ML17156A931
| ML17156A931 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/16/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17156A930 | List: |
| References | |
| NUDOCS 8811280218 | |
| Download: ML17156A931 (3) | |
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+~*~4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
85 TO FACILITY OPERATING LICENSE NO.
NPF-14 AND AMENDMENT NO.
52 TO FACILITY OPERATING LICENSE NO.
NPF-22 PENNSYLVANIA POWER 5 LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NOS. 50-387 AND 50-388 SUS UEHANNA STEAM ELECTRIC STATION, UNITS 1
AND 2
- 1. 0 INTRODUCTION By letter dated February 24, 1988 as revised June 10,
- 1988, Pennsylvania Power 8 Light Company (the licensee) requested an amendment to Facility Operating License Nos.
NPF-14 and NPF-22 for the Susquehanna Steam Electric Station (SSES),
Units 1 and 2.
The proposed amendments would remove Figure 6.2. 1-1, Offsite Organization and Figure 6.2.2-1, Unit Organization, and replace them with a narrative description of the offsite and onsite organizations'unctional requirements in Technical Specifications Sections 6.2. 1 and 6.2.2.
These changes are based on the staff guidance provided to the licensees in Generic Letter 88-06.
In addition to the removal of the organization charts, the licensee has proposed some changes in the nomenclature of Section 6.8.2.
2.0 EVALUATION In Generic Letter 88-06 the staff outlined the rationale for removal of the organization charts from the technical specifications.
In that Generic Letter the staff found that with appropriate changes to the administrative control requirements, the onsite and offsite organization charts may be removed.
The necessary changes consist of general requirements that capture the essential aspects of the organizational structure represented by the organization charts.
In the guidance to the Generic Letter 88-06, the staff stated that the regulatory requirements in 10 CFR 50.36 regarding administrative control related to organization and management will be satisfied if the licensees can ascertain that their organizational structure will ensure a safe operation of the facilities.
The staff distilled the essential organizational characteristics which are not included in sections of the technical specifications other than organization charts, and summarized them as follows:
1.
A requirement that 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 organization C~g <2802ie 88>ppp387 pod ADOCK P
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2.
3.
- charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
Designation of an executive position that has corporate responsibility for overall plant nuclear safety and authority to take such measures as may be needed to ensure acceptable performance of staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
Designation of a management position in the organization that is responsible for overall unit operation and has control over those onsite activities necessary for safe operation and maintenance of the plant.
Designation of.those positions in the onsite organization that require a senior reactor operator (SRO) or reactor operator (RO) license.
5.
Provisions of sufficient organizational freedom to be independent of operational pressures to those individuals who perform the functions of health physics, quality assurance, and training of the operating staff.
The licensee has evaluated the essential organizational requirements included in its documents, related to SSES Units 1 and 2 operation and has addressed the above staff positions as follows:
Item 1 is proposed to become Specification 6.2.1.a.
The required information is currently contained in FSAR Section 13.1, which is updated in accordance with 10 CFR 50.71.
2.
Item 2 is proposed to become Specification 6.2. l.c.
The responsibility of the Senior Vice President-Nuclear is currently implicit in Figure 6.2. 1-1, and is discussed in detail in FSAR Section 13.1..
3.
Item 3 is proposed to become Specification 6.2. l.b.
The responsibility of the Superintendent of Plant-SSES is currently implicit in Figure 6.2.2-1, and is discussed in detail in FSAR Section 13.1.
4 ~
5.
Item 4 is proposed to become Specification 6.2.2.g.
The requirement for the Supervisor of Operations to hold an SRO license is currently shown on Figure 6.2.2-1.
Further SRO/RO requirements are currently provided (and will be retained) in Table 6.2.2-1, "Minimum Shift Crew Composition."
Item 5 is proposed to become Specification 6.2.1.d.
The requirements for independence from "operating pressures" is
currently implicit on Figure 6.2.1-1 for the gA and Training functions.
For Health Physics, this requirement is consistent with the FSAR Subsections 13.1.2.2.3 and 12.5.1.
The staff has reviewed the above licensee assessments and concurs with the licensee's observations.
The staff concludes that since the licensee has proposed all the essential elements determined by the staff, to be necessary to assure safe operation of the facility as provided in 10 CFR 50.36, the proposed removal of the organization charts and the associated changes are acceptable.
The staff has also reviewed the licensee's proposal to change the nomenclature in Section 6.8.2 and has determined that the changes will have no effect on the safe operation of the facility, and are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
The amendments relate to changes in recordkeepinq, reporting, or administrative procedures or requirements.
Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b} no environmental impact statement nor environmental assessment need be prepared in connection with the issuance of these amendments.
- 4. 0 CONCLUSION The Commission made a proposed determination that these amendments involve no significant hazards consideration which was published in the Federal Re ister (53 FR 30141'n August 10, 1988 and consu'Ited with the State onnennsy vansa.
No public comments were received, and the State of Pennsylvania did not have any comments.
The staff 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,'nd (2) such activities will be conducted in compliance with the Commission's regulations and'the issuance of these amendments will not be inimical to the common defense and security nor to the health and safety of the public.
Principal Contributor:
Mohan C. Thadani Dated:
November 16, 1988