ML20095C747

Proposed Tech Spec to Add Analysis Technique to List of Approved Core Operating Limits Analytical Methods in TS for Plant

ML20095C747
Person / Time
Site:	Calvert Cliffs
Issue date:	12/07/1995
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20095C745	List: ML20095C742 ML20095C747
References
NUDOCS 9512120197
Download: ML20095C747 (3)

Text

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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' i

(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" (il d L se t inwfbdowJ The core operating (e.mits shall be determined 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.

l c.

Inoperable Meteorolcgical Instrumentation, Specification 3.3.3.4.

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

J.

Specific Activity of Primary Coolant, Specification 3.4.8.

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t4 e Dcm Mi. O. G. M 9 Donalcl(un) to Mr. R. c. N 6 (tme),

clJe4 1/ q H, I9W, " Approve l To We Osnvo fu [l<m Tieknig oe,' n Ft a:a t

u S { a,n L :n.a break ik s;> - Calvu f cl; f f > hivelue Po w n P in i, vo/f do s. ( cud 1 LTAL Aos. M 909 7 7 cd M 9G899),"

CALVERT CLIFFS - UNIT 1 6-26 Amendment No. 199 9512120197 951207 DR ADOCK 050

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Baltimore Gas and Electric Company December 7,1995

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,6.0 -ADMINISTRATIVE CONTROLS (c) Letter from Mr. G. C. Creel (BG&E) to NRC Document i

Control Desk, dated February 7,1989. "Calvert Cliffs i-Nuclear Power Plant Unit No. 2; Docket 50-318. Request' l

for Amendment, Unit 2 Ninth Cycle License Application" s

(d) Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10, 1990, " Safety i

Evaluation Raport Approving Unit 2 Cycle 9 License i

Application"

@l) C sot inset below]

c.

The core operating (e.mits shall be detemined such that all li applicable limits g., fuel themal mechanical limits, core thermal hydraulic limits. Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, l

and accident analysis limits) of the safety analysis are met, f

j d.

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

l 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.

I f

c.

Inoperable Meteorological Instrumentation, Specification 3.3.3.4.

1 l

l 7

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. 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.

Un s u + 3 L e H e Srm p(r. 0.G. M c on/JLyac ) % pv. a. e % % L ta),e(Ad si 19 W, " byrov~l h Us<. Con vo lof;u Taln, i

n :~ m ;n s{ a Un Aq k k /%wl s:s - Calvd Cl;[]> bla clea Po w n P ~ f und Mo> I <" d '-

y (TAL Mo3 M 90 s9 7 m,d M 90s99)."

CALVERT CLIFFS - UNIT 2 6-26 Amendment No. 176

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