ML20199F683
| ML20199F683 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/23/1998 |
| From: | Mckee P NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199F688 | List: |
| References | |
| NUDOCS 9802040079 | |
| Download: ML20199F683 (4) | |
Text
_ _ _ _.
@ itouq 9e
+4 UNITED STATE 8 g
,j NUCLEAR REGULATORY COMMISSION
't W ASHINGTON, D.C. 3084H001 49.....
NORTHEAST NUCLEAR ENERGY COMPANY. ET At.
DOCKET NO. 50-423 MILLSTONE NUCLEAR POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
156 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 November 14, 1997, 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 tho 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 appli<. ole requirements have been satisfied.
9002040079 900123 PDR ADOCK 050004 3
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 30ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 156, 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 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 7
I Phillip F. McKee Deputy Director for Licensing Special Projects Office Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 23, 1998
ATTACHMENT TO LICENSL' #4ENDMENT NO.156 FAtillTY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Appendix A, Technical Specifications, with the attached page. The revised page is ideitified by amendment number and contains a vertical line indicating the area of change.
Remove Insert 3/4 5-4 3/4 5-4 i
EMERRENCY CORE C0OLING SYSTEMS
$URVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
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 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 351,'4*MV8813 SI Pump Master Miniflow OPEN Isolation 3SIL*HV8840 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 Injection b.
At least once per 31 days by:
1)
Verifying that the ECCS piping, except for the operating centrifugal charging pump (s) and associated piping, the RSS pump, the RSS heat exchanger and associated piping, is full of water, and 2)
Verifying that each valve (manual, power-operatec, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.
By a visual inspection which verifies that no loose debris (rags, 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:
1)
Verifying automatic interlock action of the RHR System from the Reacte,r Coolant System by ensuring that with a simulated signal greater than or equal to 412.5 psia the interlocks prevent the valves from being opened.
MILLSTONE - UNIT 3 3/45-4 Amendment No. pp. 77. Jpp, JJJ. JJ7,156 0664