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        %    9 Duxu Powna GOMPANY 18.0. ISOJC 33189 i
9 Duxu Powna GOMPANY 18.0. ISOJC 33189 GHAHLOTrt?. N.C. 28242 i
GHAHLOTrt?. N.C. 28242
!! AL 11. TUCKER ressynon we rarasor*7 (704) 373-4531 mii tras Piusoe or <we Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i
            !! AL 11. TUCKER                                                                                                         ressynon we rarasor*7                                                                                                     (704) 373-4531 mii tras Piusoe or <we Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i                     Attention:           Ms. E. G. Adensam, Chief f                                          Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414
Attention:
Ms. E. G. Adensam, Chief Licensing Branch No. 4 f
Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414


==Dear Mr. Denton:==
==Dear Mr. Denton:==
 
My letter of August 12, 1982 transmitted a summary of the ultimate capacities of the Catawba containment vessel penetrations.
My letter of August 12, 1982 transmitted a summary of the ultimate capacities of the Catawba containment vessel penetrations.                                       Information on the purge penetration isolation valves was not available at that time. Duke is revising the specification for these valves to require that the valves maintain contain-ment integrity at the ultimate capacity of 72 psig. The vendor (Fisher Controls, Inc.) will provide Duke with analyses certifying the valves for these require-ments. Attachment 1 is a revised summary of containment penetration ultimate i                       capacities.
Information on the purge penetration isolation valves was not available at that time. Duke is revising the specification for these valves to require that the valves maintain contain-ment integrity at the ultimate capacity of 72 psig. The vendor (Fisher Controls, Inc.) will provide Duke with analyses certifying the valves for these require-ments. Attachment 1 is a revised summary of containment penetration ultimate i
j Very truly yours, l
capacities.
Hal B. Tucker ROS/php i                       Attachment cc:   Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission l
Very truly yours, j
Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. P. R. Van Doorn NRC Residert inspector Catawba Nuclear Station i
l Hal B. Tucker ROS/php Attachment i
cc:
Mr. James P. O'Reilly, Regional Administrator l
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. P. R. Van Doorn NRC Residert inspector Catawba Nuclear Station i
Mr. Robert Guild, Esq.
Mr. Robert Guild, Esq.
t                             Attorney-at-Law 314 Pall Mall l                             Columbia, South Carolina 29201 l
t Attorney-at-Law 314 Pall Mall l
i 8209230216 820914 l         PDR ADOCK 05000413
Columbia, South Carolina 29201 l
i 8209230216 820914 l
PDR ADOCK 05000413 l
?
?
A                                 PDR l
A PDR


Mr. Harold R. Denton, Director September 14, 1982 Page 2 cc: Palmetto Alliance 2135h Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 Mr. Henry A. Presler, Chairman Charlotte-Mecklenburg Environmental Coalition 943 Henley Place Charlotte, North Carolina 28207
Mr. Harold R. Denton, Director September 14, 1982 Page 2 cc: Palmetto Alliance 2135h Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 Mr. Henry A. Presler, Chairman Charlotte-Mecklenburg Environmental Coalition 943 Henley Place Charlotte, North Carolina 28207


