ML20044G035
| ML20044G035 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/18/1993 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044G036 | List: |
| References | |
| GL-89-14, NUDOCS 9306010348 | |
| Download: ML20044G035 (7) | |
Text
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,p* Guq I*t UNITED STATES y.
!.., W j
NUCLEAR REGULATORY COMMISSION j
f WASHINGTON, D.C. 20S!&0001 r
%f.n
,/
POWER AUTHORITY OF THE STATE OF NEW YORK i
DOCKET N0. 50-333 i
dAJES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.188 License No. DPR-59 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Power Authority of the State of New York (the licensee) dated February 22, 1993, complies with the 4
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 9306010348 930518 PDR ADOCK 05000333 P
l l
v.
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as 4
revised through Amendment No.188, 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.
)
l FOR THE NUCLEAR REGULATORY COMMISSION l
7 M a.[ M Robert A. Capra, Director Project Directorate I-1 l
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Chnges to the Technical Specifications Date of Issuance:
May 18, 1993 l
l 1
p-ATTACHMENT TO LICENSE AMENDMENT NO.188 FACILITY OPERATING LICENSE NO DPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:
Remove Pages Insert Paces 5
5 6
6 30 30 30e 30e
+
9 Y
k i
4
.i t
i e
i I
m JAFNPP 1.0 (cont'd) opened to perform necessary operational activities.
R.
Safety Limits - The safety limits are hmits within which the reasonable maintenance of the fuel cladding integrity 2.
At least one door in each airlock is closed and and the reactor coolant system integrity are assured.
sealed.
Violation of such a limit is cause for unit shutdown and review by the Atomic Energy Commission before 3.
All automatic containtnent isolation valves are resumption of unit operation. Operation beyond such a operable or de-activated in the isolated position, limit may not in itself result in serious consequences but it indicates an operational deficiency subject to regulatory 4.
All blind flanges and manways are closod.
review.
N.
Bated Power - Rated power refers to operation at a reactor S.
Secondary Containment inteority - Secondary containment power of 2.436 MWt. This is also termed 100 percent integrity means that the reactor building is intact and the power snd is the maximum power level authorized by the following conditions are met:
operating license. Rated steam flow, rated coolant flow, rated nuctear system pressure, refer to the values of these 1.
At least one door in each access opening is closed.
para netet s when the reactor is at rated power.
2.
The Standby Gas Treatment System is operable.
O.
Reactor Power Operation - Reactor power operation is any operation with the Mode Switch in the Startup/ Hot 3.
All automatic ventilation system isolation valves are Standby or Run position with the reactor critical and above operable or secured in the isolated position.
1 percent rated thermal power.
T.
Deleted l
P.
Reactor Vessel Pressure - Unless otherwise indir ated,
' reactor vessel pressures listed in the Technical Specifications are those measured by the reactor vessel steam space sensor.
Q.
Refuelina Outaae - Refueling outage is the period of time between the shutdown of the unit prior to refueling and the startup of the Plant subsequent to that refueling, f.If4,188 Amendment No.
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JAINPP 3.
LEninna Conditions for Operation 4.
Surveillance Reauirements 3
3.0 fteneral 4.0 General Acolicability:
Aeolicability:
Applies to the general LCO requirereents of Section 3.
Applies to the general surveillance requirements of Section 4.
Obiective:
Obiective:
To specif y the general requirements applicable to each Limiting To specify the general requirements applicable to each Condition for Operation listed in Section 3.
surveillance requirement in Section 4.
Soecification:
Specification:
A.
Limiting Conditions for Operation and ACTION A.
Surveillance Requirements shall be applicable during the requirements shall be applicable during the OPERATIONAL OPERATIONAL CONDITIONS (modes) specified for CONDITIONS (modes) specified for each specification.
individual Limiting Condition for Operation unless otherwise stated in the individual Surveillance 3
Adherence to the requirements of the Limiting Condition Requirements.
for Operation and associated ACTION within the specified time interval shall constitute compliance with the B.
Each Surveillance Requirement shall be performed within specification. In the event the Limiting Condition for the specified surveillance interval with a maximum Operation is restored prior to expiration of the specified allowable extension not to excecci 25 percent of the time interval, completion of the ACTION statement is not specified surveillance interval.
required.
C.
In the event a Limiting Condition for Operation and/or C.
Performance of a Surveillance Requirement within the associated ACTION requirements cannot be satisfied specified time interval shall constitute cornpliance with because of circumstances in excess of those addressed in OPERABILITY requirements for a Limiting Condition for the specification, the unit shall be placed in COLD Operation and associated ACTION stetements unless SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless otherwise required by the specification. Surveillance corrective measures are completed that permit operation requirements do not have to be performed on inoperable under the permissible ACTION or until the reactor is placed equipment.
in an OPERATIONAL CONDITION (mode) in which the specification is not applicable. Exceptions to these requirements shall be stated m the individual specifications.
f3, 188 Amendment No.
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