ML20203A111

Rev 0 to M-771, RBCCW Heatup Immediately Following DBA- Loca

ML20203A111
Person / Time
Site:	Pilgrim
Issue date:	11/21/1997
From:	Harizi P, Oconnor G, White T BOSTON EDISON CO.
To:
Shared Package
ML20203A083	List: ML20203A078 ML20203A111 ML20203A123
References
M-771, M-771-R, M-771-R00, NUDOCS 9802230275
Download: ML20203A111 (15)

Text

I ATTACHMENT D CALC. NO. M-771 REV. O RBCCW HEATUP IMMEDIATELY FOLLOWING A DBA-LOCA Page 1 of 15 9002230275 900211 DR ADOCK0500g3 1

i CALCULATION COVER SHEET P!LGRIM NUCLEAR POWER STATION SHEET 1OF h including Attachments CALC. NO. M-771 REV. @ FILE NO. SR @ RTYPE NSR R B4.01

Subject:

RBCCW Heatup immediately Following a DBA-LOCA Preliminary calc. O Finalization Discipline Division Manager: Thomas F. White Due Date:

~

f Approval /s/: .

Date: Final Calc. @

M '

4/i/ 9~7 V '

I Independent lieviewer: 9eome E. O'Connor /s/ bO m Statement Attached O Page(s) By: Philip D. Harizi Date Ch'k'd George E. O'Connor Date Agreed h, Il*l8~97 {Q' Illl j

/

A. Statement of Problem Attachment 1= l Pgs B. Summary of Results and Recommendations Attachment 2 = I Pgs C. Method of Solution D. Input Data and Assumptions E. Calculations / Analyses F. References G. List of Attachments Total Pages Sections A to G = 4 Pgs Total Pages Attachment 1 to 2 = 2 Pgs This design analysis O DOES, @ DOES NOT require revision to affected design documents.

Affected Design Documents: PAoVIPES INPur To CALC, M-fo64, A PDC O IS, @ IS NOT Required.

A Safety Evaluation O IS, @ IS NOT Required.

This design analysis O DOES, @ DOES NOT affect the piping analysis index (pal). If the pal is affected, initiate a revision to Calculation M561.

Minor revisior's made on pages , of this calculation. See next revision.

Replaces Calc. No. Voided By Calc No. O Or Attached Memo

I i

l CALCULATION SHEET ggg PREPARED BY: M-i CALC.# M 771 CHECKED BY: 0 REV, _0 DATE 18 NOV 97 SHEET 2- OF /2 A. Statement of Problem i It is necessary to consider the efTect on the RBCCW system of operation immediately following the Design Basis Loss of Coolant Accident (DBA LOCA). The containment heat removal function of the RilR system is assumed to be initiated 10 minutes aner the reactor shutdown. For a LOCA that does not include a Loss of 0ffsite Power (LOOP) or an AC power load shed, the RBCCW and SSW systems initially remain operating in their normal mode with no automatic actions and are considered to remain in normal operation until containment heat removal is initiated. After a LOOP or load shed, the RBCCW and SSW systeras shut down and are automatically restaded with only the minimum required

. loads operating and it is necessary to evaluate the potei dat heat transfer needs that must

be met during the initial 10 minutes before any operator actions are considered to occur.

1 Although su0icient heat removal is expected to be provided by the SSW system with only

a single pump operating, it is the purpose of this calculation to demonstrate the

acceptability of considering no heat transfer from RBCCW to the 91timate heat sink during i the initial 10 minutes following a DBA LOCA with a LOOP or load shed.

I

B. Summary of Results and Recommendations j lt is acceptable for there to be no heat transfer from the RBCCW system to lhe ultimate heat sink for the first 10 minutes following a DBA LOCA. The fixed heat loads on the RilCCW system will result ni approximately 5*F increase in the RBCCW water l tcmperature within the first 10 minutes for the more limiting 1,oop B. The Drywell j Coolers may also provide significant heat transfer to the RBCCW system. This provides 3 containment heat removal that is not assumed to occur in the design basis analysis prior to 10 minutes. The resulting heat transfer to the ultimate heat sink that begins at 10 mim.tes j would initially be greater than for the design basis case (refer to Section E).

