ML20076E064
| ML20076E064 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/09/1991 |
| 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 | |
| ML20076E067 | List: |
| References | |
| DPR-50-A-163 NUDOCS 9108150059 | |
| Download: ML20076E064 (3) | |
Text
2 EECh
/gk Io g
/4-e UNITED STATES 3
5le, ' !
WASHINGTON. D.C. 20%5 i
NUCLEAR REGULATORY COMMISSION
- d @
o
.%.,<,5 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPAhT GPU NUCLEAR CORPORATIO'.
DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING L1"ENSE Amendment No.163 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(the licensee) dated July 9, 1991, as supplemented by letter dated August 6, 1991, 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 Loipter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Commisalon'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 l
have been satisfied.
l L
9108150059 910809 PDR ADOCK 05000289 l
p PDR
, 2.
Accordingly, paragraph 2.c.(8)2 of Facility Operating License No. DPR-50 is hereby amended by adding a footnote to read as fellows:**
- If leakage exceeds the baseline leakage rate by more than 0.2 gpm during the _ remainder of the Cycle 8 operation, the facility shall be shutdown and leak tested, Operation at leakage rates of up to 0.2 gpm above the baseline leakage rate shall be acceptable during the remainder of Cycle 8 operation. After the 9R refueling outage, the leakage limit and accompanying shutdown requirements revert to 0.1 gpm above the baseline leakage rate.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.
FOR Tile NUCLEAR REGULATO 'Y C0hMISSION J6 in f. Stolz, Director fro'ectDirectorate1-4 b'fision of Reactor Projects - I/II office of Nuclear Reactor Regulation attachment:
Page 6 of License Date of Issuance:
August 9, 1991
- Page 6 is attached, for convenience, for the composite license to reflect this change.
o 1.
.i 6-i (8) -Repaired steam Generators in order-to confirm the leak-tight integrity of the Reactor Coolant System,-including'the steam generators, operation of the facility shall be'in accordance with the following:
1.
Prio'r to initial criticality,.GPU Nuclear Corporation shall
~
submit to NRC the results of the steam generator hot test program and a, summary of its mansgement review.
2.
GPU Nuclear Corporation shall confirm baseline primary-to-
- secondary leakage rate established during the. steam generator hot _ test program.
If leakage exceeds the baseline leakage rate by more than 0.1 gpm *,.the f acility shall be shut down and -leak l tested.
If any increased leakage above baseline is due to defects in the tube free span, the leaking tube (s) shall be removed from service. The baseline leakage shall be re-established, provided that-the leakage limit of Technical Specification 3.1.6.3 is not exceeded.
3.-
GPU-Nuclear Corporation shall complete its post-critical test program at'each power range (0-5%, 5%-50%, 50%-100%) in conformance with the program _ described in Topical Report 008, Rev. -3, and shall'have-available the results of that test program and a summary of its management review, prior to ascension-from each power range and prior to normal _ power operation.
4.
G90 Nuclear Corporation shall conduct eddy-current examinations, consistent with the extended inservice inspection plan def,ined in Table 3.3-1 of NUREG-1019, either. 90 calendar days af ter.
reaching full power, or 120 calendar' days after exceeding 50%.
power operation, whichever comes first.
In the event of plant operation for an extended period at less than 50% power, GPU Nuclear Corporation shall provide an assessment at the end of_
180 days of operation at power levels between 5% and 50%, such assessment to contain recommendations-and supporting information as to the necessity of a special eddy-current testing (ECT) g shutdown before the end of the refueling cycle._ (The NRC staff-wil1~ evaluate that _ assessment ar.d. determine Lthe time of the next eddy-current examination, consistent with the other provisions of the license conditions.) 'In the absence of such an assessment, a special ECT shutdown shall take place before an additional 30 days of operation at power above 5%.
- 1f leakage exceeds the baseline.. leakage rate by more than 0.2 gpm.during the remainder of the Cycle 8 operation, the facility shall be shutdown and leak tested. Operation at leakage rates of up to 0.2 gpm above the-i i =
baseline leakage rate shall be acceptable'during the remainder of-Cycle 8 operation. After the 9R refueling outage, the-leakage limit and accompanying shutdown requirements revert to 0.1 gpm above the basel.ine l.
leakage _ rate.
Amendment No. J8T, 163 i
~
.