., . 4) .PLANT OPERATIONS MANUAL

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| Volume 05 05-S-02-VI-3!

Section 02 Revision: 10

Date: 3-22-82

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OFF-NORMAL EVENT PROCEDURE,

EARTHQUAKE

SAFETY RELATED/

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! Prepared: 1 N - .". - . . ,

/ (Reviewed: / :. . r

Nuclear Plant Quality Superintendent echnical Review'

Reviewed: O#'

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~ Oper ions Superintendent

<d -|Approved:~

' Assistant Plant Manager

PSRC: , f fL42.4.( } V4 - - ,s* E!

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List of Effective Pages:

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CRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

| Tit le: Earthquake |No.: 05-S-02-VI-3 lRevision: 10 iPage: 1 |,

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1.0 PURPOSE / DISCUSSION

! 1.1 This procedure outlines the steps to be taken to place the plant in asafe condition if an earthquake should occur.

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1.2 The Emergency Plan should be initiated in accordance with EPP 10-S-01-1,if one or more of the Emergency Action Levels is exceeded or is likely to

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1.3 Based on the historical data and regional and local geologic structural'

features, the Safe Shutdown Earthquake (SSE) limit is 0.15g and the.

Operating Basis Earthquake (OBE) Limit is about 0.75g. Southern UnitedStates earthquakes are generally infrequent and characterized by lowi

magnitudes and intensity. Plant seismic design requirements areclassified as Seismic Class I or II. Seismic Class I structures, systemand components are essential for a safe plant shutdown. Seismic Class IIstructures, systems and components, if failed, will not result in releaseof radiation in excess of 10 CFR 100 limits but are required forcont inued plant operation and are vulnerable to an earthquake of lower;

seismic intensity than that requiring a plant shutdown. In the event anOBE limit is indicated, an immediate controlled plant shutdown should beinit iat ed.

(} In the event of an earthquake, the Seismic Monitoring System alarms at- seismic intensity limits and records the seismic event vibratory ground

motions and the resultant responses of selected Seismic Class Istructures, systems and components (Refer to Table 2). This recorded

i data will be retrieved af ter the earthquake, evaluated, and compared withthose used for plant design.

The Seismic Monitoring System consists of seismic triggers and switches,

| strong motion accelerometers and accelerographs (SMA), magnetic-tapeseismic cassette recorders, playback and strip chart plot t inginstruments on panel SH13-P856, and remote peak recording accelerographs.

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The seismic triggers initiates STRONG MOTION ACCELEROMETER SYSTEMACTIVATION alarm, yellow EVENT ALARM light, EVENT INDICATOR flag andstarts all 5 SMA cassette recorders at a seismic intensity of 0.01gaccelerat ion. As the seismic intensity increases , the Containment andDrywell OBE and SSE seismic switches initiate their respect'ive alarms astheir seismic horizontal and vertical component setpoints are exceeded(Refer to Table 1)..

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{ GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

| Title: Earthquake (No.: 05-S-02-VI-3 | Revision: 10 (Page: 2 |

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Ii 2.0 SYMPTOMS

k 2.1 If the seismic event intensity exceeds 0.01g, one or both of the SeismicTriggers will initiate:

2.1.1 STRONG MOTION ACCELEROMETER SYSTEM ACTIVATION Alarm on Panel~

SH13-P856.

2.1.2 Start of all 5 SMA cassette tape recorders.

2.1.3 EVENT INDICATOR flag changes from black to white (must be manually-

I r'es et when recorder cassettes are renewed).

2.1.4 EVENT ALARM yellow light is ON (will go 0FF when seismic event.

intensity decreases below .0lg on both seismic triggers). j

2.2 The following alarms will be received cn panel SH13-P856 as seismicintensity exceeds the OBE and eventually SSE setpoints of the 4 seismicswitches (see Table 1):

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2.2.1 CONTAINMENT OPERATING BASIS EARTHQUAKE.

([] 2.2.2 DRWELL OPERATING BASIS EARTHQUAKE

2.2.3 CONTAINMENT SAFE SHUTDOWN EARTHQUAKE

'2.2.4 DRWELL SAFE SHUTDOWN EARTHQUAKE

2.3 Moderate to severe oscillations in plant and surrounding structures.

2.4 A severe earthquake may result in a Turbine trip and/or Reactor Scram.j

3.0 AUTOMATIC ACTIONSf

3.1 With at least one of the two Seismic Triggers indicating greater than,'

0.Olg acceleration, all 5 Seismic Monitoring System cassettemagnetic-tape recorders start and record the seismic acceleration data

| from the Strong Mot ion Acceldrometers (SMA) given in Table 1.|

3.2 The self powered triaxial permanent Peak Recording Accelerographs (PRA)record peak seismic event acceleration data (see Table 2).

