ML20137D904

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Application for Amends to Licenses DPR-42 & DPR-60,providing Supplemental Info to Amend Re Cooling Water Sys Emergency Intake Design Bases
ML20137D904
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 03/20/1997
From: Sorensen J
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20137D901 List:
References
NUDOCS 9703260339
Download: ML20137D904 (1)
v • d • e


Text

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, 3 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY

. PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET Nos. 50-282 1 50-306 >

REQUEST FOR AMENDMENT TO OPERATING LICENSES DPR-42 & DPR-60 LICENSE AMENDMENT REQUEST DATED January 29,1997 Amendment of Coolina Water System Emercancy Intake Desian Bases  ;

Northern States Power Company, a Minnesota corporation, by this letter dated March 20,1997, provides supplemental information in support of the subject license amendment request dated January 29,1997. Attachment 1 provides the reviewed I and approved Prairie Island earthquake procedure. l 1

This letter and its attachments contain no restricted or other defense information. 1 I

NORTHERN STATES POWER COMPANY By k g6el P-.' S6rensen Am /

Plant Manager, Prairie Island Nuclear Generating Plant On this MO day of before me a notary '

public in and for said County, personally appeared, Joel P. Sorensen, Plant Manager, Prairie Island Nuclear Generating Plant, and being first duly sworn i acknowledged that he is authorized to execute this document on behalf of Northern i States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and b f the statements made in it are true and that it is not interposed for del y.

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. 14ARCIA K. lac 0lE i

NOTARYPUBLIC4 ANNE 90TA HENNEPN COUNTY nlyCommiselon Expres Jan.31,2000 wwwmMMMAMMwwwwwMww I

9703260339 970320 l PDR ADOCK 0500o282 j P PDR -

I PRAIRIE ELAND NUCLEAR GENERATIN3 PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES l ,

TITLE: NUMBER:

AB-3 EARTHQUAKES REV: 12 l Section l . Page 1 of 24 I

l TABLE OF CONTENTS l Section Title Page 1.0 PURPOSE.................................................. 2 2.0 PROCEDURES............................................... 2 2.1 Sy m pt o ms . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.2 Automatic Actions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.3 Immed! ate Actions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.4 Subsequent Manual Actions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.5 R ecovery Action s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3.0 ATTAC H M E NTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4.0 R E F E R E N C ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 4.1 Developmental References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 4.2 Implementing References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6

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ATTACHMENTS '

ATTACHMENT A - SEVERITY EVALUATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 ATTACHMENT B - PROCEDURE TO INTERPRET SEISMIC EVENT DATA . . . 10 ATTACHMENT C - VISUAL INSPECTION OF EQUIPMENT AND STRUCTURES AFTER EARTHO U AKE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 LIST OF TABLES TAB LE 1 - S E I S M IC M O N ITO R S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 TABLE 2 - MAXIMUM CL FLOW RATE THROUGH EMERGENCY INTAKE LIN E VS. RIVER ELEVATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 t

O.C. REVIEW DATE:

( REVIEWED BY: . ,,, , mi DATE:y/. tom f l ,3-&o17 . '-

APPROVED BY: y DATE: J - 2 C'-f 7 s o u n ~, n c, l

( , n V J I 't VU Q ,

PRAIRIE 12 LAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES

.y, .

~ REV: 12 Page 2 of 24 1.0 PURPOSE This procedure describes the actions necessary to place the units in a safe condition following a seismic event detected at the Prairie Island site. These actions depend upon the  ;

severity of the event and the level of deterioration of plant systems, structures, components and offsite power sources.

I 2.0 PROCEDURES l 1

2.1 Symptoms  ;

l 2.1.1 Receipt of Annunciator 47023-0603, SEISMIC EVENT.

l 2.1.2 Detection of earth tremor by personnel.  :

2.2 Automatic Actions E earth tremor is detected by the seismic recording system, THEN activation of magnetic tape recorders will occur.

2.3 Immediato Actions Indication of a decreasing safeguards bay level will

"* ***"*** *XPeditious reduction of cooling water load to NOTE * - ensure maintenance of adequate heat sink. It is expected l that flow reduction can be achieved in 15 minutes. l Bay level Indicators are not seismically quallfled but will I NOTE: fall in the conservativo direction so action based on observed indication is appropriate.

2.3.1 Monitor safeguard bay level indication for evidence of blockage in the intake canal (LI-41011, Ll-41017 & LI-41503). E indicated safeguards bay level is decreasing, THEN:

A. Trip both reactors. i B. Perform E-0, Reactor Trip or Safety injection, while continuing with the SUBSEQUENT ACTION cooling water reduction steps of this procedure.

2.3.2 E safeguards bay level is NOT decreasing, THEN continue monitoring level while evaluating earthquake severity per Attachment A.

