ML20004B761
| ML20004B761 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/22/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004B758 | List: |
| References | |
| NUDOCS 8106010007 | |
| Download: ML20004B761 (5) | |
Text
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O SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 69 TO FACILITY OPERATING LICENSE NO. DPR-32 AND AMENDMENT NO. 69 TO FACILITY OPERATING LICENSE NO. DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-280 AND 50-281 Introduction Virginia Electric and Power dompany (the licensee) has made applications for amend =ents to License Nos. DPR-32 and DPR-3,7 for the Surry Power Station, Unit Nos. 1 and 2.
These applications are dated March 31, August 28, and Nove=ber 14,1980, as supplemented August 4,1980 and February 23, 1981.
The proposed amend ents consist of changes to the Technical Specifications which revise the Administrative Controls, Section 6.
The changes reflect corporate and plant reorganization including the addition of an.jssistant Station Manager, establishment of a Safety Evaluation and Control group to replace the System Nuclear dafety and Operating Co=mittee and the addi-tion of a Shift Technical Advisor.
Discussion and Evaluation Technical Specifications Figure 6.1-1 has been r[ vised to show the new structure of the offsite orgaci:ation for facility management and technical support.
Information provided by Figure 6.1-1 was previcusly provided by Figures 6.1-1 and 6.1-2.
The previous positions of Senior Vice President-Power and Vice President-Power Supply and Production Operations have been deleted from the Technical Specifications.
The deleted positions have been replaced by the Executive Vice President-Power, the Senior Vice President-Power Operations, and the Vice President-Nuclear Operations.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.
8196010007
l L As indicated by Figure 6.1-1, the Manager-Nuclear Operations and Main-tenance and the Manager-Nuclear Technical Services replace the previous position of Director-Nuclear Operations. Both =anagers will report to the Vice President-Nuclear Operations. The Manager-Nuclear Operations and Maintenance has responsibility for the supervision of the Nuclear Station Managers. Both Nuclear Station Managers and the Director-Oper-ation and Maintenance Services report to the Manager-Nuclear Operations and Maintenance. The Section Supervisor-Training, the Section Supervisor-Operation and Maintenance Support, and the See:1on Supervisor - Ad=inistra-tive Services will report to the Director-Operation and Maintenance Services.
Reporting to the Manager-Nuclear Technical Services are the Director-Chemis-try and Health Physics, the Director-Technical Analysis and Control, and the Director-Safety Evaluation and Control.
The August 28, 1980 submittal (Serial No. 732) proposed the transfer of the responsibility from the existing System Nuclear Safety and independent review to the Safety Evaluation and Control (SEC) staff Operating Ccm=ittee(SyNSOC) and prepot ad the transfer of the System Nuclear Safety and Operating Committee audit responsibility to the Quality Assurance Department.
The Safety Evaluation and Control staff will be composed of a Director and a I
mini =um 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 advise the Vice President-Nuclear Operations on the activities of the-Saf~ety Evaruation and Control staf'f.
This organira-tional structure will assure that surficient attention is directed towstds is cognizant examination and evaluation of safety concerns and that management g
of the results of these Safety Evaluati n and Contrcl st:ff reviews.
the independent reviews The Safety Evaluation and Control staff will provide required by ANSI N13.7-1976/ANS 3.2 (Ad=in-of station operational ac.ivities Controls and Quality Assurance Program for Operational Nuclear Power strative Plants), which are presently provided by the System Nuclear Safety and Operat-The advantages of this proposed change are threefold.
ing Committee.
First, the Safety Evaluation and Control staff is composed of indivi-nuclear experience in their respect ive technical direct duals with Presently, Safety Evaluation and Control staff specialists disciplines.
=eet or exceed the criteria proposed in rechnical Sp*cification 6.1.C.2.b.
The proposed requirement in Specification 6.1.C.2.b exceeds the criteria for review " staff specialists" established in ANSI N18.1-1971/ANS 3.1-i 1973 (Standard For Selection and Training of Personnel for Nuclear Power Plants) and meets the present qualificatien position of the Com=issicn.
Additionally, the Director -Saf ety Eval.ation and Control exceeds the established by ANSI N18.1-1971/ANS 3.1-1978 for the Supervisor l
criteria of an independent review staff.
Future Safety Evaluation and Centrol staff members may not meet the qualification criteria for " staff specialists" positiens; however, such individuals will not be directly responsible for the independent review functica of Safety Evaluatica and l
Control.
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Secondly, the independent reviews of station operational activities by the Safety Evaluation and Control staff will be perfortned on a continuous basis as part of their routine responsibilities. This is in contrast to an intermittent or scheduled review cemmittee approach; therefore, the Safety Evaluation and Control reviews will be responsive to station time censtraints while also providing a more comprehensive review of items presently processed by the System Nuclear Safety and Operating Committee.
Finally, other Safety Evaluation and Control staff routine responsibili-ties 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 majority of the expertise necessary to perform indeper.-.
dent review activitias; however, technical consultants and in-house specialists will be utilir ed for special concerns when Safety Evaluation and Control re-iew 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 Safety, Evaluation and Control staff by upgrading the quality and timely processing of the independent reviews of station operational activities.
Specification 6.1.C.2.1 for Surry Units No. 1 and No. 2 requires the perfor-mance of audits of station activities under the cognizance of the Syste, Nuclear Safety and Operating Committee.
