ML20245L263

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Used Molded Case Circuit Breakers Installed in Safety- Related Applications, Safety Evaluation 252
ML20245L263
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 11/11/1988
From: Silverberg T
NORTHERN STATES POWER CO.
To:
Shared Package
ML20245G738 List:
References
252, NUDOCS 8907050425
Download: ML20245L263 (63)


Text

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.,' ,.PINGP 279, Rev. 6 ~ SAFETY EVALUATION F

Pego 1 of 2-

, Retention: Life (NON-MODIFICATION)

SE No. 2 52 -

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Addendum ~

Page 1 of 2 All Safety Evaluations for safety related changes and tests other than Modifications SHALL be submitted on this form. '

TITLE: (kSeA 01c de c$ [ pee- (ivta/i (3rea kerc lu s h (lecQ /u S a le/7 RefaledL M y t h cp .p,.ci.,.c.

1. DESCRIPTION (Attach additional sheets as necessary)

JHis c htJ See 1

2. YES l[l TECHNICAL SPECIFICATION / LICENSE AMENDMENT OR UNREVIEVED NO l@ SAFETY OUESTION
a. Amendment Request Transmittal DATE:
b. Authorizing Letter Received DATE:

PREPARED BY: / # // W D, ATE : /M/'O /ff REVIEWED BY: , I,ma 7 Aaa DATE: //['MPf' OPERATIONS COMMITTEE REVIEV: DATE: ///N!Y PPROVED.BY:

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DATE: //[// // /

COPY TO: Techni al Support Training Supervisor .DATE: ,

SAFETY AUDIT COMMITTEE REVIEW DATE:

(For Technical Specification / License Amendments or Unreviewed Safety Questions the SAC SHALL review the change prior to implementation).

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.d e-SAFETY EVALUATION M Z8A USED MOLDED CASE CIRCUIT BREAKERS INSTALLED IN SAFETY-RELATED APPLICATIONS TABLE OF CONTENTS 1

PAGE

SUMMARY

AND CONCLUSIONS .................................... 2 WHY USED BREAKERS WERE INSTALLED ........................... 5 GENERAL ANALYSIS ............................. ............. 9 DETAILED ANALYSIS ......................................... 12 I. #11 Battery Charger ............................. 12 II. 12, 21 and 22 Battery Chargers .................. 18 III. 12 and 22 Feedwater Isolation Valves ............ 18 IV. Panel 136 ....................................... 23 FAILURE EVALUATION ........................................ 26-FIGURES 1 THRU 15 ATTACHMENTS 1 THRU 9 IBM

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SUMMARY

AND CONCLUSIONS The purpose of this evaluation is to justify continued operation of Prairie Island Unit.s 1 and 2. During a.recent NRC procurement audit, concern was raised over the use of used molded case circuit breakers (MCCBs) in certain safety-related applications. l 2

2 In response to these ' concerns, the following can be said:

1. The breakers were not tampered with 2.- The breakers were tested satisfactorily l
3. The breakers do not affect the ability to safely shutdown the plant Due to the procurement audit and other concerns raised over substandard electrical parts (IEIN 88-19 and IEIN.88-46) a visual inspection was made of eight breakers from the same purchase order that have not been installed. All have a 2 1/2" by 1/16" slot machined into each side of the upper half of the casing where it mates.with the lower half. All have are chute ventilation screens on the line side. All have the upper and lower halves of the casings riveted together. None show significant signs of damage. None show scratches or marks beyond what would be expected from normal handling. NSP believes there is no external pq evidence indicating that these breakers have ever been il disassembled. ,

.All the breakers have been tested. Except for one MCCB, all passed the test. The MCCB that failed was not used. The reason'these specific breakers were needed was Appendix R circuit coordination.

The test demonstrated the breakers met the requirements for this application. All the breakers used passed the test and, therefore, satisfied the needed circuit protection.

One or more of the breakers will be dismantled and inspected. NSP is in the process of locating an expert on GE MCCBs. Then in the presence of representatives from NSP, NRC and the MCCB expert, one or more breakers will be dismantled and inspected. This inspection will provide additional confidence that the breakers have not been modified from original factory specifications.

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I This evaluation examines:  !

1. Why the breakers were installed j i
2. A general assessment of what effect breaker failure I would have on plant safety I
3. A detailed look at the application of each breaker and what effect its failure would have on plant safety To summarize, the breakers were installed to meet Appendix R circuit coordination requirements. Used breakers were installed because the breakers needed to coordinate are no longer made.

The'used breakers were located with the assistance of General Electric, the original equipment manufacturer.

NSP believes the breakers can fulfill the design function. There is no evidence that the breakers have been tampered with. The breakers have been tested for and are used in an application where overcurrent circuit coordination is needed. The breakers have been shown to meet that function. There is-no evidence that the MCCBs are more likely to fail than any other breaker. However, the rest of this analysis looks at what would happen if the breakers did fail.

Failure of the breaker will not affect plant safety. Any breaker

' failure will not impair the ability to bring the plant to a safe shutdown condition. In fact, there could be a simultaneous failure of all the breakers and both units could be brought to a safe shutdown condition. In some cases there may be a loss of redundancy; however, it would be detected and corrected during the first 7 steps of the emergency procedures. These are immediate, memorized actions.

There is no new mechanism for brecker failure. Any circuit breaker in the plant can fail as described in this report. In fact, under fault conditions it is impossible to determine with properly operating breakers if the breaker closest to the fault will open or the next breaker upstream will open. Thus, the conditions described in this report, loss of a single load or loss of an entire MCC apply to all molded case circuit breakers.

The circuit breakers in auestion do not create the possibility for an accident or malfunctio'n of a different type than evaluated previously in the USAR or any subsequent commitments.

