ML20108E092
| ML20108E092 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/29/1984 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20100P367 | List: |
| References | |
| HNP-1-3980-1, NUDOCS 8412140186 | |
| Download: ML20108E092 (4) | |
Text
_
PROCEDURE DATA PACI(AGE
!A}
DOClJMENT NO: HNP -3980-1 s
SERIAL NO: R10-MPL NO:
RTYPE: G15 19 XREF:
TOTAL SHEETS: 3 FREGUENCY: Once/G Months CPMPLETED DY:
DATE COMPLETED: _
I HAVE REVIEWED THIS DATA PACI(AGE FOR COMPLETENESS AND AGAINST ACCEPTANCE CRITERI A IN ACCORDANCE WITH HNP--830, ACCEPTABLE UNACCEPTABLE REVIEWED DY: _
DATE REVIEWED:
REMARMS:
8412140186 841129
~~~
~
~~
PDR ADOCK 05000321 V
PDR u./.
g Page 1 of 3 HNP-1-3980 R10
_m_.
DATA PACKAGE 1 KINEMETRICS SMA-3 REASON FOR TEST
)
's -
(
) SURV.,
(
) MR NO.
(
) OTHER TEST PERFORMANCE
_-------__--_------------_---4--_-_---_-_--__.
STEP NO, CONDITION COMPLETED BY E 2-Key Switch to DFF E.3.a Mey Switch to TEST (CW)
E.3,b Mey Switch to CALID (CW) g E.3.c Key Switch to NAT FREG (CW)
E.3.d Key Switch to CALIB (CCW)
E.3.e Key Switch to TEST (CCW)
E,3, F Mey Switch to OFF (CCW)
E.3 9 Mey Switch to GPERATE E.4 Event Indicator White p)
SYSTEM RESTORATION INDEPENDENT VERIFICATTON REGUIRED i%j NOTE In equipment component position verifications, initia111ng a step on a procedure Data Package shall attent to the accomplish-ment of the procedure step, The step shall be initialed follow-ing completion of each separate step before proceeding to another
- step, CONDITION COMPLETED BY VERIFIED BY Check tape cassettes removed, Event Indicator Glack.
Tape cassette r e, p l a c e d,
Event Indicator 01ack, Status check tape forwarded to I & C Supervisor.
. - - - - ~ ~ - - - - - - - -..------------
Cover replaced on SMA-3.
-s
. t 8
V) t Mey switch to operate.
.--------------------- -------------------..--------------~------------
Page 2 of 3 HNP-t-3980 R10 L_
k
):
~ DATA PACKAGE l'(CONT
)-
~
(.-
' ~
~TFST RESI1.TR-1: ~
.('-
'); Acceptable-(.
) Non-Acceptable, Shift Supervisor Notified Reason-for-SNon-Acceptance / Comments 1
(
f
- n..
i-a h
a t.
(-:;,O s
~ COMPLETED BY DATE i
t t'
i.
I
?-
1 I
1 i
Page 3 of 3 HNP-1-39BO R10
f SwAv OA II.
System Details
- f.,u A.
Physical Description Figure 3.2 (1)
The term " reactor building" is nearly synonomous with " secondary containment" as one barrier in the overall radioactive material release barrier. The primary containment consists of the drywell in which the reactor vessel is located, the pressure suppression chamber, and a number of process line reinforcements. The reinforced concrete reactor vessel support structure, constructed within the primary containment, is a
not a part of either containment.
I The reactor building, of all buildings on the site, is the most essential for nuclear safety. The release of radioactive materials must be minimized under all credible circumstances.
The building design must permit operations to continue through and after any earthquake not more severe than the operating basis earthquake (OBE). The design basis earthquake (DBE) is twice as severe. Safe shutdown must be possible if it occurs.
k (Earthquake sensor recorders and annunciators are located in the control room.)
1.
The Reactor Building is basically a reinforced concrete structure, with structural steel framing which consists of the following major structural components:
o Reinforced concrete foundation mat o
Reinforced concrete floors supported by structural steel framing o
Reinforced concrete or concrete block interior walls o
Stainless steel lined reinforced concrete spent fuel pool, reactor well, steam dryer, separator storage pool, and fuel transfer canal o
HPCI room is integral with the reactor building o
Reinforced concrete exterior walls up to the refueling floor level o
Exterior walls above the refueling floor consist of structural steel columns and prefabricated concrete panels o
The reactor building is equipped with blowout panels
~
3.2-2 M