ML20092N315
| ML20092N315 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/26/1995 |
| From: | Marsh L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20092N318 | List: |
| References | |
| NUDOCS 9510050257 | |
| Download: ML20092N315 (7) | |
Text
.. -
A pS 40u9 y
- a UNITED STATES j
j NUCLEAR REGULATORY COMMISSION 3
2 WASHINGTON, D.C. 20666 4001
\\...../
I BALTIMORE GAS AND' ELECTRIC COMPANY DOCKET NO. 50-317 l
CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 206 i
License No. DPR-53 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated June 2, 1995, complies with the standards and i
requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR l
Chapter I; 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 (1) 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; DI 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.
i 2.
Accordingly, the license is amended by changes to the Technical 1
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2. of Facility Operating License No. DPR-53 is hereby i
amended to read as follows:
4 9510050257 950926 4
PDR ADOCK 05000317 P
,e.,
,-n
2.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 206, 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 and j
shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMISSION bl w
Ledyard B. Marsh, Director Project Directorate I-I Division of Reactor Projects - I/II 3
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 26, 1995 O
s 4
l
l f Meu lt UNITED STATES g
s j
NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 2065M001
'+9.....,o
,1 BALTIMORE GAS AND ELECTRIC COMPANY 1
DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACTLITY OPERATING LICENSE Amendment No. 184 License No. DPR-69 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated June 2, 1995, 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.
There is reasonable assurance (1) that the activities authorizeri 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 common defense and security or to the health and safety of the public; and E.I 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:
c
4 l
2.
Technical Snecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 184, 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 and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMISSION X$3l2zA Ledyard B. Narsh, Director
~
Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 26, 1995 4
i-
+
t 4
P ATTACHMENT TO LICENSE AMENDMENTS 8tD DMENT NO. 206 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 184 FACILITY OPERATING LICENSE NO. OPR-69 DOCKET NOS. 50-317 AND 50-318 Revise Appendix A as follows:
Remove Paaes Insert Paqgi 3/4 4-6 3/4 4-6 i
i i
5
3/4.4 REACTOR C0OLANT SYSTEM 3/4.4.2 SAFETY VALVES, LIMITING CONDITION FOR OPERATION 3.4.2.1 The following pressurizer code safety valves shall be OPERABLE:
Lift
.As-Found As-Left Iglyg Settinas Tolerance Tolerance RC-200 2500 psia
+24/-1%
i 1%
RC-201 2565 psia i 2%
i 1%
APPLICABILITY: MODES 1, 2 and 3.
ACTION: With one pressurizer code safety valve inoperable, either restore the inoperable valve to OPERABLE status within 15 minutes or be in NOT SNUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
OPERASLE:$t least one of the above pressurizer code safety valves shall be 3.4.2.2 APPLICABILITY: MODES 4 and 5.
ACTION: With no pressurizer code safety valve OPERABLE, immediately suspend all operations involving positive reactivity changes and place an OPERABLE shutdown cooling loop into operation.
SURVEILLANCE REQUIREMENTS i
4.4.2 No additional Surveillance Requirements other than those required by Specification 4.0.5.
4 i;.
c i.
c Both-valves may be removed in MODE 5 provided at least one valve is replaced by a spool piece which allows the pressurizer to relieve directly.to the quench tank.
I
.CALVERT. CLIFFS - UNIT 1 3/4 4-6 Amendment No. 206
3/4.4' REACTOR C0OLANT SYSTEM 3/4.4.2 SAFETY VALVES i
i -
LIMITING CONDITION FOR OPERATION i
3.4.2.1 The following pressurizer code safety valves shall be OPERABLE:
Lift As-Found As-Left 1g]21
-Settinos Tolerance Tolerance RC-200 2500 psia
+2%/-1%
i 1%
RC-201 2565 psia i 2%
1 1%
i APPLICABILITY: MODES 1, 2 and 3.
ACTION: With one pressurizer code safety valve inoperable, either restore l
tae inoperable valve to OPERABLE status within 15 minutes or be in NOT j
SNUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1 3.4.2.2 At least one of the above pressurizer code safety valves shall be OPERABLE:
APPLICABILITY: MODES 4.and 5.
f ACTION: With no pressurizer code safety valve OPERA 8LE, immediately suspend all operations involving positive reactivity changes and place an 0PERABLE shutdown cooling loop into operation.
4 SURVEILLANCE REQUIREMENTS 4.4.2 No additional Surveillance Requirements other than those required by l
3pecification 4.0.5.
2 4
w e
3 c
Both valves may be removed in MODE 5 provided at least one valve is 4
replaced by a spool piece which allows the pressurizer to relieve directly to the quench tank.
CALVERT CLIFFS - UNIT 2 3/4 4-6 Anwndment No.184
--