They do not increase the probability of occurrence of an accident or malfunction of equipment important to safety previously analyzed in the USAR or subsequent commitments.

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'- They do not < increase the consequences of any. accident or -

malfunction of equipment important to safety previously analyzed in' the ' USAR or subsequent ' commitments.

They do not reduce the margin of safety as defined in the~ basis for any Technical _ Specification.

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l -- WHY USED BREAKERS WERE INSTALLED ,

The electrical configuration of Prairie Island 480 Volt Motor Control Center (MCC) S'y stem has several MCC's fed from other MCC's. With this configuration, coordination between the source

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l and load circuit breakers is a closely balanced process.

The plant electrical design for MCC's was made to include subfed MCC's approximately 20 years ago when the plant Architect and Engineer consultant found that the number of components requiring a 480 volt MCC source. could not be supplied from existing MCC's, and no additional 480 volt bus feeder breakers were available.

The A&E concluded that on such a subfed MCC, the loads had closely related functions so the loss of any one load would I

effectively. cause the -loss of all the loads on that subfed MCC; thus protection device coordination between load and source devices was not required. Subsequently, Appendix R made it necessary to reconsider this design decision.

In the specific cases, interference between the characteristics of the two devices, source and load circuit breakers, prevented proper protective device coordination. This was first determined in the Electrical System Coordination Study performed by Impell 1 1  !

Corp. , issued in February 1987, and was a finding in the PI hk Appendix R audit of March 1987.

See Figures 1 to 6 IBM

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.There are two specific coordination issues.

The first is coordination between a GE 50 ampere THED circuit breaker and a 200 ampere GE THFK circuit breaker. 'In this c'ase, the transition between the thermal magnetic (timeover current) and magnetic instanteous (short circuit) trip ,

characteristic'of the 50 ampere circuit breaker overlapped the transition section of the 200 ampere circuit breaker.

Proper coordination could not be determined in this overlap region.

The second is coordination between the GE THED 50 ampere-circuit breaker and the 100 ampere GE THED circuit breaker.

In this case, a portion of the thermal magnetic trip characteristic of the 50 amp breaker intersected the thermal' magnetic. characteristic of the 100 amp circuit breaker.

t Again, proper coordination of the two devices could not be effected.

Panel 136 coordination was not considered a safety concern during the Appendix R audit because the only significant load, the fuel oil transfer pump for the engine driven cooling water pump, supplies an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day tank, which allows replacement of the panel 136 source device. The changing of circuit breaker type from THED to THEF did improve coordination. -

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breaker. The THED circuit breaker characteristic has a wide tolerance on both the thermal magnetic trip region and the transition region. This tolerance is so large that the largest size THED circuit breaker that can be coordinated with the 200 amp THFK is a 35 ampere THED, and the largest THED that can be coordinated with a 100 amp THED is a 15 ampere device.

The GE THEF circuit breaker, also supplied with our safeguards MCC's, has a much tighter tolerance on the thermal magnetic and transition portions of its characteristic curve and, by computer analysis, it was found that the 50 ampere size could be coordinated with both the 200 ampere THFK and the 100 ampere THED.

We found that we had no 50 ampere THEF circuit breakers available as spares at either Prairie Island or at Monticello, and that we could not procure new circuit breakers from GE because it had been discontinued in 1970. We, therefore, attempted to find spare or used THEF 50 circuit breakers with the aid of Lakeland Engineering.

Lakeland contacted General Electric.

l l General Electric then located " Bud Furgeson's" in California as a source for the 50 ampere THEF circuit breakers. These were used l breakers. A purchase order with Lakeland was then written to buy these circuit breakers commercial grade, used.

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Upon receipt, these. circuit breakers were tested with existing.

plant procedures to verify conformance to . published thermal overcurrent characteristic curves. The circuit breakers were again. tested when the MCC cells were assembled to replace the' existing 50 amp THED cells. These tests were based on NEMA ABl.

The circuit breakers were visually inspected for apparentLdamage.

They were then mechanically cycled to verify the contact opening and closure. They were next tested at 300% of rated current to verify tripping within the manufacturer's published trip curves, and then mechanically cycled again.

In our July 1988 Appendix R inspection, the protection-coordination issues were resolved to the satisfaction of the inspectors, posing no safety problems. The THEF breakers installed satisfy the circuit coordination requirement of Appendix R.

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GENERAL ANALYSIS

.In the event of an accident and 'a failure of one of the breakers '

in question, the plant can be brought to a safe shutdown /cooldown condition. This is based on the following paragraphs. . There it is. stated that only a single train of any' engineered safety system is needed. It also says t' hat a breaker failure.will affect-only a single safeguards train.

There are many mechanisms that can cause a breaker to' fail. .This evaluation-does not examine how a breaker fails, but looks at the effects of a failed breaker. There are basically two effects from a failed breaker:

1) It opens prematurely (no electrical fault downstream of breaker)
2) It opens late or not at all (fault downstream of breaker or it is the source of the fault)

If it opens prematurely, the individual load is lost. If it is delayed, it is assumed that the upstream breaker is actuated. This causes the entire MCC to be de-energized.

If the fault is located internal to the breaker, then the effect is the same as the case where the fault is downstream of the breaker and the breaker does not open on a fault.

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l The breakers in. question are used in seven safety related applications

-(see Figures 7 to 13).

- 11,12, 21 and 22 battery chargers

' - 12 and 21 main feedwater motor operated isolation valve

- AC distribution panel 136 This evaluation will examine how the two failure modes . affect each load and how 'that affects plant operability and safety. Before a detailed analysis starts, it is very clear that either failure mode of any of the breakers will not impair the ability to safety shutdown the plant, This. statement is based on conclusions from the Updated Safety Analysis Report (USAR) and plant design philosophy. Attachments 1 and 2 are excerpts from the USAR. The USAR points out that the. safeguards system and electrical systems are redundant. All safety systems are designed such that a single train of the system can meet the engineered safety features of the plant. For example, see Attachment 3 which discusses losing one train of the safety injection system (SI).