PRAIRIE ISLAND NUCLEAR CENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES l

TITLE: NUMBER: I EARTHQUAKES AB-3 REV: 12 Section

Page 3 of 24 2.4 Subseauent Manual Actions l 2.4.1 E safeguards bay level is decreasing rapidly such that loss of suction to safeguards cooling water pumps is imminent, THEN trip all four Circulating Water Pumps.

Cooling Water flow must be reduced to <11,600 GPM to bo within the capacity of the Emergency intake Line. Total NOTE:; cis wtr flow is indicated by the sum of F1-4101201 and  ;

F1-4101301 OR F1-4150401 and FI-4150501. (Seismically 1 qualified instruments) l 2.4.2 Reduce cooling water system flow to less than 11,600 GPM by isolating flow to  !

loads in the following preferential order:

A. Turbine Building loads.

CLOSE MV-32031,1 TURB BLDG CLG WTR HDR MV.

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1.

E unable to CLOSE MV-32031 from the Control Room, i THEN direct the dedicated seismic event operator to locally CLOSE MV-32031 using its handwheel.

2. CLOSE MV-32033,2 TURB BLDG CLG WTR HDR MV.

E unable to CLOSE MV-32033 from the Control Room, THEN direct the dedicated seismic event operator to locally CLOSE MV-32033 using its handwheel. l l

B. Containment FCUs. l l

1. CLOSE MV-32132,11 FC CLG WTR RTRN ISOL MV A.

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2. CLOSE MV-32135,12 FC CLG MR RTRN ISOL MV A.
3. CLOSE MV-32147,21 FC CLG WTR RTRN ISOL MV A.
4. CLOSE MV-32150,22 FC CLG WTR RTRN ISOL MV A.
5. CLOSE MV-32138,13 FC CLG WTR RTRN ISOL MV A.

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6. CLOSE MV-32141,14 FC CLG WTR RTRN ISOL MV A.

! 7. CLOSE MV-32153,23 FC CLG WTR RTRN ISOL MV A.

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8. CLOSE MV-32156,24 FC CLG WTR RTRN ISOL MV A.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES NUMBER:

REV: 12 i secuoni Page 4 of 24 C. Component Cooling.

1. Verify at least one Component Cooling Pump running for each unit.
2. IE both CC Pumps are running for a unit, THEN stop one CC Pump for each applicable unit.
3. CLOSE the Clg Wtr inlet MV for the idle CCHX for each unit.

ll NOTS *^ Th'* Procedure assumes that both DDCLPs have started and 121 MDCLP is idle.

'! NOTE *. It will be necessary to place the pump control switches in

" PULLOUT" to prevent automatic restart.

2.4.3 WHEN the cooling water system total flow demand is less than 13,000 GPM, the total number of running cooling water pumps taking suction from the safeguards bay should be reduced to one.

A. Place the idle safeguards bay cig wtr pmp control switch in " PULLOUT".

B. Turn one of the running safeguards bay cooling water pump control switches to "STOP" AND place in " PULLOUT.

2.4.4 Cooling water flow to the in-service Component Cooling Heat Exchanger will be limited by the setting of the travel stop on the outlet flow control valve.

lE further reduction of flow is necessary, THEN throttle CLOSED the CCHX Cooling Water Outlet Manual Valve. (Chain Operated) 2.4.5 lE CST inventory cannot be maintained, THEN refer to C28.1 AOP2, LOSS OF CONDENSATE SUPPLY TO AUXILIARY FEEDWATER PUMP SUCTION.

2.4.6 1E instrument air is lost, THEN refer to C34 AOP1, LOSS OF INSTRUMENT l AIR, Attachment A, step 9, for operation of one Control Room Chiller. i i

2.4.7 Evaluate earthquake severity per Attachment A.  !

PFkAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES

%~ TITLE:

l 7 NUMBER:

EARTHQUAKES A 3 l

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, Section REv: 12 Page 5 of 24 2.5 Recovery Actions i 2.5.1 Restore any cooling water loads that can be supported by the running Cooling.

Water Pump. Maintain total cooling water flow <11,600 GPM OR determine allowable increased flow based on visual observation of river level at intake screenhouse. (See Table 2)

A. In-service component cooling heat exchanger:

E Clg Wtr Outlet Manual Valve was throttled, THEN OPEN as necessary to establish desired flow.

B. E desired to gain e.dditional flow to the FCUs, THEiN CLOSE one or both Cig Wtr B-P MVs to turbine oil coolers.

MV-32371,11/12 TURB OIL COOLERS CLG WTR BYPASS MV '

MV-32372,21/22 TURB OIL COOLERS CLG WTR BYPASS MV -

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C. Fan Coil Unit operation: i

1. CLOSE FCU Clg Wtr Outlet MV B. ,

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2. OPEN FCU Cig Wtr Outlet MV A. l l

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3. Throttle OPEN FCU Cig Wtr Outlet MV B to obtain desired flow

(=450 GPM).

