ML20052C239: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:__ _ _      - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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PUBLIC SERVICE SMOM STAM se ans osc.
* SMOM STAM PUBLIC SERVICE                                se ans osc .
Companyof NewHampsher e 1671 Worcester Road Framingham, Massachusetts 01701 (617) - 872 - 8100 4
Companyof NewHampsher e                       1671 Worcester Road Framingham, Massachusetts 01701 (617) - 872 - 8100 4   D April 30, 1982 SBN -264                                 ggggg,                                               1 T.F. B7.1.2                 g.                                                           -
D April 30, 1982 SBN -264
: ggggg, 1
T.F. B7.1.2 g.
7_
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MAY3                 1992w 78 n 822x a GuaaT urexarg %
MAY3 1992w 78 n x a urexar %
                                                                                    \
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rc United States Nuclear Regulatory Conmission                                                                                                 &
822 GuaaT g rc United States Nuclear Regulatory Conmission Washington, D. C. 20555 t
Washington, D. C. 20555                                                           t Attention:         Mr. Frank J. Miraglia, Chief Licensing Branch #3 Division of Licensing Re f e re nc es :   (a) Construction Permits CPPR-135 and CPPR-136, Docket No s . 50-443 and 50-444 (b) USNRC Le t te r , d a t ed Ma rc h 1, 1982, " Request for Additional Information," F. J. Miraglia to W. C. Tallman (c) PSNU Letter, dated April 2, 1982, " Response to 480 Series RAIs; (Containment Systems Branch)," J. DeVincentis to F. J. Miraglia
Attention:
Mr. Frank J. Miraglia, Chief Licensing Branch #3 Division of Licensing Re f e re nc es :
(a) Construction Permits CPPR-135 and CPPR-136, Docket No s. 50-443 and 50-444 (b) USNRC Le t te r, d a t ed Ma rc h 1, 1982, " Request for Additional Information," F. J. Miraglia to W. C. Tallman (c)
PSNU Letter, dated April 2, 1982, " Response to 480 Series RAIs; (Containment Systems Branch)," J. DeVincentis to F. J. Miraglia


==Subject:==
==Subject:==
Line 30: Line 35:


==Dear Sir:==
==Dear Sir:==
We have enclosed a response to the subject RAI which was not included in the Ref erence (c) responses.
We have enclosed a response to the subject RAI which was not included in the Ref erence (c) responses.
Very t ruly yours, YANKEE ATOMIC ELECTRIC COMPANY 4tA/J
Very t ruly yours, YANKEE ATOMIC ELECTRIC COMPANY
[g I
[g 4tA/J J. DeVincentis I
J. DeVincentis Project Manager Enclosure 8205040525 820430 PDR ADOCK 05000443 l 9bs\
Project Manager Enclosure 9
I F                     PDR
8205040525 820430 l
PDR ADOCK 05000443 I bs\\
F PDR


I-i
I-i i
* i RAI 480.13 (6.2.3)
RAI 480.13 (6.2.3)
!              Verify that all openings in the secondary containment (such as personnel doors
Verify that all openings in the secondary containment (such as personnel doors and equipment hatches) are equipped with alarms and position indicat6rs'that l
;              and equipment hatches) are equipped with alarms and position indicat6rs'that l             ' annunciate in the control. room.
' annunciate in the control. room.
l i
l i
l             RESPONSE l             All doors leading to the secondary containment enclosure area are alarmed on the i             security panel located in the central and secondary alarm stations. The equip-l             ment hatches require mechanical assistance to open them and will be controlled by administrative procedures, no alarm or position indication is provided.
l
l             FSAR 6.2.3.2 will be revised.
 
===RESPONSE===
l All doors leading to the secondary containment enclosure area are alarmed on the i
security panel located in the central and secondary alarm stations. The equip-l ment hatches require mechanical assistance to open them and will be controlled by administrative procedures, no alarm or position indication is provided.
l FSAR 6.2.3.2 will be revised.
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4 l
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a l
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                                                                ..m- _.          _  ,_      - ,-
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* SB 1&2 FSAR f.
 