Attachment 4 discusses the philosophy used when designing subfed MCC's; the seven loads that use the THEF breakers in question are on subfed MCC's. Subfed MCC's have only functionally related loads. What this means is, if one load or the entire MCC is lost, IBM

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l-i only a single train of an engineered safeguard system would be affected. A premature opening of the breaker will cause an individual load to be ' lost. A~ delayed breaker opening (in the event of an electrical. fault) will cause the entire subfed MCC to be lost. -Therefore, because a breaker failure will affect only a single safeguard train and'the other train is adequate to bring the plant to a safe shutdown condition. The breakers in question do not affect the safe shutdown of the plant.

Based upon our external inspection of the subject MCCB's, which concluded.that there was no evidence of tampering, we find no reason to believe that the probabiluy of internal shorting of the breaker is any greater 'than for any other breaker installed.

Therefore, the single failure assumptions of the safety analysis report are unaffected.

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. DETAILED ANALYSIS 'l d

I.- '#11 Battery Charg'er (Breaker #112-33)

The purpose-of #11 battery charger is to:-

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~1) Supply DC loads off DC' Panel'#11

2) To maintain #11 battery in a fully charged condition such that if.#11 charger is lost there will be'no loss .of power to' the DC loads.

,s In-general, the DC panel supplies the following loads:

- Switch gear control power.

- Two instrument channel inverters

- Event monitoring instrument inverter-

- Emergency diesel generator control power

- Reactor protection actuation logic 4

- Safeguards actuation logic i-I t

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IAi t Premature' Breaker Opening-

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What Happens If there is no electrical fault, a prematureLopening I

.results in a loss of #11 battery.' charger. #11Lbattery will

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automatically power all affected loads. . Under normal. .j p operating conditions #11 battery /could supply loads for about'70 hrs. before it.should be recharged (see.

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attachments 5 & 6). Under a station blackout (SBO)1 condition,-

  1. 11 battery could carry.its loads for about.2 3/4 hours (see attachments 5 & 6) before recharging is-needed.

Station blackout loading.is the most limiting case. SBO-is discussed here only because it represents the highest-load that the' battery could see.. Under an actual SBO-condition, there would be no AC power to supply the-battery charger.

How Discovered The control room operators are immediately notified of the breaker trip from the annunciator "#11 Battery Charger AC Failure".

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Normal' Operation  ;

l During normal operation the problem is corrected.by repairing-the breaker. The control room operators would' contact station electricians. -After determining that there is no fault the electrician would. replace the breaker. The breaker-could be replaced and tested within 1 hours. Ltis is well within the battery life of 70. hours.

In the unlikely event that the breaker could not be repaired immediately, DC loads can be shed. . Plant operating procedure-C20.9 gives instructions on extending the battery-life by-shedding and transferring certain loads to. alternate sources. l This is done with the intent of maintaining the plant on line. If the. battery' charger cannot be returned to service within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, Technical-Specification 3.7-2 requires that the unit be shut down and cooled down. q

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Accident Conditions 1

If the battery charger breaker opens during an accident, it will supply _ loads for at least 2 3/4 hours. This assumes no load shedding or transferring. It also assumes that both trains of safeguards equipment are operating. This is well beyond the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> that is specified in the USAR (USAR Vol.

3-8,5). It should slso be noted here that as previously specified only one train of safeguards equipment is needed to bring the plant to a shutdown /cooldown condition.

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What Happens MCC 1AC1'will become_deenergized if the supply to #11 battery charger fails to open under a fault condition (see Figure 7).

The following will occur:

- Inverter 17, event monitoring power supply, will transfer to its DC source (battery #11).

- Inverter 11, white instrument bus power supply, will transfer to its DC source (battery #11).

- Inverter 13, blue instrument bus power supply, will transfer to its DC source (battery #11).

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- #11 battery charger will be deenergized.

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- Panel 117 will be deenergized. Panel 117 is'a backup power supply to some primary side control systems. It is the only power supply to some secondary control systems. The net effect of losing panel 117 is that the plant can continue to run in a safe manner; however, the l plant's efficiency will be reduced due to loss of power to equipment such as feedwater heater level control.

(see attachmen' 7 - Load Lists).

How Discovered The control room operators will be alerted to the problem by a series of alarms. The most obvious will be:

- #11 Battery Charger AC Failure

- #17 Inverter Bypassed

- #11 Inverter Bypassed

- #13 Inverter Bypassed Normal Operation As stated earlier, the plant will continue to operate if MCC 1ACl is lost. However, the secondary side efficiency will be reduced due to control problems. Also, some secondary 1 1

side system alignments will have to be altered due to loss of power.

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From'aiplant. safety standpoint.this is equivalent to losing-

'just'#11' battery. charger. All : reactor control and safeguards' systems:are power'ed and function normally.

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7 The= main effect .is loss of #11 Battery Charger. 'This situation' was discussed in the previous section '(premature opening of the battery charger breaker).

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' Accident Conditions Again, the main effect due to losing MCC 1ACl is loss of #11 battery charger. This situation is addressed in cthe premature breaker opening section, t

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provide more than the 1 hr. ' capacity, specified in the USAR to safely shut down the plant.

Normal Station Battery Operation Black-Out Life Battery Load Load I i 11 1 ~35 amps 230 amps 2 3/4 12 ~35 amps 522 amps 1.6 21 , ~35 amps 207 amps 4 l

22 l ~35 amps l 464 amps 2 Therefore, there is no further discussion on these chargers.

