ML17054B552
| ML17054B552 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/01/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Niagara Mohawk Power Corp |
| Shared Package | |
| ML17054B553 | List: |
| References | |
| DPR-63-A-071 NUDOCS 8504170018 | |
| Download: ML17054B552 (18) | |
Text
~R REQy P
+
O~
Cy A.
+**y0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 AMENDMENT TO FACILITY OPFRATING LICENSE Amendment No. 7l License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated May 1, 1984 as supplemented and clarified October 22, 1984, 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 (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:
85041700l8 85040l PDR ADOCK 05000220 PDR L~
(2) Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment Ho.
71, 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.
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 1, 1985 FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch 82 Division of Licensing
ATTACKMENT TO LICENSE AMEND'MENT NO.
71 FAC!LITY OPERATING I ICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise the Appendix A Technical Specifications by removing and inserting the fol1owing pages:
Existino Paae iiia Revised
~Pa e
illa 24lii4 24lii5 24!il 6 241i i7 241i i8 The revised areas are indicated by margina1 1ines.
SECTION 3.6.5 Radioactive Material Sources 3.6.6 Fire Oetection 3.6.7 Fire Suppression 3.6.0 Carl)on Oioxid>> Suppression System 3.6.9 Fire Hose Stations 3.6.10 Fire Barrier Penetration Fire Seals 3.6.11 Accident Honitoring Instrumentation 3.6.12 Aeactor Protection System Motor Generator Set Monitoring 3.6.13 Reeote Shutdown Panels 3.6.14 f)adioactive Effluent Instrumenat ion 3.6.15 Radioactive Effluents 3.6.16 Radioactive Effluent Treatment Systems 3.6.17 Explosive Gas Hixture 3.6.10 Mark I Containmen t 3.6.19 Liquid Waste lto)<lup Tanks
'OESCA IPTIOA 4.6. 5 4.6.6 4.6.7 4.6.0 4.6.9 Radioactive Haterial So))rces Fire Oetection Fire Suppression Carbon Oioxide Suppression System Fire llose Stations 4.6.10 Fire Barrier Penetration Fire Seals 4.6. 11 4.6.12 4.6.13 Accident Honi toring Instrumentation Reactor Protection System Hotor Generator Set Monitoring
. Remote Shutdown Panels 4.6.14 Radioactive Effluent Instrumentation 4.6.17 Exp)osive Gas Mixture 4.6. 10.
Hark I Cont a inmen t 4.6.19 Liquifl Waste Iloldup Tanks 4.6.15 Radioactive Effluents 4.6. 16 Aad ioactive Effluent Treatment Systems PAGE 24)k 24)m 241 q 24 lu 24)y 24)cc 24)ee
- 24) i i)
- 24) i i 4 24)jj 24)ww 241qqq 241tt t 24 I vvv 24)xxx 3.6. 20 Aadio logical Enviro))mental Moni toring Prograln 4.6.20 Aa61io)ogica)
Environmental Honitoring Program 24)zzz 3.6.21 Interlaboratory Comparison ProtJ) alii
- 3. 6. 22 Land Use Census tt) be st)l))))i t ted at a future date 4.6.2) 4.6. 22 Inter I abora tory Comparison Program I.and Use Census 241111 24)nnn iiia Amendment tlo. P6, 71
LIMITING CONDITION FOR OPERAT ION SURVEILLANCE REOUlREHENT 3.6.13 REMOTE SHUTDOWN PANELS 4.6.13 REMOTE SHUTDOWN PANELS App 1 icabi 1 ity:
Applies to th
~ operating status of the remote shutdown panels.
Applicability:
I Applies to the periodic testing requirements for the remote shutdown panels.
Objective:
To assur e the capability of the remote shutdown panels to provide 11 initiation of the emergency condensers independent of the main/auxiliary control room 2) control of the notor-operated steam supply valves independent:
of the main/auxiliary control room and 3) parameter monitoring outside the control room.
Objective:
To assure the capability of the remote shutdown panels to provide 11 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 monitorinq outside the control room.
Specification:
a.
During power operation and whenever the reactor coolant temperature is greater than 2 12'F, at least one remote shutdown pane 1 shall be operable.
Specification:
The remote shutdown panels surveillance shall be performed as indicdted 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.
During each major refueling outage 1.
Each remote shutdown panel shall be demonstrated to initiate the emergency condensers independent of the main/auxiliary control room.
Amendment No.
71 241i i4
LIMITING CONDITION FOR. OPERATION 3.6.13 REMOTE SHUTDOWN PANELS (Continued)
A remote shutdown pane) shall be considered inoperable if either the emergency condenser condensate return valve control switch is inoperable, either rotor-operated steam supply valve control switch is inoperable, or the number of operable instrumentation channels is less than that required by Table 3.6. 13-1.
c.
If Speci. ication 3.6.13.a cannot be met, commence an orderly shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
~nd be in cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
SURVEILLANCE REQUIREMENT 4.6. 13 REMOTE SHUTDOWN PANELS (Conti"~'M) 2.
Each remote shutdown panel shall be deox nstrated to open both the motor-operated steam valves.
~
~
Amendment No.
71 241i i 5
TABLE 3.6-13-1 REMOTE SHUTOOWN PANEL MONITORING L~imitin Condition for 0 aration INSTRUMENT Reactor Pressure Reactor Water Level Reactor Water Temperature Torus Water Temperature Drywell Pressure Emergency Condenser Water Level Drywell Temperature "All Rods In" Light MINIMUM NUMBER OF OPERABLE CHANNELS Amendment No.
71 2411 i6
TABLE 4.6.13-1 REMOTE SHUTDOWN PANEL MONITORING Surveillance Re uirement Parameter Sensor Check Instrument Channel Calibration Reactor Pressure Reactor Mater Level Reactor Water Temperature Torus Water Temperature Drywell Pressure Emergency Condenser Water Level Drywell Temperature "All Rods In" Light Once per day Once per day Once per day Once per day Once per day Once per day I
Once per day Once per refueling cycle Once per 3 months (a)
Once per 3 months (a)
Once per refueling cycle Once per refueling cycle Once per 3 months (a)
Once per refueling cycle Once per refueling cycle N/A (a)
The indicator located at the remote shutdown panel will be calibrated at the frequency listed in Table 4.6.13-1.
Calibration of the remaining channel instrumentation is provided by Specification 4.6.2.
Amendment No.
71 241ii 7
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 remote shutdown panel provides the necessary capabilities consistent with 10CFR50 Appendix R.
Therefore, only one remote shutdown panel 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 that 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 contro'I 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.
I 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.
Amendment No.
71 24 1 i i8