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GRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDUREi

| Title: Earthquake lNo.: 05-S-02-VI-3 IRevis ion: 10 |Page: 3 |'

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j 4.0 IMMEDIATE OPERATOR ACTION

I 4.1 If a seismic event has occured and has activatId any c' ntrol room seismice

| alarm, activate the Emergency Plan in accordance with EPP 10-S-01-1.'

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I 4.2 If the seismic event has. exceed either the safe shutdown or operatingI basis earthquake as determined by the annunciators in 2.2 above, or if

the seismic event has damaged any Category I structures, systems, orcomponents, immediately proceed to place the plant in cold shutdown at

! the maximum allowed rated per 101 03-1-01-3, Plant Shutdown,i

f 5.0 SUBSEQUENT ACTION

| 5.1 If the seismic event has not initiated either the CONTAINMENT OPERATING', BASIS EARTHQUAKE or DRYWELL OPERATING BASIS EARTHQUAKE alarms, perform

the following: '#1

: 5.1.1 Exercise all CRD Mechanisms in accordance with surveillance testI 06-0P-1C11-W-0001.i' 5.1.2 Perform the Emergency Diesel Generator Functional Tests inI accordance with 06-0P-1P75-M-0001, 06-OP-1P75-M-0002, and>

{ ()) 06-0P-1P81-M-0002..

i 5.1.3 Perform the Plant AC and DC Electrical Power Distribution Weekly'

! Lineup in accordance with 06-0P-1R20-W-0001,e

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5.1.4 Check and evaluate plant parameters for abnormal changes or.

condit ions. The following checks and evaluations give someindication of the nature, extent , and location of the earthquake

j damage:..

a. Check major plant variables: Control Rod positions, reactor'

power and water level, area and process radiation monitors,feedwater and steam flows, generator load, condenser vacuumand turbine generator vibration and bearing temperatures. ' ,

b. Check plant annunciator panels for abnormal condit ions.

c. Check the off gas radiation monitors. An increase inradiation level is an indication of increasing fuel leaks or

| of Of f Gas System problems.!l

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GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE,

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d. Check of f gas flow. A large inc rease in of f gas flowindicaces increased air in-leakage probably due to failure ofcondenser, air ejector, or the connected systems and pipingnormally under vacuum.

e. Check running equipment for any spurious trips.

f. Check the leak detection system for indications of leaks.

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5.1.5 A comprehensive physical inspection shall be made of the plantwith particular attention paid to the following systems:

a. Emergency Core _Coolins. Systems including the Condensate ,

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Storage Tank !?,

b. SLC tanks and associated piping,

f c. Spent fuel pool level and liner leak detection system!! d. Liquid and gaseous waste disposal systemi (j)! e. Component cooling water system.

f. Secondary portion of the plant including batteries , generatori

| ' hydrogen and methane supply systems, and main turbine and feed! pump lube oil systems'

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5.2 If the seismic event has exceeded either the CONTAINMENT SAFE SHUTDOWN,

EARTHQUAKE or DRYWELL SAFE SHUTDOWN EARTHQUAKE, the plant shall not be

|| returned to service until an evaluation has been made by the Plant

{, Manager.

5.3 Any observed seismic damage to the plant shall be documented so that it;

| can be related to the intensity of the earthquake. ;

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GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE's

| Title: Earthquake |No.: 05-S-02-VI-3 | Revis ion: 10 |Page: 5 |'

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j TABLE 1,

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| Seismic Trigger | | | |

| Device No. I Setpoint | . . Description | Loc at ion |.

| 1 i Unit 1 Containment i Exterior Cntet , Aux |'

|SC85-XS N006 1 0.0lg | Base Slab . - - I . Bld g , South, El. 93'l} | | | Unit 1 Drywell Wallt Exterior Drwl Wall, |

t ISC85-XS-N007 | 0.Olg | | Southwest, El. 140' |i ?

