ML20118C051
| ML20118C051 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/28/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20118C049 | List: |
| References | |
| NUDOCS 9210090159 | |
| Download: ML20118C051 (7) | |
Text
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- g menRu SAFETY EVALVATION BY THE OrrICE OF NVCLEAR REACTOR REGULATION filATED TO AMENDMENT N0.163 TO FAClllTY OPERATING llCENSE N0. DPR-77 AND AMENDMENT NO 153 10 FAClllTY OPERATING llCENSE NO. DPR-79 JENNESSEE VALLEY AUTHORITY SE0V0YAH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 1.0 INTRODUCTIQy By application dated May 28, 1992, and amended by letter dated July 14, 1992, the Tennessee Valley Authority (TVA or the licensn) proposed in amendment to the Technical Specifications (TS) for Sequoyah Nuclear Plant (SQN) Units 1 and 2.
The proposed changes would revise Specification 6.2.3.4 to reflect a restructuring of personnel titles within TVA's Nuclear Power organization.
Specifically, TVA proposed changing the title of the person to whom the Independent Safety Engineering (ISE) reports from Manager of Nuclear Managers Review Group to Manager, Nuclear Reviews.
By letter dated July 14, 1992, TVA proposed that this title be changed to Manager, Nuclear Experience Review /
Independent Safety Engineering, in addition, the licensee has proposed a change to Specifications 6.3.1 and 6.4.1 to indicate that the staff qualification and training program require-ments are specified in the Nuclear Quality Assurance Plan.
The change to Specification 6.10.2i would reflect the current TVA organizational nomen-clature for the Nuclear Quality Assurance (QA) Plan and the change to Specification 6.5.1.2 would update the title of the Quality Assurance Manager serving on the Plant Operations Review Committee (PORC).
2.0 EVALVATIOR As part of an organizational change in September 1991 TVA brought the corporate Nuclear Experience Review function into the Nuclear Managers Review Group (NMRG). At that time the name of the group was changed from NMRG to Nuclear Reviews to more accurately reflect the expanded organizational responsibilities.
This change did not affect the ISE, since the same reporting relationships were maintained.
Since then, organizational changes within the management structure of TVA's Nuclear Power organization have been made to provide a sharper focus on oversight and assessment functions. This action resulted in the need to change Specification 6.2.3.4 to show the ISE reporting to the Manager, Nuclear Experience Review / independent Safety Engineering.
With this change, the ISE will continue to perform independent on-site reviews within the corporate Nuclear Assurance organization.
It also maintains compliance with NUREG-0737 921009o139 920928 PDR ADOCK 0500 7
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_ _ ___._ _.. _ _ _ - - --- - - - - - - - - - - guidance and the Standard TS by ensuring that ISE reports to a high-level corporate official in a technically-oriented position who is not in the management chain for power production, and who is not an integral part of the QA organization; i.e., the Manager, Nuclear Experience Review / independent Safety Engineering.
In an effort to make the TS consistent with both the Nuclear Qualit Assurance Plan and current regulatory guidance, the licensee proposed changes a Specification 6.3.1, FACILITY staff QUAllf! CATIONS.
The proposed changes would substitute the references to ANSI N18.1-1971, the March 28, 1980 NRC letter, and Regulatory Guide 1.8 with a reference to the TVA Nuclear Quality Assurance Plan.
These changes reflect the requirements of Regulatory Guide (RG) 1.8, Revision 2, for all new personnel qualifying for positions i
identified in Regulatory Position C.1 af ter Janyary 1,1990.
Personnel qualified for these positions before this date would continue to meet the requirements of RG 1.8, Revision 1-R.
As specified in Regulatory Position C.2, all other positions will meet the requirements of the American National Standards Institute /American Nuclear Society Standard N18.1-1971.
These requirements are also currently reflected in the TVA Nuclear Quality Assurance Plan.
However, the NRC staff has determined that parts of the proposed change to Specification 6.3.1 should not be removed in order to ensure that appropriate enforceability of the programs of the applicable standards (which include important details for the proper implementation of these programs) is retained.
Therefore, the staff has denied:
(a) removal of the reference to ANSI N18.1-1971; (b) removal of the reference to the Site Radiological Control Manager qualification specification to Regulatory Guide 1.8, September 1975; and (c) insertion of the reference to the TVA Nuclear Quality Assurance Plan.
The staff has, however, determined that removal of the statement "the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees" is acceptable.
As a result, Specification 6.3.1 will read:
"Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Site Radiological Control Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975." These conclusions and changes have been discussed with the TVA staff.
The licensee also proposed changes to Specification 6.4.1. TRAINING, to make the TS consistent with both the Nuclear Quality Assurance Plan and current regulatory guidance.
This proposed change would reflect the 1987 revision to 10 CFR 55 that allowed facilities to substitute programs based on a systematic-approach to training methodology and to conduct training using a plant-referenced simulator certified by'the NRC, for the existing regulatory-based programs.
This revision reflected the Commission's acceptance of industry initiatives and provides flexibility to licensees who maintain accreditation through the National Academy for Nuclear Training and who conduct training of operators ou certified, plant-referenced simulators.
It eliminated Appendix A of 10 CFR 55 and superseded the operator licensing requirements of NUREGs 0737 and 0094.