} The containment heatup analysis performed by GE [Ref. 7] treats the heat removal system comprised of RilR, RBCCW and SSW in a quasi steady-state manner by calculating 2

steady state temperature conditions at fixed time increments using a Suppression Pool profile that is based on a dynamic containment thermal analysis. The method for calculating instantaneous heat transfer rates and temperatures for the RliR, RBCCW, and SSW loops is included in [Ref. 2) At a point in time, the heat transfer is based on only the Suppression Pool temperature, the SSW heat sink temper;ture, and the steady state K factors for the RilR and RBCCW heat exchangers. There is no containment heat removal assumed prior to the 10 minute point. At 10 minutes, the heat transfer is calculated as a steady-state parameter without regard to the previously existing RBCCW temperature or the heat capacity of the system. If the existing RBCCW temperature is higher than the steady state value, then a higher instantaneous RBCCW heat transfer rate will result and the loop temperature will quickly decrease to the values given in the design basis analysis which is the bounding case for comainment heat removal.

It is shown that the RBCCW temperature during the first 10 minutes following a LOCA/ LOOP will not exceed 100 F based on the fixed heat loads and should not exceed

CALCULATION SHEET C Boston Edison PREPARED BY: M CALC.# M 771 CHECKED BY: bf6 REV. 0 DATE 18 NOV 97 2 bHEET , _3 _ OF /2-130 F including the potential containment heat removal via the Drywell Coolers. It is concluded that any containment heat removal that occurs via the Drywell Coolers during the first 10 r.tinutes will initially result in greater net heat transfer at 10 minutes and is therefore bounded by the design basis analysis.

l Although this calculation demonstrates the acceptability of considering no heat removal

, via the SSW system for the first 10 minutes, it is ext -eted that at le st one SSW pump will l be operating during this period following a LOCA/ LOOP. The flow from one pump in the

! SSW system would provide significant heat removal from the active RBCCW heat exchanger and the resulting temperatures would be well below the values postulated in this analysis.

C. Method of Solution The heat capacity of the RBCCW system is determined by totaling the water volume of the system in the mumal operation lineup with the RilR heat exchanger isolated.

The heat loads on the system during the first 10 minutes following a LOCA/ LOOP are calculated two different ways. For the RWCU and FPC heat exchangers, the residual heat transfer from the stagnant water in the heat exchanger to the RBCCW water is determined. For the other system components, the rated heat transfer rate is used to determine the heat load for the initial 10 minute period.

D. Input Data and Assumptions Following a 1.OCA/ LOOP or load shed, the RBCCW system is restarted per the load shedding logic [Ref.17]. The first SSW pump is restarted at C seconds after the LOOP.

The RBCCW flow is reinitiated by the start of the first RBr'CW pump at 45 seconds afler the LOOP. The containment heat removal function of the RHR system is not assumed to be initiateu until 10 minutes after the LOCA.The RBCCW system restarts in the same lineup from which it was shut down, which is assumed to be the normal power operation mcde. The containment heat removal function is manually initiated by the operator.

During the first 10 mmutes, the KilR heat exchanger is assumed to remain isolated with no RBCCW cooling water flow. 'Iherefore, the heat loads on_the system are considered to be those that are in the normal system lineup but operating under conditions ofload shedding. The assumed heat loads afler a LOCA/ LOOP are as follows:

RBCCWlap A:

1. RBCCW water will flow through the Recire Pump MG Set Oil Cc olers and will remove the residual heat from these units.

2 - RbCCW water will flow through all the equipment area coolers. The fans will only be operating on the safety-related area coolers for RilR and RCIC.

l 4

CALCULATION SHEET ggg PREPARED BY: k cal.C. # M.'r ' CHECKED BY: -

O 1 REV. O DATE 18 NOV.97 i SHEET 4 OF l2.  ;

i

3. RBCCW water will flow through the RilR Pump Seal Coolers with the RilR water

- temperature beginning at approximately 130*F to 140 F.

