ML20196J672
ML20196J672 | |
Person / Time | |
---|---|
Site: | Calvert Cliffs ![]() |
Issue date: | 12/08/1998 |
From: | Bajwa S NRC (Affiliation Not Assigned) |
To: | |
Shared Package | |
ML20196J676 | List: |
References | |
NUDOCS 9812100165 | |
Download: ML20196J672 (7) | |
Text
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S UNITED STATES g
.j NUCLEAR REGULATORY COMMISSION
'2 WASHINGTON, D.C. 20066-0001 o
A BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO.1 AMENDMENT TO FTCILITY OPERATING LICENSE Amendment No. 229 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 li~ 1,asee) dated October 16,1998, 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 wie. the application, the provisions of the Act, and the rules and regulations of the Commission; l
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 amendment will not be inimical to the common defense and security or to the health and safety of the public; and l
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.
l 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 i
Operating License No. DPR-53 is hereby amended to read as follows:
l l
i 9812100165 981208 PDR ADOCK 05000317 P
2-2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 229, 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 REQULATORY COMMISSION Q
l' S. Si gh Bajwa, Director y Project Directorate 1-1 l
Division of Reactor Projects - l/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 8, 1998
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k UNITED STATES
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g Ig NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20665 0001 49*****,d BALTIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 204 License No. DPR-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Baltimore Gas and Electric Company (the licensee) dated October 16,1998, 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 safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this arnendment 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.
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:
l 2-2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 204, are herebyincorporated 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 COMMISSION
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S. Si gh Bajwa, Director Proje Directorate 1-1 Divisi of Reactor Projects - Ih!
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
December 8, 1998
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ATTACHMENTTO LICENSE AMENDMENTS AMENDMENT NO. 2 2 9 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 204 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 i
Revise Appendix A as follows:
Remove Paoes Insert Paoes I
3.3.1 -11 3.3.1 - 11 3.3.2 - 1 3.3.2 - 1 i
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- Pages that did not change but are overleaf l
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1
RPS Instrumentation-Operating
(
3.3.1 l
Table 3.3.1-1 (page 3 of 3)
Reactor Protective System Instrumentation l
SURVEILLANCE FUNCTION MODES REQUIREMENTS ALLOWABLE VALUE 9b. Asymmetric Steam 1, 2 SR 3.3.1.1 s 135 psid Generator Transient SR 3.3.1.4 (ASGT)(b)
SR 3.3.1.7 SR 3.3.1.8 SR 3.3.1.9
- 10. Loss of Load.)
Id I')
SR 3.3.1.6 NA I
I')
Bistable trip unit may be bypassed when NUCLEAR INSTRUMENT POWER is <
l 1E-4% RTP or > 12% RTP. Bypass shall be automatically removed when j
l NUCLEAR INSTRUMENT POWER is 2 1E-4% RTP and < 12% RTP.
l (b)
Bistable trip unit may be bypassed when NUCLEAR INSTRUMENT POWER is <
1E-4%.
Bypass shall be automatically removed when NUCLEAR INSTRUMENT POWER is 2 1E-4% RTP.
During testing pursuant to LC0 3.4.16, trips may be bypassed below 5% RTP.
"I Bistable trip unit may be bypassed when steam generator pressure is
< 785 psig.
Bypass shall be automatically removed when steam generator pressure is 2 785 psig.
Id)
Bistable trip unit may be bypassed when NUCLEAR INSTRUMENT POWER is <
15% RTP.
Bypass shall be automatically removed when NUCLEAR INSTRUMENT POWER is 215% RTP.
I'I Trip is only applicable in MODE 1, NUCLEAR INSTRUMENT POWER 215% RTP.
l IU CHANNEL CHECK only applies to Wide Range Logarithmic Neutron Flux l
Monitor.
(8)
The Reactor Coolant Flow-Low allowable value shall be 2. 95% for Unit 2 only, through Cycle 12.
1 CALVERT CLIFFS - UNIT 1 3.3.1-11 Amendment No. 229 CALVERT CLIFFS - UNIT 2 Amendment No. 204
RPS Instrumentation-Shutdown 3.3.2 3.3 INSTRUMENTATION 3.3.2 Reactor Protective System (RPS) Instrumentation-Shutdown LC0 3.3.2 Four Rate of Change of Power-High RPS bistable trip units, associated measurement channels, and automatic bypass removal features shall be OPERABLE.
APPLICABILITY:
MODES 3, 4, and 5, with any reactor trip circuit breakers closed and any control element assembly capable of being withdrawn.
NOTE----------------------------
Bistable trip units may be bypassed when NUCLEAR INSTRUMENT l
POWER is < IE-4% RTP. Bypass shall be automatically removed when NUCLEAR INSTRUMENT POWER is 2 1E-4% RTP.
l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One Rate of Change of A.1 Place affected I hour Power-High bistable bistable trip unit in trip unit or bypass or trip.
associated measurement channel AND inoperable.
A.2.1 Restore affected 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> bistable trip unit and associated measurement channel to OPERABLE status.
OB CALVERT CLIFFS - UNIT 1 3.3.2-1 Amendment No. 229 CALVERT CLIFFS - UNIT 2 Amendment No. 204
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