ML20128G255
| ML20128G255 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/03/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20128G240 | List: |
| References | |
| NUDOCS 9610080410 | |
| Download: ML20128G255 (3) | |
Text
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NUCLEAR REGULATORY COMMISSION o
2 WASHINGTON, D.C. 3088H001
%,.....,o SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATipH 1
RELATED TO AMEN 0 MENT NO.186 TO FACILITY OPERATING LICENSE NO. DPR-51 ENTERGY OPERATIONS. INC.
ARKANSA5 NUCLEAR ONE. UNIT NO. 1 DOCKET NO. 50-313
1.0 INTRODUCTION
By letter dated April 29, 1996, Entergy Operations, Inc. requested changes to the Arkansas Nuclear One, Unit 1 (ANO-1) Technical Specifications (TSs) to s
expand the current Core Operating Limits Report (COLR).
Specifically, the variable low reactor coolant system (RCS) pressure-temperature protective limits and the variable low RCS pressure trip (VLPT) setpoint would be relocated to the COLR.
The staff's evaluation of the proposed changes follows.
2.0 EVALUATION The licensee requested TS changes in accordance with 10 CFR 50.90. The specific changes are as follows:
1)
Specification 2.1.3 Specification 2.1.3, including the associated Bases, will be revised to relocate Figures 2.1-1 and 2.1-3 and design nuclear power peaking factors from the TSs to the COLR. These figures will be combined in the COLR.
2)
Specification 2.3.1 Table 2.3-1 will be revised to relocate the VLPT setpoint from the TSs to the COLR. The associated Bases Figure 2.3-1 will be relocated to the COLR.
Items C (RCS Pressure) and D (Coolant Outlet Temperature) of the Bases will also be revised to reflect the relocation of the VLPT setpoint and Figure 2.3-1.
3)
Specification 6.12.3.1 Specification 6.12.3.1 will be revised to add the variable low RCS pressure-temperature protective limits and the VLPT setpoint as being documented in the COLR.
9610080410 961003 PDR ADOCK 05000313 p
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. Although there have only been a few previous revisions to the ANO-1 VLPT setpoint, it is anticipated that an increasing number of future changes will be made in order to accommodate advanced core designs.
For example, the licensee anticipates that a more restrictive VLPT setpoint will be required for Cycle 14 in order to prevent the control rod insertion limits from i
severely impacting plant operation.
In addition, a further revision may be required for Cycle 15 in order to credit the margin allowed by the use of a statistical core design methodology. Therefore, due to' these expected l
frequent changes to the YLPT setpoint for future cycles of ANO-1, the staff considers the VLPT set 9oint an appropriate cycle-specific COLR ites.
The licensee has requested that the cycle-specific variable low RCS pressure-temperature protective limits and the VLPT setpoint, be relocated from the TSs to the COLR. The staff has reviewed the proposed change and has determined that these cycle-specific parameters may be modified by the licensee, without affecting nuclear safety, provided that such changes are determined usir.g the NRC-approved methodologies specified in TS 6.12.3.2.
The approved calculational basis for the variable low RCS pressure-temperature protective limits and the VLPT setpoint exists in BAW-10179P-A, " Safety Criteria and Methodology for Acceptable Cycle Reload Analyses," which is referenced in TS 6.12.3.2.
NRC approval and a license amendment would be required prior to 1
using a methodology other than one approved and specified in TS 6.12.3.2.
Because plant operation will continue to be limited in accordance with the values of the cycle-specific variable low RCS pressure-temperature protective limits and the VLPT setpoint, using NRC-approved methodologies, the staff finds the proposed changes acceptable and consistent with NRC guidance contained in Generic Letter 88-16 on modifying cycle-specific parameters.
The staff has concluded that the relocation of the variable low RCS pressure-temperature protective limits and the VLPT setpoint to. the COLR is acceptable for the following reasons:
(1) these parameters are cycle-specific and, therefore, meet the intent of Generic Letter 88-16, (2) reference to and the requirement for conformance to these limits remains in the TSs, assuring conformance with 10 CFR 50.36, and (3) plant operation continues to be limited in accordance with the values of these parameter limits that are established using NRC-approved methodologies specified in the TSs and will ensure that operation will be consistent with applicable limits of the safety analysis.
The proposed TS changes appropriately reflect relocation of the specified parameters to the COLR and, therefore, are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Arkansas State official j
was notified of the proposed issuance of the amendment. The State official j
had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (61 FR 28613). The amendment also changes reporting and recordkeeping requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment. will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
L. Kopp Date: October 3, 1996 1