ML14175A627
| ML14175A627 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 08/29/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A628 | List: |
| References | |
| DPR-23-A-048 NUDOCS 8009180113 | |
| Download: ML14175A627 (7) | |
Text
UNITED STATES WASHINGTON, D. C. 20555 CAROLINA POWER AND LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power and Light Company (the licensee) dated August 1, 1980 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.3 of Facility Operating License No.
DPR-23 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 48, are hereby incorporated in the license. The Licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
- A iteVen A. Varga, 4ief Operating Reactors Branch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 29, 1980
ATTACHMENT TO LICENSE AMENDMENT NO. 48 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO.
50-261 Replace the following page of the Appendix A Technical Specification with the enclosed page. The revised page is identified by Amendment Number and contains a vertical line indicating the area of change.
Remove Insert 3.10-2 3.10-2 3.10-2A 3.10-11 3.10-11 3.10-11A
- 3. 10. 1.5 Except for physics tests, LE a full length -euiitro. ruo is wi ri drawn as follows:
at positions >200 steps and is 15 inches out of alignmenL with its bank position, or at positions <200 steps and is >7.5 inches out of alignment with the average of its bank's position then within two hours perform the following:
- a.
Correct the situation, or b).
Determine hv measurement the hot channel factors and app lv Specification 3.10.2.1, or
- c.
Limit power to 70 percent of rated power for three-loop operation.
3.10.1.6 Insertion limits do not apply during physics tests or during periodic exercise of individual rods.
However, the shutdown margin indicated in Figure 3.10-2 must be maintained except for the low power physics test to measure control rod worth and shutdown margin. For this test the reactor may be critical with all but one full length control rod inserted.
3.10.2 Power Distribution Limits 3.10.2.1 At all times except during low power physics tests, the hot channel factors defined in the basis must meet the following limits:
F (Z) < (2.20/P) X K(Z) for P >.5 Q
F (Z) < (4.40) X K(Z) for P <.5 Q_
FN 1.55 (1 + 0.2(1-P))
AH 3.10-2 Amendment No.
48
where P is the Eraction of licensed power at which the core is operating, K(Z) is based on the function given in Figure 3.10-3, and Z is the core height location of F.
3.l0-2A Amendment No. 48
shutdown margin. The specified control.rod insertion limits meet the design basis criteria on (1) potential ejected control rod worth and peaking factor,( 4 ) (2) radial power peaking factors, P and (3) required margin shutdown.
The various control rod banks (shutdown banks, control banks) are each to be moved as a bank; that is, with all rods in the bank within one step (5/8 inch) of the bank position. Position indication is pro vided by two methods:
a digital count of actuation pulses which shows the demand position of the banks, and a linear position indicator (LVDT) which indicates the actual rod position.(2) At rod positions >200 steps, full power reactivity worths of the control rods are sufficiently small sucti that a 15-inch indicated misalignment from the rod bank has no significant effect on the incore power distribution and is therefore allowable. For rod positions <200 steps, maintaining indicated rod position within 7.5 inches of the average of the indicated bank position provides an enforceable limit which assures design distribution is not exceeded.
In the event that an LVDT is not in.service, the effects of a malpositioned control rod are observable on nuclear and process information displayed in the control room and by core thermocouples and in-core movable detectors. The determination of the hot channel factors will be performed by means of the movable in-core detectors.
The two hours in 3.10.1.5 are acceptable because complete rod mis alignment (control rod 12 feet out of alignment with its bank) does not result in exceeding core safety limits in steady state operation at rated power and is short with respect to probability of an independent accident.
If the condition cannot be readily corrected, the specified reduction in power will ensure that design margins to core limits will be maintained under both steady state and anticipated transient conditions.
3.10-11 Amendment No.
48
The intent of the test to measure control rod worth and shutdown margin (Specification 3.10.1.6) is to measure the worth of all rods less the worth of the worst case For an assumed stuck rod; that is, the most re active rod.
The measurement would be anticipated as part of the initial startup program and infrequently over the life of the plant, to be associated primarily with determinations of special interest such as end of life cooldown, or startup of fuel cycles which deviate from normal
- 3.10-11A Amendment. No.
48