]

4. RBCCW watei will flow through the Core Spray Pump motor bearing cooler with the j pump operating.

I 5 5. The Fuel Pool Cooling pumps stop and are not automatically restarted. The RBCCW

, water will flow through the shell side of the Fuel Pool Cooling heat exchanger and 1

will transfer heat from the stagnant Fuel Pool water on the tube side until it is cooled

) to the same temperature.

i BBCCW lapfIt

! 1, During a LOOP, the Reactor Water Cleanup Pump stops and is not automatically j restarted since the system has no safety related function. The RBCCW water will j flow through the shell side ornon-regenerative heat exchangers and will transfer heat

from the stagnant reactor water on tl>e tube side until it is cooled to the same temperature.

2. Following a LOCA/ LOOP, the Drywell Cooler fans stop and are not automatically restarted since the coolers have no safety-related heat removal function. The -

RBCCW water will flow through the cooler tubes and will transfer heat from the coolers at a rate that is dependent on the Drywell conditions.

3. RBCCW water will flow through the Recire Pump seal cooler and motor oil cooler with the pump not operating.

4. RBCCW water will flow through all the equipment area coolers. The fans will only be operating on the safety related area coolers for RHR and llPCI.

5. RilCCW water will flow through the RilR Pump Seal Coolers with the RHR water -

temperature beginning at approximately 130 F to 140'F.

6 RBCCW water will flow through the Core Spray Pump motor bearing cooler with the pump operating.

7. RBCCW water will flow through the CRD Pump cooling system with the pump not operating.

8. The Fuel Pool Cooling pumps stop and are not automatically restarted. The RBCCW water will flow through the shell cide of the Fuel Pool Cooling heat exchanger and will transfer heat from the stagnant Fuel Pool wates on the tube side until it is cooled to the same temperature.

Based on the above heat loads, RBCCW Loop-B is the more limiting case. This calculation will therefore evaluate Loop B only.

~_ - - _ - _ - - - _ . _ .. . _ _ _ _ . -

CALCULATION SHEET gg,gg PREPARED BY: M

CALC. # M.771 CHECKED BY: O REV. O DATE 18 NOV.97

) SHEET T OF /2  ;

1 i  !

l l To determine the heht capacity of the RBCCW system, it will be assumed that there is no

heat transfer to the ultimate heat sink during the first 10 minu.es after a LOCA/ LOOP,

! i.e., there is no heat removal via the SSW system.

1 An acceptable r.taximum temperature that may be applied to the RDCCW system during

) the thst 10 minutes aller a LOCA/ LOOP with no SSW heat sink is 130'F. This l temperature is considered conservative for the following reasons:

! e 130 F is an acceptable inlet temperature for all components on the RBCCW system.

j Although it is above the cooling water temperature needed to achieve the rated heat transfer performance of the area coolers and heat exchangers, it will not adversely afrect these components and rated performance is not required during the first 10 minutes following the LOCA/ LOOP.

e 130'F defines the maximum temperature for a mild environment per the PNPS j Enviroamental Qvalification (EQ) program [Ref.19]. The EQ analysis for secondary

containment is not affected by the assumptions for SSW heat removal during the

[ initial 10 minutes of a LOCA/ LOOP and remains bounding.

e 130 F s the maximum predicted temperature for the RBCCW cooling water for the RilR Shutdown Cooling function [Ref. 4]. This temperature is acceptable for the ,

RilR Pump seal cooler under the more severe conditions of Shutdown Cooling with the RllR water temperature at 300'F.

, e 130 F is a acceptable temperature for the cooling water to the Core Spray Pump i

motor lube oil cooler for this period of time. The motor outime drawing [Ref.18]

specifies a madmum cooling water inlet tempeinture of 165'F for short periodt 4

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j CALCULATION SHEET

$ hm Edm PREPARED BY: M  :

cal.C. #

M 771 CHECKED BY: k_ () _

l REV. 0 DATE _18 NOV 97 SHEET b OF M. .

