ML20197C247
| ML20197C247 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/31/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Power Authority of the State of New York |
| Shared Package | |
| ML20197C252 | List: |
| References | |
| DPR-59-A-102 NUDOCS 8611060017 | |
| Download: ML20197C247 (6) | |
Text
. -.. _.. _
i g
UNITED STATES
[
g NUCLEAR REGULATORY COMMISSION Q
R WASHINGTON, D. C,20065 1
\\*****
I I
POWER AUTHORITY OF THE STATE OF NEW YORK s
DOCKET NO. 50-333 4
JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.102 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by the Power Authority of the State i
of New York (the licensee) dated October 9, 1984, complies with the standards and re as amended (the Act)quirements of the Atomic Energy Act of 1954, a
, and the Comission's rules and regulations set forth in 10 CFR Chapter I; 4
}
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the 4
Comission; C.
There is reasonable assurance (1) that the activities authorized i
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be j
conducted in compliance with the Commission's regulations; i
D.
The issuance of this amendment will not be inimical to the comon defense ard security or to the health and safety of the l
public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l' Accordingly, the license is amended by changes to the Technical 2.
Specifications as indicated in the attachment to this license amendment i
and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby l
amended to read as follows:
i l
l 8611060017 861031
(
fDR ADOCK 03000333 PDR
.,_,._..m._..
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.102, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b#
Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications l
Date of Issuance: 10-31-86
v--.-
.:.... :-.-.a,=.
a-7 i :1.
//
i ATTACHMENT TO LICENSE AMENDMENT NO. 102 FACILITY OPERATING LICENSE NO DPR-59 DOCKET NO. 50-333 Replabe the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Fates s
141 141a*
142
- Page added r
t' e
4 4
i
'I d
A l
i f
I i
4
?
j
-si I
\\
l' t.
~.
~
.lAPtiPP 3.6 (cont'd) 4.6 (cont'd) 4.
Except as specified in 3.6.C.3 above, the reactor coolant water shall not exceed the following limits with steaming rates greater than or equal to 100,000 lb/hr and during reactor shutdowns.
Conductivity 5 4mho/cm Chloride ion 0.5 ppm 5.
If Specification 3.6.C cannot be mot, the reactor shall be placed in a cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D.
Coolant Leakage 4.6.D Coolant Leakage 1.
Anytime irradiated fuel is in the reactor vessel and the reactor coolant Reactor coolant leakage rate inside the primary containment shall be j
temperature is above 212*P, the reactor coolant leakage into the primary con-monitored and recorded once every tainment~shall b,e limited to:
- 4. hours utilizing the primary Con-tainment Sump Monitoring System 5 gpm unidentified Icakage (equipment drain sump monitoring and a.
floor drain sump monitoring).
b.
2 gpm increase in unidentified leakage within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
(This limitation shall apply only after a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at oper-ating pressure.)
The total reactor coolant leakage c.
j into the primary containment shall not exceed 25 gpm.
2.
With any reactor coolant system leakago greater than any one of the limits speci-fled in 3.6.D.1.a or 3.6.D.l.c above, the leakage rate shall be reduced to within these limits Amendmont No. JM g 102 141
JAFNPP l
t
.q 3.6 (cont'd),
4.5 (cont'd) l t
within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the re$ctor shall be in at least the hot standby con-dition within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold condition within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
r 3.
If the increase in* unidentified leak-age as specified in 3.6.D.l.b is ex-coeded, the source of the leakage shall be identified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the reactor shall be in at least hot standby condition 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 condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.
The primary Containment Sump Monitoring Sydtem (Equipment Drain Sump Monitoring e
and Floor Drain Sump Monitoring) and the Primary Containment Atmosphere Mon-l itoring System (Gaseous and Particulate) shall be operable during reactor power operation.
b l
i b
i Amendment No.102 141a
JAFNPP 3.6 (cont'd) 4.6 (cont'd)
S..
With the Primary Containment Sump 3.
Drywell Continuous Atmosphere Monitoring System (Equipment Radioactivity Monitoring System Drain Sump Monitoring or instrumentation shall be functionally Floor Drain Sump Monitoring) tested and calibrated as specified inoperable, r~estore the in Table 4.6.2.
system 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 immediately initiate an orderly shutdown and he'in.at least hot standby condition 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 condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
6.
With the Primary Containment Atmosphere Radioactivity Mon-itoring System (gaseous) or the Primary Containment Atmosphere Radioactivity Monitoring System (particulate). inoperable, operation may continue for up to 30 days provided grab samples of the containment atmosphere are obtained 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 />.
Otherwise be 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 following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I l
1 Amendmant tio. g 102 142
~
--