ML20044B788
| ML20044B788 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/23/1993 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044B789 | List: |
| References | |
| NUDOCS 9303040263 | |
| Download: ML20044B788 (10) | |
Text
s a ucuq'o UNITED STATES
! " ' A ' 'E NUCLEAR REGULATORY COMMISSION n
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W ASHINGTON, D. C. 20555
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POWER AUTHORITY OF THE STATE OF NEW YORK D_0CKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE A:aendment No.187 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 August 10, 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) 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.
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:
i 9303040263 930223 PDR ADOCK 05000333 P
2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.187, 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 7 a a. Ce Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
i Changes to the Technical Specifications Date of Issuance: February 23, 1993 4
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I ATTACHMENT TO LICENSE AMENDMENT NO.187 l
t FACILITY OPERATING LICENSE NO. DPR-59 f
DOCKET NO. 50-333 i
Revise Appendix B as follows:
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V UMITING CONDITIONS FOR OPERATION SURVEILI.ANCE REQUIREMENTS treatment system under the following conditions:
1.
An instrumerd check shall be performed daily when the 1.
The offgas dilution steam flow instrumentation shall alarm 9"*'
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and automatically isolate the offgas recombiner system at 2.
An instrument channel functional test shall be performed low flow less than or equal to 6300 pounds per hour or once per operating cycle.
high flow greater than or equal to 7900 pounds per hour.
3.
An instrument channel callbration shall be performed once 2.
The offgas recombiner inlet temperature sensor shall alarm per operating cycle.
and automatically isolate the offges recombiner system at a temperature of not less than 125'C.
3.
The offges recombiner outlet temperature shall alarm and automatically isolate the offgas treatment system at a temperature of notless than 150*C.
c.
In lieu of continuous hydrogen or oxygen monitoring, the c.
With condenser offgas treatment system recombiner in service, condenser offges treatment system recombiner effluent shall be in lieu of continuous hydrogen or oxygen monitoring, the analyzed to verify that it contains less_than or equel to 4%
hydrogen content shall be verllied weeldy to be less than or hydrogen by volume, equel to 4 % by volume.
1 in the event that the hydrogen content cannot be verifled, l
d.
With the requirements of the above specilications not satisfied, operation of this system may continue for up to 14 days.
restore the recombiner system to within operatin0 speellications or suspend use of the charcoal treatment system within 48
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Amendment No. lis, &lF, 187 as w.--
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BASES i
1 IV.A, to assure that the releases of radioactive materials in gaseous effluents will be kept
- as low as is reasonably achievable."
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3.5 MAIN CONDENSER STEAM JET AIR EJECTOR (SJAE)
This specification is provided to assure that remedial action is taken to limit the noble gas release rate at the SJAE. The requirement provides reasonable assurance that the amount of noble gas that must be treated and/or released is controlled to a level that prevents exceeding the limits specified in 10 CFR 20, Apperdx B, Table 11.
Two air ejector offgas monitors are provided and when their trip point is reached, cause an isolation of the air ejector offgas line. Isolation is initiated when both instruments reach their high trip point or one has an upscale trip and the other a downscale trip. There is a 15 minute delay before the air ejector offgas isolation valve is closed. This delay is accounted for by the 30 minute holdup time of the offgas before it is released to the stack.
Both instruments are required for trip but the instruments are so designed that any instrument failure gives a downscale trip.
3.6 OFFGAS TREATMENT SYSTEM This spec!fication is provided to ensure that the system will be ava!!able for use when required to reduce projected doses due to gaseous releases. This specification assures that the requirements of 10 CFR 50.36a,10 CFR 50, Appendix A, Genera! Design Criterion 60, and design objective in 10 CFR 50, Appendix 1, Section 11.D are met. The specified limits goveming the use of appropriate portions of the systems are specified as a suitable fraction of the guide values set forth in 10 CFR 50, Apperg!!x 1, Sections 11.B and II.C, for gaseous effluerra.
The requirement for offgas treatment system operabil!!y provides assurance that the release of radioactive materials in gaseous waste wl!! be kept 'as low as is reasonab!y achievable." Operabl!!ty of the system is based upon start-up d the second turbine drfven feedwater pump. This is due to the fact that excess air in-leakages in the main condenser as a resutt of operating only one turbine drtven feedwater pump will exceed offgas treatment system lim!tations and consequently render the system inoperable. Start up of the second turbine driven feedwater pump will decrease air in-leakages and assure offgas treatment system ava!! ability.
3.7 OFFGAS TREATMENT SYSTEM EXPLOSIVE GAS MIXTURE INSTRUMENTATION This spectfication is provided to ensure thdt the concentration of potentia!!y explosh>e gas mixtures contained in portions of the offgas treatment system not designed to vathstand a hydrogen explosion is maintained below the lower explosive limit of tyydrogen. Operation of the offgas recombiner system ensures that the concentration of hydrogen in the offgas charcoa! fitters remains below combustible levels.
Amendment No. D$,187 41
BASES t
Thus it provides assurance that the releases of radioactive rnaterials will be controlled in conformance with the requirements of 10 CFR 50, Appendix A, General Design Criterion I
- 60. The low steam flow trip point is based on 92% of design steam flow and reroutes the
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offgas to prevent overheating or ignition of the recombiner catalyst. The high steam flow i
trip point isolates the recombiner on excess steam flow that may be associated with a pipe break downstream of the recombiner.
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3E STANDBY GAS TREATMENT SYSTEM (SBGTS) f Four radiation monitors are provided which initiate isolation of the reactor building and operating of the SBGTS. The monitors are located as follows: two in the reactor building ventilation exhaust duct and two in refuel floor ventilation exhaust duct. Each pair is considered a separate system. The trip logic consists of any upscale trip on a single i
monitor or a downscale trip on both monitors in a pair to cause the desired action.
Trip settings for the monitors in the refvaling area ventilation exhaust ducts are based upon i
in!!iating normal ventilation isolation and SBGTS operation so that most of %e activity released during the refueling accident is processed by the SBGTS.
The radiation monitors in the refueling area ventilation duct which initiate building isolation and standby gas treatment operation are arranged in a one out of two logic system. The bases given in Appendix A Bases 4.2 for the rod blocks apply here also and were used to arrive at the functional testing frequency. The air ejector offgas monitors are ceri,6cted in a two out of two logic arrangement. Based on experience with instruTnonts of similar design, a testing interval of once every three months has been found adequate.
3.9 MECHANICALVACUUM PUMP ISOLATION 3.10 MAIN CONTROL ROOM VENTILATION RAD!ATION MONITOR
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Amendment No.fd, 187 42