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2 E. Calculations / Annines

, The volume of water in the RBCCW system during normal operation with the RllR heat

exchanger isolated is used to calculate mass and heat capacity as follows:

l l HilCCW 38tentilcaLDPEily Normal Operation Parameters; 109'F = Shellinlet [Ref.1]

_80'F = Shell Outici  ;

j 90 F = Average Temperature

Volume = 919 3 8' [Ref. 5) ,

! Density - 62. i IbnVR 8

/. (919.3 0') * (62.1 lbnvR5 ) = 57,000 lbm lleat Capacity = til

• Cp (Utu/'F) where: tri = mass of water (Ibm)

Cp = specific heat (BttVibm'F) 1 i .. (57,000 lbm) * (l.00 Btu /lbm F) = $7,000 Btu / F Ihe_IlhLCDn!Ilhtl1101Lfffl1LcEhjicallnallsn.1he RBCCW sysicin11,nop-B) is as follows:

BWCU llcallischangers E 216A & B i The heat transfer from the stagnant reactor water in the Reactor Water Clean ip Non Regenerative lleat Exchangers is as follows:

Normal Operation Parameters

225'F = Tube inlet [Ref.13]

] 120*F = Tube Ou11e1

173 F ' Average Temperature i Volume = (13.0 R'/shell)

• 2 shells = 26.0 R [Ref.14]

i Density = 60.7 lbnVM 3 /. (26.0 8') * (60.7 lbnVR') u 1,580 lbm

, lleat Transfer = lil

• Cp

• AT where: AT = temperature change ( F)

/. (1,580 lbm) * (1.00 Blu/lbm'F) * (173 F - 100 F) = 115,340 Iltu i

l l

1

l CALCULATION 8HEET gg, gg PREPARtiD BY: 9b4 CALC.# M 771 CHECKED BY: b bh 1 l

. REV. O DATE 18 NOV 97 SHEET  ? OF 11 i

Rh'CILPump_ Cooling System P-204 A & 11 It is conservative to assume that the pump cooling system transfers its rated heat removal j for the 10 minute period:

Rated lleat Transfer = 200,000 Iltu/llr (Ref.I1)

I /. (200,000 litu/llr) * (10/60 lirs) = 33,330 litu l lil]ILbmiplenLCnolcLII 203 AAC,[1 l It is conservative to assume that the seal cooler transfers its rated heat removal far the j 10 minute period;

! Rated lleat Transfer = 10J,000 Blu/lir each [Ref.12)

! /. (100,000 litu/llr) * (10/60 lirs) * (2 coolers) = 33,330 Iltu 4

l C6_Spsy Pump MotoLDsating Cooler p-215 A & B lt is conservative to assume that the bearing cooler transftrs its rated heat removal for the 10 minute period:

l Rated lleat Transfer = 15,000 litu/ilr [Ref.12]

i - -

/. (15,000 litu/Ilt) * (10/60 lirs) = 2,500 litu licci1EfumplinL6: Motor llcatingfenler E-213 A & B and E-214 A til

, it is consavative to assume that the pump cooler transfers its rated heat removal for the

10 minute period:

Rated lleat Transfer = 32,000 Iltu/llr each pump [Ref.12]

l /. (32,000 Iltu/lIr) * (10/60 lirs) * (2 pumps) = 10,670 Iltu T

-e n ,n , - ,,n . - r--~-+,v-,,w-, v.,,-. ,-~,,.r.-e-, .--.--------r-~,-w,,- , . , - ,.,,+w,., . , _ ,.,.,,-..w, -n,..,~v .,--,v,-n- ,,,------eme--nv-,---- - ~ , - -

h l CALCULATION SHEET ggg PREPARED BY: M CAL.C. # M.771 CHECKED BY: O

REV. _0 _

DATE 18-NOV.97 SHEET 8 OF 12 I

CRilj' ump Cooling System P-209AAD .-

l' is conservative to assume that the pump cooler transfers its rated heat removal for the

j. 10 minute period: ,

) Rated lleat Transfer - 40,000 litu/ilt [Ref.I1)