1 III Feedwater Isolation to #12 Steam Generator (MV-32024 Bkr #123-36) [#22 Steam Generator-MV-32029 Bkr #223-37]

The purpose of #12 [#22] Steam Generator feedwater isolation valve is to provide one train of containment isolation.

It receives an auto close signal from the containment isolation (CI) Train B circuitry. Back up containment isolation is provided by the check valve F-8-2 (2F-8-2) located in containment. (See Figure 14)

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L III.A. Premature Breaker Opening What Happens*

A CI signal causes MV-32024 to get a close signal, which results.in the br'eaker opening. (Attempting to open MV-32024 when it is closed is not considered here s

because the valve is already in the safe condition).

A CI occurs as a results of a safety injection (SI) or a manuel initiation.  ;

How Discovered f

The Control Room operators would be alerted to MV-32024 i i

(MV-32029) not being closed because its light on the l i

Containment Isolation panel would not be lit. Also, the Emergency Response Computer System (ERCS) would alert the operator. The operator would then look at the valve's indicating lights on the control board. Becauce both the open and closed light would be out the operator would know the breaker had tripped.

I Normal Operation This valve is not operated during normal operation; therefore there is no impact.

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' Accident' Conditions

'One of the initial memorized actions-following a SI is

.to verify _that all containment isolation valves are i closed. Using the instrumentation discussed above the Control Room operator would direct the-Auxiliary Building operator to manuall'y close MV-32024 (MV-32029).- Until MV-32024 (MV-32029) is closed, isolation is provided by the check valve F-8-2 (2F-8-2). Either the check valve or the motor valve by themselves provide adequate containment isolation (USAR Vol 2 Section 5.2)'.

III.B. Breaker Not Opening What Happens-Assuming there is an electrical fault downstream of 123-36 (223-37) a CI signal ~will deenergize MCC lKA2 (MCC 2KA2). This is because breaker'123-36 fails to open under a fault condition (See Figure 11). Attachment'8 is a load list of what loads are deenergized.

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How Discovered

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This will on'ly occur as a result of an SI/CI. As the Control Room Operator goes th, rough the iEitial action on an SI, they will discover some "SI Active" lights not lit and some " Containment Isolation" lights not l'it. They.

will also notice no control board light indication.for the affected valves.

Normal Operation MV-32024 (MV-32029) is not operated during normal operation.

e Accident Conditions The operator will immediately be alerted to the "SI Active" and " Containment Isolation" lights not being lit. All the valves affected are Train B valves. Therefore, Train A valves are providing the intended safety function. Part of the operators' immediate initial actions will be to take local manual control of the valves and place them in the required position. For this case, the following will need to be done manually:

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-: close 3 containment isolation valves open two SI valves s .

close one' component cooling valve open 3 containment spray valves (if'needed) lit will not be possible'to' establish Train B E recirculation if it is needed until repairs are i affected.

It must be pointed out that only. Train B' equipment is affected; Train A is functioning normally. . Train A can fulfill all safeguards functions. Manual alignment of Train B equipment is needed to restore' full' redundancy.

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IV. AC Distribution Panel 136 (Breaker #112-50)-

i The purpose of paIndl 136'is to supply loads such as.the fuel oil day.: tank fill pump and cooling water. strainer control (see attachment 9).

A. Premature Breaker Opening What'Happens Breaker' #112-50 opens causing a loss of power to panel #136. -There is no immediate effect.

How Discovered The Control Room will bc alerted by high cooling. water strainer DP.

Normal Operation No immediate actions are needed. Eventually, power should be restored to panel 136 so the cooling water strainer can backwash. -

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,: f Accident Conditions No immediate' actions are needed. Eventually power should be restored to Panel 136 so the cooling water strainer can backwash. Panel 136 is also needed to fill the fuel oil day tanks for #12 cooling water pump and the diesel driven fire pump. The day tanks are sized such that the pumps can operate for about 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

However, other pumps in the fuel oil system can be used to fill the day tanks.

1 B. Breaker Not Opening e What Happens If breaker 112-50 doesn't open under a fault condition, the supply breaker to MCC 1ABl n'.ll open deenergizing MCC 1ABl. (See Figure 13)

How Discovered Annunciators will be actuated in the control room.

Operator investigation will reveal that MCC 1ABl is i

deenergized.

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Normal Operation No immediate actions are needed Eventually power should be restored to ensure proper operation of the cooling water system.

Accident Conditions The only immediate effect during an accident situation will be that one of the cooling water valves that separates the two units cooling water headers will not close. This is backed up by another train A valve.

The operators will determine that the train B valve is open from the SI active light not being lit. One of their immediate actions will be to close that valve.

Eventually power should be restored to MCC 1ABl to ensure proper long term operation of the cooling water system.

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Failure Evaluation

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The purpose of th'is section is to described the. thought ,

. process used in evaluating the MCCB's.

First it was assumed that th'e breakers fail. The-breaker fails differently depending on if there is an' electrical fault or not. For' example, if there is no fault downstream of the breaker, the breaker opens. This causes'the load supplied by the breaker to be lost. If there is a fault downstream,.the breaker doesn't open. As a result, the next breaker upstream opens, clearing the fault. However, this will cause an MCC to become de-energized, th..refore losing all functions powered from it.

Different examples of plant failures had to be looked at assuming the breakers in question =would not operate correctly. For example if the following is assumed:

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- A fault removes Train A safeguards equipment. j l

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- Train B safeguards equipment functions _,

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normally except for the breakers in question. 1 l

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The results are:."

- 11 and 12 battery charger would fail, but the batteries would back them'up.

