ML20058L929
| ML20058L929 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/09/1993 |
| From: | Menning T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058L932 | List: |
| References | |
| NUDOCS 9312200070 | |
| Download: ML20058L929 (5) | |
Text
.
4p0 **%
,,4 l*,
UNITED STATES f,, IZL ^ j NUCLEAR REGULATORY COMMISSION
^
f WA6HINGToN, D.C. 205t&0001
%,...../
P_0WER AUTHORITY OF THE STATE OF NEW Y_0E DQ(_KET NO. 50-333 1AMES A. FITZf6 TRICK NUCLEAR POWER PLANI AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 200 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated September 25, 1992, 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 (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) tnet 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.
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-59 is hereby amended to read as follows:
9372200070 931209 PDR ADOCK 05000333-P PDR
f
. (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 200, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
~~&Lla ep Robert A. Capra, Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 9, 1993 8
P j
i
8TTACyMENT TO LICENSE 'APENDMENT NO. 200 FACILITY OPERATING LICENSE NO. OPR-59 DOCKET NO. 50-333 t
Revise Appendix A as follows:
Remove Paaes Insert Paoes 151 151 162a 162a i
e f
I t
?
I i
r l
l
!~
I i
l l
JAFNPP 3.6 and 4.6 BASES (cont'd) leakage were also considered in establishing the limits. The The capacity of the drywell sump pumps is 100 gpm, and the behavior of cracks in piping systems has been experimentally capacity of the daywell equipment drain tank pumps is also and analytically investigated as part of the USAEC-sponsored 100 gpm. Removal of 50 gpm from either of these' sumps can Reactor Primary Coolant System Rupture Study (the Pipe be accomplished with considerable margin.
Rupture Study). Work utilizing the data obtained in this study indicates that leakage from a crack can be detected before the The performance of the Reactor Coolant Leakage Detection crack grows to a dangerous or critical size by mechanically or System will be evaluated during the first 5 years of plant thermally induced cyclic loading, or stress corrosion cracking operation, and the conclusions of this evaluation will be or some other mechanism characterized by gradual crack reported to the NRC.
growth. This evider;ce suggests that for leakage somewhat greater than the limit specified for unidentified leakage, the it is estimated that the main stearv, line tunnel leakage probability is small that imperfections or cracks associated detectors are capable of detecting a leak on the order of 3,500 with such leakage would grow rapidly. However, the Ib/hr. The system performance will be evaluated during the establishment of allowable unidentified leakage greater than first 5 years of plant operation, and the conclusions of the that given in 3.6.D on the basis of the data presently available evaluation will be reported to the NRC.
would be premature because of uncertainties associated with the data. For leakage of the order of 5 gpm as specified in The reactor coolant leakage detection systems consist of the 3.6.D. the experimental and analytical data suggest a drywell sump monitoring system and the drywell continuous reasonable margin of safety such that leakage of this atmosphere monitoring system. The drywell continuous magnitude nould not result from a crack approaching the atmospher' monitoring system utilizes a two-channel monitor critical size for rapid propagation. Leakage less than the to provide information on particulate and noble gas activities in magnitude specified can be detected reasonably in a matter of the drywe!! atmosphere. Two independent and redundant a few houis utilizing the available leakage detection schemes, systems are provided to perform this function. This system and if the origin cannot be determined in a reasonably short supplements the drywell sump monitoring system in detecting time, the Plant should be shut down to allow further abnormal leakage that could occur from the reactor coolant investigation and corrective action.
system. In the event that the drywell continuous atmosphere monitoring system is inoperable, grab sample will be taken on a periodic basis to monitor drywell activity.
Amendment No. 28,190, 200 151
JAFNPP TABLE 4.6-2 Minimum Test and Calibration Freauency for Drywell Continuous Atmosobere Radioactivity Monitorina System i
inst. Channel Inst. Functional Test Calibration Sensor Check 1.
Air Particle Analyzer None Onco / 3 mos.
once / day 2.
Gaseous Activity Analyzer None Once / 3 mos.
Once / day I
Amendment No.
200
.