ML20198R014
| ML20198R014 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/28/1998 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198R018 | List: |
| References | |
| NUDOCS 9901080063 | |
| Download: ML20198R014 (8) | |
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i UNITED STATES
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,j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 i
POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT 4
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 249 License No. DPR-59
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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 July 6,1998, 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i
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, cod (ii) that such activities will be conducted in compliance with the Commission's
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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 i
been saE3fied.
l 2.
Accordingly, the license is amended by changes to the Technical Specifications l
as indicated in the attachment to this lice ue amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:
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9901080063 981228 PDR ADOCK 05000333 P
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(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 24 9, and the Environmental Protection Plan contained in Appendix B are incorporated into Facility Lice;1se No. DPR-59. PASNY shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
2.
This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
S. Singh Bajwa, Director i
Project Directorate I-1 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
December 28, 1998 l
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 249 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50 333 Revise Appendix B as follows:
Remove Paoes insert Paaes 29 29 37 37 37a 1
40 40 42.
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JAFNPP 4
LIMITINC v0NDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i
. b.
Except as specified in 1. and 2. below, both SJAE b.
Operation of the SJAE radioactive offgas monitors shall
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system radiation monitors shall be operable during be verified by performing instrument surveillance as reactor power operation. The trip time delay setting for specified on Table 3.10-2.
closure of the SJAE isolation valve shall not exceed 15 i
m n.
1.
A channel may be placed in an inoperable status for l
up to six hours during periods of required surveillance without placing the Trip System in the tripped condition provided the other OPERABLE channel is monitoring that Trip Function.
Otherwise, in the event that one of the two SJAE radiation monitors is made or found to be inoperable, continued reactor power operation is pe.missible provided that the inoperable monitor is j
tripped.
t 2.
Upon the loss'of both SJAE system radiation monitors, either temporarily monitor radiation levels at the SJAE or initiate an orderly shutdown and have the main steam isolation valves closed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
t Amendment No. -93, 249 29
- JAFNPP-Table 3.10-1'
' i' RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE SYSTEMS Minimum No.
cf Operable in;trument Total Number of '
l Channels per Instrument Channels -
l Trip System Trip Function Trip Level Setting Provided by Design Action 1(a)
Refuel Area Exhaust Monitor (b) 2 (c) or (d) 1(a)
Reactor Building Area Exhaust Monitors (b)
'2
_ d)
(
(j) -
SJAE Radiation Monitors
< 500,000 Ci/sec 2
(e) i 1(a)
Turbine Building Exhaust Monitors (b) 2 (f) 1(a)
Radwaste Building Exhaust Monitors (b) 2 (f)
(k)
Main Control Room Ventilation s4 x 10 cpm"-
1-(g) 8
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(h)
Mechanical Vacuum Pump Isolation s3 x Normal Full 4
(h)
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Power Background NOTES FOR TABLE 3.10-1 (s)
A channel may be placed in an inoperaole status for up to six hours during periods of required surveillance without placing the Trip System in the tripped condition provided the other OPERABLE channel is monitoring that Trip t-unction, that is, trip capability is v
maintained.
An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the indicated action shall be taken.
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r (b) Trip level setting is in accordance with the methods and procedures of the ODCM.
(c)
Cease operation of the refueling equipment.
(d) Isolate secondary containment and start the SBGTS.
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i' (s). Bring the SJAE release rate below the trip level within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or isolate either the SJAE or all main steam lines within the next 12_
i hours.
t Amendment No. 93, 127, 203, 211, 249 h
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4.
JAFNPP Table 3.10-1 RADIATION MONITORING SYSTEMS.THAT INITIATE AND/OR ISOLATE SYSTEMS NOTES FOR TABLE 3.10-1 (cont'd.)
(f)
Refer to Appendix B LCO 3.1.c and LCO 3.1.d.
(g) Control room isolation is manually initiated.
(h)
Uses same sensors as primary containment isolation on high main steam line radiation. Refer to Appendix A Table 3.2-1 for minimum number of operable instrument channels and action required.
7 (i)
Conversion factor is 8.15 x 10 cpm - 1pCi/cc.