The Train B feedwater containment isolation valve would not close, but it is backed up by a check valve.

- Therefore, the plant can be brought to a safe.

shutdown condition, Another scenario is to assume there is a fault downstream of the breaker for MV-32024 (123-36 see Figure 11). Breaker 123-36 fails to open. Breaker 123-15 opens, clearing the fault and de-energizing MCC 1KA2. As discussed in the evaluation, a number of Train B safeguard valves don't actuate, but they are backed up by the Train A safeguard valves.

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This is an extremely conservative approach. First, assuming all.the breakers in_ question open up under normal.loadsLis very conservative.' All loads have operated with the breakers in question installed. This is part of our normal testing procedure before a breaker is. declared operable. - ,

Second, all of the breakers 'in question have been. tested to ensure they coordinate with the upstream breaker. Thus, assuming the upstream breaker must open to clear a fault is also very conservative.

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ATTACHMENT 1 >I

. PRAIRIE ISLAND SECTION 8 l PLANI ELECTRICAL SYSTEMS 8.1 fUMMARY Each main generator feeds electrical power at 20 KV through its isolated pharm bus to the associated Main Transformer. The power requirements for station and unit auxiliaries are supplied by an Auxiliary Transformer (Unit Auxiliary Transformer) connected to the isolated phase bus, following practices that have been highly satisfactory for fossil-fueled and other nuclear units.

Auxilf.ary power for startup, shutdown and normal backup is supplied from auxiliary transformers designated IR and 2R. Transformer 1R is the normal backup source for Unit 1 and is connected ' to the 161kV external power system.

Transformer 2R is the normal backup source for Unit 2 and is connected to the 345kV external power system (via a 345-35kV substation transformer). Bus ties are provided to allow crossfeeding should one transformer be out of service.

Redundant offsite power sources are provided of sufficient capacity to supply 82-056 all critical loads for either or both units. Each Safeguards bus has a preferred and alternate oefsite source consisting of a startup transformer or a cooling tower substation transformer. The cooling tower substation sources are not large enough to also serve as a redundant startup source. Emergency backup power, to ensure continuity of supply for critical loads, is supplied from two onsite, quick-start d1esel genarators.

The function of the Auxiliary Electrical Systee is to provide reliable power to those auxiliaries required during any nor=al or emergency mode of plant operation.

l l The design of the system is such that sufficient . independence or isolation between the various sources of electrical power is provided in order to guard against concurrent loss of all auxiliary power.

All electrical systems and components vital to plant safety, including the l . diesel generators, are designed as Class I systems so that their integrity is not impaired by the Design Basis Earthquake, vind storms floods, or disturbances to the external electrical system. Power, control and instrument cabling, motors and other electrical equipment required for operation of the I

eng;ineered safety features are suitably protected against the effects of either a Design Basis Accident, or of severe external environmental phenomena in order to assure a high degree of confidence in the operability of such components in the event their nie is required.

Independent alternate power systems are provided with adequate capacity and testability to supply the required engineered safety features and protection systems.

The plant is supplied with nor=al, standby, and emergency power sources as i

follows:

1

a. The main source of auxiliary power during operation of either Unit is the Unit's generator. Power is supplied via the Unit Auxiliary Transformer that is connected to the main leads of the generator.

8.1-1 RIV 1 12/82

se 251 l i

,t l

c l

l PRAIRIE ISLAND .

b. Standby power required during startup, shutdown, and after reactor trip of either. Unit is supplied from the Northern States Power- j Company's 161-KV and 345-KV transmission systems.

j l

c. ' Two diesel generator sets common to both Units. are connected to the i engineered safety features buses cf both Units-to supply emergency shutdown power in the event of loss of all other a-c auxillary power.

d.- Emergency power supply of vita'l instruments, for control and for emergency lighting for each Unit is supplied from two 125V d-c

, station batteries.

The djesel' generators are connected to the separate 4160-volt auxiliary-system buses of both Units. Each set is started automatically on a safety injection signal from.elther Unit or'upon the occurrence of under-voltage on either,of its corresponding L160-volt auxiliary buses. Each diesel has adequate.

capacity to supply the engineered safety features for the Design Basis Accident in one Unit, and to allow the second Unit to be placed in a safe shutdown condition in the event of loss of outside electrical power. No accident is assumed in the second Unit.

i i

8.1-2 REV 0 12/81 e

, av r ~- 1 eY _

ll PRAIRIE ISLAND

e. Long-term cooling. After any calculated successful initial operation of the ECCS the calculated core temperature shall be maintained at an acceptably low value and d="*y heat shall be removed for the extended period of time rer,. ed by the long-lived radioactivity remaining in the core.

For any rupture of a Steam pipe and the associated uncontrolled heat removal )

from the core, the Safety injection System adds shutdown reactively so that >

l with a stuck rod, no of f site power ano minimum engineered saf ety f eatures.

there is nd consequential damage to the Reactor Coolant System and the core  ;

remains in place and intact.

I f Redundacy and segregation of instrumentation and components are incorporated to assure that postulated malfunctions will not impair.the ability of the I system to meet the design criteria. The system is effective in the event of . i loss of normal plant auxiliary power coincident with the loss of coolant, and can accommodate the failure of any single component or instrument channel,to i respond actively in the system. During the recirculation phase of a loss-of- }'

coolant accident, the system can accommodate a loss of any part of the flow path since back up alternative flow path capability is provided.

The ability of the Safety injection System to meet its design criteria is l presented in Section 6.2.3. The analysis of the accidents is presented in I

Section IL.

6.2.1.2 Inseection of Emereenev Core teoline System Design provisions are made to facilitate access to the critical parts of the reactor vessel internals. Injection nozzles, pipes, valves and safety injection pumps for visual or boroscopic inspection for erosion, corrosion and vibration wear evidence, and for non-destructive inspection where such techniques are desirable and appropriate.

