ML20094Q024
| ML20094Q024 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/24/1995 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20094Q026 | List: |
| References | |
| NUDOCS 9512010016 | |
| Download: ML20094Q024 (5) | |
Text
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t UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. mi k
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1.
METROPOLITAN EDISON COMPANY d
1 JERSEY CENTRAL POWER & LIGHT COMPANY l
PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION
]
DOCKET NO. 50-289 i
THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 1
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AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 199 License No. DPR-50 y
1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated May 24, 1995, as supplemented July 24, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; 4
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 Commission's regulations and all applicable requirements have been satisfied.
i i
9512010016 951124 PDR ADOCK 05000289 P
! i 2.
Accordihgly, 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.199, 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 implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY C0leilSSION l
Phillip F. McKee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 24, 1995 i
ATTAC MENT TO LICENSE AMENDMENT NO.199 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 contain vertical lines indicating the area of change.
Remove Insert 1-8 1-8 4-3 4-3
)
4 8
5 4
. 1.24 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT is a TMI-l specific document that provides core
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operating limits for the current operating mioad cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.5. Plant operation within these operating limits is addressed in individual specifications.
1.25 FREQUENCY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2. 'All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. The 25 % extension applies to all frequency intervals with the exception of "F." No extension is allowed for intervals designated "F."
s TABLE 1.2 i
FREOUENCY NOTATION 1
J NOTATION FREOUENCY S
Shiftly (once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) 2' D
Daily (once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)
W.
Weekly (once per 7 days)
M Monthly (once per 31 days)
Q Quarterly (once per 92 days)
S/A Semi-Annually (once per 184 days)
R Refueling Interval (once per 24 months)
P S/U Prior to each reactor startup, if not done during the previous 7 days P S/A Within six (6) months prior to each reactor startup 1
P Completed prior to each release N/A (NA)
Not applicable E
Once per 18 months F
Not to exceed 24 months l-8 Amendment No. 72,137,155,173,171,199 3
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p TABLE 4.1-1 E
INSTRUMENT SURVEILLANCE REQUIREMENTS a
CHANNEL DESCRIPTION CHECK TEST CALIBRATE REMARKS E
1.
Protection Channel NA M
NA Coincidence Logic 0
2.
Control Rod Drive Trip NA M
NA (1) Includes independent testing of shunt Breaker and Regulating trip and undervoltage trip features.
g Rod Power SCRs i
3.
Power Range Amplifier D(1)
NA (2)
(1) When reactor power is greater than 15%.
h (2) When above 15% reactor power run a heat balance check once per shift. Heat balance calibation shall be performed whenever heat balance exceeds indicated neutron power by more than two percent.
p 4.
Power Range Channel S
M M(1)(2) (1) When reactor power is greater than 60% verify imbalance w
using incore instmmentation.
(2) When above 15 % reactor power calculate axial offset upper and lower chambers after each startup if not done within the previous seven days.
5.
Intermediate Range Channel S(l)
P S/U NA (1) When in service.
6.
Source Range Channel S(l)
P S/A NA (1) When in service.
7.
Reactor Coolant Temperature S
M F
Channel i
-.