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| | Seismic Switch | Setpoint | | |

{ | Device No. I Horiz. IVerticall Description | Loc at ion |

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|SC85-XS-N008 |0.20g |0.25g IUnit 1 Containment | Exterior Cntmt, Aux # |

i |(SSE) | | | Base Slab IBldg South, E1. 93' |

I I I I I |.''|SC85-XS-N009 |0.llg |0.12g | Unit 1 Containment | Exterior Cntmt, Aux |

|(OBE) | | | Base Slab I Bldg South , El. 93' |j.; | i i i i 1

. |SC85-XS-N010 10.32g |0.25g | Unit 1 Drywell Wall | Exterior Drwl Wall, I

j (_j |(SSE) l | | | Southwest, El. 140' |i

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|SC85-XS-N011 |0.17g |0.12g | Unit 1 Drywell Wall | Exterior Drwl Wall, |*

|(OBE) | |- | | Southwest, E1.-140' |

I | Strong Motion i SMA i .| |

| Accelerometer | Recorder | Description | Location |<

' IDevice No. I | | |

| | | lExterior Cntmt , Aux Bldg |

|SC85-XE-N001 | XR-R601 | Unit 1 Cntet Base Slab | So uth , El . 93 ' I

.| | Exterior Drwl Wall, I;SC85-XE-N002 | XR-R602 Unit 1 Drywell Wall | So uthwe s t , El. 140' |

| | | |SGTS Fitr Train A Support ||SC85-XE-N003 1 XR-R603 I Unit 1 Aux Bldg |E1. 154' l

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|SX85-XE-N004 | XR-R604 | SSW Pumphc,ose A | Behind LC25 BAS , E1. 133' |

| | | |Between Rdwst Bldg, Unit IlISC85-XE-N005 | XR-R605 l Site Free Field |Clg Twr and Warehouse, |

| | | |E1. 132' |

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GRAND CULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE

ITitle: Earthquake INo.: 05-S-02-VI-3 | Revision: 10 (Page: 6 |

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; TABLE 2

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I | Accelerograph | Description | Location |

| Device No. |- I - |

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| SC85-XR-R001 | Unit 2 Containment Base Slab | (Later) 1.

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| SC85-XR-R002 | Unit 2 Drywell Wall I (Later) |'

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| SC85-XR-R003 I Unit 2 Aux Bldg I (Later) |

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l~SSW Pumphouse B ISSW Pump House B" || SC85-XR-R004

1 SC85-XR-R006A | Unit 1 Aux' Blda Base Slab 193' El.~ ~ ' ~ ~

|| _ .| _ lAux. Bldg. Northwest ~ l

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i I i e || SC85-XR-R006B | Unit 2 Aux Bldg Base Slab | (Later) |

| | | South Side ot Contain- || SC85-XR-R005A | Unit 1 Containment Dome (exterior) | ment Dome 208' El. |

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| SC85-XR-R005B i Unit'2' Containment Dome" (eitterior) | (Later) |~

| | | West- End of Diesel Gen.]J | SC85-XR-R007A I Unit 1 Standby Diesel Generator 11 1133' El. |-

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| SC85-XR-R007B | Unit 2 Standby Diesel Generator 21 l (Later) |

| | IH.P. Area Storage Room || SC85-XR-R008 ~l ~ Control Bldg Base Slab ~"'ICont'rol Bldg ~ 93'~El. |

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| SC85-XR-R600 | Control Room IPanel SH13-P856 |

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| IC85-XR-R010 | Unit 1 Reactor Vessel Support IVessel Support |,

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I I~ ~ - | Re' ~irc ~ Pipihi ~ ~~ "~~ ~ l| "1C8 5-XR-R011~ ~ l' Unit!'l ' Reactor Recird' Pip'ing' c

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IMain' Steam' Piping |.-

| I C85-XR-R0'12 ~^1~ Unit l'Maih~ Steam Piping| .

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| IC85-XR-R013 | Unit 1 LPCS Piping |LPCS Piping |

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|HPCS Piping || IC85-XR-R014 | Unit 1 HPCS Piping| 1 I I

| 2C85-XR-R010 | Unit 2 Reactor Vessel Support |(LATER) {

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| 2C85-XR-Roll | Unit 2 Reactor Recire Piping |(LATER) |

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1 2C85-XR-R012 | Unit 2 Main Steam Piping |(LATER) |

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| 2C85-XR-R013 | Unit 2 LPCS Piping l(LATER) |

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{, | 2C85-XR-R014 | Unit 2 HPCS Piping |(LATER) |

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