ML20128L723
| ML20128L723 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/03/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20128L692 | List: |
| References | |
| NUDOCS 9610150176 | |
| Download: ML20128L723 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D.C. 20515 0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION 1
RELATED TO AMENDMENT NO.158 TO FACILITY OPERATING LICENSE NO. DPR-13 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELL'TRIC COMPANY SAN ON0FRE NUCLEAR GENERATING STATION. UNIT N0. I l
DOCKET NO. 50-206 l.0 INTRODUCTION By letter of March 13, 1996, Southern California Edison Company (SCE or the licensee) submitted a request for a c.hange to the San Onofre Nuclear Generating Station, Unit No. 1 (SONGS 1), Facility Operating License No. DPR-13.
The requested change would revise Section 2.0 of the SONGS 1 Operating License to remove a reporting requirement that is redundant to reporting requirements in 10 CFR 50.72 and 50.73. Additionally, the amendment makes administrative and editorial changes to the Permanently Defueled Technical Specifications (PDTS), which constitute Appendix A of the Operating License.
2.0 DISCUSSION AND EVALUATION As a result of an agreement with the California Public Utilities Commission, SONGS 1 was permanently shut down on November 30, 1992, and defueling of the reactor was completed by the licensee on March 6, 1993.
Upon certification of completion of defueling of the reactor to the NRC by the licensee, amendment of the Facility Operating License to a possession-only status became effective on March 9, 1993.
The reactor remains defueled with the fuel stored in the spent fuel pool.
SONGS 1 is permanently defueled and cannot be operated or have fuel placed in the reactor under the terms of its license.
On December 28, 1993, Permanently Defueled Technical Specifications (PDTS) were issued for SONGS 1.
The PDTS replaced the existing Technical Specifications in their entirety.
The PDTS reflect the reduced number of postulated accidents against which the defueled plant must be protected while ensuring the safe, long-term storage of irradiated fuel in the spent fuel pool.
In its letter of March 13, 1996, the licensee proposed to revise Section 2.0 of the Operating License for SONGS 1.
Additionally, the licensee proposes to make administrative and editorial changes in Section D6, Administrative Controls, of the Permanently Defueled Technical Specifications (PDTS) for SONGS 1.
Evaluation of the proposed changes to Section 2.0 and the PDTS are discussed in the following paragraphs.
9610150176 961003 DR ADOCK 0500 6
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. License Condition 2.0 License Condition 2.0 requires that any violations of the requirements stated in the license conditions of Section 2.C(1) through 2.C(4) be reported to the l
NRC with initial notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and a written follow-up within 30 days.
License Condition 2.D further requires that the reporting be consistent with items (b), (c), and (e) of 10 CFR 50.73, " Licensee event report system." License Condition 2.C(2) requires Jiat SONGS 1 be maintained in accordance with the Technical Specifications.
The licensee contends that the inclusion of License Condition 2.C(2) in License Condition 2.0 is redundant because 10 CFR 50.73(a)(2)(1)(B) also requires the licensee to report "Any operation or condition prohibited by the plant's Technical Specifications."
In addition, the licensee has noted that 10 CFR 50.73(g) states that "The requirements contained in this section replace all existing requirements for licensees to report ' Reportable Occurrences' as defined in individual plant Technical Specifications."
The requested change is administrative in nature.
The licensee will continue to be rcquired to conduct activities at the plant in accordance with the NRC-apiroved Technical Specifications and will still be required to report violations or deviations from the Technical Specifications as specified in i
10 CFR 50.72 and 50.73.
The NRC staff finds that reporting License Condition 1
2.C(2) under License Condition 2.D is duplicative and that removal of this reporting requirement will not preclude reporting of deviations from the Technical Specifications. Additionally, the staff finds that the absence of this reporting requirement will not adversely affect public health and safety.
Therefore, the staff finds the proposed change acceptable.
Permanently Defueled Technical Specifications The PDTS changes that the licensee has proposed are the result of changes in Southern California Edison's nuclear organization, a need to reassign a responsibility associated with the Onsite Review Committee (0SRC) to a different Vice President and to change an associated 24-hour notification consistent with this reassignment of responsibility, and the need to make editorial improvements in Section D6.
The changes are discussed in the following paragraphs.
Section D6 of the PDTS describes SCE's management structure, titles, and responsibilities.
The description reflects the management structure as it existed when the PDTS was submitted in May 1993 for NRC approval.
- However, organizational changes have been made since then, making some of the PDTS information obsolete.
In June 1993, the position of "Vice President - Engineering & Technical Services" was created.
This position assumed some of the responsibilities previously assigned to the " Senior Vice President." During later changes, the two positions of " Station Manager" and "Vice President and Site Manager," were replaced by the single position of "Vice President - Nuclear Generation."
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. This position has assumed the responsibilities previously associated with the
" Station Manager" and the "Vice President and Site Manager." The licensee proposes to revise the text of Section D6 throughout (Sections 1.1, 1.2, 2.1.c, 5.1.7, 5.2, 5.3, 6.1.b, 7.1, and 8.2) to reflect these organizational changes.
