ML20045H300
| ML20045H300 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/12/1993 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML20045H301 | List: |
| References | |
| REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-OR, NPF-49-A-080 NUDOCS 9307200063 | |
| Download: ML20045H300 (5) | |
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UNITED STATES l'
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 ILORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 HILLSTONE NUCLEAR POWER STATION. UNIT N0 J AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 License No. NPF-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee) dated March 19, 1993, 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 Commission; 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 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.
930720o063 930712 PDR ADOCK 0500 3
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. 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 i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 80
, and the Environmental Protection 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 REGULATORT COMMISSION O
J n F. Stolz, Director ofctDirectorateI-4 sion of Reactor Projects - I/II O ice of Nuclear Reactor Regulation
Attachment:
1 Changes to the Technical l
Specifications q
Date of Issuance: July 12, 1993 l
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ATTACHMENT TO LICENSE AMENDMENT NO,80 FACILTIY OPERATlHG LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove J_qigr_t 3/4-4-38 3/4-4-38 3/4-4-39 3/4-4-39 D
F f
1 a
F REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 An Overpressure Protection System shall be OPERABLE with either a or b below:
a.
Two relief valves, as follows:
1.
Two power-operated relief valves (PORVs) with lift settings which do not exceed the limit established in Figure 3.4-4a or Figure 3.4-4b, as appropriate, or 2.
Two residual heat removal (RHR) suction relief valves each with a setpoint of 450 psig, or 3.
One PORV with lift settings within the limits specified in Figure 3.4-4a or Figure 3.4-4b, as appropriate and one RHR suction relief valve with a setpoint of 450 psig.
b.
The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 5.4 square inches.
APPLICABILIH: MODE 3 when the temperature of any RCS cold leg is less than or equal to 350*F and MODE 4; MODE 5, and MODE 6 when the head is on the reactor vessel.
ACTION:
a.
With one of two required relief valves inoperable in MODE 3 or 4, restore two relief valves to OPERABLE status within 7 days or depressurize and vent the RCS through at least a 5.4 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b.
With one of two required relief valves inoperable in MODE 5 OR 6, either (1) restore two relief valves 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 (2) complete depressurization and venting of the RCS through at least a 5.4 square inch vent within a total of 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
c.
With both of the required relief valves Lnoperable, complete depressurization and venting the RCS theough at least a 5.4 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
d.
With the RCS vented per ACTIONS a, b or c, verify the vent pathway at least once per 31 days when the pathway is provided by a valve (s), that is locked, sealed or otherwise secured in the open position; otherwise, verify the vent pathway every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
MILLSTONE - UNIT 3 3/4 4-38 Amendment No. JE, E7,80 0112
REACTOR CDOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEM LIMITING CONDITION FOR OPERATION ACTION (Continued) e.
In the event the PORVs, the RHR suction relief valves, or the RCS vent (s) are used to mitigate an RCS pressure transient, a Special Report shall be prepared and submitted to the Comission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances initiating the transient, the effect of the PORVs, the RHR suction relief valves, or RCS vent (s) on the transient, and any corrective action necessary to prevent recurrence.
f.
Entry into an OPERATIONAL MODE is permitted while subject to these ACTION requirements.
SURVEILLANCE RE0VIREMENTS 4.4.9.3.1 Each PORY shall be demonstrated OPERABLE by:
a.
Performance of an ANALOG CHANNEL OPERATIONAL TEST on the PORY actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORY is required OPERABLE and at least once per 31 days thereafter when the PORV is required OPERABLE; b.
Performance of a CHANNEL CALIBRATION on the PORV actuation channel at least once per 18 months; and Verifying the PORV isolation valve is open at least once per c.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the PORY is being used for overpressure protection.
4.4.9.3.2 Each RHR suction relief valve shall be demonstrated OPERABLE when the RHR suction relief valves are being used for cold overpressure protection as follows:
a.
For RHR suction relief valve 3RHS*RV8708A, by verifying at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that 3RHS*MV8701A and 3RHS*MV8701C are open; b.
For RHR suction relief valve 3RHS*RV87088, by verifying at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that 3RHS*MV8702B and 3RHS*MV8702C are open; and c.
Testing pursuant to Specification 4.0.5.
MILLSTONE - UNIT 3 3/4 4-39 Amendment No. 80, 0112
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