ML20097E346

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Amends 210 & 188 to Licenses DPR-53 & DPR-69,respectively, Adding Convolution Analytical Technique for Analysis of Pretrip MSLB Event
ML20097E346
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 02/05/1996
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20097E350 List:
References
NUDOCS 9602130464
Download: ML20097E346 (7)
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Text

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k UNITED STATES g

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20066-0001 o%...../

BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-317 CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 210 License No. DPR-53 1.

The Nuclear Regulatory Commission (the Commission) has found that:

j A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated December 7, 1995, 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;

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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 activitie.s 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.

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:

9602130464 960205 PDR ADOCK 05000317 P

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. 2.

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 210, 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 CO M ISSION I-p%.

Y Ledyard B. Narsh, Director Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 5, 1996

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4 UNITED STATES NUCLEAR REGULATORY COMMISSION E

WASHINGTON, D.C. 20eeHo01

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BALTIM0RE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR POWER PLANT. UNIT NO. 2 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 188 License No. DPR-69 1.

The Nuclear nequlatory Commission (the Commission) has fourid that:

A.

The application for amendment by Baltimore Gas and Electric Company (the licensee) dated December 7, 1995, 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 (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; 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.

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:

. 4 2.

Technical Snacifications The Technical Specifications contair.ed in Appendices A and B, as revised through Amendment No. 188, 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.

l FOR THE NUCLEAR REGULATORY COMilSSION h

4 Ledyard B. Marsh, Director Y roject Directorate I-l P

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specificatioris Date of Issuance: February 5, 1996 s

ATTACHMENT TO LICJMSJ_Bif3QMEMIS AMENDMENT NO 210 FACILITY OPERATING LICENSE NO. DPR-53 AMENDMENT NO. 188 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NOS. 50-317 AND 50-318 Revise Appendix A as follows:

Bg nve Paaes Insert Paaes 6-26 6-26 1

9

i 6.0 ADMINISTRATIVE CONTROLS 4

(c)

Letter from Mr. G. C. Creel (BG&E) to NRC Document l

Control Desk, dated February 7,1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket 50-318. Request for Amendment, Unit 2 Ninth Cycle License Application" i

i (d)

Letter from Mr. S. A. McNeil, Jr. (NRC) to 1

Mr. G. C. Creel (BG&E), dated January 10, 1990, " Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" l

i (42)

Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995. " Approval to Use

.i i

Convolution Technique in Main Steam Line Break Analysis -

Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 l

(TAC Nos. M90897 and M90898) c.

The core operating limits shall be detemined such that all a)plicable limits (e.g., fuel thermal mechanical limits, core i

tiemal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met, d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

j SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report.

These reports shall be submitted covering the activities identified below 1

pursuant to the requirements of the applicable reference specification:

a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

J c.

Inoperable Meteorological Instrumentation, Specification 3.3.3.4.

e.

Core Barrel Movement, Specification 3.4.11.

f.

Fire Detection Instrumentation, Specification 3.3.3.7.

g.

Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, 3.7.11.4, and 3.7.11.5.

h.

Penetration Fire Barriers, Specification 3.7.12.

1.

Steam Generator Tube Inspection Results Specification 4.4.5.5.a and c.

J. Specific Activity of Primary Coolant, Specification 3.4.8.

I CALVERT CLIFFS - UNIT 1 6-26 Amendment No. 210 1

t

I 6.0 ADMINISTRATIVE CONTROLS (c)

Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7,1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket 50-318. Request for Amendment, Unit 2 Ninth Cycle License Application" (d) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990 " Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" (42)

Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995, " Approval to Use Convolution Technique in Main Steam Line Break Analysis -

Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 (TAC Nos. M90897 and M90898) l The core operating (e.mits shall be detemined such that all li c.

applicable limits g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report.

These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a.

ECCS Actuation, Specifications 3.5.2 and 3.5.3.

c.

Inoperable Meteorological Instrumentation Specification 3.3.3.4.

e.

Core Barrel Movement, Specification 3.4.11.

f.

Fire Detection Instrumentation, Specification 3.3.3.7.

g.

Fire Suppression Systems, Specifications 3.7.11.1, 3.7.11.2, 3.7.11.3, 3.7.11.4, and 3.7.11.5.

h.

Penetration Fire Barriers, Specification 3.7.12.

i 1.

Steam Generator Tube Inspection Results, Specification 4.4.5.5.a and c.

j. Specific Activity of Primary Coolant, Specification 3.4.8.

k.

Containment Structural Integrity, Specification 4.6.1.6.

CALVERT CLIFFS - UNIT 2 6-26 Amendment No. 188

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