2.5.2 To reduce any possible influx of debris laden water from the circulating water pump intake bays into the suction of the safeguards bay, CLOSE both safeguards bay gates.

2.5.3 Manually backwash each safeguards traveling screen, one at a time, for 10 minutes every 30 minutes.

2.5.4 Consult Technical Support Center for guidance on redistribution of cooling water flow.

3.0 ATTACHMENTS 3.1 Attachment A, Severity Evaluation 3.2 Attachment B, Procedure to Interpret Seismic Event Data

PhlAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN GTATES POWER COMPANY ABNORMAL PROCEDURES g, NUMBER: j REv: 12 l Sectio'n' Page 6 of 24 l 3.3 Attachment C, Visual Inspection of Equipment and Structures After Earthquake  !

3.4 Table 1, Seismic Monitors 3.5 Table 2, Maximum CL Flow Rate Through Emergency Intake Une vs. River Elevation

4.0 REFERENCES

l 4.1 Developmental References 4.1.1 FSAR Section 1, Page 1.3-2 1

4.1.2 PINGP Technical Manual, XH-597-54 i

1 4.1.3 EPRI NP-6695, " Guidelines for Nuclear Plant Response to an Earthquake", I dated December 1989 4.2 Implementing References 4.2.1 E-0, Reactor Trip or Safety injection 4.2.2 C28.1 AOP2, LOSS OF CONDENSATE SUPPLY TO AUXILIARY FEEDWATER PUMP SUCTION 4.2.3 C34 AOP1, LOSS OF INSTRUMENT AIR 4.2."4 C37.11 AOP1, LOSS OF SAFEGUARDS CHILLED WATER l

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES TITLE:

NUMBER:

EARTHQUAKES AB-3 REv: 12

/seation' Page 7 of 24 Page 1 of 3 ATTACHMENT A - SEVERITY EVALUATION PURPOSE This attachment directs activities to evaluate the severity of the earthquake to determine the necessary actions to be performed to ensure continued safe operation of the plant.

It is enticipated that the plant site will not experience any significant earthquake motion during its lifetime. However, the plant is designed to respond elastically to earthquake ground motion as high as 6 percent gravity in the horizontal direction and 4 percent in the vertical direction. Provisions have also been made for safe shutdown of the reactors if ground motion reaches as high as 12 percent gravity in the horizontal direction and 8 percent gravity in the vertical direction. This procedure will dictate the actions to be taken following the seismic recording system actuation by the " Seismic Event" (3 percent vertical or horizontal), " operational basis Earthquake" (4 percent vertical or 6 percent horizontal), or a

" Design Basis Earthquake" (8 percent vertical or 12 percent horizontal) trigger sensor.

Information concerning epicenter and time of current NOTE *. seismi events w ridwide an be obtained from the National Earthquake information Center, Boulder, Colorado (1-303-273-8500) OB (1-800-525-7848).  :

i it should be noted that the actual "g" level accelerations used in this procedure are considered more accurate and usefulinformation for the site than the Richter Scale magnitude conveyed to the general public by the media.

SEISMIC MONITORS l l

1.0 Table 1, Seismic Monitors, lists the areas that are automatically monitored after an activation signal.

2.0 Upon activation, the seismic recording system will record, on magnetic tape, all twelve channels of four triaxial accelerometers. The preselected accelerometer will display visually on the graphic recorder the three axes of its vibration.

3.0 Each of the eleven accelerographs will record, on magnetic tape, peak amplitude vibrations.

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PRAIRIE 12 LAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES TITLE: NUMBER:

EARTHQUAKES AB-3 _

' REV: 12 Section -

Page 8 of 24 Page 2 of 3 ATTACHMENT A - SEVERITY EVALUATION [ Cont'd]

REQUIRED ACTIONS 1.0 Suspend all fuel handling and crane operations, s 2.0 lE the " OPERATIONAL BASIS EARTHQUAKE" or the " DESIGN BASIS EARTHQUAKE" annunciator is received, and the graphic recorded concurs, THEN perform an orderly shutdown of both units to Cold Shutdown AND perform plant inspections using Attachment C as guidance.

3.0 Activate the Emergency Plan using the following criteria for classification:

A. " SEISMIC EVENT", Notification of Unusual Event.

B. " OPERATIONAL BASIS EARTHQUAKE", Alert.

C. " DESIGN BASIS EARTHQUAKE", Site Area Emergency. l 4.0 Notify I&C Specialist to perform an evaluation of the seismic recorder data to l determine the severity of the event as follows: l A. Display on the graphic recorder all 12 channels of the 4 triaxial accelerometers.

Refer to Attachment B to determine the percent of gravity on a time basis.

