ML20059N943
| ML20059N943 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  (DPR-53-A-148, DPR-69-A-129) |
| Issue date: | 10/12/1990 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059N944 | List: |
| References | |
| NUDOCS 9010240143 | |
| Download: ML20059N943 (9) | |
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UNITED STATES
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50 317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT 1 AMENDMENT.TO FACILITY 0PERATING LICENSE Amendment No. 148 License No. DPR-53 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (thelicensee)datedJune 16, 1988, as supplemented on September 30, 1989, and August 3, 1990, 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 o>erate in conformity with the application the provisions of tie Act, and the rules and regulations of the Comission;-
C.
Thereisreasonableassurance(1)thattheactivitiesauthorized 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 as indicated in the attachment to this license amendment,andparagraph2.C.(2)ofFacilityOperatingLicense No. DPR-53 is hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.148, are i
hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical i
Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION h) /)19$~
obert A. Capra. Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 12, 1990 j
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UNITED STATES
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BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT 2 AMENDMENT T0. FACILITY OPERATING. LICENSE Amendment No.129 License No. DPR-69 1.
The Nuclear Regulatory Comission (the Comission) has found that:
1 A.
The application for amendment by Baltimore' Gas and Electric Company
' l (the licensee) dated June 16, 1988, as supplemented on September 30 1989, and August 3, 1990, complies with tie standards and requirements
' j 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 tie Act, and the rules and regulations of the Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the i.ealth 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 not be inimical to the comon defense anc. 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 as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No.
DPR-69 is hereby amended to read as follows:
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',; Y, 2-(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.129. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
1 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION I
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) obert A. Capra, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 12, 1990 L
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l ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 148 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO, 129 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Revise Appendix A as follows:
Remoye P nel insert Panes i
3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42 1
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1 2
TABLE 3.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION 9
r-N MINIMUM
.5 CHANNELS p
INSTRUMENT OPERABLE ACTION 1.
Containment Pressure 2
31 2.
Wide Range Logarithmic Neutron Flux Monitor 2
31 E
3.
Reactor Coolant Outlet Temperature 2
31
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4.
Pressurizer Pressure 2.
31 5.
Pressurizer Level 2
31 6.
Steam Generator Pressure 2/ steam generator 31 3
7.
Steam Generator Level (Wide Range) 2/ steam generator 31
_q 3.
Auxiliary Feedwater Flow Rate 2/ steam generator 31
[
9.
RCS Subcooled Margin Monitor 1
31 h
10.
PORV/ Safety Valve Acoustic Flow Monitoring 1/ valve 31
- 11. PORY Solenoid Power Indication I/ valve 31
- 12. Feedwater Flow 2
31
- 13. Containment Water Level (Wide Range) 2 32, 33
- 14. Reactor Vessel Water Level 2*
34, 35 l
- 15. Core Exit Thermocouple System 2 locations / core quadrant 31 l-i
.I DD A channel has eight sensors in a probe. A channel is operable if four or more sensors, one or more in h
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the upper three and three or more in the lower five, are operable.
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TABLE 4.3-10 POST-ACCIDENT' MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS s
-e CHANNEL CHANNEL o
C INSTRUMENT CHECK CALIBRATION m
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l.
Containment Pressure M
R 2.
Wide Range Logarithmic Neutron Flux Monitor.
M N.A.
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3..
Reactor Coolant Outlet Temperature M
R
- 4. -Pressurizer Pressure M
R
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5.
. Pressurizer Level M
R
~6. ~ Steam Generator Pressure M
R 7.
Steam Generator Level (Wide Range)
M R
b 8.
Auxiliary Feedwater Flow Rate M
R
{
9.
RCS Subcooled Margin Monitor M
R
- 10. PORV/ Safety' Valve Acoustic Monitor N.A.
R
- 11.. PORY Solenoid Power Indication N.A.
N.A.
- 12. Feedwater Flow M
R
- 13. Containment Water Level (Wide Range)
M R
E
N.A.
o.
- 15. Core Exit Thermocouple System M
R*
=
r E
.y The performance of a channel calibration operation exempts the Core Exit Thermocouple but includes all' electronic components. The Core Exit Thermocouple shall be calibrated prior to installation in the reactor core.
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-. - 's TABLE 3.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION c,
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(I MINIMUM CHANNELS f[2I INSTRUMENT 0PERABLE ACTION 1.
Containment Pressure 2
31
(
2.
Wide Range Logarithmic Neutron Flux Monitor 2
31 3.
Reactor Coolant Outlet. Temperature 2
31
((
4.
Pressurizer Pressure 2
31 5.
Pressurizer Level 2
31 6.
Steam Generator Pressure 2/ steam generator 31 i
7.
Steam Generator Level (Wide Range) 2/ steam generator 31
}{
8.
Auxiliary Feedwater Flow Rate 2/ steam generator 31 9.
RCS Subcooled Margin Monitor 1
31 g,
ft 10.
PORV/ Safety Valve Acoustic Flow Monitoring 1/ valve 31 11.
PORY Solenoid Power Indication 1/ valve 31 12.
Feedwater Flow 2
31 l
- 13. Containment Water Level (Wide Range) 2 32, 33
- 14. Reactor Vessel Water level 2*
34, 35 f
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- 15. Core Exit Thermocouple System 2 locations / core quadrant 31 1
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? 10 A channel.has eight sensors in a probe. A channel is operable if four or more sensors, one or more in
?"%g the upper three and three or more in the lower five, are operable.
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TABLE 4.3-10 g, -
3 POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
E CHANNEL CHANNEL
-INSTRUMENT CHECK CALIBRATION 1.
Containment Pressure M
R 2.
Wide Range Logarithmic Neutron Flux Monitor M
N.A.
[
3.
' Reactor Coolant Outlet Temperature M
R
- 4. -Pressurizer Pressure M
R S.
Pressurizer Level M
R 6.
Steam Generator Pressure M
R R
- 7.. Steam Generator Level (Wide Range)
M R
[
8.
Auxiliary Feedwater Flow Rate M
R k
9.
RCS Subcooled Margin Monitor M
R 10.
PORV/ Safety Valve Acoustic Monitor M.A.
R
- 11. PORY Solenoid Power Indication N.A.
N.A.
12.
Feedwater Flow M
R
- 13. Containment Water Level (Wide Range)
M R
Eg
- 14. -Reactor Vessel Water Level M
N.A.
[
- 15. Core Exit Thermocouple System M
R*
5'.-
F
.Og The performance of a channel calibration operation exempts the Core Exit Thermocouple ewg but includes all electronic components. The Core Exit Thermocouple shall be calibrated
- h prior to installation in the reactor core.
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