ML17056A465
| ML17056A465 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/21/1989 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056A466 | List: |
| References | |
| NUDOCS 8912010111 | |
| Download: ML17056A465 (16) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION
'OCKET NO. 50-220 NINE NILE POINT NUCLEAR STATION UNIT 1 ANENDtIEtIT TO FACILITY OPERATING LICENSE Amendment No. 111 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Nohawk Power Corporation (the licensee) dated Hay 4, 1988, 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 wi 11 be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment wi 11 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:
89120ioiii 89ii21 DR ADQCK 05000220 PNU
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
111, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Speci fi ca tions Date of Issuance:
november 21, 1989 Robert A. Capra, Director Project Directorate 1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
111 TO FACILITY OPERATIN4 LICENSE-NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as fo11ows:
Remove Pa es 195 196 217 221 223 Insert Pa es 195 196 217 221 223
TABLE 4.6.2a (Cont'd)
INSTRUMENTATION THAT INITIATES SCRAM Surveillance Re uirement Parameter Sensor Check Instrument Channel Test Instrument Channel Calibration
(&)
Shutdown Position of Reactor Mode Switch None Once during each major refueling outage None (9)
Neutron Flux (a)
IRH (i)
Upscale (ii)
Inoperative (b)
APRH (i)
Upscale (ii)
Inoperative (iii)
Downscale (10) Turbine Stop Valve Closure None None None None Once/week Once/week Once/week Once per 3 months Once/week(m),
Once per 3 months None Once/week(m),
Once per 3 months ~
Once per operating cycle (ll) Generator Load Rejection None Once per month Once per 3
months Amendment No. ill 195
NOTES FOR TABLES 3.6.2a and 4.6.2a (a)
Hay be bypassed when necessary for containment inerting.
(b)
May be bypassed in the refuel and shutdown positions of the reactor mode switch with a keylock switch.
(c)
May be bypassed in the refuel and startup positions of the reactor mode switch when reactor pressure is less than 600 psi.
(d)
No more than one of the four IRH inputs to each trip system shall be bypassed.
(e)
No more than two C or 0 level LPRH inputs to an APRH shall be bypassed and only four LPRH inputs to an APRM shall be bypassed in order for the APRH to be considered operable.
No more than one of the four APRM inputs to~
each trip system shall be bypassed provided that the APRH in the other instrument channel in the same core quadrant is not bypassed.
A Travelling In-Core Probe (TIP) chamber may be used as a substitute APRH input if the TIP is positioned in close proximity to the failed LPRH it is replacing.
(f)
Calibrate prior to starting and normal shutdown and thereafter check once per shift and test once per week until no longer required.
(g)
IRM's are bypassed when APRH's are onscale.
APRM downscale is bypassed when IRH's are onscale.
(h)
Each of the four isolation valves has two limit switches.
Each limit switch provides input to one of two instrument channels in a single trip system.
(i)
Hay be bypassed when reactor power level is below 4SL.
(j)
Trip upon loss of oil pressure to the acceleration relay.
(k)
Hay be bypassed when placing the reactor mode switch in the SHUTDOWN position and all control rods are fully inserted.
(1)
Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2a, the primary sensor will be calibrated and tested once per operating cycle.
(m)
This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during reactor operation when THERMAL POWER
> 25'K of RATED THERMAL POWER.
Adjust the APRM channel if the absolute difference is greater than 2X of RATED THERMAL POWER.
Any APRH channel gain adjustment made in compliance with Figure 2.1.1 shall not be included in determining the absolute difference.
Amendment No.
111 1') 6
TABLE 3.6.2g (cont'd)
INSTRUMENTATION THAT INITIATES CONTROL ROD HITHORAHAL BLOCK Limitin Condition for 0 eration Parameter Hinimum No.
of Tripped or Operable Tri S stems Hinimum No. of Operable Instrument Channels Per Operable Tn S stem Set Point Reactor Mode Switch Position in which Function Must Be 0 erable 0O QP 8
CA CK
- c. Downscale
- d. Upscale (3)
APRH
- a. Inoperative
- b. Upscale (Biased by Recirculation Flow)
-c. Downscale Amendment No. ill 2 (h) 2 (h) 2 (h) 3 (b) 3 (b) 3 (c) 3 (c) 3 (c) 5 percent of full scale for each scale
< 88 percent of full scale for each scale Figure 2.1.1(h) 2 percent of full scale X
X X
X X
X X
X X
X (d)
(d)
X 217
TABLE 4.6.2g (Cont'd)
INSTRUMENTATION THAT INITIATES CONTROL ROD NITHDRAHAL BLOCK Surveillance Re uirement Parameter Sensor Check Instrument Channel Test Instrument Channel Calibration (3)
- a. Inoperative
- b. Upscale (Biased by Recirculation Flow) c.
Downscale (4)
Recirculation Flow a.
Comparator Off Normal None None None None Once per month Once per month Once per month Once per month None Once per 3 months Once per 3 months Once per month b.
Flow Unit Inoperative c.
F low Uni t Upscale None None Once per month Once per month Once per month Once per month Amendment No. ill 22I
NOTES fOR TABLES 3.6.2 and 4.6.2 (a)
No more than one of the four SRH inputs to the single trip system shall be bypassed.
(b)
No more than one of the four IRH inputs to each instrument channel shall be bypassed.
These signals may be bypassed when the APRH's are onscale.
(c)
No more than one of the four APRH inputs to each instrument channel shall be bypassed provided that the APRM in the other instrument channel in the same core quadrant is not bypassed.
No more than two C or 0 level LPRH inputs to an APRH shall be bypassed and only four LPRM inputs to only one APRH shall be bypassed in order for the APRH to be considered operable.
In the Run mode of operation, bypass of two chambers from one radial core location in any one APRH shall cause that APRH to be considered inoperative.
A Travelling In-Core Probe (TIP) chamber may be used as a substitute APRM input if the TIP is positioned in close proximity to the failed LPRH it is replacing.
If one APRH in a quadrant is bypassed and meets all requirements for operability with the exception of the requirement of at least one operable chamber at each radial location, it may be returned to service and the other APRH in'that quadrant may be removed from service for test and/or calibration only if no control rod is withdrawn during the calibration and/or test.
(d)
Hay be bypassed in the startup and refuel positions of the reactor mode switch when the IRM's are onscale.
(e)
This function may be bypassed when the count rate is 100 cps.
(f)
One sensor provides input to each of two instrument channels.
Each instrument channel is in a separate trip system.
( g)
Calibrate prior to startup and normal shutdown and thereafter check once per shift and test once per week until no longer required.
(h)
The actuation of either or both trip systems will result in a rod block.
Amendment No.
111 223
V