B. Using the Magnetic Developer Kit, determine the amplitude of each of the 11 accelerographs.

i 5.0 Visually inspect all areas receiving 3 percent of gravity horizontal or vertical accelerations and greater. The inspection SHALL specifically include the Safeguards Chill Water System shown on Flow diagram NF-39603-3. IE necessary, THEN initiate actions for break / leak in this system per C37.11 AOP1, LOSS OF SAFEGUARDS CHILLED WATER.

6.0 Areas receiving 6 percent of gravity horizontally or 4 percent of gravity vertically will have related equipment and components hydrostatically tested. In addition, primary and secondary leakage rate tests, including all Class I ventilation systems, will be performed.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES

- TITLE: NUMBER:

AB-3 EARTHQUAKES 7

. w. REV: 12 Page 9 of 24 Page 3 of 3 ATTACHMENT A - SEVERITY EVALUATION [ Cont'd]

7.0 1E the Operational Basis Earthquake limits were reached, THEN all safeguards systems will be tested and control rod motion and control will be proven. The protection system will be calibrated and tested.

A. Inspect all Class I building and structures for loss of integrity.

B. A general plant site radiation survey will be performed. Restart of the plant will be under strict administrative control with special emphasis on radiation detection surveys.

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES TITLE: NUMBER:

EARTHQUAKES AB-3

REv
12 w Section Page 10 of 24 Page 1 of 3

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ATTACHMENT B - PROCEDURE TO INTERPRET SEISMIC EVENT DATA TRIAXIAL ACCELEROMETER DEFLECTION IN PERCENT GRAVITY (G)

Definitions:

1) Seismic Event: 3% deflection vertical or horizontal
2) Operational Basis Earthquake: 4% vertical or 6% horizontal '
3) Safe Shutdown Earthquake: 8% vertical or 12% horizontal Procedure: Use Figure B-1 as a guide.
1. Using the event " START" and "END" marker positions, construct a reference line on each trace corresponding to 0% deflection.

1 Recording unit may experience an initial power up l perturbation which dampens out in under 1 second and/or 1 NOTE: an occasional intermittent high frequency noise spike l which will be observed on all traces the same time. These l occurrences are not related to the event.

2. Using calibrated calipers, complete Table B-1 as follows:

C. ' Find AND measure the highest peak from the reference line for each trace.

D. Find AND measure the lowest peak from the reference line for each trace.

i E. Record the greater of 2A and 2B in Table B-1 for each trace.

conversion factor based on o.2sgl40mm at a gain setting

' NOTE *.

of 4 as derived from the reference [1].

F. Multiply each value in Table B-1 by 0.00625 g/mm AND enter the result in the %G column in Table B-1.

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES P, TITLE:

2 NUMBER:

-9

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4. .? REV: 12

' Sen 'P + If Page 11 of 24 Page 2 of 3

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ATTACHMENT B - PROCEDURE TO INTERPRET SEISMIC EVENT DATA TRIAXIAL ACCELEROMETER DEFLECTION IN PERCENT GRAVITY (G)

G. Compare the results in Table B-1 to the definitions above to determine if the Seismic Trigger is valid, or if the Operational Basis Earthquake or Design Basis Earthquake was exceeded.

TABLE B SEISMIC DEFLECTION IN PERCENT GRAVITY Accelerometer Accelerometer Deflection Measured Conversion

  • Deflection l Tag No. Gain Setting Direction Deflection Factor From Peak '

p uoem.o.) (mm) to (%G) Amplitude ]

(mm) (%G) i 28395 Longitudinal (L) (mm) (%G)

Vertical (V) (mm) x 2.232 (%G/mm) (%G) i Transverse (T) (mm) (%G) J l

28396 Longitudinal (._) (mm) (%G)

Vertical (V) (mm) x 2.212 (%G/mm) (%G)

Transverse (T) (mm) (%G) 28397 Longitudinal (L) (mm) (%G)

Vertical (V) (mm) x 2.427 (%G/mm) (%G)

Transverse (T) (mm) (%G) 28398 Longitudinal (L) (mm) (%G)

Vertical (V) (mm) x 2.688 (%G/mm) (%G)

Transverse (T) (mm) (%G)

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  • Conversion factors are based on an accelerometer gain setting of X4, if gain setting is different, l&C Engineering SHALL determine the new gain setting.

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' PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES TITLE: NUMBER 4

. EARTHQUAKES AB-3 l i . , . , _ . . . -

REV: 12 Section :

Page 12 of 24 1

1 Page 3 of 3 ATTACHMENT B - PROCEDURE TO INTERPRET SEISMIC EVENT DATA TRIAXIAL ACCELEROMETER DEFLECTION IN PERCENT GRAVITY (G) i FIGURE B Example of Seismic Event

)

Highest Peak i

f X4:1)  !

