ML17304A682
| ML17304A682 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/25/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17304A681 | List: |
| References | |
| SL-88-06, SL-88-6, NUDOCS 8811030193 | |
| Download: ML17304A682 (6) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION.BY THE OFFICE OF NUCLEAR. REACTOR REGULATION RELATED TO AMENDMENT NO. 40 TO FACILITY OPERATING LICENSE NO. NPF-41, AMENDMENT NO.
27 TO FACILITY OPERATING LICENSE NO.
NPF-51 AND AMENDMENT NO. 16 TO FACILITY OPERATING LICENSE NO.
NPF-74 ARIZONA PUBLIC SERVICE COMPANY, ET. AL.
PALO VERDE NUCLEAR GENERATING STATION UNITS 1
2, AND 3 DOCKET NOS.
STN 50-528, STN 50-529 AND STN 50-530
1.0 INTRODUCTION
By letter dated August 25, 1988, as supplemented by letter dated Octo-ber 18, 1988, the Arizona Public Service Company (APS) on behalf of itself, the Salt River Project Agricultural Improvement and Power District, Southern California Edison
- Company, El Paso Electric Company, Public Service Company of New Mexico, Los Angeles Department of Mater and Power, and Southern California Public Power Authority (licensees),
requested changes to the Technical Specifications for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Appendix A to Facility Operating License Nos.
NPF-41, NPF-51, and NPF-74, respectively).
The proposed changes would delete Technical Specification Figures 6.2-1 "Offsite Organization" and 6.2-2 "Onsite Organization".
Technical Specification 6.2.1 would be changed to add general requirements that capture the essential aspects of the organizational structure that are defined by the existing onsite and offsite organization char ts.
2.0 DISCUSSION The NRC staff has evaluated the proposed changes and has concluded that they are acceptable.
The staff's evaluation is given below.
The content required in the Administrative Controls Section of the Technical Specifications is specified in 10 CFR 550.36.c(5).
That provision requires that the technical specifications contain provisions relating to organization and management procedures, recordkeeping, review and audit, and reporting that are necessary to assure operation of the facility in a safe manner.
It does not specifically require inclusion of organizational charts in the technical specifications.
In Generic Letter (GL) 88-06, "Removal of Organizational Charts from Technical Specification Administrative Controls Requirements" dated 88ii030i93 SSi025 PDR ADOCK 05000528 P
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March 22, 1988, the NRC provided guidance for the removal of organi-zation charts from the TS.
Generic Letter 88-06 concludes that the removal of organization char ts from the technical specifications will provide greater flexibilityfor licensees to implement changes in both the onsite and offsite organizational structure.
With regard to Palo Verde, the licensee states that removal of the organization charts from the technical specifications will not affect plant operations.
Having organization charts in the'echnical specifi-cations duplicates those charts listed in Chapter 13 of the
As in %he past, the NRC will continue to be informed of organizational changes and management personnel titles through other required controls.
For example, 10 CFR 550.34(b)(6)(i) requires that the applicant's organizational structure be included in the FSAR.
Consistent with GL 88-06, Section
- 13. 1 of the Updated FSAR currently provides a
functional descr iption of the organization, a functional description of key personnel positions, and detailed organization charts.
The organi-zation charts in the Updated FSAR are more detailed than those presently in the technical specifications.
As required by 10 CFR 550.71(e),
the licensee submits annual revisions to the Updated FSAR.
The removal of the organization charts and title changes represent no
~eduction in the cur rent safety requirements, because the following conditions are included in the technical specifications by these amend-
- ments, per the recommendations of GL 88-06:
a ~
Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.
Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.
These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 550.71(e).
b.
There shall be an individual executive position (Executive Vice President ANPP) in the offsite organization having corporate re-sponsibility for overall plant nuclear safety.
This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support in the plant so that continued nuclear safety is assured.
c.
There shall be individual management positions (Plant Managers) in the onsite organization having responsibility for overall unit safe operation and having control over those onsite resources necessary for safe operation and maintenance of the plant.
d.
Although the individuals who train the oper'ating staff and those who carry out health physics and quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.
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Additionally the recommendation in GL 88-06 to designate those positions in the onsite organization that require a senior reactor operator or reactor operator license is currently covered by Technical Specification 6.3.1 "Unit Staff gualifications".
This specification is not changed by the proposed amendments.
As discussed
- above, because removal of licensee organization charts from the PVNGS TS meets the requirements of 10 CFR 5 50.36, and because these amendments meet the guidelines of GL 88-06, the NRC staff finds them acceptable.
3.0 CONTACT WITH STATE OFFICIAL The Arizona Radiation Regulatory Agency has been advised of the proposed determination of no significant hazards consideration with regard to these changes.
No comments were received.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments involve changes in administrative procedures and require-ments.
Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 551.22(c)(10).
Pursuant to 10 CFR 551.22(b),
no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
- 5. 0 CONCLUSION The staff has concluded, based on the considerations discussed
- above, that (I) 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
We, therefore, conclude that the proposed changes are acceptable.
Principal contributor:
M. Davis Dated:
October 25, 1988
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