ML14183A327
| ML14183A327 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 01/26/1996 |
| From: | Matthews D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML14183A328 | List: |
| References | |
| NUDOCS 9601310160 | |
| Download: ML14183A327 (6) | |
Text
t~
REG(.,0 0P1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 167 License No. DPR-23
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee), dated September 11, 1995, 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.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 3.8. of Facility Operating License No. DPR-23 is hereby amended to read as follows:
9601310160 960126 PDR ADOCK 05000261 P
-2 B".
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 167, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Direct r Project Directorate II-1 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 26, 1996
ATTACHMENT TO LICENSE AMENDMENT NO, 167 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO, 50-261 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Paget 3.10-1 3.10-1 3.10-11 3.10-11 3.10-15 3.10-15
3.10 REQUIRED SHUTDO ARGINS. CONTROL ROD, AND POWER@ )TRIBUTION LIMITS Applicability Applies to the required shutdown margins, operation of the control rods, and power distribution limits.
ObJective To ensure (1) core subcriticality after a reactor trip and during normal shutdown conditions, (2) limited potential reactivity insertions from a hypothetical control rod ejection, and (3) an acceptable core power distribution during power operation.
Speci fi cati on 3.10.1 Full Length Control Rod Insertion Limits 3.10.1.1 (Deleted by Change No. 21 issued 7/6/73) 3.10.1.2 When the reactor is critical, except for physics tests and full length control rod exercises, the shutdown control rods shall be limited in physical insertion as specified in the CORE OPERATING LIMITS REPORT (COLR).
3.10.1.3 When the reactor is critical, except for physics tests and full length control rod exercises, the control rods shall be limited in physical insertion as specified in the COLR. Control rod bank insertion beyond the limits specified in the COLR shall be corrected within the time criteria established by the axial power distribution methodology or within one.(1) hour, whichever occurs sooner. If bank insertion is not restored to the specified limits (i.e., within one (1) hour or within the time criteria established by the axial power distribution methodology, whichever is sooner) the reactor shall be placed in the hot shutdown condition utilizing normal operating procedures within six (6) hours.
3.10.1.4 At 50 percent of the cycle as defined by burnup, the limits shall be adjusted to the end-of-core values as specified in the COLR.
3.10-1 Amendment No. 141, 167
shutdown margin. The
- ified control rod insertion lios meet the design basis.criteria on (1) potential ejected control rod worth and peaking factor.) (2) radial power peaking factors, F,. and (3) required shutdown margin.
When the control Rod Banks are outside the acceptable insertion limits, they must be restored to within those limits. The restoration may be accomplished either by repositioning control rods to the insertion limits consistent with core power or by boration to reduce power to be consistent with the power limit associated with the existing rod position. Restoration of rod position to the power dependent insertion limit ensures adequate Shutdown Margin in accordance with Figure 3.10-2.
Operation beyond the insertion limits is allowed (for a short time period in order to take conservative action) because the simultaneous occurrence of either a LOCA, loss of reactor coolant flow accident, ejected rod accident, or other accident during this short time period, together with an inadequate power distribution or reactivity capability, has an acceptably low probability. The allowed completion time of one hour for restoring the banks to within the insertion limits provides an acceptable time for evaluating and repairing minor problems without allowing the plant to remain in an unacceptable condition for an extended period of time.
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 provided 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.
At rod positions 200 steps, full power reactivity worths of the control rods are sufficiently small such 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 the misalignment of a single control rod up to 9 feet above its bank or 12 feet below 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. 74, 167 Basis Change, PPNSC June 4, 195
Strict control of the 0 difference is not possible due certain physics tests, control rod exercises, or during the required periodic excore calibration which require larger flux differences than permitted. Therefore, the specification on power distribution are not applicable during physics tests, control rod exercises, or excore calibrations; this is acceptable due to the extremely low probability of a significant accident occurring during these operations.- Excore calibration includes that period of time necessary to return to equilibrium operating conditions. In some instances of rapid plant power reduction, automatic rod motion will cause the flux difference to deviate from the target band when the reduced power level is reached. This does not necessarily affect the xenon distribution sufficiently to change the envelope of peaking factors which can be reached on a subsequent return to full power within the target band; however, to simplify the specification, a limitation of one hour in any period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is placed on operation outside the band. This ensures that the resulting xenon distributions are not significantly different from those resulting from operation within the target band. The instantaneous consequence of being outside the band, provided control rods inserted beyond the physical insertion limits specified in the COLR are returned to within said physical insertion limits within the time criteria established by the axial power distribution methodology or one hour, whichever occurs sooner, is not worse than a 10 percent increment.in peaking factor for flux differences in the allowable range specified in the COLR for 90 percent of rated power or 0.9 x APL (whichever is less). Therefore, while the deviation exists, the power level is limited to 90 percent of rated power or 0.9 x APL (whichever is less) or lower depending on the indicated flux difference.
If, for any reason, flux difference is not controlled with the target band for as long a period as one hour, then xenon distributions may be significantly changed and operation at 50 percent of rated power is required to protect against potentially more severe consequences of some accidents.
As discussed above, the essence of the limits is to maintain the xenon distribution in the core as close to the equilibrium full power condition as possible. This is accomplished by using the chemical volume control system to position the full length control rods to produce the required indication flux difference.
3.10-15 Amendment No. 07 in 141 167