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The training program structure and content guidance continue to be governed by the corporate-level training program described in the Nuclear Quality Assurance Plan using procedures contained in the Nuclear Power Training Manual.
These program procedures, which are quality related, are subject to review in accordance with 10 CFR 50.59.
They describe the programs that are accredited by the National Academy for Nuclear Training.
Accreditation is not granted or maintained unless compliance with the academy-published guidelines is established.
These guidelines are consistent with, and in many areas exceed, the previous regulatory requirements.
However, the NRC staff has determined that certain proposed changes to Specification 6.4.1 should be retained in order to ensure appropriate enforceability of the provisions of the applicable standards which include important details for the proper implementation of these programs.
Therefore, the staff has denied the proposed change to remove the reference to ANSI N18.1-1971 and insert a reference to the TVA Nuclear Quality Assurance Plan.
The staff has, however, determined that removal of the reference to the March 28, 1980 letter is acceptable.
These conclusions and changes have been discussed with the TVA staff.
The proposed change to (pecification 6.5.1.2 is administrative in nature and reflects the current organizational nomenclature.
The change to the title of the Plant Operations Review Committee (PORC) member frcm Quality Engineering and Monitoring Supervisor, to Quality Audit and Monitoring Manager would not change the duties or responsibilities of the member, nor does it result in a change to the ability of the PORC to perform its designated functions.
'the change to Specification 6.10.2.i is also administrative in nature since it reflects the current title given to the document that summarizes the Quality Assurance program.
The purpose and requirements remain unchanged.
With the exception of the proposed changes to Specification 6.3.1 and 6.4.1 that were found to be unacceptable as described above, the staff has determined that the other proposed changes represent no change to the implementation of the associated regulations and are consistent with the appropriate regulatory guidance, or are administrative in nature.
Therefore, the ataff has determined that they are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendments.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments involve changes to administrative procedures or requirements.
The Commission has previously issued proposed findings that the amendments involve no significant hazards consideration, and there has tan no public comments on such findings (57 FR 30262 and 57 FR 34591).
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Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR Sl.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
l 5.0 CONCl0S10f1 1he Commission has concluded, based on the considerations discussed above, that:
(1) there is reasenable 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.
Principal Contributor:
D. LaBarge Date: September 28, 1992 a
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UNITED STATES NUCLEAR REGULATORY COMMISSION IENNESSEE VALLEY AUTHORITY S HUOYAH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET N05. 50-327 AND 50-318 NOTICE OF PARTIAL DENIAL OF AMENDMENT TO FAcIllTY OPER AND OPPORTUNITY FOR HEARING The U.S. Nuclear Regulatory Commission (the Commission) has denied a portion of a request Oy the Tennessee Valley Authority (TVA or the licensee) for an amendment to facility Operating License Nos. DPR-77 and DPR-79 issued to the licensee for operation of the Sequoyah Nuclear Plant, Units 1 and 2, located ir. Toddy Daisy. Tennessee.
Notice of Conalderation of Issuance of Amendment to facility Operating License and Proposed No Significant Hazards Consideration and Determination and Opportunity for Hearing was published in the FEDERAL REGISTER on July 8, 1992 (57 FR 30262) and renoticed on August 5, 1992 (57 FR 34S91).
The purpose of the licensee's amendment request was to revise the Technical Specifications (TS) to 'ref'ect a restructuring within TVA's Nuclear Power Organization affecting the Independent Safety Engineering manager, change the reference document that contains the facility staff qualification and training-requirements, and update Plant Operations Review Committee membership.
The staff has determined that the proposed change to substitute the references to ANSI N18.1-1971, the March 28, 1980 NRC letter, and Regulatory Guide 1.8, with a reference to the TVA Nuclear Quality Assurance Plan in
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_ Specification 6.3.1 cannot be granted.
Similarly, the proposed substitution of the references to ANSI N18.1-1971 in Specification 6.4.1 with a reference to the TVA Quality Assurance Plan cannot be granted.
The licensee was notified of the Commission's denial by letter dated September ?8,1992.
By November 2,1992, the licensee may demand a hearing with respect to the denial described above.
Any person whose interest may t'e affected by this proceeding may file a written petition for leave to intervene.
A request for hearing or petition for leave to intervene must be filed with the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC, 20555, Attention:
Docketing and Services Branch, or may be delivered to the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, by the above date.
A copy of any petitions should also be sent to the Office of the General Counsel, Tennessee Valley Authority, 400 West Summit Hill Drive, Ell 833 Knoxville, Tennessee 37902, attorney for the licensee.
For further details with respect to this action, see (1) the application for amendment dated May 28, 1992, which was modified by letter dated July 14, 1992, and (2) the Conmission's letter to the licensee dated September 28, 1992.
These documents are availaole for public inspection at the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC, and at the local public document room located at the Chattanooga 4(amilton County Library,1001 Broad Street, Chattanooga, Tennessee 37402.
A copy of item (2) may be obtained upon request addressed to the U.S. Nuclear l
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3 Regulatory Commission, Washington, DC, 20555 Attention:
Document Control Desk.
Dated at Rockville, Maryland, this 28th day of September, 1992.
FOR THE NUCLEAR REGULATORY COMMISSION
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!v'<bli Fr'ederick J. Hebd n, Director Project Directorate 11-4 Division of Reactor Projects - f/11 Office of Nuclear Reactor Regulation-d
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