ML20207M366
| ML20207M366 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/06/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207M305 | List: |
| References | |
| NUDOCS 8810180240 | |
| Download: ML20207M366 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION c
WASHING TON, D. C. 20665 n
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SAFETY EVALUATION BY THE,0FFICE OF NUCLEAR REACTOR _ REGULATION RELATED TO AMENDMENT NO.131 TO FACILITY OPERATING LICENSE NO. DPR-66 AND AMENDMENT NO. 7 T0_ FACILITY OPERATING LICENSE NO NPF-73 DUQUESNE LIGHT COMPANY OHIO ED! SON COMPANY
_ PENNSYLVANIA POWER COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATI E UNITS 1 AND 2 DOCKET NOS.
50-334 AND 50-412 INTRODUCTION By letter dated June 11, 1988 Duquesne Light Company (the licensee, acting as agent for all the above listed utilities) proposed changes to Section 6 of the Technical Specifications for Beaver Valley Pcwer Station Units 1 and 2.
The changes involve removing specific descriptions of the licensee's onsite and offsite or descriptions. ganizations and replacing them with more general narrative Guidance for these changes was provided to licensees and applicants by Generic Letter 88-C6 dated March 22, 1988.
BACKGROUND Consistent with the guidance provided in the Standard Technical Specifications for Westinghouse reactors, Specifications 6.2.1 and 6.2.2 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 necessitated license amendments to reflect the desired changes in these organizations.
Because of these limitations on organizational structure, the nuclear industry i
has highlighted this as an area for improvement in the TS. The Shearon Harris licensee proposed changes to remove organization charts from its TS under the lead-plant concept. This activity has the endorsement of 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 gogy h g
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w organization charts are captured by other regulatory requiremelits, 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 would be met and that would not be retained with the removal of the organization charts. The applicable regulatory requirements are those administrative controls that are necessary to 4
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 ~.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 NPF-63 for the Shearen Harris Nuclear Power Plant that i
incorporated these changes to their TS.
Subsequently, the staff developed guidance on an acceptable fortnat for similar license amendnent requests.
Gereric Letter 88-06 provided this guidance to all power reactor licensees and applicants.
EVALUATION The licensee's proposed changes to the Beaver Valley Pcwer Station Units 1 l
and 2 TS are in accordance with the guidance provided by Generic Letter 88-06 i
as follows:
(1) Specifications 6.2.1 and 6.2.2 were revised to delete the references to Figures 6.2-1 and 6.2-2, which were removed from the TS. These j
l changes are in accordance with Generic Letter 88-06 and are acceptable.
(2) Functional requiren+nts of the offsite and onsite organizations were defined and added to Specification 6.2.1, and they are consistent with the guidance provided in Generic letter 88-06. As in the past, the NRC will continue to be informed of organizational changes through other required controls.
In accordance with 10 CFR 50.34(b)(6)(i), the licensee's organizational structure was included in the Final Safety
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Analysis Report, and as required by 10 CFR 50.71(e), the licensee submits i
annual updates to the FSAR.
In addition, Appendix B to 10 CFR 50 and 10 CFR'50.54(a)(3) govern changes to organization described in the quality assurance program; some of these organizational changes require 2
prior NRC approval.
Therefore, the use of a gevral narrative description in Section 6.2.1 is acceptable.
l (3) The organization chart (Fig 6.2-2) for the unit staff did not stipulate j
senior reactor operator or reactor operator license-qualified pesitions.
j Hence, this is not an applicable consideration for these amendments.
i (4) Other sections have been revised so that the position titles conform with i
those used in the licensee's current organization and the narrative I
description of Section 6,2.1.
These sections are:
6.5.1.6.
6.5.1.7, i
6.5.1.8, 6.5.2.?, 6.5.?.9, 6.5.2.10.c. 6.7.1.b. 6.7.1.d. 6.8.3.c. and l
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6.17.
These changes are all acceptable since they follow the guidelines of Generic Letter 88-06.
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Sect' on 6.8.3 c has been revised for both units to clarify approva' requ' rerents for tenporary procedure. changes.
This change is cons"stent with Section 6.8.2 which provides for approval of changes in 6.8.1 by the Plant Manager, predesignated alternate or a predesignated manager to whom the Plant Mana0er has assigned in writing the responsibility for review and approval of specific subjects. This is a clarification of an existing requirement and is acceptable.
(6) The following changes were made to correct purely typographical errors:
Unit 2 TS, Section 6.2.3.4 was corrected to specify that "a summary a.
i report shall be" forwarded to the Vice President Nuclear Group.
1 b.
The heading over Unit 1 TS Section 6.5.2.9 has been corrected to "Authority" from "Audits" c.
Unit ? TS, Section 6.8.2, missing words "of intent" have been i
supplied.
These editorial corrections are all acceptable.
.E.N.V.I.R.O.N.M.E.N.T.A.L..C.O.N.S.I.D E R AT I O N l
l These amendrents relate to changes in recordkeeping, or administrative
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precedures or requirements. Accordingly, the amendments meet the eligibility criteria fer categorial exclusion set forth in 10 CFR 51.22(c)(10). Pursuant l
to 10 CFR 5.22(b), no environnental impact statenent or environnental assessnent need be prepared in connection with the issuance of these amendments.
CONCLU_S_.IO_N We have 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, and (2) such l
activities will be conducted in compliance wit 1 the Commission's F
regulations and the issuance of the amendnents will net be inimical to the i
cortten defense and security or to the health and safety of the public.
Dated: October 6,1938 P
Pri n e i pa l _C,o,n t,r,1,b,u,t or :
i P. S. Tam
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