ML20087G573
| ML20087G573 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/14/1995 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20087G575 | List: |
| References | |
| NUDOCS 9508170113 | |
| Download: ML20087G573 (5) | |
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NUCLEAR REGULATORY. COMMISSION
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY
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GPU NUCLEAR CORPORATION DOCKET NO. 50-289 l
THREE MILE ISLAND NUCLEAR STATION.-UNIT NO. I t
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.195 j
License No. DPR-50 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The-application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated April 19,-1994, as supplemented on March.8, 1995, complies with the standards and requirements-of the Atomic i
Energy Act of 1954, as amended (the Act),'and the Commission's rules and regulations set forth in 10 CFR Chapter I; j
i B.
The facility will operate in conformity with the application, the-l provisions of the Act, and the rules and regulations of the Commission; 1
C.
There is reasonable assurance (i) 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; j
D.
The issuance of this amendment will not be inimical to the common i
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 Commission's regulations and all applicable requirements have been satisfied.
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9508170113 950814 "
PDR ADOCK 05000289 P
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No.
DPR-50 is hereby amended to read as follows:
(2)~ Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.195, 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 C0ffilSSION l
hh Phillip F. McKee, Director Project Directcrate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 14, 1995 j
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ATTACHMENT TO LICENSE AMENDMENT NO. 19s FACILITY OPERATING LICENSE NO. DPR-50 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 i
contain vertical lines indicating the areas of change.
Remove Insert I
6-7 6-7 6-8 6-8
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Any other matters involving safe operation of the nuclear power plant which a reviewer deems appropriate'for consideration, or which is referred to the independent' reviewers.
6.5.2.6 -QUALIFICATIONS
-The independent reviewer (s) sh'll either have a Bachelor's a
Degree in Engineering or the Physical Sciences and'five (5) years of professional level experience in the area being.
reviewed or have 9 years of appropriate experience in the field of'his speciality. An individual performing reviews may possess
' competence in more than on specialty area. Credit toward experience will be given for advanced degrees on a one-for-one basis up to a maximum of two years.
RECORDS 6.5.2.7 Reports of reviews encompassed in Section 6.5.2.5 shall be prepared, maintained and transmitted to the cognizant division Vice President.
6.5.3 AUDITS 6.5.3.1 Audits of unit activities shall be performed in accordance with the?
1 TMI-1 Operational Quality Assurance Plan.
These audits shall I
encompass:
a.
The conformance of unit operations to provisions contained within the Technical Specifications and applicable license conditions.
b.
The performance, training and qualifications of the entire unit staff.
l c.
The verification of the non-conformances and corrective actions program to be ' properly implemented and documented as related to action taken.to correct deficiencies occurring in unit equipment, structures, systems or methods of operation that affect nuclear safety.
l d.
The performance. of activities required by the Operational Quality Assuranca Plan to meet the criteria of Appendix "B" 10 CFR 50.
e.
The Emergency Plan and Implementing procedures.
f.
The Security Plan and implementing procedures.
g.
The Fire Protection Program and implementing procedures.
h.
The Offsite Dose Calculation Manual (0DCM) and implementing procedures.
g 6-7 Amendment No. 11, 77, 84,195
- i. The Process Control Program and implementing procedures for i
solidification of radioactive wastes.
- j. The performance of activit!es required by the Quality Assurance Program to meet criteria of Regulatory Guide 4.15, December, 1977.
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Any other area of unit operation considered appropriate i
by the 10SRG or the Office of the President - GPUN.
6.5.3.2 Audits of the following shall be performed under the cognizance of the vice president responsible for technical support:
a.
An independent fire protection and loss prevention program inspection and audit shall be performed utilizing either qualified licensee personnel or an outside fire protection firm.
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b.
An inspection and audit of the fire protection and loss l
prevention program, by an outside qualified fire consultant.
HECORDS 6.5.3.3 Audit reports encompassed by sections 6.5.3.1 and 6.5.3.2 shall be forwarded for action to the management positions responsible for the areas audited within 60 days after completion of the audit.
Upper management shall be l
informed per the Operation Quality Assurance Plan.
6.5.4 INDEPENDENT ONSITE SAFETY REVIEW GROUP (IOSRG) STRUCTURE I
6.5.4.1 The 10SRG shall be a full-time group of engineers, experienced in nuclear power plant engineering, operations i
and/or technology, independent of the unit staff, and located on site.
ORGANIZATION 6.5.4.2 a.
The 10SRG shall consist of a manager and a minimum staff of 3 members who meet the qualifications of 6.5.4.5.
Group expertise 1
shall be multi-disciplined.
b.
In the event of an unanticipated vacancy in the 10SRG staff, the number of staff can be two (2) members for a period of not to exceed six (6) months while the vacancy is being
- filled, c.
The 10SRG shall report to the director responsible for nuclear safety assessment.
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Amendment No. 11, 77, 99, 139, 149,195 i
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