ML20004C394
| ML20004C394 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/22/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004C393 | List: |
| References | |
| NUDOCS 8106030477 | |
| Download: ML20004C394 (5) | |
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~ UNITED STATES NUCLEAR REGULATORY COMMISSION Xj e
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.' SAFETY EVALUATION BY THE'0FFICE OF NUCLEAR' REACTOR REGULATION'
- RELATED TO AMENDMENT NO. - 30 TO FACILITY OPERATING LICENS AND' AMENOMENT-NO.11 T0 FACILITY OPERATING LICENSE NO. NPF-7
- VIRGINIA' ELECTRIC AND POWER COMPANY
= NORTH ANNA POWER STATION, UNITS NO.1 AND NO. 2 DOCKET NOS. 50-338 AND 50-339
Introduction:
The Virginia Electric and Power Company (the licensee) has made applicati_on -
for amendments to Facility Operating License No. NPF-4 and No. NPF-7 for the North Anna Power Station, Units No.1 and 2 (NA-1821. The applications are dated July 30. August 28, and October 15, 1980 as supplelmented by letters
' dated August 1,1980 and February 23,195;.
The proposed amendments consist of changes to the Technical Specifications which revise the Administrative Controls, Section 6.
The changes reflect corporate and plant reorganizations including the addition of an Assistant Station Manager and establishment of a Safety Evaluation and Control group to replace the Systems Nuclear Safety and Operating Committee.
Discussion:
Technical Specifications Figure 6.2-1 has been revised to show the ner structure
-of the offsite organization for facility management and technical support. The previous positions of Senior Vice President-Power and Vice President-Power Supply and Production Operations have been deleted from the Technical Spect-fications. The deleted positions have been replace by the Executive Vice President-Power,,the Senior Vice President-Power Operations, and the Vice President-Nuclear Operations. All previous references to the Senior Vice President-Power and Vice President-Power Supply and Production Operations positions have been revised to reference either the Senior Vice President-Power Operations or the Vice President-Nuclear Operations positions.
4 As indicated by Figure 6.2-1, the Manager-Nuclear Operations and Maintenance and the Manager-cluelear. Technical Services replace the previous position of Director..uclear Operations. Both managers will report to the Vice President-Nuclear Operations. The Manager-Nuclear Operations and Maintenance has responsibility for the supervision of the Huclear Station Managers. Both Nuclear Station Managers and the Director-Operation and Maintenance Services
~ report to the Manager-Nuclear Operations and Maintenance. The Section Supervisor-Traininp, the Section Suoervisor-0peration and Maintenance Support, and -the Section Supervisor-Administrative Services will report to the Director-
. Operation and Maintenance Services. Reporting to the Manager-Nuclear Technical Services are the Director-Chemistry and Health Physics, the Director-Technical Analy-is and Control, and the Director-Safety Evaluation and Control.
8106030
,s-o The August 28, 1980 submittal (Serial No. 731) proposed the, transfer of the
-independent review responsibility from the existng System Nuclear Safety and Operating Committee (SyNSOC) to the Safety Evaluation and Control (SEC) staff and proposed the transfer of the System Nuclear Safety and Operating Committee audit responsibility to the Quality Assurance Department.
The SafetyL Evaluation and Control staff will be composed of a Director and a minimum of three staff members qualified to perform independent reviews..The Director-Safety Evaluation and Control will report to the Manager-Nuclear Technical Services, who will -advist the Vice President-Nuclear.0perations on the activities of the Safety Evaluation and Control Staff. This orpaniza-tional structure will assure that sufficient attention is directed towards examinatio n and evaluation of safety concerns and that management is cognizant of the results of these Safety Evaluation and Control staff reviews.
The Safety Evaluation and Control staff will provide the independent reviews of station operational activities required by ~ ANSI N18.7-1976/ANS 3.2 (Admin--
l strative Controls and Quality Assurance Program for Operational Nuclear Power Plants), which are presently provided by thi System Nuclear Safety and Opera-ting Committee. The advantages of this proposed change-are threefold.
1.
The Safety Evaluation and Control staff is composed of individuals with direct nuclear experience in their respective technical disciplines.
Presently, Safety Evaluation and Control staff specialists meet or exceed the criteria proposed in Technical Specification 6.1.C.2.b.
The proposed requirement in Specificatton 6.1.C.2.b exceeds the criteria for review
" staff specialists" established in ANSI N18.1-1971/ANS 3.1-1978 (Standard For Selection and Training of Personnel for Nuclear Power Plants) and meets the present qualification position of the Commission. Additionally, the Director-Safety Evaluation and Control exceeds the criteria established by ANSI N18.1-1971/AHS 3.1-1978 for the Supervisor of an independent review staff. Future Safety Evaluation and Control staff members may l
not meet the qualification criteria for " staff specialists" positions; however, such individuals will not be directly responsible for the independent review function of Safety Evaluation and Control.
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- 2. - The independent reviews of the station operational activities by the Safety Evaluation and Control staff will be performed on a continuous basis as part of their routine responsibilities. This is in contrast to an intermittent or scheduled review comraf ttee approach; therefore, the l
Safety Evaluation and Control reviews will be responsive to station time constraints while also providing a more comprehensive review of items presently processed by the System Nuclear Safety and Operating Committee.
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-3. ' Oth' er Safety Evaluation and Control staff routine responsibilities require continuous review of industry-wide operational experience, technical information, and regulatory issues. This effort should main-'
tain a high level of " state-of-the-art" expertise within Safety Evalua-tion and Control regarding operational activities and general industry concerns. It is anticipated.that the Safety Evaluation and Control staff will provide the m.jerity of. the expertise necessary.to perform indepen-dent review activities;' however, technical consultants and in-house
-specialists will be utilized for special concerns _when Safety-Evaluation -
and Control review requires _ additional expertise.
