ML20099M257
| ML20099M257 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/28/1995 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20099M259 | List: |
| References | |
| NUDOCS 9601030274 | |
| Download: ML20099M257 (6) | |
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-t UNITED STATES j
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2006Hloci
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NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.124 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 July 14, 1995, complier, 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 (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.
9601030274 951229 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 Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.124
, 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 90 days of issuance.
FOR THE NUCLEAR REGULATORY CONilSSION Phillip F.
Kee, Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 28, 1995
1 ATTACHMENT TO LICENSE AMENDMENT NO.124 FACILITY OPERATING LICENSE NO. NPF-49 4
4 DOCKET NO. 50-423 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 3/4 5-4 3/4 5-4 3/4 5-5 3/4 5-5 1
3/4 5-6 3/4 5-6 i
i h
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1
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves a.
are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position 3SIH*MV8806 RWST Supply to SI Pumps OPEN 3SIH*MV8802A SI Pump A to Hot Leg Injection CLOSED 3SIH*MV8802B SI Pump B to Hot Leg Injection CLOSED 3SIH*MV8835 SI Cold Leg Master Isolation OPEN 3SIH*MV8813 SI Pump Master Miniflow OPEN Isolation 3SIL*MV8840 RHR to Hot Leg Injection CLOSED 3SIL*MV8809A RHR Pump A to Cold Leg OPEN Injection 3SIL*MV8809B RHR Pump B to Cold Leg OPEN I
Injection b.
At least once per 31 days by:
1)
Verifying that the ECCS piping, except for the RSS pump, heat exchanger and associated piping, is full of water by venting the ECCS pump casings and accessible discharge piping high points, and 2)
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
By a visual inspection which verifies that no loose debris (rags, c.
trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions. This visual inspection shall be performed:
1)
For all accessible areas of the containment prior to establish-ing CONTAINMENT INTEGRITY, and 2)
At least once daily of the areas affected (during each day) within containment by containment entry and during the final entry when CONTAINMENT INTEGRITY is established.
d.
At least once each REFUELING INTERVAL by:
l 1)
Verifying automatic interlock action of the RHR System from the Reactor Coolant System by ensuring that with a simulated or actual Reactor Coolant System pressure signal greater than or equal to 390 psia the interlocks prevent the valves from being opened.
MILLSTONE - UNIT 3 3/4 5-4 Amendment No. JP, U, #7.124 was
l EMERGENCY CORE C0OLING SYSTEMS l
SURVEILLANCE REQUIRENENTS (Continued) 2)
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or abnormal corrosion.
e.
At least once each REFUELING INTERVAL by:
'l 1)
Verifying that each automatic valve in the flow path actuates to its correct position on a Safety Injection actuation test signal, and 2)
Verifying that each of the following pumps start automatically upon receipt of a Safety Injection actuation test signal:
a)
Centrifugal charging pump, b)
Safety Injection pump, and c)
RHR pump.
3)
Verifying that the Residual Heat Removal pumps stop automatically upon receipt of a Low-Low RWST Level test signal.
f.
By verifying that each of the following pumps develops the indicated differential pressure on recirculation flow when tested pursuant to Specification 4.0.5:
1)
Centrifugal charging pump 2 2411 psid, 2)
Safety Injection pump 1 1348 psid, 3)
RHR pump 1 165 psid, and 4)
Containment recirculation pump 2 130 psid.
g.
By verifying the correct position of each electrical and/or mechanical position stop for the following ECCS throttle valves:
1)
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE, and 2)
At least once each REFUELING INTERVAL.
l ECCS Throttle Valves Valve Number Valve Number 3SIH*V6 3SIH*V25 3SIH*V7 3SIH*V27 NILLSTONE - UNIT 3 3/4 5-5 Amendment No. JP,124 was
D1ERGENCY CORE COOLING SYSTENS SURVEILLANCE REQUIRENENTS (Continued)
ECCS Throttle Valves Valve Number Valve Number 3SIH*V8 3SIH*V107 3SIH*V9 3SIH*V108 3SIH*V21 3SIH*V109 3SIH*V23 3SIH*Vlll h.
By performing a
flow balance test following completion subsystem l of modifications to the ECCS subsystems that alter the flow characteristics and verifying that:
1)
For centrifugal charging pump lines, with a single pump running:
a)
The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 339 gpm, and b)
The total pump flow rate is less than or equal to 560 gpm.
2)
For Safety Injection pump lines, with a single pump running:
a)
The sum of the injection line flow rates, excluding the highest flow rate, is greater than or equal to 442.5 gpm, and b)
The total pump flow rate is less than or equal to 670 gpm for the A pump and 650 gpm for the B pump.
3)
For RHR pump lines, with a single pump running, the sum of the injection line flow rates is greater than or equal to 3976 gpm.
l i
NILLSTONE - UNIT 3 3/4 5-6 Amendment No. pp,124 mos