L r.
L r.
CATAWBA fiUCLEAR STATION ULTIMATE CONTAINMEtlT CAPACITY ANALYSIS SUMitARY Ultimate Internal Location                           Pressure (PSI)                                     Criterion
CATAWBA fiUCLEAR STATION ULTIMATE CONTAINMEtlT CAPACITY ANALYSIS SUMitARY Ultimate Internal Location Pressure (PSI)
: 1. Containment Shell 72                               Nbnlinear Axisymmetric Analysis
Criterion 1.
: 2. Base Anchorage                                 81                               Concrete Shear
Containment Shell 72 Nbnlinear Axisymmetric Analysis 2.
: 3. Penetrations
Base Anchorage 81 Concrete Shear 3.
: a. Personnel Air Lock                         79                               Plastic Moment in Bulkhead
Penetrations a.
: b. Equipment Hatch                           94                               Tensile Failure of Hatch Cover Flange
Personnel Air Lock 79 Plastic Moment in Bulkhead b.
: c. Spare Penetrations                       1275                               Yield of Pipe Cap
Equipment Hatch 94 Tensile Failure of Hatch Cover Flange c.
: d. Electrical Penetrations                 > 72                               Connector Module Leakage
Spare Penetrations 1275 Yield of Pipe Cap d.
: e. Bellows Assemblies       . . .          > 72                               Manufacturer's Recommendation
Electrical Penetrations
: f. Purge Penetrations                       > 72                               Specified to Manufacturer N
> 72 Connector Module Leakage e.
e                                                                      ST e
Bellows Assemblies
R 5
> 72 Manufacturer's Recommendation f.
e
Purge Penetrations
_ - - _ _      m       - _      --  -  .      _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _}}
> 72 Specified to Manufacturer N
ST e
e R
5 e
m
-}}

Latest revision as of 20:01, 16 December 2024

Forwards Revised Summary of Containment Penetration Ultimate Capacities.Fisher Controls Will Supply Util W/Analyses Certifying Containment Integrity of Valves
ML20065C116
Person / Time
Site: Catawba  
Issue date: 09/14/1982
From: Tucker H
DUKE POWER CO.
To: Adensam E, Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8209230216
Download: ML20065C116 (3)
v • d • e


Text

,

9 Duxu Powna GOMPANY 18.0. ISOJC 33189 GHAHLOTrt?. N.C. 28242 i

!! AL 11. TUCKER ressynon we rarasor*7 (704) 373-4531 mii tras Piusoe or <we Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i

Attention:

Ms. E. G. Adensam, Chief Licensing Branch No. 4 f

Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414

Dear Mr. Denton:

My letter of August 12, 1982 transmitted a summary of the ultimate capacities of the Catawba containment vessel penetrations.

Information on the purge penetration isolation valves was not available at that time. Duke is revising the specification for these valves to require that the valves maintain contain-ment integrity at the ultimate capacity of 72 psig. The vendor (Fisher Controls, Inc.) will provide Duke with analyses certifying the valves for these require-ments. Attachment 1 is a revised summary of containment penetration ultimate i

capacities.

Very truly yours, j

l Hal B. Tucker ROS/php Attachment i

cc:

Mr. James P. O'Reilly, Regional Administrator l

U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. P. R. Van Doorn NRC Residert inspector Catawba Nuclear Station i

Mr. Robert Guild, Esq.

t Attorney-at-Law 314 Pall Mall l

Columbia, South Carolina 29201 l

i 8209230216 820914 l

PDR ADOCK 05000413 l

?

A PDR

Mr. Harold R. Denton, Director September 14, 1982 Page 2 cc: Palmetto Alliance 2135h Devine Street Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 Mr. Henry A. Presler, Chairman Charlotte-Mecklenburg Environmental Coalition 943 Henley Place Charlotte, North Carolina 28207

L r.

CATAWBA fiUCLEAR STATION ULTIMATE CONTAINMEtlT CAPACITY ANALYSIS SUMitARY Ultimate Internal Location Pressure (PSI)

Criterion 1.

Containment Shell 72 Nbnlinear Axisymmetric Analysis 2.

Base Anchorage 81 Concrete Shear 3.

Penetrations a.

Personnel Air Lock 79 Plastic Moment in Bulkhead b.

Equipment Hatch 94 Tensile Failure of Hatch Cover Flange c.

Spare Penetrations 1275 Yield of Pipe Cap d.

Electrical Penetrations

> 72 Connector Module Leakage e.

Bellows Assemblies

> 72 Manufacturer's Recommendation f.

Purge Penetrations

> 72 Specified to Manufacturer N

ST e

e R

5 e

m

-

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