ML20011F112
| ML20011F112 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/21/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011F107 | List: |
| References | |
| NUDOCS 9003010119 | |
| Download: ML20011F112 (2) | |
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SAFETY EVALUATION BY.THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 37'TO FACILITY.0PERATING. LICENSE NO. DPR-73 GPU NUCLEAR-CORPORATION THREE MILE ISLAND NUCLEAR STATION UNIT NO. 2 DOCKET NO.-50-320 INTRODUCTION By letter dated December 27, 1988, GPU Nuclear Corporation (GPUN or the licensee)requestedtheapprovalofachangetotheAppendixATechnical Specifications of Facility Operating License No. DPR-73 for Three Mile Island
' Nuclear Station, Unit No. 2.
On July 13, 1989 the licensee submitted Supplement 1 to the requested technical specification change. The proposed amendment would revise technical specifications related to unit staff qualifications once the facility completes defueling and enters Mode 2.
DISCUSSION AND EVALUATION The licensee proposes to revise Aopendix A Technical Specifications Sections 6-3, Unit Staff Qualifications atd Section 6.8 Procedures. The proposed
- changes would resolve potential inconsistencies between qualifications of unit staff personnel, required by the Technical Specifications, and the plant conditions after defueling.
Section 6.3, Unit Staff Qualifications requires that unit staff personnel must comply-with ANSI-N18.1 of 1971. ANSI-N18.1 of 1971 states that certain positions of the plant staff either hold or be capable of acquiring an operator's license. Additionally, the ANSI standard states that the Plant Manager position requires either an individual or designated alternate have a Senior Reactor Operating (SRO) license or have the background required to sit for the exam.
Once defueling of TMI-2 is completed and the licensee has demonstrated that
.the possibility of an inadequate criticality is precluded then the licensee can, as allowed by the current Technical Specifications, transition to Mode 2.
In Mode 2 the Technical Specifications no longer require licensed operators to be present at TMI-2.
The licensee has proposed adding to Section 6.3.1 the statement that once the facility enters Mode 2 the requirements of ANSI-NIB.1 of 1971 pertaining to unit staff operator qualifications not apply. The licensee asserts that since there will no longer be a requirement for SR0s after they enter Mode 2, the remainder of the unit staff should not be required to have an SRO license or be required to have the background to sit for the examination.
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The licensee however has stated'that during Modes 2 and 3, GPU Nuclear will continue to apply the educational and experience requirements of ANSI-N18.1 of 1971 to the TMI-2 staff with the exception of unit staff licensed operator requirements and unless otherwise noted in the Technical Specifications.
The staff finds the proposed change acceptable and sees no justification for the SRO license requirements for the position of Plant Manager once the facility is defueled.
Section 6.8, Procedures requires, under 6.8.3.1.b.(1), that for those plant procedures which affect the operational status of the unit systems or equipinent, i
proposed changes to the procedures must be approved by two members of the unit management staff, at least one of whom holds a SRO license. The licensee proposes to delete the requirement that one of the individuals holds a SRO license once the plant is defueled and transitions to Mode 2.
Again the licensee asserts that once the plant is defueled then there would be no justification for retaining the requirement for a menber of the Unit Management staff to maintain a SRO license.
The staff finds no justification for the SRO license requirement once the facility is defueled and has determined that the proposed change is acceptable.
ENVIRONMENTAL CONSIDERATION This amendment relates to changes in administrative procedures or requirements.
Accordingly, the amendment meets the elig)ibility criteria for categorical exclusion set forth in 10.CFR 51.22(c)(10. Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
CONCLUSION We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: Michael T. Masnik Dated: February 21, 1990 f
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