., (40,000 litu/llr) * (10/60 lirs) = 6,670 Iltu fitell'.00LCnolinglientlitshimgtrLli 20 Mall The her,t transfer from the stagnant fuel nool water on the tube side of the FPC 4

Ileat Exchanger is as follows:

l Normal Operation Parameters: 125 F = Tube inlet [Ref. 3)

! Il6*F = Tube Outltt

120*F = Average Temperature ,

f Volume = (0.3339 in'/144) * (20 R) * (97 tubes) = 4.5 n' [Ref. 3]

lhnsity = 61.7 lbnVQ'

,.* (4.5 n') * (61.7 lbm/A') = 278 lbm IIcat Transfer = m

• Cp

• dT

., (278 lbm) * (1.00 Btu /lbm*F) * (120 F - 100 F) = 5,560 Btu Atc.a Coolcu During the first 10 minutes following a LOCA/ LOOP, the reactor building compartments will not increase significantly in temperature and will certainly remain below 130 F. Only the safety related coolers may operate aller load shedding. Therefore, tb e will not be significant heat removal by the area coolers For this calculation, a oc . mative total heat

!-ral rate of 450,000 Btu /Ilr is assumed during this period.

fransfer = 450,000 Blu/lir v l50,000 Iltu/llr) * (10/60 lirs) = 75,000 Blu ,

-...-.- - _ - ~. - - -._ _ - - --- - . - - . -

CALCULATION SHEET ggg PREPARED BY: h i

4 CALC. # M 771 CHECKED BY: k90 v -

) REV, 0 DATE 18 NOV.97

) SHEET 9 OF 12.

i l

j

Inlalligat Transfct Ths am of the heat loads for the first to minutes followirg a LOCA/ LOOP are:

1 115,340 1 33,330 j 33,330- '

, 2,500 10,670 6,670

5,560 i 75,000

===m---

l Total = 282,400 Htu a

The heatup due to this heat load is:

(282,400 litu) / (57,000 litu/'F) = $.0 F The resulting RBCCW temperature from this heat load is then:

95.0 F + 5.0 F = 100.0 F 110welLCe91rtlhaLIInfer Following a LOCA/ LOOP, the Drywell Cooler fans stop and are not automatically

restarted. There may be significant heat transfer to % coolers initially via condensation

! due to the LOCA Drywell conditions of high temperature steam even with no fan

operation. Ilowever, the Drywell Coolers are designed as air coolers and the closely spaced fins would quickly load up with condensate that would prevent the continuation of eflicient condensation heat transfer. The Drywell Coolers would nonetheless provide ,

some containment heat removal which is only considered to occur via the RilR heat exchanger beginning at 10 minutes, The heat removed would increase the RBCCW temperature above the 100 F determined above. This would provide a higher initial shell-l side temperature for the RBCCW heat exchanger at the time that the SSW heat sink is j assumed to become elTective, aller which the RBCCW outlet temperature would quickly j drop to the analytical values given in the [Ref. 2] design basis analysis. Therefore, the

, heat transfer at the 10 minute point will be initially greater than assumed in the analysis and there would be a greater net containment heat removal at that point in time. It is concluded that this condition is bounded by the design basis analysis that assumes no

containment heat removal prior to 10 ininutes. '

f

_ , _ , _ _ _ _ _ _ , _ . . _ . - . , . _ _ . _ . - . , _ - _ . _ ~ . _ . _ , , , . _ - . _ . , _ ~ _ _ _ - - .

CALCULATION SHEET Boston Edison PREPARED BY: $"

CALC. # M 771 CHECKED BY; Q

REV. , O DATE 18-NOV 97 SHEET _ ,.jp OF l2.

The remaining consideration is that the illlCCW temperature at 10 minutes does not exceed a value that would adversely affect the system coinponents. This maximum allowable value may be conservatively stated as 130 F. The heat capacity of RilCCW will thereby allow the following heat transfer rate:

(130T - 100 F) * (57,000 litu/*F) / (10/00 lirs) '= 10,260,000 Iltu/llr The maximum design heat transfer rate for the Diywell Coolers with both the normal and standby lims for each unit operating after a scram is 5,624,000 Iltu/llr [Ref.15]

Considering this, the heat transfer from the Drywell Coolers following a LOCA/ LOOP is i not espected to exceed the above value, and the R11CCW water temperature will emain below 1307.

