ML17054C117
| ML17054C117 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/15/1987 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17054C116 | List: |
| References | |
| NUDOCS 8705260335 | |
| Download: ML17054C117 (12) | |
Text
gp,R RECy, (4
0~i 0
+>>*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-410 NINE MILE POINT NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
2 License No. NPF-54 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated March ll, 1987, as supplemented March 16, 18 and 31, 1987 and April 2, 3, 7, 23 and 28, 1987, 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 hy 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 Comission'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 deleting items l.a.(2), (3) and (4) of Attachment 1 and 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-54 is hereby amended to read as follows:
87052b0335 8705l5 PDR ADOCK 050004l0 P
~
~
~
~ {2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the
'nvironmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No. 2, are hereby incorporated into this license.
Niagara Mohawk Power Corporation 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.
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 15, 1987 FOR THE NUCLEAR REGULATORY COMMISSION RM~GL. C~~~
Robert A. Capra, Acting Director Project Directorate I-1 Division of Reactor Projects, I/II
~p,R 4Egy, (4
P UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
2 TO FACILITY OPERATING LICENSE NO. NPF-54 DOCKET NO. 50-410 Revise Appendix A as follows:
Remove Paqes 2~3 3/4 6-6 3/4 6-23 Insert Pa es 2-3 3/4 6-6 3/4 6-23
0
~
~
TABLE 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUE Intermediate Range Monitor,-
Nuetron Flux High m
le Cl I
a.
Neutron Flux - Upscale, Setdown b.
Fl ow-Biased Simul ated Thermal Power - Upscale 2.
Average Power Range Monitor:
<15X of RATED THERMAL POWER
<20K of. RATED THERMAL POWER
<120/125 d>vsssons of full scale
<122/125 d>visions of full scale 1)
Flow-Biased 2)
High-Fl ow-Cl amped c.
Fixed Neutron Flux-Upscale d.
Inoperative 3.
Reactor Vessel Steam Dome Pressure
-, High 4.
Reactor Vessel Water Level-Low, Level 3
5.
Main Steam Line Isolation Valve - Closure 6.
Main Steam Line Radiation-High 7.
Drywell Pressure
- High 0.66 (W-aW)('). 5n, th maximum of <113.5X of RATED THERMAL POWER
<118K of RATED THERMAL POWER
<1037 psig
>159.3 in. above instrument zero*
<8X closed
<3.0 x full-power background
<1.68 psig
<0.66 (W-~W)(') + 5e, with maximum of <115.5X of RATED THERMAL POWER
<120X of RATED THERMAL POWER NA
<1057 psig
>157.8 in. above instrument zero
<12K closed
<3.6 x full-power background
<1.88 psig
" See Bases Figure 83/4 3-1.
(a) The Average Power Range Monitor Scram Function varies as a function of recirculation loop drive flow (W).
hW is defined as the difference in indicated drive flow (in percent of drive flow which produces rated core flow) between two loop and single loop operation at the same core flow.
AW=O for two loop operation.
hW=5X for single loop operation.
TABLE 3.6.1.2"1 ALLOWABLE LEAK RATES THROUGH VALVES IN POTENTIAL BYPASS LEAKAGE PATHS LINE DESCRIPTION 4 Hain Steam Lines Hain Steam Drain Line (Inboard)
Main Steam Drain Line (Outboard) 4 Postaccident Sampling Lines Drywell Equipment Drain Line Drywell Equipment Vent Line Drywell Floor Drain Line Drywell Floor Vent Line RWCU Line Feedwater Line CPS Supply Line to Drywell CPS Supply Line to Drywell CPS Supply Line to Supp.
Chamber CPS Supply Line to Supp.
Chamber VALVE MARK NO 2MSS"AOV6A, B, C, D
2HSS*AOV7A, B, C, D
2HSS*HOVlll, 112 2HSS*HOV208 2CHS"SOV77A, B
2CMS*SOV74A, B
2CHS"SOV75A, B
2CMS"SOV76A, B
2DER*HOV119 2DER"MOV120 20ER" HOV130 2DER"MOY131 2DFRAMOV120 2DFR"HOV121 2DFR"HOV139 2DF R"HOV140 2WCS"HOV102 2WCS*HOV112 2FWS"AOV23A 2FWS"V12A 2FWS~AOV23B 2FWS "V12B 2CPS"AOV104 2CPS"AOV106 2CPS" SOY120 2CPS"SOY122 2C PS
"AOY105 2C PS"AOY107 2CPSASOV119 2C PS" SOV121 TERMIN-ATIONN REGION Turbine Bldg.
Turbine Bldg.
Turbine Bldg.
Radwaste Tunnel Radwaste Tunnel Radwaste Tunnel Radwaste Tunnel Radwaste Tunnel Turbine Bldg.
Turbine Bldg.
Standby Gas Trtmt. Area Standby Gas Trtmt. Area Standby Gas Trtmt. Area Standby Gas Trtmt. Area PER VALVE*
LEAK RATE, SCFH 6.0
- 1. 875
- 0. 625 0.2344
- 1. 25
- 0. 625
- 1. 875 0.9375 2.5
- 12. 0
- 4. 38
- 0. 625
- 3. 75
- 0. 625
~ Test conditions:
air medium, 40 psig.
NINE MILE POINT - UNIT 2 3/4 6-6 Amendment No.
2
TABLE 3.6.3-1 PRIMARY CONTAINMENT ISOLATION VALVES ISOLATION VALVE NO.
VALVE FUNCTION VALVE ISOLATION GROUP SIGNAL(a)
MAXIMUM CLOSING TIME (SECONDS) t M
00 A.
Automatic 2HSS"AOV6 A,B,C,D 2HSS~AOV7 A,B,C,D 2HSS*HOV208 2HSS"MOV111 2HSS"HOV112 Inside MSIV Outside MSIV HSL Drain Line Outside IV Hain Steam Drain Line Inside IV Main Steam Drain Line Outside IV Z,X,C,D,E,P,T,R,RH,AA 3 to 5 Z,X,C,D,E,P,T,R,RM,AA 3 to 5 Z,X,C,D,E,P,T,R,RH,AA 18 Z X C D~E~P~T~R~RM AA 60 Z,X,C,D,E,P,T,R,RH,AA 60 CJl I
2RHS*HOV33 A,B 2RHS*MOV104 2RHS*MOV40 A,B 2RHS*MOV67 A,B 2RHS"MOV112 2RHS*MOV113 2CSH*HOVlll 2ICS*HOV164 2CCP"MOV94 A,B 2CCP"HOV17 A,B 2CCP~MOV16 A,B 2CCP*MOV15 A,B RHS Cont.
Spray Outside IVs RHS Reactor Head Spray Outside IV Shutdown Cooling Return Outside IVs SDC Inboard IV Bypass Valves SDC Supply Inside IV SDC Supply Outside IV CSH Test Return to Suppression Pool Outside IV RCIC Vacuum Breaker Outside IV CCP Supply to RCS Inside IVs CCP Supply to RCS Outside IVs CCP Return from RCS Pumps Inside IVs CCP Return from RCS Pumps Outside IVs RH and
- ll H 5 F, RH 8
B,F,Z,RM 8
B,F,Z,RM 8
B,F,Z,RM 8
B,F,Z,RH 35 50 29 18 29 29 60 18 30 30 30 30 2DFR*HOV120 g'DFR"MOV121 DFR Drain Tank Line Outside IV DFR Drain Tank Line Inside IV 8
B,F,Z,RH 8
B,F,Z,RH 45 45