Project Directorare 11-3 Division of Reactor Projects -
I/Il
Enclosure:
As stated cc:
.See next page PDII-3 I-3 I-3 MRood astis:sw DMatthews 0 /11/88 0 X/1
/88 0 Y/13/88 3808 2 6 0383 8082 3 PDR ADOCK 05000:269 P
ENCLOSURE PROPOSED WORDING OF DUKE POWER COMPANY'S OCONEE TECHNICAL SPECIFICATIONS
- 1. Definition 1.9 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.
Plant operation within these core operating limits is addressed in individual specifications.
- 2. Technical Specification 3.1.3.5 and Bases 3.1.3.5 Except for physics tests...
during the approach to criticality. The regulating rods shall then be positioned within the acceptable operating limits for regulating rod position provided in the CORE OPERATING LIMITS REPORT.
Bases (The Duke Power Company's submittal of September 3, 1987 is acceptable with regard to the wording of the last sentence of the last paragraph on Technical Specification Page 3.1-9.)
- 3. Technical Specification 3.1.11 Bases (The Duke Power Company's submittal of September 3, 1987 is acceptable with regard to the wording of the second paragraph of the Bases on Technical Specification Page 3.1-23.)
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- 4. Technical Specification 3.5.2.2.d.2.c 3.5.2.2.d.2.c Position the remaining rods... limits of Specification 3.5.2.2.a and within the acceptable operating rod position withdrawal/insertion limits for regulating rod position provided in the CORE OPERATING LIMITS REPORT.
- 5. Technical Specification 3.5.2.3 3.5.2.3 The worths of single inserted control rods during criticality are limited by the restrictions of Specification 3.1.3.5 and the control rod position limits provided in the CORE OPERATING LIMITS REPORT.
- 6. Technical Specification 3.5.2.5.c 3.5.2.5.c Position limits are specified for regulating and axial power shaping control rods.
Except for physics tests or exercising control rods, the regulating control rod insertion/withdrawal limits shall be maintained within the acceptable operating limits for regulating rod position provided in the CORE OPERATING LIMITS REPORT for the particular number of operating reactor coolant pumps (4, 3, 2).
- 7. Technical Specification 3.5.2.6 3.5.2.6 Reactor power imbalance shall be monitored on a frequency not to exceed two hours during power operation above 40 percent rated power. Except for physics tests, imbalance shall be maintained within the acceptable
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.operating limits for reactor power imbalance provided in the CORE OPERATING LIMITS REPORT.
- 8. Technical Specification 3.5.2.6 Bases (The Duke Power Company's submittal of September 3, 1987 is acceptable with regard to the wording of the first sentence of the second paragraph of Technical Specification Page 3.5-11.)
- 9. Technical Specification 3.5.2 Bases (The Duke Power Company's submittal of September 3, 1987 is acceptable with regard to the wording of (1) the first sentence of the first paragraph and (2) the last paragraph of Technical Specification Page 3.5-12.)
- 10. Technical Specification 6.9 6.9 CORE OPERATING LIMITS REPORT Specification 6.9.1 Core operating limits shall be established prior to each reload cycle, or prior to any remaining part of a reload cycle, for the following:
(1) Power Dependent Rod Insertion Limits for Specifications 3.1.3.5, 3.5.2.2.d.2.c, 3.5.2.3, and 3.5.2.5.c.
(2)
Power Imbalance Limits for Specification 3.5.2.6 and shall be documented in the CORE OPERATING LIMITS REPORT.
4 6.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically:
(1) DPC-NE-1002A, Reload Design Methodology II, October 1985.
(2) NFS-1001A, Reload Design Methodology, April 1984.
6.9.3 The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.
6.9.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.
Mr. H. B. Tucker Oconee Nuclear Station Duke Power Company Units Nos. 1, 2 and 3 cc:
Mr. A. V. Carr, Esq.
Mr. Paul Guill Duke Power Company Duke Power Company P. 0. Box 33189 Post Office Box 33189 422 South Church Street 422 South Church Street Charlotte, North Carolina 28242 Charlotte, North Carolina 28242 J. Michael McGarry, III, Esq.
Bishop, Libermdn, Cook, Purcell & Reynolds 1200 Seventeenth Street, N.W.
Washington, D.C. 20036 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 525 1700 Rockville Pike Rockville, Maryland 20852 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Johes Street Raleigh, North Carolina 27603 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621