CALCULATION SHEET - g PREPARED BY: N CALC.# M 771 CHECKED BY: bQ REV. O DATE 18 NOV 97 SHEET ll OF l 2.

F. Br'erences

1. IlECo Calculation hi 64i Rev. O "RilCCW lleat Exchanger Performance"

2. Ill!Co Calculation hl 664 Rev. I " Containment lleat Removal"

3. IlECo Calculation hi 672 Rrv. O " Fuel Pool Cooling Ileat Exchanger Performance"

4. 11ECo Calculation hi 737 Rev,0 "RllR Shutdown Cooling Evaluation"

5. IlliCo Calculation N 81 Rev. O "hiaximum RllCCW Temperature Upon Loss of SSW"

6. IIECo Calculation S&S A 91 Rev. El " Containment and Decay lleat Removal Analysis inputs"

7. Gli Report GE NE T23-00749 01 " Containment lleat Up Analysis with ANS 5.1 Plus 2 Sigma Decay lleat" November 1997 with Transmittal of Data Tables as Attachment, SUDDS/RF // 97 96 8, FSAR Section 8.5 " Standby AC Power Source"

9. FSAR Section 10.5.5.3 RilCCW" Accident and Transient Operations"

10. FSAR Section 14.5.3 " Loss of Coolant Accident"

11. Ilechtel Design liasis Report h1DilR 13 Rev. O " Reactor and Turbine lluilding Cooling Water Systems"

12. GE Specification 22 Al281 AF Rev. 4 " Closed Cooling Water System for Reactor Service"

13. Vendor hianual V 1034 RWCU lleat Exchangers

14. IlECo Dwg 23518-8 Rev. El "Non Regenerative lleat Exchanger"

15. IlECo Dwg Shi 432 Sil 1 Rev. E6 " Functional Description Drywell Atmosphere Cooling System" 16, llECo Dwg Shi-433 Sil 1 Rev. E2 'T metional Description Standby AC Power System Diesel Generator Emergency Loads"

17. IlECo Dwg Shi-433 Sil 6 Rev. E7 "Punctional Desciiption Standby AC Power System Diesel Generator Load Shedding & Sequential Loading"

18. I!ECc Dwg 2639-15 Rev. E2 " Outline Drawing Core Spray Pump hiotors"

19. IlliCo Specification E-536 Rev. 6 " Environmental Parameters for Use in the Environmental Qualification of Electrical Equipment per 10CFR50.49"

20. llolman, .I P., "licat Transfer" Fourth Edition, hicGraw-liill llook Company, New York,1976.

t i

! CALCULATION SHEET h m Ed h PREPARED BY: 3%d--

2 CALC.# M 771 CHECKED BY: N{d w

REV. 0 DATE 18 NOV 97 5

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SHEET l2 OF. 12.

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G. List of Attachments

Attachment 1 = Independent Verification Statement Record Attachment 2 = Preliminary Evaluation Checklist i

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CALC M 771 Rev 0 Att ichment i PJge 1 of 1 Calculation - Independent Verification Statement Record Calculation # M 771, Revision # 0 has been independently verified by the foikr ting mr . hod (s), as noted below:

Mark each item / ts, no or not applicable (N/A) and initial each item checked by you.

Design Review @ including verification that:

. Design inputs were correctly selected and included in the calculation.

. DiD Assumptions are adequately described and are reasonable.

. Df 0 Input or assumptions requiring confirmation are identified, and if any exist, the calculation

. N@ has been identified as " Preliminary" and a " Finalization Due Date" has been specified.

Design requirements from cpplicable codes, standards and regulatory documents are identified and reflectec a the design.

. $0 Applicable construction and operating experience was considered in the design.

l . StDThe calculation number has been properly obtained and ente 1.

l

. #fDAn appropriate design method or computer code was used.