\A  % m n

'~ "

A AI A ik. 2 h " - -

Reference U Vj Y x,:2) tine Lowest Peak . I

- Power Up .

)

Perturbation Pick maximum value between X(1) & X(2) j 1

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PRAIRIE 1: LAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES EARTHQUAKES l gg REv: 12 Page 13 of 24 Page 1 of 10 ATTACHMENT C - VISUAL INSPECTION OF EQUlPMENT AND STRUCTURES AFTER EARTHQUAKE Equipment / Structure Types of Inspections

1. Equipment 1. Check equipment anchorage / isolation mounts for damage; e.g.,

- - Fans stretching or loosening of anchor bolts or nuts; rocking or sliding of equipment.

2. Check for damage to attached conduit and ground straps. j
3. Check for damage or distortion to fan housing or tearing of fabric noise eliminators due to seismic loads imposed by attached ducts.  ;
4. Check for evidence of excessive fan vibration and/or noise. May be i an indication of misalignment between the motor and fan shafts. '
5. Check clearance between fan wheel and housing. j l
6. Check for damage due to impact or earthquake induced flooding or spraying. -
7. Check for belt tightness and/or slippage; e.g., belt smoke / odor.
8. Check local alarms, breakers and protective devices for actuation / trips.

-- Air Compressors 1. Check equipment anchorage / isolation mounts for damage; e.g., stretching or loosening of anchor botts or nuts; rocking or sliding of equipment.

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2. Check for damage due to impact or earthquake induced flooding or spraying.
3. Check for excessive noise and/or vibration.
4. Check for air leaks if compressor is running continuously rather than cycling on and off.
5. Check for belt tightness and/or slippage; e.g., belt smoke / odor.
6. Check local alarms, breakers and protective devices for actuation / trips.

-- Battery Racks 1. Check battery rack anchorage for damage; e.g., stretching or loosening of anchor bolts or nuts; evidence of rocking or sliding of racks.

2. Check for distortion of rack structure.

l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES Z TITLE: NUMBER:

REV: 12 Section ;

Page 14 of 24 l

Page 2 of 10 l

ATTACHMENT C - VISUAL INSPECTION OF EQUIPMENT AND STRUCTURES AFTER EARTHQUAKE [ Cont'd)

Equipment / Structure Types of Inspections

-- Battery Racks 3. Check for evidence of rocking or sliding of batteries on the racks, (Cont'd) buckling or distortion of the bus bars, condition of the spacers between batteries.

4. Check for damage due to impact or earthquake induced flooding or spraying.
5. Check buses / cables / ground straps for damage, distortion or ,

chafing. l

6. Check local alarms, breakers and protective devices for actuation / trips.

-- Static Inverters and 1. Check equipment anchorage for damage; e.g., stretching or Battery Chargers loosening of anchor bolts or nuts; rocking or sliding of equipment.

2. Check for damage to attached conduit and ground straps.
3. Check for distortion of cabinet structure.
4. Open cabinet, check to see that internally mounted components are secure and undamaged.
5. Check for damage due to impact or earthquake induced flooding or spraying.

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6. Check local alarms, breakers and protective devices for actuation / trips.

-- Air Handlers 1. Check equipment anchorage / isolation mounts for damage; e.g.,

stretching or loosening of anchor bolts or nuts; rocking or sliding of equipment.

2. Check for damage to attached conduits and ground straps.
3. Check for damage to air handler due to seismic loads imposed by attached ducts or tearing of fabric noise eliminators.
4. Check for damage due to impact or earthquake induced flooding or spraying.
5. Check for belt tightness and/or slippage; e.g., belt smoke / odor.
6. Check local alarms, breakers and protective devices for actuation / trips.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES m ..

TITLE: NUMBER:

EARTHQUAKES AB-3 REV: 12

w. _m

,s Page 15 of 24 Page 3 of 10 ATTACHMENT C - VISUAL INSPECTION OF EQUIPMENT AND STRUCTURES AFTER EARTHQUAKE [ Cont'd]

Equipment / Structure Types of Inspections

- - Chillers 1. Check equipment anchorage / isolation mounts for damage; e.g.,

stretching or loosening of anchor bolts or nuts; rocking or sliding of equipment.

2. Check for damage to attached conduits and ground straps.
3. Check for leakage or damage to chiller components due to seismic loads imposed by attached ducts and piping.
4. Check for damage due to impact or earthquake induced flooding or spraying.
5. Check for belt tightness and/or slippage; e.g., belt smoke / odor.
6. Check local alarms, breakers and protective devices for actuation / trips. -
7. Check for refrigerant leakage.

-- Transformers 1. Check equipment anchorage for damage, stretching or loosening of anchor bolts or nuts; rocking or sliding of equipment.

2. Check for damage to attached conduits and ground straps.
3. Check oil reservoir level.

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4. Check the nitrogen blanketing system and fire deluge system for damage.
5. Check for damage due to impact or earthquake induced flooding or spraying.

