ML20210T572

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Rev 2 to Off-Normal Instruction ONI-D51, Earthquake (Unit 1). Supporting Documentation Encl
ML20210T572
Person / Time
Site: Perry, 05000000
Issue date: 08/19/1985
From: Falls R
CLEVELAND ELECTRIC ILLUMINATING CO.
To:
Shared Package
ML20195C722 List:
References
FOIA-86-91 ONI-D51-01, ONI-D51-1, NUDOCS 8605300686
Download: ML20210T572 (12)


Text

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OM4B: ONI-D51 Page: i Rev.: 2 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT OPERATIONS MANUAL Off-Normal Instruction TITLE: EARTHQUAKE (UNIT 1)

REVISION: 2 EFFECTIVE DATE: 8/27/85 4

FNPP ~

. PERRY PLANT DEPARTMENT ,

CONTROLLED COPY  ;

No. O g 3 oirE PREPARER: Robert G. Falls gg REVI NER: ,

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PORC MEETING NO.: 85-62 7/25/85

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OM4B: ONI-D51 Page: 11

  • Rev.: 2 Earthquaka ONI-D51 Table of Contents

{ Section Title h i

1.0 INDICATIONS 1 1.1 Annunciator Alarms 1 1.2 Changes in Plant Operating Parameters 1 l 1. 3 - -

Other Symptome 1 i

2.0 , AUTCBIATIC ACTIONS . . . 1 3.0 DOSDIATE ACTIONS 2 4.0 SUPPLEMENTAL ACTIONS 2 I 5.0 ATTACMENTS 4,

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m OM4B: ONI-D51 i Page: 111 Rev.: 2 1

10CFR50.59 Applicability Check Yes No ,

I l Is there a change to the plant as described in ~ _ [

the FSAR? , 7 : q ,, . , _ j , 7, Is there a change to a procedure / instruction as /

,3 ,

described in the FSART Is there a test or experiment not described in v/

! the FSAR?

  • Is there a change to the Technical Specifi- v/

j cations?

1 (If yes, perform a 10CFR50.59 Safety Evaluation per PAP-0305)  !

k j^ Applicability Checdb k 4

Performed By: ,b NJ Date: T\dk .

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SCOPE OF REVISION:

1 -

' l Rev. 2 - Revised in entirety including: ,

1. Added 1.3.

1

2. Defined OBE & SSE under 1.0.  ;

i 3. Hoved step to shutdown plant' to 4.0. i j 4. Converted caution on radiation requirements into a step. l i

5. Added step checking M29, various plant parausters, and I l completion of SVI D51-T0279, T0289A, T0295, T0304A &  :

j T5370. -

i

0. Reworded reference to EPI-A1. .
7. Reworded Steps 3.0.1 and 4.0.9.  !

i

8. Added requirements for recovery of magnetic tapes and l l N etched event cards.  ;
9. Deleted 4.0.1 and renumbered subsequent steps.
10. Rev bare not included due to the extensive effect of this  !

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OM45: ONI-D51 Page: 1 Rev.: 2 Earthquake . :. -

1.0 INDICATIONS ,

Evaluations of regional and local geological features in conjunction with historical data have resulted in. . ths following:

  • - . . we p w: ,

Operating Basis Earthquake (OBE) is .053 on the vertical axis  !

and .075g on the horizontal axis, i Safe Shutdown Earthquake (SSE) is .13 on the vertical axis and '

.15g on the horizontal axis.

1.1 Annunciator Alarms i

1. SEISMIC AIARM P969. .

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2. SEISMIC HONITOR TRBL. ..

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'1.2 ChangesinPlantOperatingParameters(,, ,

m 1. Varies depending on severity of earthquake. .

1.3 Other Symptoms

1. H e following alarms / indications are received on H51-P021:
a. He EVENT INDICATOR will turn white af ter the earthquaka has been recorded. -
b. He EVENT AIARM is illuminated. i
2. Noticeable seismic shock inside th's control room or plant.

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2.0 AUTOMATIC ACTIONS .

1  ;

1. H e triaxial time history accelerograph will turn on at .005g. l
2. He following recorders any initiate due to sensor vibration l or component failures: . u; , ,,

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a. Triaxial Peak Accelerograph(s).. , ,.
b. Triaxial Response Spectrum Recorder (s).

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OM45: ONI-D51 Page: 2

, .Rev.: 2 3.0 IMMEDIATE ACTIONS'

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1. Determine if the Operating Resis Earthquake (OBE) acceleration limits have been exceeded by use of RIGH lights on panel 1H13-

! P969 and other indications as appropriate. .~.

4 a - . . - . -

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. ., . 3 m .g  : ,, ..; A

2. .If the ' seismic
  • event happens while; refueling. operations are being ' performed, suspend core alterations. j.- .

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, 4.0 SUPPLEMENTAL ACTIONS .