: 6. The system is designed to retain functional capability while experiencing a loss of offsite power concurrent with a LOCA and any single active component failure.
SB 1&2 FSAR f.
6.2.3.2 System Design
6.
: a. Containment Enclosure The containment enclosure is a right cylindrical structure with a hemispherical dome. This structure, together with connecting penetration and equipment areas, completely encloses the containment, forming a second barrier to the escape of radioactive sources in the event of an accident. The inside diameter of the cylinder, constructed of reinforced concrete, is 158 feet. The vertical wall varies in thickness from 15 to 36 inches, and the dome is 15 inches. The inside of the dome is 5'-6" above the top of the containment structure. Design and performance data are listed in Table 6.2-82. The annular cylinder formed by the containment and the enclosure is shown on Figures 1.2-2 through 1.2-6. Codes, standards and guides applied in the design of this structure are discussed in Subsection 3.8.4.2.
The system is designed to retain functional capability while experiencing a loss of offsite power concurrent with a LOCA and any single active component failure.
: b. Features in Support of the Containment Enclosure All piping penetrating the containment structure is sealed and
6.2.3.2
(-                anchored at the containment liner plate, and at the containment
 
>                      enclosure, in such a way as not to be overstressed by thermal or seismic-induced motion. Electrical penetrations are sealed and anchored at the containment liner plate.
===System Design===
The containment recirculation sump lines are enclosed in a sleeve which extends out to a vessel which encloses the first isolation
a.
'                      valve outside the containment. This enclosure serves to contain any leakage from the sump line and first isolation valve.
Containment Enclosure The containment enclosure is a right cylindrical structure with a hemispherical dome. This structure, together with connecting penetration and equipment areas, completely encloses the containment, forming a second barrier to the escape of radioactive sources in the event of an accident. The inside diameter of the cylinder, constructed of reinforced concrete, is 158 feet. The vertical wall varies in thickness from 15 to 36 inches, and the dome is 15 inches. The inside of the dome is 5'-6" above the top of the containment structure. Design and performance data are listed in Table 6.2-82.
Provisions are made to test, initially and periodically, the sump
The annular cylinder formed by the containment and the enclosure is shown on Figures 1.2-2 through 1.2-6.
  -                    line and valve enclosure by pressure decay or other 10CFR50, Appendix J, suggested methods.
Codes, standards and guides applied in the design of this structure are discussed in Subsection 3.8.4.2.
The containment enclosure isolation features are discussed in Subsections 9.4.6.2 and 6.5.1.                 g ggy All personnel doors and equipment hatches i the containment enclosure are under administrative control. They are provided with position _ indicators and alarms having rendout and alarm capability g the g a     ~ ~ - ' ' ::c. These doorways and hatches must be closed to insure a negative pressure in the containment enclosure.
b.
m~           fff/MMY AND scconD/?gf
Features in Support of the Containment Enclosure
(                                       /fL.MM GTA DsNs 6.2-57}}
(-
All piping penetrating the containment structure is sealed and anchored at the containment liner plate, and at the containment enclosure, in such a way as not to be overstressed by thermal or seismic-induced motion. Electrical penetrations are sealed and anchored at the containment liner plate.
The containment recirculation sump lines are enclosed in a sleeve which extends out to a vessel which encloses the first isolation valve outside the containment. This enclosure serves to contain any leakage from the sump line and first isolation valve.
Provisions are made to test, initially and periodically, the sump line and valve enclosure by pressure decay or other 10CFR50, Appendix J, suggested methods.
The containment enclosure isolation features are discussed in Subsections 9.4.6.2 and 6.5.1.
g ggy All personnel doors and equipment hatches i the containment enclosure are under administrative control. They are provided with position _ indicators and alarms having rendout and alarm
~ ~ - ' '
These doorways and hatches capability g the g a
::c.
must be closed to insure a negative pressure in the containment enclosure.
m~
fff/MMY AND scconD/?gf
(
/fL.MM GTA DsNs 6.2-57
-}}

Latest revision as of 07:47, 18 December 2024

Forwards Response to Containment Sys Branch Request for Addl Info 480.13,supplementing Util 820402 Response.All Doors Leading to Secondary Containment Encl Area Alarmed on Security Panel in Central & Secondary Alarm Stations
ML20052C239
Person / Time
Site: Seabrook  NextEra Energy icon.png
Issue date: 04/30/1982
From: Devincentis J
PUBLIC SERVICE CO. OF NEW HAMPSHIRE, YANKEE ATOMIC ELECTRIC CO.
To: Miraglia F
Office of Nuclear Reactor Regulation
References
SBN-264, NUDOCS 8205040525
Download: ML20052C239 (3)
v • d • e


Text

__ _ _

PUBLIC SERVICE SMOM STAM se ans osc.

