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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'                                           ,
6.0 ADMINISTRATIVE CONTROLS (c)
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
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
: c.                                          li The core operating applicable        limits (e.mits               g., fuelshall                  be determined thermal mechanical such limits,that coreall thermal hydraulic limits, Emergency Core Cooling Systems (ECCS)                                                   1 limits, nuclear limits such as SDM, transient analysis limits,                                                     I and accident analysis limits) of the safety analysis are met.
(d)
: d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
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.
1 I
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.
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:
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 l
a.
: c. Inoperable Meteorolcgical Instrumentation, Specification 3.3.3.4.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
I
l c.
: e. Core Barrel Movement, Specification 3.4.11.
Inoperable Meteorolcgical Instrumentation, Specification 3.3.3.4.
: f. Fire Detection Instrumentation, Specification 3.3.3.7.
I e.
: 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.
Core Barrel Movement, Specification 3.4.11.
: h. Penetration Fire Barriers, Specification 3.7.12.
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.
: i. Steam Generator Tube Inspection Results, Specification 4.4.5.5.a and c.
J. Specific Activity of Primary Coolant, Specification 3.4.8.
J.
t;.,,,0   t.
Specific Activity of Primary Coolant, Specification 3.4.8.
t4 e Dcm Mi . O. G. M 9 Donalcl(un) to Mr. R. c. N 6 (tme),
t;.,,,0 t.
clJe4 1/ qt H, I9W, " Approve l To                         u We Osnvo fu [l<m Tieknig oe ,' n Ft a:a 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),"
t4 e Dcm Mi. O. G. M 9 Donalcl(un) to Mr. R. c. N 6 (tme),
CALVERT CLIFFS - UNIT 1                                                       6-26                 Amendment No. 199 9512120197 951207 DR     ADOCK 050       '57
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
'57


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l           ,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
l
(d) Letter from Mr. S. A. McNeil, Jr. (NRC) to                                           !
,6.0 -ADMINISTRATIVE CONTROLS (c) Letter from Mr. G. C. Creel (BG&E) to NRC Document i
!                                      Mr. G. C. Creel (BG&E), dated January 10, 1990, " Safety i                                     Evaluation Raport Approving Unit 2 Cycle 9 License 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"
Application"
                          @l) C sot inset below]
@l) C sot inset below]
!                      c.                       li The   core operating applicable    limits        (e.mits g., fuel shall themalbemechanical deteminedlimits, such that core all thermal hydraulic limits. Emergency Core Cooling Systems (ECCS)
c.
!                          limits, nuclear limits such as SDM, transient analysis limits, l                         and accident analysis limits) of the safety analysis are met, f
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
j                     d. The COLR, inclutiing any mid-cycle revisions or supplements, shall
and accident analysis limits) of the safety analysis are met, f
;                          be provided upon issuance for each reload cycle to the NRC.
j d.
l             SPECIAL REPORTS
The COLR, inclutiing any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
"            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.
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:
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.
a.
1 l                                                                                                             l 7                     e. Core Barrel Movement, Specification 3.4.11.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
: f. Fire Detection Instrumentation, Specification 3.3.3.7.
I f
: 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.
c.
: h. Penetration Fire Barriers, Specification 3.7.12.
Inoperable Meteorological Instrumentation, Specification 3.3.3.4.
: i. Steam Generator Tube Inspection Results, Specification 4.4.5.5.a                       ,
1 l
and c.
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.
: j. Specific Activity of Primary Coolant, Specification 3.4.8.
: k. Containment Structural Integrity Specification 4.6.1.6.
k.
Un s u + 3 L e H e Srm p(r. 0.G. M c on/JLyac ) % pv. a. e % % L ta),e(Ad Aq si 19 W, " byrov~l h Us<. Con vo lof;u Taln, n :~ m ;n s{ a Un i
Containment Structural Integrity Specification 4.6.1.6.
k k /%wl s:s   y - Calvd Cl;[]> bla clea Po w n P ~ f und Mo> I <" d '-
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
(TAL Mo3         M 90 s9 7 m,d M 90s99)."
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 '-
CALVERT CLIFFS - UNIT 2                       6-26                 Amendment No. 176
y (TAL Mo3 M 90 s9 7 m,d M 90s99)."
_ . - .      -      _ .        -            - , -              . . _ -}}
CALVERT CLIFFS - UNIT 2 6-26 Amendment No. 176
.. _ -}}

Latest revision as of 08:46, 13 December 2024

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  Constellation icon.png
Issue date: 12/07/1995
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20095C745 List:
References
NUDOCS 9512120197
Download: ML20095C747 (3)
v • d • e


Text

.-

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.

t;.,,,0 t.

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

'57

f ATTACHMENT (3) c r

a p

4

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Baltimore Gas and Electric Company December 7,1995

l

,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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