-- Vertical Pumps 1. Check equipment base plate and anchorage for da.nage; e.g.,

stretching or loosening of anchcr bolts or nuts and equipment movement.

2. Check casing below base plate for damage due to ground settlement / movement.
3. Check for evidence of excessive noise and/or vibration and seal l leakage. May be an indication of misalignment between the motor 1 and pump shaft.
4. Check for damage to pump housing from seismic loads imposed by attached piping.
5. Check for damage to shaft housing.

PRAIRIE 1: LAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY e

ABNORMAL PROCEDURES TITLE: NUMBER:

AB-3 EARTHQUAKES REv: 12

-secuen<

Page 16 of 24 Page 4 of 10 ATTACHMENT C - VISUAL INSPECTION OF EQUIPMENT AND STRUCTURES AFTER EARTHQUAKE [ Cont'd]

Equipment / Structure Types of Inspections

-- Vertical Pumps 6. Check for damage due to impact or earthquake induced flooding or (Cont'd) spraying.

7. Check local alarms, breakers and protective devices for actuation / trips.
8. Check pump and motor bearings for overheating / lubrication.
9. Check for damage to attached conduit and ground straps.

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-- Horizontal Pumps 1. Check equipment base plate and anchorage for damage; e.g.,

stretching or loosening of anchor bolt or nuts and equipment movement.

2. Check for evidence of excessive noise and/or vibration and seal leakage. May be an indication of misalignment between motor and pump shaft.
3. Check for damage to pump housing due to seismic loads imposed by attached piping.
4. Check for damage due to impact or earthquake induced flooding or spraying.
5. Check local alarms, breakers and protective devices for

. actuation / trips.

6. Check pump and motor bearings for overheating / lubrication.
7. Check for damage to attached conduit and ground straps.

-- Motor-Generators 1. Check equipment anchorage / isolation mounts for damage; e.g., i stretching or loosening of anchor bolts or nuts; rocking or sliding of j equipment. 0

2. Check for noise and/or vibration caused by misalignment between motor and generator shaft, especially if they are no mounted to a common base.
3. Check for damage to attached conduits and ground stmps. l j
4. Check for damage due to impact or earthquake induced flooding or I spraying.
5. Check local alarms, breakers and protective devices for j actuation / trips.

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l PRAIRIE ISLAND NUCLEAR GENERATING PLANT l NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES

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TITLE: NUMBER:

A AB-3

'M EARTHQUAKES REv: 12 SectionT V Page 17 of 24 Page 5 of 10 ATTACHMENT C - VISUAL INSPECTION OF EQUIPMENT AND STRUCTURES AFTER EARTHQUAKE [ Cont'd]

Equipment / Structure Types of Inspections

-- Motor Control 1. Check equipment anchorage for damage; e.g., stretching or Centers loosening of anchor bolts or nuts; rocking or sliding of equipment.

2. Check for damage to attached conduits and ground straps.
3. Check for distortion of cabinet structure.
4. Open cabinet, check to see that all internally mounted components, including relays and breakers, are secure and undamaged.
5. Check for damage due to impact or earthquake induced flooding or spraying.
6. Check controls, breakers and protective devices for actuations/ trips.

-- Low Voltage Switchgear 1. Check equipment anchorage for damage; e.g., stretching or loosening of anchor bolts or nuts; rocking or sliding of equipment.

2. Check for damage to attached conduits and ground straps.
3. Check for distortion of cabinet structure.
4. Open cabinets, check to see that all internally mounted components, including relays and contacts, are secure and  ;

undamaged. '

~

5. Check for damage due to impact or earthquake induced flooding or l spraying. l 1
6. Check local alarms, breakers and protective devices for j actuation / trips. j l
7. Reset any trips. Investigate any retrips after reset.

-- Medium Voltage 1. Check equipment anchorage for damage; e.g., stretching or Switchgear loosening of anchor bolts or nuts; rocking or sliding of equipment.

2. Check for damage to attached conduit and ground straps.
3. Check for distortion of cabinet structure.
4. Open cabinets, check to see that allinternally mounted components, including relays and contacts, are secure and undamaged.

l 5. Check for damage due to impact or earthquake induced flooding or spraying.

PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY

, ABNORMAL PROCEDURES

, @ . ,, wr TITLE: NUMBER:

EARTHQUAKES AB-3

- REv: 12 l Page 18 of 24  !

l Page 6 of 10 ATTACHMENT C - VISUAL INSPECTION OF EQUIPMENT AND STRUCTURES AFTER EARTHQUAKE [ Cont'd]

Equipment / Structure. Types of Inspections

-- Medium Voltage 6. Check local alarms, breakers ands protective devices for )

Switchgear (Cont'd) actuation / trips. j

7. Reset any trips. Investigate any retrips after reset.

]

-- Distribution Panels 1. Check equipment anchorage for damage; e.g., stretching or loosening of anchor bolts or nuts; rocking or sliding of equipment.