As a result of this change, safety will be enhanced by the proposed transfer of independent review responsibilities from the System Nuclear Safety and Operating Committee to the Saf?*, Evaluation and Control staff by upgrading the quality and timely processing of the independent reviews of station operational activities.
Specification 5.5.2.8 for North Anna Units No.1 and No. 2 requires the perfomance of audits of station activities under the cognizance of the System Nuclear Safety and Operating Committee. As a result of this proposed change, the audit responsibilities outlined in Specification 6.5.3.1, which are pre-sently being performed under the congnizance of the System Nuclear Safety and Operating Committee by the Quality Assurance Department, will be transferred to the Ouality Assurance Department. Such a transfer will provide for appropriate organizational channels for the reporting of audit results, ensure the availability of appropriate technical expertise for the performance of these audits, and ensure that these audits are performed in an effective and-timely manner.
As a result of the reorganization of the Licensing and Quality Assurance Department, the Licensing function has been transferred to Safety Evaluation and Control and the Quality Assurance organization has been restructured. The Executive, Manager-Quality Assurance will be responsible for the quality assurance effort encompassing the areas of engineering, construction, and operational activities of both the fossil and the nuclear stations. He will also be responsible for the area of corporate emergency resoonse planning and impl ementation. The Executive Manager-Quality Assurance will report to the Senior Vice President-Power Operations. The Manager-Ouality Assurance, Opera-tions will be responsible for implementing quality assurance programs which are related to the operational activities of the fossil and nuclear power stations. He will report to the Executive Manager-Quality Assurance. The Director-Quality Assurance, Nuclear Werations will be responsible for the implementation of quality assurance programs which are related to the opera-tional activities associated with the nuclear power stations. He will report to the Manager-Quality Assurance, Operations.
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The ~ organization charts for the' North Anna Environmental Technical Specific-tions and the Appendix "A" Technical Specifications have been revised.-to reflect the restructuring. of the.0uality _ Assurance Department and changes to -
other organization titles. The previous. title of Executive Manager-Licensing and Quality Assurance has been revised to Executive Manager-Quality Assurance..
In addition, the positions of Manager-Quality Assurance, Operations and
- Director-Quality Assurance, Nuclear Operations _ are shown on the organization
~ hart.-
c Technical Specification Figure.6.2-2 has been revised to show the-new struc--
ture.of the North Anna: Power Station organization. As explained above, the Station Manager reports to the Manager-Nuclear-Operations and Maintenance.
.The licensee's July 30, 1980 submittal(Serial No. 487) proposes revised Section 6.0 to add the new position of Assistant Station Manager to the North
- Anna Power, Station organization. The Assistant Station Manager will be directly responsible for the safe operation and maintenance of the power station. He.will serve in a coordinating capacity to the Station Manager, for the off-site. activities of-the Station. During the absence of the Station Manager the Assistant Manage'r will act as Station Manager. The Assistant Station Manager will also be the Vice Chairman of the Station Nuclear Safety and Operating Committee (SNS0C). The Superintendent-Operations, the Superinten--
dent-Maintenance, and the Superintendent-Technical Services will report to the Assistant Station Manager. All three of these superintendents will remain 1
members of the SNSOC.
l The positions of 0perating Supervisor and Auxiliary Operator have been elimi-nated from the organization chart. In addition, the position title of Assistant Control Room Operator has been revised to Control Room Operator Trainee. The positions of Maintenance Coordinator and Mechanical Supervisor have beer-eplaced-on the Station organization chart by the position of Supervisor-Mechanical Maintenance. Both the Maintenance Coordinator and the Mechanical Supervisor report to the Supervisor-Mechanical Maintenance. Other title changes made to the organization chart include the change of Supervisor-Safety Engineering to Engineering Supervisor (Safety Engineering), the change of Engineering Supervisor to Engineering Supervisors to reflect the two positions of Engineering Supervisor-Perfomance and Tests and Engineering Supervisor-Design Changes and Projects and, the change of Training Supervisor to Supervisor-Huclear Training. The Supervisor-Health Physics position has j
been shifted such that he will now report directly to the Station Manager instead of reporting to the Superintendent-Technical Services. The positions of Supervisor-Nuclear Training and Supervisor-Administrative Services will also report to the Station Manager.
Evaluation:
The proposed changes to the Administrative Controls, Section 6 of the NA-l&2 Appendix' A Technical Specifications fomalize the if censee's new corporate and plant organization. Based on our review, we conclude that the licensee's new organization is acceptable.
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5-Also, we concludeIthat the Safety Evaluat' ion and Control group ~will ~ provide timely' processing of the independent reviews of station operational activities.
Environmental Consideration:
We have determined that the amendments do not authorize a change in -
effluent types or total amounts nor an Lincrease.in power level and will not result in 'ary significant environmental impact. Having made this determination, we have further concluded that the amendments involve an-action which is insignificant from the standpoint of -
environmental _ impact and, pursuant to 10 CFR $51.5(d)(4), that an environmental -impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of these amendments.
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Conclusion:==
We~ have concluded, based on the consideratiers discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consequences of accidents previously considered and do not involve a.significant decrease in a safety margin, the amendments do not-involve a significant hazards consideration, (2) there is reasonable' assurance that the health and safety _ of the public will not be endangered by operation in the proposed manner, and (3) 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 or to the health and safety of the public.
Date: May 22, 1981 e
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