6.2.1.3 Testine of Emereenev Core Cooline Svstem Comconents The design provided for periodic testing of active components of the Safety injection System for operability and functional performance'.

j Power sources are arranged to permi, individual actuation of each active l

component of the Safety injection system.

The safety injection pumps can be tested periodically during plant operation using the minimum flow recirculation lines provided. The residual heat removal pumps are used every time the residual heat removal loop is put into operation. All remote operated valves can be exercised and actuation circuits can be tested during routine plant operation.

6.2-2 REV 0 12/81 g m -- .

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PRAIRIE ISLAND l

l 6.2.3.5 Single Failure Analvsis A single active failure analysis is presented in Table 6.2-8a. All credible active system failures are considered. The analysis of the loss-of-coolant 1 accident presented in Section 14 is consistent with the single failure l analysis.

It is based on the worst single failure (generally a pump failure) in both the j safety injection and residual heat removal pumping systems. The analysis f shows that the f ailure of any single active component will not prevent fulfilling the design function. .

In addition, an alternative flow path is available to maintain core cooling if any part of the recirculation flow path becomes unavailable. This is evaluated in Table 6.2-8b. This evaluation includes all the piping in each recirculation path. A rupture anywhere in a flow path associated with any of these components requires the operator to isolate the entire path and use the alternate flow path, which action can be accomplished from the control room.

A ruptured flow path would be detected and identified by flow indication.

Rupture of a residual heat removal loop external to the Shield Building would be detected and identified (and therefore adequately located) by sump water level and by airborne activity indications associated specifically with that loop.

The su=p pumps for the RER pits are each powered by one of the rvo diesel generators.

Failure analyses of the component cooling and cooling water system under loss-of-coolant accident conditions are described in Section 10.4.2 and 10.4.1 respectively.

A single failure analysis of the Emergency Core Cooling System (ECCS) and its supporting subsystems is included in a report titled "ECCS Actuation System" submitted to the NRC dated December 22, 1976. Additional information was submitted by letters dated July 17 August 5 and September 10, 1981.

The analysis was reviewed and accepted by the NRC per Reference 4. The analysis demonstrates that the ECCS and supporting subsystems meet the single f ailure criterion as defined in IEEE STD 270-1971. The NRC requested a Technical Specification change to cover the control of evo valvas (SI-14-1 and SI-14-2, see Figure 6.2-2). Either of these valves being closed would prevent the "S" SI pu=p from inj ecting into the cold legs. Following plant 82-1.l review, the NRC was inf ormed that these valves are already cavered in the Technical Specifications under a general specification dealing with valves which could affect an injection path, o

6.2-3' RE"' 1 12/82 Sh a

~

ATTACEMENT 3

1 TELEPHONE MEMORANDUM DATE 7/12/88 1

BY E. Burke i WITH R. Peterson, E. Haupt Fluor-Daniel I SUBJECT Prairie Island Design Basis For Subfed MCC's l

. i i

I spoke with Bob and Ed to find out what the original design basis was for subfeeding MCC's at Prairie Island.

They told me that the original reason was that the number of .

electrical leads increased beyond.the capacity for the j

existing MCC's to hold the required number of cells, and new MCC's could not be fed from the existing 480 volt switchgear because there were not enough circuit breakers avai?.able to supply the number of new MCC's required.

Each subfed MCC was carefully laid out so that each would have functionally'related loads connected to it and that a loss of any load on the MCC would. effectively disable all the ,

loads on that MCC. Therefore,' coordination of protective  !

devices on the subfed MCC with the source device or. the upstream MCC was not required.

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INTERNAL CORRESPONDENCE i

]

11-8-1988 From: George Aandahl PI-NTS i To: Terry Silverberg PI Subj ect: Blackout-Related Information for JCO The attached Safety Evaluation was part of Project 82N505, and was an Addendum to the Station Blackout coping Study <

Report published in September 1987. The report examines the  ;

capacity and loading of each Safeguards battery, and provides '

an estimate of the time to discharge the battery to -l 1.81 V/ cell under Blackout conditions. The load study portion 1' of the report was provided to NSP as a data set which can be run on Lotus 1-2-3. L The new proposed revision of ECA 0.0 specifies that the P250 computer and the Containment-area Emergency Lighting shall be deeneergized under Blackout conditions to extend battery j life. I conservatively estimated the benefit of eliminating  ;

the Containment Emergency Lighting at 40 A. At this time a reasonable number for calculating the power consumed by the P-250 is not available, so I ran the data set estimating a reduction in load on #16 Inverter at 40/ 60/ 80/ and 100 A.

The total load used in the study for Inverter #16 is 168 A.

The following results were obtained:

BATT. CASE _L_O_A_D, R E D U C T I O N (A) AMPS /Pos Plt TIME (min) 12 1 lighting 40 computer 0 63 82 2 lighting 40 computer 40 57.8 57 3 lighting 40 computer 60 55.2 107 4 lighting 40 computer 80 52.6 116 i I

5 lighting 40 computer 100 50.0 125 22 1 lighting 40 q computer 0 53.5 113 l l

2 lighting 40  ;

computer 40 48.4 134 l 3 lighting 40 computer 60 45.9 148 4 lighting 40 )

computer 80 43.4 161  !

l l

M mm

~ -

ATTACHMFTr 5

INTERNAL CORRESPONDENCE l

5 lighting 40 computer 100 40.8 176 Actual load imposed.by the P-250 computer (s) will be measured 11-9-1988, to provide a basis for calculating the actual reduction in battery load under Blackout conditions.