. Mf0 A mathematical check has been performed.

. $0The output is reasonable compared to the input.

Alternate Calculation O including verification of asterisked items noted above.

The attemate calculation ( pages) is attached.

Qualification Testing O for design feature including verification of asterisked items noted above and the following:

The test was performed in accordance with written test procedures,

. Most adverse design conditions were used in the test.

Scaling laws were established and venfied and error analyses were performed, if applicable.

Test acceptance enteria were clearly related to the design calculation.

Test results (documented in ) were reviewed by the calculation Preparer or other cognizant engineer, independent Reviewer Comments:

/S/ ~

/- N //!/8 97 Independent Reviewer /batel Preparer concurrence with findings and comment resolution

/S/ h ._ I 9 7 Prepardr or Other ognizant Engineer NESD 3.06 Rev 7 Exhibit 3.06-C If D

CALC M 771 Rev 0 ,

Attachment 1 Page 1 of 1 PRELIMINARY EVALUATION CHECKLIST RType A9.02

1. IDENTIFICATION: Document Number: m il Revision O D:scription: R TC.ml %ty J% < ./. ,st y 7:n. v,'y a. M A LocA

2. CLASSIFICATION:

n

$3 Yes O No a. Does the proposed change involve "Q* listed equipment?

] Yes O No b. For a new procedure, a new temporary procedure, or a major tevision; does the new procedure, new temporary procedure, or the change proposed by the major revision contain procedural steps or requirements in the FSAR? If yes, identify FSAR sections.

O Yes Dd No c. Is this a new procedure or temporary procedure that is Fue Protection Program related or a major revision that makes an existing procedure Fire Protection Program related?

3. PRELIMINARY EVALUATION l 0 Yea M No a. Could this modify plant characteristics or procedural steps described in the FSAR? If yes, identify section:

O Yes M No b. Could this affect the design of systems, structures or components described in the FSAR?

O Yes M No c. Could this affect the function of systems, structures or components described in the FSAR?

O Yes M No d. Could this affect the method of performing the function of systems, structures or components described in the FSAR?

O Yes N No e. Could this indirectly affect the capability of safety related systems, structures or ccenponents described in the FSAR to perform their functions?

O Yes M No f. Could this defeat an ESF or safety system interlock? [OE 95.0120]

O Yes M No 0 Does this create a new test not described in the FSAR that could affect plant safety?

O Yes @ No h. Could this change assumptions used in the accident analyses described in FSAR Chapter 147 l 11 yet, identify sections:

O Yes N No I. Could this change affect the abihty of a systnm required to achieve and maintain safe shutdow.)in the event of a fire?

O Yes M No J. Could this change affect a requirement of, or major commitment to 10CFRSO Appendix R7 0 Yes R No k. Could this change affect a iequirement of IE Circular 8018 (for Radioactive Waste Systems)?

O Yes M No I. Could this affect the function of systems or componento required for compliance with the Limiting Conditions for Operation in the Technical Specifications?

O Yes M No m. In the judgment of the evaluator, is a Safety Evaluation required?

4. SAFETY EVALUATION REQUIRED 7 0 Yes ')Q No if the answer to any questions in Part 3 is "Yes', then a Safety Evaluation is required prior to implementation.11 a safety Evaluation is not required, provide an explanation below: Rev/6 y rG ca /v /u,s' de, s eg ,lae p oeL (ee.e.Ao'ser to y <<r* 0 %* *t-7 ntIC L<~rnr. toeo'Hlu c. s h n Ut,q a.:, n g, gr5g x ,

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GENERAL. REFERE 4CE MATERIAL U FSAR Section Tech Snees pgal u.Jahns /Desian Specs / Procedures Other g, .y P r* t. , t . 7 o in. *I. T. 3 1.. L. 3 L N.3 3

5. PREPARED BY: 1U 9AwD Lem~ f 52 Sh SA Cw Date. #Mo/9 7 ' '

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APPROVED BY; i

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Exhibit 4 NOP83E5 Rev 10

. -_ _ _ _ _ -