ML17055B377
| ML17055B377 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/07/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17055B378 | List: |
| References | |
| NUDOCS 8603130199 | |
| Download: ML17055B377 (14) | |
Text
qO~ R<0O>
c" 0
I
~
OO I
I
~+*<<+
t UNITED STATES t
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO.
50-2PO NINE MJI E POINT NIICLEAR STATION, UNIT NA.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
79 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has
<ound that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated lanuary 15,
- 1986, as supplemented March 3, 1986, 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 conformitv with the application, the provisions of the Act, and the rules and requlations of the Commission; C.
There is reasonable assurance (i) that the activities authorized bv this amendment can be conducted without endanaerinq the health and safety of the oublic, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not he inimical to the common defense and security or to the health and safety nf the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all aonlicable requirements have been satisfied.
2.
Accordinqlv, the license is amended bv chanqes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph P.C.(2) of Facility Onerating License No.
DPR-63 is hereby amended tn read as follows:
8603i30i99 860307 PDR ADOCN, 05000220, P
1 u
2.
Accordingly, the license is amended by changes to the Technical Snecifications as indicated in the attachment to this license amendment and Paragraph P.C.(2) of Facility Operating License Nn.
APR-63 is hereby amended to read as follows:
(2)
Technical Specification The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, are hereby incoroorated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date o< is uance.
FOR T NUC FAR GU TOR COMMISSION Dohn
. Zwolinski, Director BWR Pr iect Directorate
¹1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 7, 1986.
ATTACHMENT TO LICENSF.
AMENDMFNT NO.
79 FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE 191 196 208 210 INSERT 191 196 208 210
TABLE 3.6.2a INSTRUMENTATION THAT INITIATES SCRAM Limitin Condition for 0 eration Parameter Minimum No.
of Tripped or Operable Tri S stems Minimum No. of Operable Instrument Channels Per Operable Tri S stem Set Point Reactor Mode Switch Position in Which Function Must Be 0 erable (1) Manual Scram (2) High Reactor Pressure (3) High Drywell Pressure (4)
Low Reactor Water Level (5) High Water Level Scram Discharge Volume 2(m) 1080 psi g 3.5 psig 53 inches (Indicator Scale)
< 45 gal.
X X
X X
X X
x (a)
(a)
X X
X (b) x x
Amendment No. Q, 79 191
NOTES FOR TABLES 3.6.2a and 4.6.2a (a)
(b)
(c)
Hay be bypassed when necessary for containment inerting.
Hay be bypassed in the refuel and shutdown positions of the v'eactor mode switch with a keylock switch.
Hay 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.
s (e)
No more than two C or 0 level LPRH inputs to an APRH shall be bypassed and only four LPRH inputs to an'PRH shall be bypassed in order for the APRH to be considered operable.
No more than one of the four APRH 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.
Calibrate prior to starting and normal shutdown and thereafter check once per shift and test once per week until no longer required.
(g)
(h)
(k)
(m)
IRH's are bypassed when APRH's are onscale.
APRH downscale is bypassed when IRH's are onscale.
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.
Hay be bypassed when reactor power level is below 45'L.
Trip upon loss of oil pressure to the acceleration relay.
Hay be bypassed when placing the reactor mode switch in the SHUTMNH position and all control rods are ~
fully inserted.
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.
One instrument channel in each trip system may be bypassed in the cold shutdown and refuel conditions during the Spring 1986 refueling outage to perform the emergency condenser piping replacement.
Amendment No. 37, 79 196
TABLE 3.6.2d INSTRUMENTATION THAT INITIATES CORE SPRAY(e)
Limitin Condition for 0 eration Parameter Minimum No.
of Tripped or Operable Tri S stems Mininum No. of Operable Instrument Channels Per Operable Tri S stem
~Set oint Reactor Mode Switch Position in Which Function Must Be 0 erable Oa l/l CL 5-IQ C/l
- ~
START CORE SPRAY PUMPS (1) High Dryweli Pressure (2) Low-Low Reactor Hater Level 2(f)
< 3.5 psig 5 inches (Indicator Scale)
(d) x (a)
(a)
(b) x x
x OPEN CORE SPRAY DISCHARGE VALVES (3) Reactor Pressure and either (1) or (2) above.
> 365 psi g x
x x
x Amendment No. gg, 87 79 208
0
NOTES FOR TABLES 3.6.2d AND 4.6.2d (a)
Hay be bypassed when necessary for containment inerting.
(b)
Hay be bypassed when necessary for performing ma]or maintenance as specified in Specification.2.1.1.e.
(c)
Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2d, the primary sensor will be calibrated and tested once per operating cycle.
(d)
Hay be bypassed when necessary for integrated leak rate testing.
(e)
The instrumentation that initiates the Core Spray System is not required to be operable, if there is no fuel in the reactor vessel.
(f)
One instrument channel in each trip system may be bypassed in the cold shutdown and refuel conditions during the Spring 1986 refueling outage to perform the emergency condenser piping replacement.
Amendment No. lg, 87, 79 210
'V