ML20005E781
| ML20005E781 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/02/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005E782 | List: |
| References | |
| NUDOCS 9001110054 | |
| Download: ML20005E781 (5) | |
Text
__
r it-r ' '
4,,,
h
'o 7
.E,
g UNITED STATES NUCLEAR REGULATORY COMMISSION n
WASHINGT ON, D. C, 20555 j
- 5 E
' 3, j
POWER AUTHORITY OF THE STATE OF NEW YORK 1
DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE.
ti; Amendment No.149 License No. DPR-59.
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated May 31, 1989 and amplified by letter dated July 7,1989, 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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical' to the comon defense and security or to the health and safety of the public; and l-L E.
The issuance of thi:; amendment is in accordance with 10 CFR Part 1:
51.of the Comission'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 L
No. OPR-59 is hereby amended to read as follows:
l l
l l
9001110004 900102 l
PDR ADOCK 05000333 p
'I
j-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amencment No.149, 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 NbCLEAR REGULATORY COMMISSION R A f ce.C W Robert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the.Technicel Specifications Date of issuance: January 2, 1990
y :. >
0'-
ATTACHMENT TO LICENSE AMENDMENT NO.149' I
FACILITY OPERATING LICEliSE NO. OPR-59 1
DOCKET NO. 50-333 :
.1 Revise Appendix A as follows:
..\\
Remove Pages
[risertPages 113 113 125 125
,.l i
i k
1 e
7__
% 'j ;
e:
g.
2 JAFNPP
'3.5 (cont'd) 4.5-(cont'd)
I b.
Flcw Rate Test -
Once/3 Months Core spray pumps shall deliver at least 4,625 gpm against a system-head correspond-ing to a. reactor vessel pressure greater than or equal to 113 psi above primary containment.
pressure.
c.
Pump Operability Once/ month d.
Motor Operated Once/ month Valve e.
Core Spray Header dip Instrumenta-tion Check Once/ day Calibrate Once/3 months i
Test Once/3 months I
i f.
Logic System Once/each Functional operating Test cycle g.
Testable Check Tested for operability Valves any time the reactor is in the cold condition exceeding 46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br />, if operability tests have not beea performed during the preceding 31 days.
l Amendment No. *O, 149 l
113
- 4;
/
JAFNPP 3.5 BASES A.
Core Spray System and Low Pressure Coolant of operable subsystems to assure the availability iniection (LPCI) Mode of the RHR System of the minimum cooling systems.. No single failure of ECCS equipment occurring during a loss-of-This specification assures that adequate emergency coolant accident under these limiting conditions cooling capability is available whenever irradi-of operation'will result in inadequate cooling of ated fuel is in the reactor vessel, the reactor core.
The loss-of-coolant analysis if referenced and Core spray distribution has been shown,-in full described in General Electric Topical Report scale tests of systems similar in' design to that NEDE-24011-P-A.
of the FitzPatrick Plant, to exceed the minimum requirements by at least 25 percent.
In addition, cooling effectiveness has been demonstrated at less than half the rated flow in simulated fuel assemblies with heater rods to duplicate the decay heat characteristics of irradiated fuel.
The accident analysis is additionally.conserva-tive in that no credit is taken for spray coolant entering the reactor before the internal pressure has fallen to 113 psi above primary containment The limiting conditions of operation-in Speci-pressure.
fications 3.5.A.1 through 3.5.A.6 specify the combinations The LPCI mode of the RHR System is designed to provide emergency cooling to the core by flooding in the event of a loss-of-coolant accident. This system is completely independent of the Core Spray System; however, it does function in combination with the Core Spray System to prevent excessive fuel clad temperature. The LPCI mode of Amendment No. g, 149 125 n-a'"
r