ML20235P270
| ML20235P270 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/14/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235P241 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 8903020158 | |
| Download: ML20235P270 (3) | |
Text
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1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIOM RELATED TO AMENDMENT NO.24 TO FACILITY OPERATING LICENSE NO. NPF-42 WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 INTRODUCTION By letter dated October 19, 1988, the Wolf Creek Nuclear Operating Corporation (the licensee) proposed an amendment that would remove the operatin corporation and onsite organization charts (Figure 6.2-1 ano 6.2-2)gfrom Section 6 of the Wolf Creek Generating Station Technical Specifications and would incorporate essential organization requirements such as lines of authority, responsibility, and communication. The amendment would also make additional editorial. changes to delete references to the removed organization charts.
The proposed changes are in accordance with NRC Generic Letter 88-06, " Removal of Organization Charts from Technical Administrative Control Requirements",
dated March 22, 1988.
BACKGROUND Consistent with the guidance provided in the Standard Technical Specifications, Specifications 6.2.1 and 6.2.2 of the administrative control requirements have referenced offsite and unit (onsite) organization charts that are provided as figures to these sections. On a plant specific basis, these organization charts have been provided by applicants and included in the Technical Specifications (TS) issued with the operating license. Subsequent restructuring of either the offsite or unit organizations, following the issuance of an operating license, has required-licensees to submit a license amendment for hRC approval to reflect the desired changes in these organizations. As a consequence, organizational changes have necessitated the need to request an amendment of the operating license.
Because of these limitations on organizational structure, the nuclear industry has highlighted this as an area of improvement in the TS. The Shearon Harris license proposed changes to remove organization charts from its TS under the lead-plant concept that included the endorsement of the proposed changes by the Westinghouse Owners Group.
In its review of the Shearon Harris proposal, the staff concluded that most of the essential elements of offsite and onsite organization charts are captured by other regulatory requirements, notably, Appendix B to 10 CFR Part 50. However, there were aspects of the organizational structure that are important to ensure that the administrative control requirements of 10 CFR 50.36 wculd be met and that would not be retained with the removal of the organization charts. The applicable regulatory 8903020158 890214 PDR ADOCK 05000432 P
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' requirements are those administrative controls that are necessary to ensure safe operation of the facility. Therefore, those aspects of organization charts for Shearon Harris that were essential for conformance with regulatory requirements were added (1) to Specification 6.2.1 to define functional requirements for the offsite and onsite organizations and (2) to Specification 6.2.2 to define qualification requirements of the unit staff.
By letter dated January 27, 1988, the staff issued Amendment No. 3 to Facility Operating License NFP-63 for the Shearon Harris Nuclear Power Plant that incorporated these changes to their TS. Subsequently the staff developed guidance on an acceptable format for license amendn.ent requests to remove the organization. charts from TS. Generic Letter 88-06 provided this guidance to all power reactors.
EVALUATION The licensee's proposed changes to its TS are in accordance with the guidance provided by Generic Letter 88-06 and addressed the items listed below, i
(1) Specifications 6.2.1 and 6.2.2 were revised to delete the references to Figures 6.2-1 and 6.2-2 that were removed from the TS.
(2) Functional requirements of the offsite and onsite organizations were defined and added to Specification 6.2.1, and they are consister.t with the guidance provided in Generic Letter 88-06. The specification notes that implementation of these requirements is documented in the Updated Safety Analysis Report.
(3) The operations supervisor, identified on the organization chart for the unit staff, is required by Specification 6.2.2 to hold a senior reactor operator license. Therefore, this requirement will be retained as a requirement following the removal of the organization chart for the unit staff.
(4) Consistent with requirements to document the offsite and onsite organization relationships in the form of organization charts, the licensee has confirmed that this documentation shall be included in the Updated Safety Analysis Report.
(5) The licensee has confirmed that no specifications, other than those noted in item (1) above, include references to the figures of the organization charts that are being removed from TS for their plant. Hence, this is not an applicable consideration, with regard to the need to redefine referenced requirements as a result of the removal of these figures.
On the basis of its review of the above items, the staff concludes that the licensee has provided an acceptable response to these items as addressed in the NRC guidance on removing organization charts from the administrative control requirements of the TS. Furthermore, the staff finds that these changes are consistent with the staff's generic finding on the acceptability l
of such changes as noted in Generic Letter 88-06. Accordingly, the staff finds the proposed changes to be acceptable.
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- ENVIRONMENTAL CONSIDERATION The amendment involves a change in Administrative requirements. 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.
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(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.
CONCLUSION The staff has concluded, based on the considerations discussed above, that:
(1) there is reasor.able essurance that the health and safety of the will rot be endangered by operation in the proposed manner, and (2) public such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the conson defense and security or to the health and safety of the public.
Date: February 14, 1989 Principal Coaiributor: Douglas V. Pickett