ML20078M741
| ML20078M741 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/09/1995 |
| From: | Mckee P Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078M746 | List: |
| References | |
| NUDOCS 9502140299 | |
| Download: ML20078M741 (4) | |
Text
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94 UNITED STATES 4
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON. D.C. 6 o%
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NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 P
AMENDMENT TO FACILITY OPERATING LICENSE R
Amendment No.103 s
License No. NPF-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated August 16, 1994, as supplemented January 10, 1995, complies with the standards and requirements of the Ato:nic Energy Act of 1954, as amended (the Act), and the Comission'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 (1) 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 comon defense and security or to the health and safety of the public; and j
E.
The issuance of this amendment is in accordance with 10 CFR Part i
51 of the Comission's regulations and all applicable requirements have been satisfied.
9502140299 950209 PDR ADOCK 05000423 p
. 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. NPF-49 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised l
through Amendment No.103
, and the Environmental Protection l
Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g
Phillip F.
cKee, Director Project Directorate I-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 9, 1995
)
1
ATTACHMENT TO LICENSE AMENDMENT NO.103 FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by amendment number ar.d contain vertical lines indicating the areas of change.
Remove Insert 3/4 5-3 3/4 5-3 n
i i
ENERRENCY COM C00 LIM SYSTDtS 3/4.5.1 ECCS SUBSYSTDIS - T_ GREATER thall OR EQUAL TO 350*F LINITIIIB COISITICII FOR OPERATICII 3.5.2 Two independent Emergency Core Cooling System (ECCS) subsystems shall be OPERA 8LE with each subsystem comprised of:
a.
One OPERABLE centrifugal charging pump, b.
One OPERABLE Safety Injection pump, c.
One.0PERABLE RHR heat exchanger,*
d.
e.
One OPERABLE containment recirculation heat exchanger, f.
One OPERABLE containment recirculation pump, and g.
An OPERABLE flow path capable of taking suction from the refueling water storage tank on a Safety Injection signal and capable of automat-ically stopping the RHR pump and being manually realigned to transfer suction to the containment sump during the recirculation phase of operation.
APPLICABILITY: MODES 1, 2, and 3.
ACTION:
a.
With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
- or be in at least HOT STANDBY
[
within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOW within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ-ing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor l
for each affected Safety Injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
l
- The allowable outage time for each RHR pump /RHR heat exchanger may be extended to 3
120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> for the purpose of pump modification to change mechanical seal and other related modifications.
This exception may only be used one time per RHR pump /RHR heat exchanger and is not valid after April 30, 1995.
NILLSTONE - LNIIT 3 3/4 5-3 Amendment No.103 un
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