ML20239A696
| ML20239A696 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/01/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20234A786 | List: |
| References | |
| DPR-50-A-132 NUDOCS 8709180125 | |
| Download: ML20239A696 (6) | |
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p, NUCLEAR REGULATORY COMMISSION
-l WASHINGTON, D C. 20555
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METROPOLITAN EDISON COMPANY 1
JERSEY CENTRAL POWER AND LIGHT COMPANY l
PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION l
s l
DOCKET NO. 50-289 l
THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.132 License No. DPR-50 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(thelicensee)datedJune 18, 1987, 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 amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;
'D.
The issuance of this amendment will not be inimical to the common 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 have been satisfied.
8709180125 870901 PDR ADOCK 05000289 P
1 2.
Accordingly, the license is amended by changes to the Tech'nical i
Specifications as indicated in the attachment to this license j
amendment, and paragraph 2.c.(2) of Facility Operating License q
No. OPR-50 is herehy amended to read as follows:
l Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 132, 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.
FOR THE NUCLEAR REGULATORY COMMISSION oh Iz, Dirk Project r ctorate I-4 Division o Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: September 1, 1987
ATTACHMENT TO LICENSE AMENDMENT N0.132,
FACILITY OPERATING LICENSE NO. DPR-50 l
DOCKET NO. 50-289 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert f
Figure 6-1 Figure 6-1 Page 6-3 Page 6-3 i
Page 6-9 Page 6-9 i
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A Site Fire B'rigade## of at least 5 members.shall be maintained onsite at all times. The Site Fire Brigade shall not include members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency, h.
The Shift Technical Advisor sha11' serve in an advisory capacity to the' Shift Supervisor on matters pertaining to the engineering R
L aspects assuring safe operation of. the unit.
]
i 6',
UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minisum qualifications of ANSI /ANS 3.1 of 1978 for comparable positions unless otherwise noted in the Technical Specifications.. Licensed operators shall meet the supplemental requirements specified in Sections A and C l
l of Enclosure 1 of. the March 28, 1980 NRC letter to all licensees.
Individuals who do not meet ANSI /ANS 3.1 of 1978, Section 4.5,- are not considered technicians or maintenance personnel for purposes of determining qualifications but are permitted to perfonn work for which qualification has been demonstrated.
r 6.3.2 The Radiological Controls Director shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977.
Each Radiological Controls Technician / Supervisor shall meet or exceed the qualifications l
of ANSI-N 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved TMI-1 Radiation Controls training program. All l
Radiological Controis-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 task s.
6.3.3 The Shift Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in unit design, response and analysis of transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Plant Training - TMI and shall meet or exceed the requirements and recommendations of Regulatory Guide 1.8 of 1977 and Appendix "A" of 10 CFR Part 55 except that Radiological Controls training may be under the direction of the l-Vice President - Quality and Radiological Controls. Licensed operators shall meet the supplemental requirement specified in Section A and C of
" of the March 28, 1980 NRC letter to all licensees.
j 6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager, Plant Training - TMI and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1976.
6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CON 1 nut me, %
6-3 Amendment Nos. II,- 32, 53, 77, 92 132 L _ _____ _
- 2) Evaluation of unit operations from a safety perspective.
- 3) Assessment of unit nuclear safety programs.
- 4) Assessment of the unit performance regarding conformance to requirements related to safety, i
- 5) Any other matter involving safe operations of the nuclear ~ power plant that the Manager-Nuclear Safety deems appropriate for consideration.
AUTHORITY 6.5.4.4 The IOSRG shall have access to the unit and unit records as necessary to perform its evaluations and assessments.
Based on its reviews, the IOSRG shall provide recommendations to the management positions responsible for the areas reviewed.
QUALIFICATIONS 6.5.4.5 The IOSRG engineers shall have either: (1) a Bachelor's Degree in Engineering or the Physical Sciences and three years of professional level experience in the nuclear power field including technical supporting functions, or (2) eight years of appropriate experience in nuclear power plant operations and/or technology.
Credit toward experience will be given for advance degrees on a one-to-one basis up to a maximum of two years.
RECORDS
- 6. 5. 4. 6 Reports of evaluations and assessments encompassed in Section 6.5.4.3 shall be prepared, approved, and transmitted to the Nuclear Safety Assessment Director, TMI-1 and Planning and Nuclear Safety Division Vice President, and the management positions responsible for the areas reviewed.
6-9 Amendment No. JJ, 77, $' 132
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