ML20202H302
| ML20202H302 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/17/1986 |
| 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 | |
| ML20202H307 | List: |
| References | |
| DPR-50-A-115 NUDOCS 8604150220 | |
| Download: ML20202H302 (6) | |
Text
'o,,
UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
8 WASHINGTON, D. C. 20565
/
- .+
METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. ll5 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.
(thelicensees)datedAugust 20, 1985, 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; 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.
8604150220 860317' PDR ADOCK 05000299 P
l 2.
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:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.115, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment becomes effective 60 days after,its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
(
i F. Stolz, Director l o
ProjectDirectoratV#6 Division of PWR Licensing-B
Attachment:
1 Changes to the Technical Specifications Date of Issuance: March 17,1986 I
ATTACHMENT TO LICENSE AMENDMENT NO. 115 l
FACILITY OPERATING LICENSE NO. OPR-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.
Pages 3-57*
3-58 4-10
- 0verleaf page included for document completeness.
l i
1 -
3.12 REACTOR BUILDING POLAR CRANE Apolicability Applies to the use of the reactor building polar crane hoists over the steam generator co=partments and the fuel transfer canal.
Objective To identify those conditions for which the operation of the reactor t ailding polar crane hoists are restricted.
Specificatien 3.12.1 The reactor building polar crane hoists shall not be operated over the fuel transfer canal when any fuel assembly is being moved.
3.12.2 During the period when the reactor vessel head is re=cved and irradiated fuel is in the reactor building and fuel is not being moved, the reactor building polar crane hoist shall be operated over the fuel transfer canal enly where necessary and in accordance with approved operating procedures stating the purpose of such use.
3.12.3 During the period when the reactor coolant system is pressurized above 300 psig, and is above 200 F, and fuel is in the core, the reactor building polar crane hoists shall not be operated over the steam generator co=partments.
Bas es i
P.estriction of use of the reactor building polar crane hoists over the fuel transfer canal when the reactor vessel head is removed to permit those operations necessary for the fuel handling and core internals operations is to precluda i
the dropping of materials or equipment into the reactor vessel and possibly damaging the fuel to the extent that any escape of fission products would result.
Restriction of use of the reactor building polar crane hoists over the steam generator compartments during the time when steam could be formed from dropping a load on the steam generator or reactor ecolant piping resulting in rupture of the systes is required to protect against a loss-of-coolant accident.
j i
1 Amendment No. 115 3-57
3.13 SECONDARY COOLANT SYSTEM ACTIVITY Applicability Applies to the Ifmiting conditions for operation when reactor coolant system pressure is greater than 300 psig or Tavg is greater than 200*F.
Objective To limit the inventory of activity in the secondary system.
Specification 3.13.1 The specific activity of the secondary coolant system shall be 1 0.10 p Ci/ gram DOSE EQUIVALENT I-131.
3.13.2 With the specific activity of the secondary coolant system > 0.10p Cf/ gram DOSE EQUIVALENT I-131, be in at least H0T STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD Shut 00kN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Bases The limitations on secondary system specific activity ensure.that the resultant off-site radiation dose will be Ifmited to a small fraction of 10 CFR Part 100 limits it. the event of a steam line rupture. This dose includes the effects of a coincide.nt 1.0 GPM primary-to-secondary tube leak in the steam generator of the affected steam line.
I I
Amendment No.
Ils 3-58
i Y
TABLE 4.1-3 Cont'd.
S
'+
Item Check E
Frequency 4.
Spent Fuel Pool Water Sample Boron concentration D
Monthly and after each makeup 5.
Secondary Coolant System Activity Isotopic analysis for DOSE At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when g
EQUIVALENT I-131 concentration reactor coolant system pressure is greater than 300 psig or Tav
_R is greater than 200*F g
6.
Boric Acid Mix Tank or Reclaimed Boric Boron concentration Twice weekly ***
.o*
Acid Tank 3
7.
Deleted 8.
Deleted 9.
Deleted r
10.
Sodium Hydroxide Tank Concentration Quarterly and after each makeup II.
Deleted El12.
Deleted Until the specific activity of the primary coolant system is restored within its limits.
Sample to be taken after a minimum of 2 EFPD and 20 days of POWER OPERATION have elapsed since the reactor was last subscritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
Deleted.
"O The surveillance of either the Boric Acid Mix Tank or the Reclaimed Boric Acid Tank is not necessary when that respective tank is empty.