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1. IftheOBEaccelerationlimitshavI'beenexceededperforma
  • normal reactor shutdown per I0I-3,,,. Power: Changes, and 10I-4, *31

' ~ Shutdown. - *

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2. Within 20 minutes of the seismic event, perform an inspection
  • l of. the Control and Computer Rooms Basidification System (M29) *47 i

for leakage. If the inspection cannot be made or leakage is

  • detected or suspected, shutdown,.the,.M29. system per 50I-M29. *

, 3. The following plant parameters should' be checked and avaivated to determine the extent and location of any plant damage i.

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a. Major plant variables

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l. 1) Control rod positions
2) Rasetor power and water level
3) Feedwater and steam flows
4) Cenerator load -
5) Condenser vacuum
6) Turbine vibration and bearing temperatures
b. Airborne, process, and area radiation monitors.
c. Susp alarus and pump-out rates.
d. Off-Gas flow rates. High flow rates indicate excessive condenser in-leakage.

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{ 4. Due to the possible degradation of plant shielding gegeetry

! ' and the increased potential for airborne / surface contamination, contact the Health Physics Unit and request surveys prior to

entry into any area which contains radioactive.or potentially l i

radioactive material. * .

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l 5. Perform thorough inspections of p1' ant areas'and systems.

Plant areas with a high priority for inspection include the following: ,

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1 m "T OM45: ONI-D51 Page: 3 Rev.: 2

a. Systems which contain reactor coolant; including Reactor Racirculation and RWCU.

. b. All systems and areas that provide cooling for the reac-tor, directly or indirectly, including cooling towers, SW and ESW pumphouses, intake and discharge structures, and suppression pool.

1-

- c. Miel pools.

..- d. -Radweste Building.

a. Energency Core Cooling Systems including the Condensate Storage Tank.

Inspections should include but not be limited to checks for:

fire,: flooding, system or component rupture, leakage, or inoperability, collapse or fracture of structures, loss of containment integrity, abnormal conditions of new or spent fuel, and any other hasardous or potentially hazardous situ-ation.

6. When conditions permit, make an entry into the drywell to 1

perform a general visual inspection of the reactor pressure l vessel and primary system components and piping to identify any obvious leakage of water or steam or other damage.

7. Recover and replace the magnetic tapes and the etched event l ,

history cards from the triaxial tias history accelerograph and the triaxial peak accelerographs. Before removing the tapes from the accolographs, record a test / calibrate sequence on each tape. Mark each tape with.the recorder number and the date when tapes are removed. j i 8. If the Control and Computer Rooms Humidification System (M29) * '

j was shutdown due to the inability to aska a system inspection

  • l within the 20 minute time requirement, inspect the system as *47 l I time permits. Return the M29 system to service per SOI-M29
  • af ter verifying that no leakage exists.~ *  ;
9. Complete the following SVIs within 30 days of the seismic i

events-

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a. SVI-D51-T0279; Triaxial Time-History Accelerograph 1 Channel Calibration.  !
b. SVI-D51-T0289A, B. & C; Triaxial Peak Accelograph Channel l

Calibration for D51-R120. R130, and R140, respectively.  ;

c. SVI-D51-T0295; Triaxial Seismic Switch Channel Calibra-tion. i
d. SVI-D51-T0304A, B, C, & D;' Triaxial Response Spectrum i

Channel Calibration. i

e. SVI-D51-T5370; Triaxial Seismic Trigger Channel Calibra- i J tion.

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OM4B: ONI-D51 v

., Page: 4 - TAST Rev.: 2

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. .. 10.. . If an OBE limit has, been exceeded, maintain the plant in Cold *

' ' - ,. "' ' Shutdotes per 101-4,- Shutdown, until the necessary studies and

  • 31 approvals. to restart the plant have been received. *
11. Determineifanenergency'actio[1evel'hasbeenexceededper

.- EPI-A1, Emergency Action Levels. Attachannt- 1 as follows:

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Natural Events Unusual.~*Event Alert

,,. (; . . , . , . . Site Area Emergency

- General Eastgency

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SECTION 5.1. Initiels l STEP INPUT INSTRUMENT AS AS LAiz ALLOWABLE PRESS. FOUND LEFT YALUE l

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OM7A: SVI-G43-T 1305- A Page: 26 Rev.: 1 Attochment 2 (cont.)

Sheet 3 of 19 SECTION 5.1. IniHals STEP INPUT INSTRUMENT AS AS LAl2 ALLOWABLE l

l PRESS. FOUND LEFT VALUE (IN H2O)  !

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, OM7A: SYl'-G43-T 1305-A Page: 27 Rev.: 1 Attachment 2 (cont.)

Sheet 4 0f 19 SECTION 5.1. Initials l STEP INPUT INSTRUMENT AS AS LAlZ ALLOWABLE

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SYl-G43-T 1305-A Page: 28 Rev.: 1 i

Attachment 2 (cont.)

Sheet 5 of 19 SECTION 5.1. Initials STEP INPUT INSTRUMENT AS AS LAIZ ALLOWABLE PRESS. FOUND LEFT YALUE (IN H2O) 14.e. 7 515 3.990 Vdc DMM1 135.e. X-MTR SIG(J1) N> M 94#

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0M7A: SYl-G43-T 1305-A i Pege: 29 Rev.: 1 Attachment 2 (cont.)

