ML20078F111
| ML20078F111 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/22/1983 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078F113 | List: |
| References | |
| NUDOCS 8310070179 | |
| Download: ML20078F111 (8) | |
Text
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BALTIM0RE GAS.AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 License No. OPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated May 27, 1983, 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, 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 safei;y 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.
8310070179 830922
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DR ADOCK 05000 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-53 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 87, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$V n,
p James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications i
Date of Issuance: September 22, 1983 t
J
'o ATTACHMENT TO LICENSE AMENDMENT NO. 87 '
FACILITY OPERATING LICENSE NO. OPR-53 DOCKET NO. 50-317 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. 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.
Page
- 3/4 6-19 O
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TABLE 3.6-1 (Continued) n.
p G
CONTAINMENT ISOLATION VALVES 9;
-d PENETRATION ISOLATION ISOLATION VALVE ISOLATION O
NO.
CHANNELS ~
IDENTIFICATION NO.
FUNCTION TIME (SECONDS) b!
NA 19-1 NA E
7 78 NA Blind Flange ILRT NA NA 19-1 NA 8
SIAS A H0V-5462 Containment Normal Sump
<13 9
NA 238M3-1 Containment Spray NA p
NA 238M3-2 N,}
10 NA 238M3-1 Containment Spray NA NA 238M3-2 NA I
Purge Air Inlet
<7**
l[
SIAS B, CRS B CV-1411 (3) 17**
n a
o O.
e
t TABLE 3.6-1 n
?
g CONTAINf1ENT ISOLATION VALVES A
PENETRATION ISOLATION.
ISOLATION VALVE ISOLATION n
NO.
CilANNEL IDENTIFICATION NO.
FUNCTION TIME (SECONDSJ g
U 1A SIAS A CV-5465 R.C. and Pressurizer Sampling
<7 SIAS A CV-5466
<7 E
SIAS A CV-5467 77 SIAS B CV-5464 17 a
IB SIAS A CV-2180 Containment Vent lleader to Waste
<7 SIAS B CV-2181 Gas 17 1C SIAS A CV-506 RCP Seals Controlled Bleedoff
<7 SIAS B CV-505 17 R
Post Accident Sampling NA' m
ID NA SV-6529*
.L Liquid Return to RC Drain Tank e
i 2A SIAS A CV-515 Letdown Line
<l3 SIAS B CV-516 71 3 NA 7113 - 1
~NA NA 7M3-1 NA E
ag 2B NA CV-517 Charging Line NA g
NA CV-518 NA r+
NA CV-519 NA
=
NA SP-210M3-2 NA o
NA 210M3-2 NA
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a nc UNITED STATES NUCLEAR REGULATORY COMMISSION o
h WASHING TON. D. C. 20555 th*....J BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318' CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE 4
i Amendment No.69 License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated May 27, 1983, 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; 4
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 i
i 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.
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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:
2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 69, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION u
James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 22, 1983 O
ATTACHMENT TO LICENSE AMENDMENT NO. 69 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 t
Replace the-following page of the Appendix A Technical Specifications with the enclosed page as indicated. 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.
Page 3/4 6-19 e
9 9
---,r y.
TABLE 3.6-1 (Continued) g G
CONTAINiiENT ISOLATION VALVES H
PENETRATION ISOLATION ISOLATION VALVE ISOLATION p
NO.
CilANNELS IDENTIFICATION fl0.
FUNCTION TIME (SECONDS 1 4y 7A NA Blind Flange ILRT flA NA 19-1 NA E
- U 7B NA Blind Flange ILRT NA N
NA 19-1 NA 8
SIAS A MOV-5462 Containment Normal Sump
<13 9
NA 238M3-1 Containment Spray NA NA 238M3-2 ilA E$
10 NA 238M3-1 Containment Spray NA NA 238M3-2 NA 13 SIAS A, CRS A CV-1410 (3)
Purge Air Inlet
<7**
p SIAS B, CRS B CV-1411 (3) 57**
a E
Be O
gf %
M O
6 g
TAllLE 3.6,1 r-M CONTAIN!!ENT ISOLATION VALVES E
PENETRATION ISOLATI0fj ISOLATION VALVE ISOLATION nC NO.
CilANNEL IDENTIFICATION NO.
FUNCTION TIME (SECONDS) m 1A SIAS A CV-54 65 R.C. and Pressurizer Sampling
<7 SIAS A CV-5466 E
SIAS A CV-5467 Q
SIAS B CV-5464 m
IB SIAS A CV-2180 Containment Vent lleader to Waste
<7 SIAS B CV-2181 Gas 57 R
SIAS B CV-505
~<7 1C SIAS A CV-506 RCP Seals Controlled Bleedoff a
-7 m'
Post Accident Sampling ID NA SV-6529*
Liquid Return to RC Drain Tank NA 2A SIAS A CV-515 Letdown Line
~<13 13 SIAS B CV-516
28 NA CV-517 Charging Line NA NA CV-518 NA NA CV-519 NA NA S P-210M3-2 NA
(
NA 210M3-2 NA 4
=
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