As a result of this proposed change, the audit responsibilities outlined in Specification 6.1.C.3.a, which are pre-sently being perfor=ed under the cognizance of the System Nuclear Safety and Operating Committee by the Quality Assurance Departnent, will be transferred to the Quality Assurance Department.
Such a transfer will provide for appropriate organizational channels for the reporti 2g 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 D partment, the Licensing function has been transf erred to Safety Evaluation and Control and the Quality Assurance organization has been restructured. The Assurance will be responsible for the quality Executive Manager-Quality ~
the areas of engineering, construction, and.
assurance effort encompassing operational activities cf both the fossil and the nuclear stations.
He will also be responsible for the area of corporate emergency response planning and implementation.
The Executive Manager-Quality Assurance will report to the Senior Vice Presi. dent-?over Operations. The Manager-Quality 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 Assuran:e, Nuclear Operations will 1.e responsible for the implementation 'of quality assurance progrars 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 Appendix "A"
Technical Specifications for Surry have been revised to reflect the restructuring < f the Quality Assurance Department and changes to other organization titles.
The previous title of Executive Manager-Licensing and Quality Assurance has been revised to Execu-tive Manager-Quality Assurance.
In addition, the positions of Manager-Quality Assurance, Operations and Director-Quality Assurance,. Nuclear Operations are shown on the organization chart. [ '
Technical Sp cification Figure 6.1-2 has been revised to show the new structure of the Surry Pner Station organization.
Figure 6.1-3, which previously provided this information, has been deleted.
As explained above, the Station Manager repcrts to the Manager-Nuclear Operations and Maintenance.
Our August 4,.1980 submittal (Serial No. 671) p:oposes revising Section 6.0 to add the new position of Assistant Station Manager to the Surry Power Station organization.
The Assistant Station Manager will be directly responsibl'e for the safe cperation 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 cf the Station Manager, the Assistant Manager will act as the Statiin Mant.;er.
The Assistant Station Manager _will also be-the Vice Chairman of the Stat.on Nuclear Safety and Operating Committee (SNSOC).
The Superintendent-Operations, the Superintendent-Maintenance, and the Su'perintendent-Technical Services will report to.the Assistant Station Manager. All three of these superintendents will remain members of the SNSOC.
The positions of Operating Supervisor and Auxiliary Operator have been elimi-cated 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 been replaced 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 =ade 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-Perfor=ance and Tests and Engineering Supervisor-Design Changes and projects and, the change of Training Supervisor to Supervisor-Nuclear Training.
The Supervisor-Heslth Physics position has been shifted such that he will now report directly to the Station Manager instead of reporting to the Superintendent-Technical Services. The positions of Superviso r.-Nuclea r Training and Supervisor-Administrative Services will also report to the Station Manager.
An appraisal of the North Anna health physics program was conducted by the NRC office of Inspection and Enforcement during the period of May 3-16, 1980.
The results of this appraisal were forwarded in a letter to Mr. J. H. Ferguson dated September 15, 1980 (Serial No. 787).
One of the NRC recoc=endations resulting from the program review is that the Supervisor-Health Physics be added as a member of the Station Nuclear Safety and Operating Co=mittee (SNSOC).
The Supervisor-Health Physics was previously a member of the SNSOC; a result of Proposed required SNSOC member as however, he was deleted as a Technical Specificatien Change No. 71, which was approved and issued by the NRC as A.undment No. 53 and No. 52 for Surry Unit I and Unit 2 respectively.
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,, In order to address this concern, the proposed change is to reinstate the 1
Supervisor-Health Physics as a member of the SNSOC. Since many operations at the station involve the health physics group in some capacity, the addition of the Supervisor -Health Physics will improve the quality of SNSOC reviews by adequately appraising the impact of radiation safety on station activities.
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The proposed changes to the AEinistrative Controls Section of the Techb-cal Specification for=alizes the licensee's new corporate and plant organ-ization. Based on our review, we conclude that the licensee's new organi-zation is accaptable.
We also conclude that the Safety Evaluation and Control group will provide tisely processing of the independent reviews of station operational activi-ties.
The proposed Technical Specification Changes incorporate TMI-2 Lessons Learned Category A changes, which were submitted by letter dated November 14, 1980. These changes revised the minimum shif: crew manning table and incor-porated reqairements related to the Shif t Technical Advisor.
We have, reviewed the Technical Specifications regarding shif t crew manning and conclude that the license h'as established the mini =um crew staf fing as delineated in NRC letter dated July 31, 1980. A Shif t Technical Advisor is also added as requested by NRC letter dated July 5,1980. We find these changes acceptable.
Environmental Consideration Ne have determined that the amendments do not autheri:e a change in effluent types or total amounts nor an i. crease in power level and will not result in any significant envircnmental impact. Having made this determination, we have further concluded that the amendments involve an action which is insignificant from the standooint of environmental impact and, pursuant to 10 CFR {51.5(d)(4), that an
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environmental impact statement or negative declaration and environ-l mental impact appraisal need not be prepared in connection with the issuance of these amendments.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendments do not involve a significant increase in the probability or consecuences of accidents previcusly 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 cperaticn in the proposed.aanner, 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.
Cate:
May 22, 1981
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