ML17059A970
| ML17059A970 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/16/1995 |
| From: | Marsh L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059A971 | List: |
| References | |
| NUDOCS 9510230026 | |
| Download: ML17059A970 (14) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 NIAGARA MOHAWK POWER CORPORATION DOC O. 50-220 N
MIL POI T NUC AR TATION UNIT 0
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
155 License No.
DPR-63 r
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated February 1,
1995, 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'orth 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-63 is hereby amended to read as follows:
95i0230026 95i0i6 PDR ADOCK 05000220 P
(2)
Technica S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 155, 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.
FOR THE NUCLEAR REGULATORY COHHISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 16, 1995 L
yard B. Hars
, Director Project Directorate I-I Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
ACHMENT TO LICENSE AMENDMENT A ENDME
- 0. i55 TO FACILITY OPERATING LICENS NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 277 278 279 281
~t 277 278 279 281
LIMITINGCONDITION FOR OPERATION SURVEILLANCEREQUIREIVIENT 3.6.13 REM TE H TD WN ANEL 4.6.13 REM TE H TD WN PANEL RdsislSJiE Applies to the operating status of the remote shutdown panels.
Applies to the periodic testing requirements for the remote shutdown panels.
gl~~iv:
g)~~iv:
To assure the capability of the remote shutdown panels to provide 1) initiation of the emergency condensers independent of the main/auxiliary control room 2) control of the motor-operated steam supply valves independent of the main/auxiliary control room and 3) parameter monitoring outside the control room.
To assure the capability of the remote shutdown panels to provide 1) initiation of the emergency condensers independent of the main/auxiliary control room 2) control of the motor-operated steam supply valves independent of the main/auxiliary control room and 3) parameter monitoring outside the control room.
5HdRJlti!
a.
During power operation, the remote shutdown panels'unctions in Table 3.6.13-1 shall be operable.
The remote shutdown panels surveillance shall be performed as indicated below:
a.
Each remote shutdown panel monitoring instrumentation channel shall be demonstrated operable by performance of the operations and frequencies shown in Table 4.6.13-1.
b.
rin h m r
AMENDMENTNO. Ad, 155 1.
Each remote shutdown panel shall be demonstrated to initiate the emergency condensers independent of the main/auxiliary control room.
277
LIMITINGCONDITION FOR OPERATION SURVEILLANCEREQUIREMENT b.
With the valve control Function inoperable, restore the required Function to operable status within 30 days.
2.
Each remote shutdown panel shall be demonstrated to open both the motor-operated steam valves.
c.
With one or more required monitoring instrument Functions inoperable, restore the required Function to operable status within 30 days or establish an alternate method of monitoring the parameter within 30 days and restore the required Function to operable status within 90 days.
d.
If the required action and associated completion time is not met, be in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
AMENDMENTNO. i(49, 155 278
TABLE3.6.13-1 REM T N
NIM RAB Reactor Pressure Reactor Water Level Reactor Water Temperature Torus Water Temperature Drywell Pressure Emergency Condenser Water Level Drywell Temperature "AllRods In" Light Emergency Condenser Condensate Return Valve and Motor-Operated Steam Supply Valves Control on the Same Panel AMENDMENTNO. 76 155 279
BASES FOR 3.6.13 AND 4.6.13 REMOTE SHUTDOWN PANELS The remote shutdown panels provide 1) manual initiation of the emergency condensers
- 2) manual control of the steam supply valves and 3) parameters monitoring independent of the'main/auxiliary control room. Two panels are provided, each located in a separate fire area, for added redundancy.
Both panels are also in separate fire areas from the main/auxiliary control room.
One channel of each Function provides the necessary capabilities consistent with 10CFR50 Appendix R. Therefore, only one channel of either remote shutdown panel monitoring instrument or control is required to be operable.
The electrical design of the panels is such that no single fire can cause loss of both emergency condensers.
Each remote shutdown panel is provided with controls for one emergency condenser loop. The emergency condensers are designed such hat automatic initiation is independently assured in the event of a fire 1) in the Reactor Building (principle relay logic located in the auxiliary control room or 2) in the main/auxiliary control room or Turbine Building (redundant relay logic located in the Reactor Building). Each remote shutdown panel also has controls to operate the two motor-operated steam supply valves on its respective emergency condenser loop. A key operated bypass switch is provided to override the automatic isolation signal to these valves.
Once the bypass switch is activated, the steam supply valves can be manually controlled from the remote shutdown panels.
Since automatic initiation of the emergency condenser is assured, the remote shutdown panels serve as additional manual controlling stations for the emergency condensers.
In addition, certain parameters are monitored at each remote shutdown panel.
The remote shutdown panels are normally de-energized, except for the monitoring instrumentation, which is normally energized.
To energize the remaining functions on a remote shutdown panel, a power switch located on each panel must be activated.
Once the panels are completely energized, the emergency condenser condensate return valve and steam supply valve controls can be utilized.
AMENDMENTNO. 4/9, 155 281