ML20009B554
| ML20009B554 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 06/23/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20009B555 | List: |
| References | |
| NUDOCS 8107160286 | |
| Download: ML20009B554 (5) | |
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EALTIM0?.E GAS AMD ELECT"If Cn"PANY E0CKET H0. c0-317 CALVERT CLITTS N"CLEAP, P0"$P. PLANT UNIT N0. 1-I AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A. 'The application for ar:ndment by Baltimore Gas & Electric Company.(the' licensee) dated May 27, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulatio.'s set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and 'ine rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangeri g the health and safety of the public, and (ii) thtt 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 securi vy or to the health and safety of the public; and E.
.The issuance of this amendment is in accordance with 10 CFR P,rt 51 of 'the Commission's regulations and all applicable 2
l requirements have been satisfied.
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Accordingly, tna sirense is amenoea oy cnances to the Teclinical
. Specifications at indicated in tne attacnment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-53 is here~uy amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective on May 27, 1981.
FOR THE NUCLEAR REGULATORY COMMISSION
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Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications-Date of Issuance: June 23, 1981 F
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- ATTACSy'T-TD LICENSE'AM.NUMENT NO.'36
.TACILITY OPEP.ATING LICENSE NO. DPR-53
' DOCKET NO. 50-317
. Replace the following page of tne Appendix A Technical Specifications with
- the enclosed page as inoicated. The revised page-is identified.by Amendment number and contains vertical. lines indicating the area of change. 'The
- corresponding. overleaf page is also provided to maintain document completeness.
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TABLE 3.3-10 POST-ACCIDENT MONITORING INSTRUMENTATION; n
,. 4 p p.
MINIMUM EE CHANNELS-
][
INSTRUMENT OPERABLE-a rr 1.
Power Range Nuclear Flux 2
ww 2.
Containment Pressure
-2 i e ce
^
((
- 3.
. Wide Range Logarithmic Neutron Flux Monitor -
'2-4.
Reactor Coolant Outlet Temperature
.2' 5.
Reactor Coolant Total Flow 2
6.
Pressurizer Pressure 2
[
7.
Pressurizer Level 2.
.3 8.
Steam Generator Pressure 2/ steam generator 9.
Steam Generator Level
.2/ steam generator 10.
Feedwater Flow 2
.l.
Auxiliary Feedwater Flow Rate 1/ steam generator
-2 $
((
12.
RCS Subccoled Ma'rgin Monitor 1
ao 13.
PORV/ Safety Valve Acoustic Flow Monitoring 1/ valve.*
5E 14.
PORV Solenoid Power Indication.
1/ valve:
ME
- Uretil. June 1,1981,. the Unit 1 inoperable. acoustic riow monitor-for pressurizer safety valve PV 201 may be replaced by observation of quench tank temperature, level and pressure and the sifety valve tail pipe temperatures once per shift.
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TABLE 4.3-10:.
POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.
nn T
GG mm yE CHANNEL; Cl!ANNEL An
-INSTRUMENT CHECK CALIBRATION CC l y.
1.
Power. Range Nuclear Flux M
Q v> v, i '
2.
Containment Pressure M
R EE qq 3.
Wide Range Logarithmjc Neutron Flux Monitor M
fL A.
ro -
4.
Reactor Coolant Outlet Temperature M
P, 5.
Reactor Coolant Total Flow
,M R
t' 6.
Pressurizer Pressure-M R
=
'r' 7.
Pressurizer Level R
A 8.
Steam Generator Tressure M
R.
-9.
Steam Generator Level M
R 10.
Feedwater Flow M
R
- 11. Auxiliary 'Feodwater Flow Rate
' M' R
- 12. JRCS Subcooled Margin Monitor M
R oo aa 13.
PORV/ Safety Valve Acoustic Monitor N.A.
R Et ?t 14.
PORV Solenoid Power Indication N.A.
N.A.
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