Batteries 11 and 21 are expected to last approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> respectively under Blackout conditions.

If you have questions about this report, or additional questions to be addressed, please call me.

Truly Yours, lo ff George Aandahl Encl.: Addendum "C" of SBC Coping Study 9

Pr: ject E.82N505 NOP.3-G F2

., p

  • l Continu: tion F rm Design Chinge N3. _82N505 Part II: '

- Addendum No o j Page /f of.4f_ l l

SAkul EVALUATION REPORT (Revised)

The existing Prairie Island Class 1E Batteries per the USAR, Section 8.5.2, were j sined to carry expec:ed shutdown loads followeg a plant trip and a loss of AC battery charging power for a period of one hour crithout the battery terminal voltsge falling below 105 volts. This was based on the original plent lead-antimony bacteries which had a 960 Amphour capacity at the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> discharge race.

This Design Change 82N505, Part III, originally provided that the 2,11owing major non-safeguard loads be removed from the present Class 1E Batteries:

1 i

11 Emergency Turbine Oil Pump From 11 Battery .

)

Emergency Lighting Panel EMI-5 From 12 Battery Electric Shop DC Power From 12 Battery 21 Emergency Turbir- Oil Pump From 21 Battery E=ergency Lighting Panel EM2-4 From 22 Battery The Fluor Electrical System Load Study - Phase II, transmi::ed by FN-4659, Augus: 6, 1982, (Attachment 2 of this Design Change Package) indicates that with the above loads removed, the Class II Batteries would provide 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> under the ,

above USAR scenario without the terminal voltage fallin; below 105 volts.

However, some of the battery load assu=ptions used in that study are

(, questionable. ,

In actuality, as of this date, the original 996 Amphour 11, 12, 21, and 22 Batteries have been replaced with nominal 1800 Amphour batteries which now provide more than one hour for the plant trip and loss of AC battery charging power (Loss of all AC scanario). The following is an updated analysis of bactery capacity for the safeguard bacteries. The scope of DC 82N505 Par: III was revised due to Q-List problems such that the Emergency Lighting Panels EMI-5 and EM2-4 were not removed from Batteries 12 and 22. The f.illowing analysis also includes that new 17, 18, 27, and 28 Inverters which vare added by Projec: 80Y124 (RVLIS).

' Battery Operating Capacity for Loss-of-ell AC in Amps per positive plata is based on the following calculation: (From IEEE 435-1983)

T =(Max N 3+N)kbA R

Where N = Nu=ber of Jos. Places, Continuous Load S

N = Corrected Ntusber of Pos. Plates Ng = No. of Pos. Plates, Random Lead K7 = Temp. Correc:fon Factor K = Design Factor D -

- Kg - Aging Fac:or NCRTHERN STATE 3 PCWER COMPANY m a i m ies Pt. ANT ENGINEERING & CONSTRUCTION t - - - -

Pr: ject E. 82N505 NOP 3-GF2 d n y

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  • 82N505 Part III '

De:*gn Change No. 0 -

. f' .

Addendum No -

- Page 6 of _lf l

S"** " ^""' Random Amos KT KA KD NT" -

X CAP./Pos.PL. 1 Min. Cap./Pos.PL/

Then X CAP.Pos. PL.' = ~ 5teadv Amos N Randem Amos T- -

KT KA XD 1 Min. Cap /Pos.PL NT= 12 For C&D LC-25 NT = 11 For Exide GN-23 Appendix I indicates the Safeguard Battery Loads and analysis results.

2actory Operating Times are as follows:

3 Battery #11. 3 Hours ,

70 Minutes Battery #12 Battery #21 4 Hours Battery #22 95 Minutes .

These numbers are conservative since all inverters were assumed to be' at maximum L load which :is not really the case.

The new plant non-safeguard batteries (31 & 42), which were installed under Part III of DC 82N505, supply the major plant non-safeguard loads. The present' loads on' these batteries and associated distribution panels ar's as shown in 1

Appendia II.

A calculation w'as cons to determine the Design Operating Time with the present leads based on Battery 31 as the worst case and assuming no AC charging:

Load Profile: Starting Motor Load - 1200 A for 1 minute .

. Continuous Load - 264 A

- Random icad - 60 A $ end of cycle for 1 minute N = 17 Positive Places for GNB NCX-2550 Battery T

g=1 (77*F assumed)

K = 1.0 D

Kg= 1. 7.5 .

Based on the calculation and the GNE Discharge Characteristic Table, 31 and 42 Batteries, would be adequate for approximately 7i hours based on final voltage  :

of 1.75 volts / cell (60 cells) - 105 volts, which is the same criteria used for

!' the safeguard batteries. Using a final voltage criteria of 108.6 volts (120 nominal, 10%), which is 1.81 volts / cell, the operating time would be 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

. . l NORTHERN STATES PCWER COMPANY re = = , t s e , PLANT ENGINEERING & CONSTRUCTION

Prtjoct E 82N505 NOP.3 GF2

.- Condnuadon Form Design Change No.82N505 Part III

[. 0 _;

Addendum No Page.l.dl-of.2d

.In order to determine' an ultimate capacity of these batteries for addition of

~ future loads, another calculation was done:

Assuming the same starting loa' d and random load as above, determine the.

maximum continuous (steady-state) load such that the batteries would last for 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s: ,

' Based on the 108.6 ' volts final voltage criteria (1.81 volts / cell), the

.naximum continuous load is 604 Kap.

For the 105 volts final voltage criteria (1.75. volts / cell) the maximum continuous load is 669 Amp.

Figures and tables referenced by Section 8.5.2 of the USAR must be changed .to . ,

reflect non-safeguard loads removed from the safeguard batteries. Specific documents are listed in other parts of the Design Change Package.