(j)
See RETS LCO 3.5.b.1 and 3.5.b.2.
(k)
A channel may be placed in an inoperable status for up to six hours during periods of required surveillance without placing the Trip Function in the tripped condition, or the indicated action shall be taken.
t Amendment No. 00,127,200,211,249 37a 4
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BASES 1
3.0 GASEOUS EFFLUENTS 3.1 GASEOUS EFFLUENT MONITORS The radioactive gaseous effluent instrumentation is provided to monitor and control the releases of radioactive materials in gaseous effluents during planned or unplanned releases. The alarm / trip set points for these instruments shall be calculated in accordance with methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR 20.
The operability and use of this instrumentation is consistent with the requirements of 10 CFR 50, Appendix A, General Design Criteria 60,63 and 64.
Refer to Appendix A Technical Specification Bases 4.2 for references pertaining to surveilbnce and allowable outage times for selected monitors listed on RETS Table 3.10-1 and Table 3.10-2.
3.3 GASEOUS DOSE RATES This specification is provided to ensure that the dore at or beyond the site boundary from gaseous effluents will be within the annual dose limits of 10 CFR 20. The annual dose limits are the doses associated with the concentrations of 10 CFR 20, Appendix B, Table 11, Column 1. These limits provide reasonable assurance that radioactive material discharges in gaseous eff'uents will not result in the exposure of a member of the public to annual average concentrations exceeding the limits specified in 10 CFR 20, Appendix B, Table 11 (10 CFR 20.106[b]). The specified limits restrict, at all times, corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to s500 mrem / year to the total body or to s3000 mrem / year to the skin.
These limits also restrict the corresponding thyroid dose rate above background to a child via the inhalation pat 9ay to s1500 mrem / year.
3.3 AIR DOSE. NOBLE GASES This specification is provided to assure that the requirements of 10 CFR 50, Appendix I, Section ll.B, III.A and IV.A are mat. The Limiting Conditions for Operation are the guides set forth in Appendix 1, Section ll.B. The specification provides the required operating flexibility and, at the same time, implements the guides set forth in Appendix 1,Section IV.A., to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable."
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i 3.4 DOSE DUE TO IODINE-131. IODINE-133. TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM L
The specification is provided to assure that the requirements of 10 CFR 50, Appendix 1, i
Section ll.C, Ill.A and IV.A are rret. The Limiting Conditions for Operation are the guides set forth in Appendix 1, Section li.C. The specifications provide the required operating flexibility and, at the same time, implement the guides set forth in Appendix 1, Section j
IV.A, to assure that the releases of radioactive materials in gaseous effluents will be kept
- as low as is reasonably achievable."
Amendment No. 00,211,24 9 40
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l BASES l
1 3.7 OFFGAS TREATMENT SYdTEM EXPLOSIVE GAS MIXTURE INSTRUMENTATION This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in portions of the offgas treatment system not designed to withstand a hydrogen explosion is maintained below the lower explosive limit of hydrogen. Operation i
l of the offgas recombiner system ensures that the concentration of hydrogen in the offgas charcoal filters remains below combustible levels.
Thus it provides assurance that the releases of radioactive materials wiil be controlled in conformance with the requirements of 10 CFR 50, Appendix A, General Design Criterion
- 60. The low steam flow trip point is based on 92% of design steam flow and raroutes the offgas to prevent overheating or ignition of the recombiner catalyst. The high steam flow trip point isolates the recombiner on excess steam flow that may be associated with a pipe break downstream of the recombiner.
3.8 STANDBY GAS TREATMENT SYSTEM (SBGTS)
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 monitor or a downscale trip on both monitors in a pair to cause the desired action.
Trip settings for the monitors in the refueling area ventilation exhaust ducts are based upon initiating normal ventilation isolation and SBGTS operation so that most of the 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 air ejector offgas monitors are connected in a two out of two logic arrangement. Based on l
experience with indruments of similar design, a testing interval of once every three months has been found adequate.
l 3.9 MECHANICAL VACUUM PUMP lOLATION 3
3.10 MAIN CONTROL ROOM VENTILATION RADIATION MONITOR l
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Amendment No. 00,107, ;;1, 24 9 42
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