ML20009A793
| ML20009A793 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/02/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20009A794 | List: |
| References | |
| NUDOCS 8107140216 | |
| Download: ML20009A793 (6) | |
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UNITED STATES gy g
NUCLEAR REGULATORY COMMISSION a
waswiscrow, o. c. 20sss l
POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT Af1ENDMENT TO FACILITY OPERATING LICENSE.i Amendment No. 56 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 June 24, 1981, 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 r_egulations of the Commission; C.
There is reasonable assurance (i) that the activities authori:ed 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 Scecifi-cations as indicated in the attachment to this license amendment, and paragraph 3.3 of Facility Operating License No. DPR-59 is hereby amended to read as follows:
8107140216 810702 PDR ADOCK 05000333 P
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.. i (B) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56, are hereby incorporated in the license. The licensee shall operate the facilit/ in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A-
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, Chief Operating Reactors Branch #2 Division of Licensing AttacFeent:
Changes to the Technical Specifications Date of Issuance:
July 2,1981 b
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ATTACHMENT TO LICENSE AMENDMENT NO.56 FACILITY OPERATING LICENSE NO. OPR-59 DOCKET NO. 50-333 Revise Appendix A Technical Specifications as follows:
Delete Replace 141 141 142 142 142a 142a 4
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6 E. 22-
o 3.6 (cont d)
J AI'lli'P 4.6 (cont'd) 4.
Except as specified in 3.6.C.3 above, the teactor coolant water shall not exceed the following limits with steaming rat.es greater t han or eo ul to 100,000 lb/hr and during re wict shntdowns.
Conductivity
'> pmho/cm Chloride ion 0.5 ppm 5.
I f Speci fi cation 3.6.C cannot be met, the reactor shal1 lie placed 3n a cold condition within 24 hr.
D. Coolant Inakage D.
Coolant I,cakage 1.
Any time irradiated fuel is in Iteactor coolant leakage rate in~ide the primas-the reactor vessel and reactor containment shall be established once/ day coolant temperature is above utilizing the Equipment and Floor Drain 212"F, reactor coolant leakage Sump Monitoring Systems.
l into the primary contaisunent from unidentifted sources shall not exceed 5 gpm,
In adlition, the total reactor coolant system Icakage it.to the primary containment shall not excen1 25 gpm.
2.
The following reactcr coolant system leakage detect ion systems nhall he operable during reactor power operation:
a.
Drywell nomp monitoring systen (equip-ment drain sump monitoring or iloor drain sump monitoring),
b.
Drywell Contirnaous Atnosplvere lpa r t i cill a t e)
Itadioact ivi t y lioni tor ing syst em, a n< l c.
Drywell Continitous Atmosphere ( q tineoun)
Itadioact i vi t.y Moni tot i nq Synt.em.
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' 3.6 (cont'd)
JAFiiPI' 4.6 (cont'd)
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With only two of the leakage detection systems operable (3.6.D.2), operation may continue for up to 30 days provided grah samples of the.
drywell atmosr'.cre are obtained 3.
Drywell Continuous ~ Atmosphere Radioactivity Monitoring System and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when thc-required gaseoun instrumentation shall be funct-or particulate grw>nitoring system ionally tested and calibrated as is inoperable; othe pise, be specified in Table 4.6-2.
H in at least' hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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i Amendmont tio. 2,il 56 142 4
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T v-3.6 (cont'd)
JAl't31'p 4.6(cont'd) 5 J
E.
Safety and Safety /Felief Valves E.
Safety and Safety / Relief Valves During reactor power oper'ating 1.
At least one half of all -
1.
conditions and prior to startup safety / relief valves shall be bench from a cold condition,'or whenever checked or replaced with bench checked reactor coolant pressure is greater valves once each operating cycle. The than atmosphere and temperature sa fety/ relief valve settings greater than 212"F, shall be set as required in Specification the safety mode of all 2.2.B.
All valves shall be tested every safety / relief valves shall be two operating cycles.
operable, except as specified by Specification 3.6.I;.2.
The Automatic Depressurization System valves shall be operable as reqisired by Specification 3.5.D.
V Amendment tio. V), )g 56 142a e
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