1

2. Check for damage to attached conduit and ground straps.  !
3. Check for distortion of cabinet structure.

1 4 Open cabinet, check to see that all internally mounted components )

are secure and undamaged. .

5. Check for damage due to impact or ea:thquake induced flooding or spraying;.
6. Reset any tripped breakers. Investigate any retrips after reset.

- Fluid / Air / Motor-Operated 1. Check for damage or distortion at attachment of operator to valve Valves body.

2. Check for damage to attached conduit / tubing, ground straps.
3. Check for damage due to impact or earthquake induced flooding or spraying.
4. Check local alarms / indicators / protective devices for actuations/ trips.
5. Stroke valve in both directions to check operation.

-- Engine-Generators 1. Check equipment anchorage / isolation mounts for damage; e.g.,

stretching or loosening of anchor bolts or nuts; rocking or sliding of equipment.

2. Check for damage to attached piping, ducts, conduits and ground straps.
3. Check for noise and/or vibration due to misalignment between engine and generator, especially if not mounted to a common base.
4. Check for damage due to impact or earthquake induced flooding or spraying.

PRAIRIE 1: LAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES A <

TITLE:

NtJMBER:

EARTHQUAKES AB-3 REv: 12 section1 +

Page 19 of 24

)

Page 7 of 10 l ATTACHMENT C - VISUAL INSPECTION OF EQUIPMENT AND STRUCTURES AFTER l 1

EARTHQUAKE [ Cont'd]

1 Equipment / Structure Types of Inspections j

-- Engine-Generators 5. Check local alarms, breakers and protective devices for (Cont'd) actuation / trips.

I i

-- Instrument Racks 1. Check equipment anchorage for damage; e.g., stretching or loosening of anchor bolts or nuts; rocking or sliding of equipment.

2. Check for distortion of rack structure.  !

l

3. Check for damage to attached conduit and ground straps.
4. Check to see that instruments mounted to the rack are secure and undamaged.
5. Check for damage due to impact or earthquake induced flooding or spraying.
6. Check local alarms, breakers and protective devices for actuation / trip:.
7. Reset any trips. Investigate any retrips after reset. j

-- Sensors 1. Check for damage to attached conduit / tubing end ground straps.

2. Check for damage due to impact or earthquake induced flooding or spraying.
3. Verify sensor operation with readout check at !ocal/ control room indicators.

I

-- Control and 1. Check equipment anchorage for damage; e.g., stretching or Instrumentation Cabinets l

loosening of anchor bolts or nuts; rocking or sliding of equipment. j

2. Check for distortion of panel structure.
3. Check for damage to attached conduit and ground straps.

4 1

4. Check to see that instruments, gages, controls, and other i equipment mounted to panels are secure and undamaged.
5. Check for damage due to impact or earthquake induced flooding or spraying.
6. Check local alarms, breakers and protective devices for actuation / trips.

i .

PRAIRIE G2 LAND NUCLEAR GENERATING PLANT l NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES l mg TITLE: NUMBER:

EARTHQUAKES AB-3 y" ~

REv: 12 1;; EfSection!

Page 20 of ?.4 Page 8 of 10 ATTACHMENT C - VISUAL INSPECTION OF EQUIPMENT AND STRUCTURES AFTER EARTHQUAKE [ Cont'd]

Equipment / Structure Types of Inspections

-- Control and 7. Reset any trips, investigate retrips after reset. ,

Instrumentation Cabinets (Cont'd)

2. Low Pressure Storage 1. Check tank anchorage for damage; e.g., stretching or loosening of Tanks anchor bolts or nuts; deformation of bolt chairs; rocking or sliding on the base.
2. Check for damage to attached piping and ground straps.
3. Check for buckling of tank walls; e.g., "elephai.i foot" buckling.
4. Check for cracking or leakage at the base plate to cylindrical shell connection. -
5. Check for damage due to impact or earthquake induced flooding or spraying.
3. High Pressure Tanks and 1. Check for damage to anchorage; e.g., stretching or loosening of Heat Exchangers anchor bolts or nuts; rocking or sliding of base plates on concrete.
2. Check for damage to attached piping.
4. Piping 1. Check for snubber damage; e.g., snubbers pulled loose from foundation bolts, evidence of excessive travel, jam up of inertia l mechanism / leakage of hydraulic fluid and bent niston rods.

]'

2. Check for damage at rigid supports; e.g., deformation of support structure, deformation of pipe due to impact with support structure.
3. Check for damage or leakage of pipe at rigid connections; e.g.,

anchor points with other equipment and structures.