Companyof NewHampsher e 1671 Worcester Road Framingham, Massachusetts 01701 (617) - 872 - 8100 4

D April 30, 1982 SBN -264

ggggg, 1

T.F. B7.1.2 g.

7_

MAY3 1992w 78 n x a urexar %

\\

822 GuaaT g rc United States Nuclear Regulatory Conmission Washington, D. C. 20555 t

Attention:

Mr. Frank J. Miraglia, Chief Licensing Branch #3 Division of Licensing Re f e re nc es :

(a) Construction Permits CPPR-135 and CPPR-136, Docket No s. 50-443 and 50-444 (b) USNRC Le t te r, d a t ed Ma rc h 1, 1982, " Request for Additional Information," F. J. Miraglia to W. C. Tallman (c)

PSNU Letter, dated April 2, 1982, " Response to 480 Series RAIs; (Containment Systems Branch)," J. DeVincentis to F. J. Miraglia

Subject:

Response to RAI 480.13; (Containment Systems Branch)

Dear Sir:

We have enclosed a response to the subject RAI which was not included in the Ref erence (c) responses.

Very t ruly yours, YANKEE ATOMIC ELECTRIC COMPANY

[g 4tA/J J. DeVincentis I

Project Manager Enclosure 9

8205040525 820430 l

PDR ADOCK 05000443 I bs\\

F PDR

I-i i

RAI 480.13 (6.2.3)

Verify that all openings in the secondary containment (such as personnel doors and equipment hatches) are equipped with alarms and position indicat6rs'that l

' annunciate in the control. room.

l i

l

RESPONSE

l All doors leading to the secondary containment enclosure area are alarmed on the i

security panel located in the central and secondary alarm stations. The equip-l ment hatches require mechanical assistance to open them and will be controlled by administrative procedures, no alarm or position indication is provided.

l FSAR 6.2.3.2 will be revised.

l' l

4 l

a l

i l-l i

..m-

SB 1&2 FSAR f.

6.

The system is designed to retain functional capability while experiencing a loss of offsite power concurrent with a LOCA and any single active component failure.

6.2.3.2

System Design

a.

Containment Enclosure The containment enclosure is a right cylindrical structure with a hemispherical dome. This structure, together with connecting penetration and equipment areas, completely encloses the containment, forming a second barrier to the escape of radioactive sources in the event of an accident. The inside diameter of the cylinder, constructed of reinforced concrete, is 158 feet. The vertical wall varies in thickness from 15 to 36 inches, and the dome is 15 inches. The inside of the dome is 5'-6" above the top of the containment structure. Design and performance data are listed in Table 6.2-82.

The annular cylinder formed by the containment and the enclosure is shown on Figures 1.2-2 through 1.2-6.

Codes, standards and guides applied in the design of this structure are discussed in Subsection 3.8.4.2.

b.

Features in Support of the Containment Enclosure

(-

All piping penetrating the containment structure is sealed and anchored at the containment liner plate, and at the containment enclosure, in such a way as not to be overstressed by thermal or seismic-induced motion. Electrical penetrations are sealed and anchored at the containment liner plate.

The containment recirculation sump lines are enclosed in a sleeve which extends out to a vessel which encloses the first isolation valve outside the containment. This enclosure serves to contain any leakage from the sump line and first isolation valve.

Provisions are made to test, initially and periodically, the sump line and valve enclosure by pressure decay or other 10CFR50, Appendix J, suggested methods.

The containment enclosure isolation features are discussed in Subsections 9.4.6.2 and 6.5.1.

g ggy All personnel doors and equipment hatches i the containment enclosure are under administrative control. They are provided with position _ indicators and alarms having rendout and alarm

~ ~ - ' '

These doorways and hatches capability g the g a

c.

must be closed to insure a negative pressure in the containment enclosure.

m~

fff/MMY AND scconD/?gf

(

/fL.MM GTA DsNs 6.2-57

-

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