ML20245G469
| ML20245G469 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 04/24/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245G456 | List: |
| References | |
| GL-88-06, GL-88-6, NUDOCS 8905030154 | |
| Download: ML20245G469 (4) | |
Text
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UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION E
<j W ASHINGTOE, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 27 TO FACILITY OPERATING LICENSES NOS. NPF-37 AND NPF-66 BYRON STATION, UNITS 1 AND,2 DOCKET NOS. 50-454 AND 50-455 A3 i
SUPPORTING AMENDMENT NO.16 TO FACILITY OPERATING LICENSES i
(
BRAIDWOOD STATION UNITS 1 AND 2 l
_ DOCKET NOS.._50-456 AND 50-457
3.0 INTRODUCTION
12y letter dated February 17,(TS) Sections 6.1 through 6.7 and Section (.13.
1989, Commonwealth Edison Company proposed changes to Technical Specifications The proposed changes t;oulo remove Figure 6.2-1, Offsite Organization, anc Figure 6.2-2, Unit Organization, and replace, them with a narrative description of the offsite and onsite organizations functional requir6ments in TS 6.2.1 and unit staff qualifications in 6.2.2.
Guidance for these proposed changes to the 15 was provideo to licensees and applicants by Generic Letter 88-06, dated j
lbrch 22,1988.
In addition, the proposed changes would change several position i
titles, responsibilities, and lines of authority to reflect a major reorganization, clurify the distribution require'nents for Onsite Reviews, and correct several typographical and editorial errors.
2.0 BACKGROUND
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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 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 NRC approval to reflect the desired
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changes in these organizations. As a consequence, organizational changes have necessitated the need to request un amendraent of the operating licence.
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" Pemoval of organization charts is a line item improvement that was proposed on a lead-plant basis for the Shearon Harris plant and was endorsed by the Westinghouse Owners Group. This change was reviewed as part of the NRC's arogram for itnprovements in TS.
The objectives of that program were established ay the Commission's Interim Policy Statement on Technical Specification Improvements.
The staff concluded that removal of organization charts from TS will provide greater flexibility for licensees to implement changes in both the onsite and offsite or5anizational structure, consistent with Commission policy.
In aadition to CECO's intent to delete organization charts, the licensee proposed to revise significant aspects of TS Section 6.
This revision would reflect changes in the Ceco organization and update station and corporate position titles, description, responsibilities, and lines of authority. The t
purpose of the organization change was to improve connunication channels and eliminate redundant levels of management.
3.0 EVALUATION The licensee's proposed changes to its TS are in accordance with the guidance provided by Generic Letter 88-0a and addressed the items listed below.
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(1) Specifications 6.2.1 and 6.2.2 were revised to delete the references to l
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, ano they are consistent with the guidance provided in Generic Letter 88-06. The specification notes that implementation of these requirements is documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organizational Authority, Activities; Section 6 Interdepartmental Rehtionships.
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(3) The senior reactor operator license qualified position of Assistant Superintendent Operating was added to Specification 6.2.2.
Therefore, this requirement that was icentified on the organization chart for the unit staff will be retained. Other senior reactor operator and reactor operator license qualified positions of the unit staff were alrehoy I
identified in areas of the TS other than Figure 6.2-2.
l (4) Consistent with requirements to docunent the offsite and onsite l
organization relationships in the form of organization charts, the licensee has confirmed that this documentation currently exists in the Quality Assurance Manual or the Management Plan for Nuclear Operations.
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4 g Cn the basis of its review of the above items, the staff concludes that the licensee has providea 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 of such enanges as noted in Generic Letter 88-06.
Ir, addition to deleting organization charts, changes in on-site and off-site company position titles, responsibilities, description, and lines of authority identified throughout TS Section 6 were made to reflect a major CECO reorganization. Station and corporate positions affecting nuclear operations and managenient are being reorganized to enhance plant safety by improving channels of communication and authority. The NRC staff concludes that the proposed TS vnendments retain all portions of organizational characteristics which are important to safety, and that the re-organizational changes should not adversely impact safe operation and management of the stations. The independence between operations and quality assurance is stili maintained.
Consequently, these amendments are acceptable.
4.0 ENVIRONMENTAL CONSIDERATION
These amenaments relate to chan g s in recordkeeping, or administrative procedures or requirements. The Commission has previously issued a oroposed finding that these amendments involve tio significant hazards consideration and there has been no public coment on such finding. Accordingly, the amendments meet the eligibility criterie for categorical exclusion set forth in 10 CFR 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 these amendments.
5.0 CONCLUSION
On the basis of the considerations discussed above, the staff concludes 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 these amendments will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributors: Thomas G. Dunning, OTSB/00EA Leonard N 01shan, NRR/DRSP Dated: April 24, 1989 I
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