4. Check for damage or leakage of piping and branch lines.
5. Check for damage to pipe at building joints and int 9rfaces between bulidings.
6. Check for damage due to impact or earthquake induced flooding or spraying.

i

PRAIRIE ISLAND NUCLEAR GENERATING PLANT '

NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES N <- TITLE: NUMBER:

EARTHQUAKES AB-3 E

c-. .

. ,r .

REv: 12 Page 21 of 24 Page 9 of 10 ATTACHMENT C - VISUAL INSPECTION OF EQUIPMENT AND STRUCTURES AFTER EARTHQUAKE [ Cont'd]

Equipment / Structure Types of Inspections

5. Electric Raceways 1. Check for deformation of dead weight supports and sway bracing.
2. Check for damage to cables at building joints and interfaces between buildings.
3. Check for damage due to impact or earthquake induced flooding or l spraying.

1 l

6. Air Handling Ducts 1. Check for deformation of dead weight supports and sway bracing. )

l

2. Check for damage to ducts at joints, j 1 3. Check for damage to ducts at building joints and interfaces between buildings. .
4. Check for damage due to impact or earthquake induced flooding or spraying.
5. Check for tearing of fabric transitions / noise eliminators.
6. Check for damage to internal filters and racks.
7. Steel Framed Structures 1. Check for damage at bolted or welded connections.

J -

2. Check for damage to anchorage; e.g., stretching or loosening of )

anchor bolts or nuts; rocking or sliding of base plates on concrete.

3. Check for distortion or buckling of braces and other compression I members. l
8. Reinforced Concrete 1. Check for new open (>0.06 inches) cracks, spalling of concrete.

Structures (Buildings, [ NOTE: Minor cracks, even if caused by the earthquake, are not Containment, Cooling considered significant unless they are large enough to result in Towers, Intake Structure) yielding of rebar.]

and Masonry Walls.

2. Check for evidence of ground settlement.
3. Check for evidence of differential horizontal and vertical movement between adjacent and/or interconnecting buildings / structures.

P'RAIRIE ISLAND NUCLEAR GENERATING PLANT

, NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES yp - We. ,

TITLE: NUMBER:

EARTHQUAKES AB-3 REV: 12 am"- ,

Page 22 of 24 Page 10 of 10 ATTACHMENT C - VISUAL INSPECTION OF EQUIPMENT AND STRUCTURES AFTER EARTHQUAKE [ Cont'd]

Equipment / Structure Types of Inspections

9. Primary Coolant System 1. Check for reactor coolant leakage at flanged joints; e.g., CRD mechanisms.
2. Check for condition of supports and snubbers for large components; ,

e.g., main coolant pumps, steam generators, pressurizer.

l

3. Check condition of CRDM support structure (PWRs only).

I l

10. Buried Pipe 1. Check for damage or leakage at pipe interface with buildings and tanks.
2. Fire main leakage will be evidenced by self excavation and '

acatuation of back up fire pumps,

^

3. Fire mains, service and circulating water piping, especially dead legs, are susceptible to buildups of corrosion and growths which are knocked loose by earthquake motion. These loosened ,

accumulations can clog screens and small diameter pipes such as j fire hose hydrants. Checks for clogging and flushing of pipe mains I are necessary.

4

P'RAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES l TITLE:

s] ' NUMBER:

.e REV: 12 1

  • =

_ Page 23 of 24 TABLE 1 - SEISMIC MONITORS 4 Triaxial Accelerometers Location

1. Unit 1 Cntmt 32.5/210/697.5 l I
2. Unit 1 Cntmt 32.5/210/765.5
3. Aux Bldg J.0/9.0/695 i
4. Unit 2 Cntmt 29/95/765.5 11 Triaxial Accelerographs Location
1. Aux Bldg J.0/9.0/695
2. Aux Bldg N.8/9.0/755
3. Aux Bldg J.0./9.0/755
4. Unit 1 Cntmt 32.5/210/697.5 I
5. Unit 1 Cntmt 32.5/210/765.5
6. Unit 2 Cntmt 29/95/765.5
7. Unit 2 Cntmt 29/95/697.5
8. Turb. Bldg. C.6/8.8/695
9. Turb. Bldg. C.6/8.8/755
10. Screenhouse C1.0/81.8/670
11. Screenhouse C1.0/81.8/695

PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY ABNORMAL PROCEDURES

TITLE: NUMBER:

EARTHQUAKES AB-3

< ;m ..

REV: 12 g

j Page 24 of 24 l

l TABLE 2 - MAXIMUM CL FLOW RATE THROUGH EMERGENCY INTAKE LINE VS. RIVER ELEVATION l

CL Flow Rate (com) River Elevation 17824 675' 17209 674' 16571 673' 15908 672' 15216 671' 14491 670' i

i 13728 669' '

12920 668' 12057 667' 11602 666'-6" l

l l

1 l

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