Sheet 6 of 19 SECTION 5.1. Inttiois STEP INPUT INSTRUMENT AS AS LAlZ ALLOWABLE PRESS. FOUND LEFT VALUE l (IN H20) '

14.e. 1001E r, e'T 4.990 Vdc DMMi f i 135.e. X-MTR SIG(J1) y g 5.01 Yde g l 14.b. DMM2 4.990 Vdc 7' goy l 135.b. ANALOG SIG(J2) C ##[ 5.010 Yde  !

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.' CONFIRMATORY ACTION LETTE_R ma m:Go4, UNITED STATES

+ , $%. NUCLEAR REGULATORY COMMisslON REGION til

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'Q 799 ROOSEVELT RO AO g g k, , .f GLEN ELLYN, ILLINOl$ 60137

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ygg 31 gggg CAL-RIII-86-01 Docket No. 50-440 Docket No. 50-441 The Cleveland Electric Illuminating Company ATTN: Mr. Murray R. Edelman Vice President Nuclear Group Post Office Box 5000 Cleveland, OH 44101 Gentlemen:

This letter confirms the telephone conversation between Dr. C. J. Paperiello of this office and yourself on January 31, 1986, related to the seismic event that occurred on January 31, 1986, in the vicinity of the Perry Nuclear Plant.

It is our understanding, with regard to this matter, that you will:

1. Conduct a thorough review to determine if the earthquake was within the Desige Basis of tte plant (FSAR).
2. Identify any damage as a result of this seismic event; determine if that level of damage was as expected.
3. Determine that all equipment, including snubbers, that actuated during this event returned to normal operating ccnditions/ positions; identify any anomalies. ,
4. Identify any acticns required to complete licensing of the plant related to this event.
5. Maintain all affected equipment in the "as found" ccndition. Therefore, take no action such as removing, repairing or replacing equipment which would destroy or cause to be lost, any evidence which would be needed to investigate this event. Routine maintenance r.ay be performed provided that no information related to the event is altered or destroyed.
6. Submit a formal report of your findings and conclusions to the NRC Region III Office within 30 days.

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CONFIRMATORY ACTION LETT_ER_

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CONFIRMATORY ACTION LETTER The Cleveland Electric Illuminating 2 J AN 311986 Company Please let us know immediately if your understanding differs from that set out above.

Sincerely,

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v u-James G. Keppler

Regional Administrator i cc w/ enclosure

J. J. Waldrcn, Manager, Perry Plant Technical Department i M. D. Lyster, Manager, Perry Plant 1 Operations Department L. O. Beck, General Supervising

, Engineer, Nuclear Licensing and i Fuel Management Section DCS/RSB (RIDS)

Licensing Fee Management Branch Resident Inspector, RIII

! Harold W. Kohn, Ohio EPA Terry J. Lodge, Esq.

James W. Harris, State of Ohio Robert H. Quillin, Ohio Department of Health 1

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I CONFIRMATORY ACTION LETTER f

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The Honorable Nunzio J. palladino .

I Chalvuon -

l Nuclear Regulator

! '1717 H Street. N.y W. Cunnission

! Mashington. D.C. 20555

paar Mr. theirunn
.

As te are sure you are suam, an earthquake struck this corning $n the heart of i '

sur congressional districts in northeast Ohio. Of immediate contam to ,us is.the '

effect cf this earthquake on the structural integrity and safety of the Perry j nuclear power plant in Perry. Ohio. .

f Please inform os hyltk00 a.m. Monday. February 3 ediether this agrthquake sawsed

! seismic forces at the Perry site in excess of those specified in the seimnic i

design for the Perry m actors. Please indicate the source of data which was i used in obtaining the seismic force estimates, as well as a description of the i process which was used in converting seismographic data into seismic force

'. estimates.

I In addition, please, answer the following. questions:

l What will be the effect of this event upon the Perry fuel load date?

! What was the nature, scope and extant of damage to safety related

and non-safety related structures, systems and cesponents? What. if any leaks, occurred in safety and non-safety related systems?

i

Did the devices which record seismic data perform in accordance with i their precurweent specifications? Was the seismic data analysis l performed in a tiasly and accurate manner?

At what time was the NRC operations omnter notified of this event?

! At what time was the Commission notified? At what time were the relevant government entities in the Perry emergency planning area

, notified? Were these communications conducted in the timely manner l specified in the perry Emergency Plant i

Wh1 e w to tre that the taformation we are requesting will necessarily

'. I he f a prell inary nature it is japortant that such prellsinary inferination be available in order that we may adequately assess the suitability of the cumuission's regulations concerning agrthquake design for the Perry plant.

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nie expct that your staff will be pmpared early next week to brief Mu6ers

of the Committees on Energy and Commerce and Interior and Insular Affairs.

as well as approprista staff.

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!: ife appreciate your cooperation.

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, Sincemly. . ,

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i ( yJ AJ y (1-OENTISi. ECK T)'

JOHN F. SEIBERLING Member of Omg ss Member of Congress

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