ML20006E030
| ML20006E030 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/31/1990 |
| From: | Jocelyn Craig Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006E031 | List: |
| References | |
| NUDOCS 9002160118 | |
| Download: ML20006E030 (5) | |
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UNITED STATES E
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> NUCLEAR REGULATORY COMMISSION n
WASHINGTON, D. C. 20555 i
DOCKET NO. 50-461 CLINTON POWER STATION _ UNIT _N_0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. NPF-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
TheapplicationforamendmentbyIllinoisPowerCompany*(IP),
and Soyland Power Cooperative, Inc., (the licensees) dated February 5, 1988; complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
Thereis'reasonableassurance(1)thattheactivitiesauthorizedby this amendnent 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 net be inimical to the comon l_
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 Comission's regulations and all applicable' requirements.have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications asindicatedintheattachmenttothislicenseamendment,andparagraph2.C.(2) l '
.of Facility Operating License No. NPF-62 is hereby amended to read as follows:-
Illinois Ewerlompany is authorized to act as agent for Soyland Power Cooperative, Inc. and has exclusive respor.sibility and control over the physical construction, operation and maintenance of the facility.
9 i%
PUR P
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Technical Specifications j
n The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 30
, are hereby-incorporated into this L
license.
Illinois Power Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L-dohn W. Craig, Director Project Directorate 111-2 l'
Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications-Date of Issuance:
January 31, 1990 I
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ATTACHMENT.TO. LICENSE; AMENDMENT NO. 30; FACILITY.0PERATING. LICENSE.NO..NPF.62 DOCKET NO. 50-461 2
Replace the following pages of the Appendix 'A' Technical Specifications with Lthe attached pages. The revised pages are identified by amendhtent number and contain vertical lines indicating the area of change.
i Remove Insert 3/4 3-8 3/4 3-8
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3/4 3-10 3/4 3-10 4
f 4
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TABLE 4.3.1.1-1 n
1 r-REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
CHANNEL-'
OPERATIONAL'
'E CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH Z
FUNCTIONAL UNIT CHECK TEST CALIBRATION (a)
SURVEILLANCE REQUIRED.
s 1.
a.
Neutron Flux'- High S/U,5,(b)
.S/U(c),W R
2' S
W R
3,4,5 b.
Inoperative NA W
NA 2, 3, 4,_5 2.
Average Power Range Monitor:(I) a.
Neutron Flux - High, S/U,S,(b)
S/U(C),W SA 2
g Setdown S
W SA 3, 4, 5
.=
w b.
Flow-Biased Simulated E
Thermal Power - High S
S/U(c),y y(d)(e),SA,R(I)
I c.
Neutron Flux - High S
S/U(c),y y(d)(e), SA 1
d.
Inoperative NA W
NA' 1,2,3,4,5 3.
Reactor Vessel Steam Dome Pressure - High S
M R(9) 1,2(I)-
4.
I9)
Low, level 3 S
M R
.1, 2.
5.
High, Level 8
'S M
R(9) 1-
[
6.
Main Steam Line Isolation 3
Valve - Closure NA-M R
1 E
7.
Main Steam Line Radiation -
High S
M R
1,2(i)-
m O
8.
Drywell Pressure - High 5
M
'R(9) 1,2(I)'
.2
- u....u
4 TABLE 4.3-1.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIONS (a) Neutron detectors may be excluded from CHANNEL CALIBRATION..
- (b) The IRM and SRM channels shall be determined to overlap for at least 1/2 de-cade during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least I decade dur-ing each controlled shutdown, if not performed within.the previous 7 days.
(c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.
(d) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION.1 when THERMAL POWER > 25% of RATED THERMAL POWER.
Adjust the APRM channel if the absolute diTference is greater than 2% of RATED THERMAL POWER.
(e) This calibration shall consist of a setpoint verification of the Neutron Flux-High and the Flow Biased Simulated Thermal Power-High trip functions.
The Flow Biased Simulated-Thermal-High trip function is verified using a calibrated flow signal.
(f) The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP system.
(g) Calibrate the analog trip module at least once per 31 days.
(h) Deleted.
(i) This calibration shall consist of verifying the 610.6 second simulated thermal power time constant.
(j) This function is not required to be OPERABLE when the reactor pressure vessel head is-removed per Specification 3.10.1.
(k) With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
(1) This function is not required to be OPERABLE when DRYWELL INTEGRITY is not required to be OPERABLE per Special Test Exception-3.10.1.
(m) The CHANNEL FUNCTIONAL TEST-and CHANNEL CALIBRATION shall include the turbine first stage pressure instruments.
- CLINTON - UNIT 1 3/4 3-16 Amendment No. 30 l