ML20011F109
| ML20011F109 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/21/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011F107 | List: |
| References | |
| NUDOCS 9003010110 | |
| Download: ML20011F109 (5) | |
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s GPU NUCLEAR CORPORATION DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION.. UNIT-NO.-2 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37-License No. DPR-73 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, (the licensee)datedDe) ember 27, 1988, as supplementend July 13, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this arr.endment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon-defense and security or.to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements l
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Accordingly,.the license is amended by changes-to the Technical Specifications as indicated in the attachment to this license amendment,andparagraph2.c.(2)ofFacilityOperatingLicense No. DPR-73 ds'hereby amended to read'as follows:
(2) Technical Specifications U
L The Technical Specifications-contained in Appendix A.Las revised through Amendment No. 37, are hereby' incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be
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< implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hn h Stolz, Director to ect Directorate e
1sion of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 21, 1990 l
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j ATTACHMENT TO LICENSE At!ENOMENT NO._37 FACILITY OPERATING LICENSE NO. DPR-73 DOCKET NO. 50-320-Replace the following pages of the Appendix A Technical Specifications with'
'i the attached pages. The revised pages are identified by amendment numb 3r and contain vertical lines indicating the areas of change.
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~ ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF'0VALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum quali-fications of ANSI-N 18.1 of 1971 for comparable positions unless otherwise
- noted in the fechnical Specifications.
During Modes 2 and 3, the requirements of ANSI N18.1-1971, that pertain to unit staff operator license qualifications shall not apply.
6.3.2 The Manager, Radiological Controls TMI-2 shall meet or exceed the quali-fications of Regulatory Guide 1.8, September 1975.
Each Radiological Controls Technician in responsible positions / Foreman shall meet or exceed the qualifica-tions of ANSI 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved TMI-2 Radiation Controls training program.
Individuals who do not meet ANSI 18.1-1971 Section 4.5.2 are not considered technicians for pur-poses of. determining qualifications but are permitted to perform work for which qualification has been demonstrated.
All Radiological Controls Technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the cognizance of the Plant Training Manager and shall meet or exceed the requirements and recommendations of Regulatory Guide 1.8 of 1977 Appendix "A" of 10 CFR Part 55 except that Radiological Controls training may be under the direction of Vice President-Radiological and Environmental Controls.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Plant Training Manager and shall meet or exceed the require-ments of Section 27 of the NFPA Code-1976.
- 6. 5 REVIEW AND AUDIT 6.5.1 Technical Review and Control
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The Office'of TMI-2 Division Director and Support Division Vice-Presidents within GPU Nuclear Coporation as indicated in Organization Plan Figure 1.1, shall. be responsible for ensuring the preparation, review, and approval of documents required by the activities within their functional area of respon-sibility for TMI-2.
Implementing approvals shall be performed at the cogni-zant section manager / director level or above.
Independent safety review and audit shall be conducted in accordance with this Technical Specification.
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THREE MILE ISLAND - UNIT 2 6-3 Amendment No. 37
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V ADMINISTRATIVE CONTROLS 6.8.2.1 Each procedure and any change to any procedure prepared pursuant to g
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'6.8.1, shall be prepared, reviewed and approved in accordance with 6.5 and will be reviewed periodically as required by ANSI 18.7 - 1976.
6Property "ANSI code" (as page type) with input value "ANSI 18.7 - 1976.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..8.2.2 ' Deleted.
6.8.3.1 ~ Temporary changes to procedures of'6.8.1 may be made provided that:
a.
The intent of the original procedure control is not altered, and b.
(1)'For those procedures which affect the operational status of unit systems or equipment, the change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator's License.
(Note:
The requirement for a Senior Reactor-Operator's License applies during Mode 1 only.) If one of the two above signatures is not by a supervisory person within the Department having cognizance of the procedure being changed, the signature of-that supervisory person within the department will also be required, or (2) For those procedures which do not affect the operational status of unit systems e equipment, the change is approved by two members of the responsible organization.
If one of the two above signatures is not by a section manager / director within the Department having cognizance of the procedure being changed, the signature of that h
section manager / director within the department will also be required, and c.
The change is documented, Independent Safety Review completed, and the required reviews and approvals are obtained within 14 days, and d.
Those changes to procedures required by Specification 3.9.13 are submitted to the NRC for review within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following approval by the management level specified for implementation by Section 6.5.1.9.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES L
6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted in accordance with 10 CFR 50.4 unless otherwise noted.
ANNUAL REPORTS 1 6.9.1.4 Annual reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 1 of each year.
- 6. 9.1. 5 Reports required on an annual basis shall include:
a.
A tabulation of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job func-tions,2 e.g., reactor operations and surveillance, inservice l-IA single submittal may be made for a multiple unit station.
The submittal l
should combine those sections that are common to all units at the station.
2This tabulation supplements the requirements of S 20.407 of 10 CFR Part 20.
THREE MILE ISLAND - UNIT 2 6-11 Amendment No. 17
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