ML17286B245
| ML17286B245 | |
| Person / Time | |
|---|---|
| Site: | Columbia  (NPF-21-A-097, NPF-21-A-97) |
| Issue date: | 12/26/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17286B246 | List: |
| References | |
| NUDOCS 9201150022 | |
| Download: ML17286B245 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
97 License No.
NPF-21 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Washington Public Power Supply System
( licensee) dated February 21, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's 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 Speci-fications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License N..
NPF-21 is hereby amended to read as follows:
920ii50022 9i1226 PDR ADOCK 05000397 P
'I el l.
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(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 97 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.'he licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION g ir~
Theodore R. quay, Director Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 26, 1991
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 97 TO FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
I REIIOVE INSERT 3/4 3-56 3/4 3-56
II P
W
TABLE 4. 3. 6-1 CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 1.
ROD BLOCK MONITOR CHANNEL CHECK CHANNEL FUNCTIONAL TEST OPERATIONAL CHANNEL CONDITIONS FOR WHICH CALIBRATION SURVEILLANCE RE UIRED 2.
3.
4.
5.
6.
a.
Upscale b.
Inoperative c.
Downscale APRM a.
Flow Biased Neutron Flux Upscale b.
Inoperative c.
Downscale d.
Neutron Flux - Upscale, Startup SOURCE RANGE MONITORS a.
Detector not full in b.
Upscal e c.
Inoperative d.
Downscale INTERMEDIATE RANGE MONITORS a.
Detector not full in b.
Upscal e c.
Inoperative d.
Downscale SCRAM DISCHARGE VOLUME a.
Water Level-High b.
Scram Trip Bypass REACTOR COOLANT SYSTEM RECIRCULATION a.
Upscale b.
Inoperative c.
Comparator N.A.
N.A.
N ~ A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
FLOW N.A.
N.A.
N.A.
S/U(b)(c), Q(c)
S/U(b)(c), Q(c)
S/U(b)(c), Q(c)
S/U(b),
Q S/U(b),
Q S/U(b),
Q S/U(b),
Q S/u(b), W(¹)
S/U(b),
W S/U(b),
W S/U(b),
W S/U(b), W(¹)
S/U(b),
W S/U(b),
W S/U(b),
W S/U(b),
Q S/U(b),
Q S/U(b),
Q N.A.
N.A.
N.A.
N.A.
N.A.
Q N.A.
R N.A.
N.A.
Q
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1 1, 2, 5
1 2,
5 2,
5 2,
5 2,
5 2,
5 2,
5 2,
5 2,
5 2,
5 5%A 5k* '
TRIP FUNCTION Tat
.E.E-E CONTROL ROO BLOCK INSTRUMENTATION SETPOIHTS TRIP SETPOIHT ALL%ABLEVALUE I
I-C
-I lO OP EaE EQl Ol m
C7 C>
1.
2e 3a h.
5.
6.
ROD BLOCK HONITOR b.
Inoperative c.
Downscale hPN a.
Flow Biased Neutron Flux Upscale b.
Inoperatfve c.
Downscale d.
Neutron Flux - Upscale, Startup SOURCE RANGE NNITORS e.
Detector not full ln b.
Upscale c.
Inoperative d.
Downscale INTERMEDIATE RANGE NNITORS a.
Detector not full in b.
Upscale c.
Inoperative d.
Downscale SCRAM DISCHARGE VOLTE a.
Water Level-High b.
Scram Trip Bypass REACTOR COOLANT SYSTN RECIRCULATION FLOV
< 0.66 M+ 40K H.A.
> 5% of RATED THERNAL PlNER
< 0.66 N+ 42K H.A.
> 5'I of RATEO THERNL USER
< 1'f RATED THERNL POWER N.A.
< 1 x 10 cps R.A.
> 0.7 cps H.A.
< 1DB/125 divisions of full scale H.h.
> 5/125 divisions of full scale
< 527 ft 2 in. elevation lt.h.
< 0.68 N+ 13%
LA.
> 3% of NTEO THENAL PNER l
< 0.66 M+ iM R.A.
E 3L of EATEO TEEENN fnnER
< 14% of RATED THENAL PtNER N.A.
< 1e6 x 10 cps
.R.A.
> O.S cps N.A.
< 110/125 divisions of full scale I.A.
> 3/125 divisions of full scale a SET ft 1 fn. eleeatfon ~
Q.A.
a.
Upscale
< 108/125 divisions of full scale H.h.
< 1(C flow deviation tfon fs varied as e function of e Itafntafned fn accordance wfth
< 111/125 divisions of full scale if.h.
< 11Ã flow deviation recirculatf on loop flow Specf ffcatfon 3.2.2.
b.
Inoperative c.
Coeparator e
verage ower ange ifonftor rod block fute 00.
The trip setting of bfs futetlon oust b