ML20077C613
| ML20077C613 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/28/1994 |
| From: | Stone J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077C614 | List: |
| References | |
| NUDOCS 9412050320 | |
| Download: ML20077C613 (6) | |
Text
-
uco ye t
UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, O.o. 206S4001
%.....}
\\
WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET N0. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 80 License No. NPF-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation), dated July 15, 1994, 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, as amended, 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 license amendment will not be inimical to the 4
common defense and security or to the health and <,afety of the public; and i
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.
9412050320 941128 PDR ADOCK 05000482 P
~.._m...
a4
_~
_.,m m.
.m..
,m..
1 t 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. NPF-42 is hereby amended to read as follows.
- 2..
Technical Specifications The Technical Specifications contained in Appendix A, as revised i
through Amendment No. 80, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
i 3.
The license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
James C. Stone, Senior Project Manager i
Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
{
Attachment:
Changes to the Technical i
Specifications Date of Issuance: November 28, 1994 1
l 1
i I
ATTACHMENT TO LICENSE AMENDMENT N0, 80 FACILITY OPERATING LICENSE N0. NPF-42 DOCKET N0. 50-482 i
i Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and contains marginal lines indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
REMOVE INSERT 3/4 3-42 3/4 3-42 I
& A 4.
4 a
+
~
+~- =
J s
= " a m -.
=
D 4
?
l i
5 b
I s
A b
t e
i b
n I
1 1
,P I
l h
e I
C I
'b k
b
+
f i
I L
i E
1
.h I
i h
.i P
' h p ~ -, -
e n..+.
-L----.----------.--------
h
TABLE 3.3-6 (Continued)
TABLE NOTATIONS
- With fuel in the respective fuel storage pool.
- With irradiated fuel in the fuel storage areas or fuel building.
3
- Trip Setpoint concentration value (pCi/cm ) is to be established such that the actual submersion dose rate would not exceed 2 mR/h in the control room.
3
- Trip Setpoint concentration value (pCi/cm ) is to be established such that the actual submersion dose rate would not exceed 4 mR/h in the fuel building.
3
- Trip Setpoint concentration value (pCi/cm ) is to be established such that the actual submersion dose rate would not exceed 9 mR/h in the containment building.
The Setpoint value may be increased up to the equivalent limits of Section 3.1 of the ODCM in accordance with the methodology and l
parameters in the ODCM during containment purge or vent provided the Setpoint value does not exceed twice the maximum concentration activity in the containment determined by the sample analysis performed prior to each release in accordance with Table 3-1 of the ODCM.
l ACTION STATEMENTS ACTION 26 - With less than the Minimum Channels OPERABLE requirement, operation may continue provided the containment purge valves are maintained closed.
ACTION 27 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, isolate the Control Room Emergency Ventilation System and initiate operation of the Control Room Emergency Ventilation System in the recirculation mode within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or with no OPERABLE channels within I hour.
ACTION 28 - With less than the Minimum Channels OPERABLE requirement, operation may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel area.
Restore the inoperable monitors to OPERABLE status within 30 days or suspend all operations involving fuel movement in the fuel building.
ACTION 29 - Must satisfy the ACTION requirements for Specification 3.4.6.1.
ACTION 30 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, isolate the Fuel Building Ventilation System and initiate operation of the Emergency Exhaust System to maintain the fuel building at a negative pressure within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or with no OPERABLE channels within I hour.
WOLF CREEK - UNIT 1 3/4 3-41 Amendment No. N, 56
TRBLE 4.3-3 i
RADIATION MONITORING INSTRUMENTATION FOR PLANT l
OPERATIONS SURVEILLANCE REQUIREMENTS l
ANALOG MODES FOR CHANNEL WHICH SURVEIL-CHANNEL CHANNEL OPERATIONAL LANCE IS FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED l
1.
Containment i
a.
Containment Atmosphere-Gaseous Radioactivity-i High (GT-RE-31 & 32)
S R
Q All l
b.
Gaseous Radioactivity-RCS Leakage Detection (GT-RE-31 & 32)
S R
Q 1, 2, 3, 4 l
c.
Particulate Radioactivity -
RCS Leakage Detection (GT-RE-31 & 32)
S R
Q 1, 2, 3, 4 l
2.
Fuel Building a.
Fuel Building Exhaust-Gaseous Radioactivity-l High (GG-RE-27 & 28)
S R
Q b.
Criticality-High Radiation Level l
- 1) Spent Fuel Pool S
R Q
(SD-RE-37 & 38)
- 2) New Fuel Pool (SD-RE-35 & 36)
S R
Q l
3.
Control Room Air Intake-Gaseous Radioactivity-High (GK-RE-04 & 05)
S R
Q All l
- With fuel in the respective fuel storage pool.
- With irradiated fuel in the fuel storage areas or fuel building.
WOLF CREEK - UNIT 1 3/4 3-42 Amendment No. 80
.