The NRC staff has determined that this is an administrative change and finds the change acceptable.
Subsection D6.5.2, contains requirements for controlling certain plant documents and changes to these documents.
These documents include procedures, technical specifications, documentation used to describe plant modifications and certain tests and experiments, the site security plan, site emergency plan, reports used to evaluate uncontrolled or unplanned release of radioactive material to the environs, and the Offsite Dose Calculation Manual.
The subsection assigns review, approval, and other administrative responsibilities regarding these documents to the " Station Manager."
Additionally, subsection D6.5.2 requires that documentation of review, approval, or other administrative responsibilities be provided to the "Vice President and Site Manager, Nuclear Generation Site" and to the Nuclear Safety Group (NSG) Supervisor. As discussed above, the positions of " Station Manager" and "Vice President and Site Manager, Nuclear Generation Site" have been replaced with the single position of "Vice President - Nuclear Generation." Therefore, the "Vice President - Nuclear Generation" is involved in the review, approval, and other administrative tasks related to the various documents discussed in subsection D6.5.2 and consequently need not receive documentation regarding the completion of these tasks. Accordingly, the licensee has proposed that subsection D6.5.2 be revised to require that only the NSG Supervisor receive the necessary documentation.
The NRC staff has determined that this is an administrative change and finds the change acceptable.
Subsection 06.5.1 contains reqJirements related to the Onsite Review Committee (OSRC).
Paragraph D6.5.1.7.b requires that in case of a disagreement between the OSRC and the " Station Manager" (0SRC chairman), written notification be provided to the "Vice President and Site Manager, Nuclear Generation Site" and the NSG Supervisor. This notification is to be provided within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the disagreement.
Paragraph D6.5.1.7.b also requires that the "Vice President and Site Manager, Nuclear Generation Site" be responsible for resolving disagreements between the " Station Manager" and the OSRC pursuant to 06.1.1.
D6.1.1 requires that the "Vice President and Site Manager, Nuclear Generation Site" be responsible for overall management of the plant, ensuring the safe storage and handling of irradiated fuel, and all site support functions.
3 The requirements described in the two previous paragraphs reflect the previously existing management structure.
The "Vice President - Nuclear Generation" now holds the responsibilities previously assigned to the " Station i
Manager" and the "Vice President and Site Manager." The "Vice President -
Engineering & Technical Services" now holds some of the responsibilities previously held by the " Senior Vice President." Therefore, the licensee believes that it is appropriate that the "Vice President - Engineering &
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. Technical Services" rather than the "Vice President - Nuclear Generation" have responsibility for resolving disagreements between the "Vice President -
Nuclear Generation" and the OSRC. Nonetheless, consistent with D6.1.1, the "Vice President - Nuclear Generation" will continue to be responsible for overall management of the plant, for ensuring safe storage and handling of irradiated fuel, and for all site support functions. Accordingly, the licensee has proposed to revise D6.5.1.7.b to incorporate changes in the 24-hour notification and the responsibilities associated with OSRC.
It has also requested deletion of the words " pursuant to D6.1.1 above" from D6.5.1.7.b because D6.1.1. does not apply to the position "Vice President -
Engineering & Technical Services." The NRC staff finds the change acceptable because it is administrative in nature and clarifies the PDTS to reflect more accurately the SCE management structure.
Subsection D6.2.1 of the PDTS requires that onsite and offsite organizations be established for plant management and corporate management, respectively.
Paragraph (a) therein requires that lines of authority, responsibility, and communications in these organizations be documented and periodically updated.
Paragraph (a) currently states that these requirements shall be documented in the FSAR.
Generic Letter 88-06, " Removal of Organization Charts from Technical Specification Administrative Control Requirements," dated March 22, 1988, provides guidance related to the documentation of organizational information.
The generic letter allows information concerning lines of authority, responsibility, and communication; functional descriptions departmental responsibilities and relations; and job descriptions for key personnel positions to be documented in the FSAR, the Quality Assurance Plan, or some other appropriate document.
The SONGS Quality Assurance Plan, titled " Topical Report Quality Assurance Program," includes SONGS 1, 2, and 3 and is updated regularly.
The licensee has requested that the documentation requirement of subsection D6.2.1 be changed to read:
"These requirements shall be documented in the SONGS Topical Report Quality Assurance Program."
NRC staff review indicates that revision of this documentation requirement is consistent with General letter 88-06, will not reduce plant safety, and will not adversely affect public health and safety.
Therefore, the staff finds the proposed change acceptable.
3.0 STATE CONSULTATION
In accordance with the regulations of the Commission, the California State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and also changes a reporting requirement.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative i
occupational radiation exposure.
The Comission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public coment on such finding (61 FR 40028). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (c)(10).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in conraction with the issuance of the amendment.
5.0 CONCLUSION
l The Comission 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, (2) such activities will be conducted in compliance with the regulations of the Commission, and (3) the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributor:
M. Webb Date:
October 3, 1996
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