ML20108E092

Rev 10 to Procedure Data Package HNP-1-3980-1, Kinemetrics SMA-3

ML20108E092
Person / Time
Site:	Hatch
Issue date:	11/29/1984
From:	GEORGIA POWER CO.
To:
Shared Package
ML20100P367	List: ML20100P364 ML20108E043 ML20108E045 ML20108E049 ML20108E057 ML20108E061 ML20108E066 ML20108E071 ML20108E074 ML20108E092 ML20108E098
References
HNP-1-3980-1, NUDOCS 8412140186
Download: ML20108E092 (4)

Text

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PROCEDURE DATA PACI(AGE

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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

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DATA PACKAGE 1 KINEMETRICS SMA-3

, REASON FOR TEST

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) .

( ) SURV.,

( ) MR NO.

, ( ) OTHER TEST PERFORMANCE

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_-------__--_------------_---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) -

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. 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) i

%j SYSTEM RESTORATION INDEPENDENT VERIFICATTON REGUIRED 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.

. ---------------------------------------- . - - - - ~ ~ - - - - - - - - . .------------

-s Cover replaced on SMA-3.

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V) Mey switch to operate. .

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Page 2 of 3 HNP-t-3980 R10 L_

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. - ~ DATA PACKAGE l'(CONT )- -

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~TFST RESI1.TR-1: ~ .('- '); Acceptable-( . ) Non-Acceptable, Shift Supervisor Notified _

Reason-for-SNon-Acceptance / Comments 1

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~ COMPLETED BY _ DATE i

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Page 3 of 3 HNP-1-39BO R10

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f. , II. System Details 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

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3.2-2 M