Based on the above discussion, it is concluded that:

~

'A. The change is not in conflict with the k'echnical Specification.

3. 'The change does not include an unreviewed safety question.

C. The changedoes involve a system described in the FSAR.

D.# The change 'does not create a possibility of an accident nor equipment *

., malfunction which is different from those previously analyzed in the

'FSAR or amendments.

E. The change also does not increase the possibility of occurrence nor the consequences of an accident or equipment malfunction wh!:h has .]

been evaluated in the TSAR or amendments. . j

. 1

'F . The change does not reduce the margins of safety as defined in the basis for Technical specifications of this plar G. Based on the above, the change does not adversely affect the safety of the plant nor the health and safety of the public. T l

Prepared By k Date ~~7!/6' 7 Reviewed I'y Date I/I![2 t -

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NCRTHERN STATES PCWER COMPANY __

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OVERALL DIMENSIONS WE!GMTS-VOLUMES OUTLINE l NOM. DR AWING: l TYPE' A.H. LENGTH WipTH HEIGHT UNPACXED ' DOMESTIC

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1 MIN.

L To 1.75 VPC Final GN13 1840 ' 24 3 ' 64 109 1 143 1 198 1 225 1 270 i 355 i 420 t $35 6 760 ! 922 1090 2035 GN15 1260 25.7 69 . 118 -

157 ' 215 . 248 295 390 465 ? 600 860 1 1046 1230 2300

( i]N. t 1 1500 a5 77 135 187 255 304 365 480 560 710 980 1230 1680 3360 2-- t 9 1600 31 1 82 145 199 280 333 400 525 615

  • 785 1075 1365 1830 3725 CN_21 1700 31 8 86 154 ' 213 300 36 1 430 565 670 856 1160 1500 t970 4085 M N d Q t800 31 9 o U t60 225 325 [ 385 ] 460 605 725 i 925 1240 t625 2100 4:30

%1.81 VPC Final l G;413

  • 1840 4 e i 103 i 136 i 185 1 212 250 1 315 i 370 l 465 . tito i 7t9 817
  • i GN15 1260 112 i 149 1 200 1 231 ' 270 + 350 1 400 l 125 690 815 922 '

GN t 7 t500 129 175 240 lJ84 336 430 i 505 i 625 805 965 1200 ,

GN.19 1600 i39 189 260 '

310 3 367 474 - 555 i 685 ' 885 1070 1385 -

GN.21 1700 147 203 283 385 -

396 515 605 ! 745 960 t 1170 1425 i

GN 23 1800 155 214 i 303 1 360 422 555 650 t 800 1035

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~

ATIACEMENT 6 l

l

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.DATE 08 SOV 88 13:02:36 REPORT' GENERATION ENGIN1 1.1 3 .;

PANEL i 117' (208/120VAC)  ;

' LOCATION: AUX BLDG 715' RELAY ROOM

. SOURCE: MCC 1AC BUS 1 BKR 112-35 TURB BLDG 695' (D8)' d

REFERENCE:

.NF-40024-1, NF-40302-1

___,____________,_______________---------------------------------2 PER CKT------ l BKR No. DESCRIPTION FUSED SWITCH DATA 1 MFG TYPE SIZE

, )

1 SPARE BUSS NON 20 I

-2 CHLCRINE DETECTOR 28434 BUSS FRN-R3 l 3 AC PANEL 118 BUSS FRN 20 j 4 122 MISC SYS RELAY RACK BUSS FRN 20 1 5 SPARE 6 RELAY CAB 1235 '

SHWMT TRIONIC 7- ANN CAB 1AP3 BUSS FRN-30 30 8 . SPARE 9 ROD DRIVE CONTROL POW BUSS NON 60 10 ANN CAB.11 THRU 16 SH5'MT TRIONIC 60 11 SPARE BUSS ~ FRN

.12 FILTER DEMIN CONT PANEL 58900 SHWMT TRIONIC 13 PANEL 115 ALT SPLY SHWMT TRIONIC 63 14 PANEL 112 INSTR BUS I BUSS FRN 100

.15 PANEL 113 INSTR BUS III BUSS FRN 100 16 PANEL 114 INSTR BUS IV BUSS FRN 100 17 PANEL 111 INSTR BUS II BUSS FRN 100 18 AC PANEL 1117 BUSS 100 19 ANN CAB 2AP3 BUSS 20 MAINT FEED TO DIST PANELS 1EMA & 2EMA BUSS 60 21 EMER LTG TRANSF SW BUSS FRN 100 22 INVERTER 16 BUSS FRN 100

..... END REPORT .....

m NERBEREIMEumulE BEEEEEEEEEEEEE M

?

ATIACEMEhr 7

L

'EdRC) ECU 1EU CELE C1 NEAR CHARGING' PUMPS SO , RET TO BUS 2REF: NF-40036; NF-40209-1;2; NH-40049-2 -

17 FINDS I k k 2.

2ELLOTOR #ITLEV NUMBERCC

, A2 123-19 SAFETY INJ TEST TO 11 RFLG WTR TK VA B 32203 1KA2

, A4 123-26 REFUELING WTR TO SAF INJ PMPS HDR ISOL 32080 1KA2

, A5 123-25 BORIC ACID SPLY TO SAFETY INJ PMPS ISO 32082 1KA2 l

, B1 123-28 11 CONTAINMENT SUMP B ISOL VA-A2 32076 1KA2 l

, B2 123-29 11 CONTAINMENT SUMP B ISOL VA B2 32078 1KA2

, B4 123-24 COMP CLNT HDR TO WST DSPL SYS HT EXGRS 32102 1KA2

, C1 123-36 FEEDWATER TO 1B STEAM GEN ISOL VA 32024 1KA2

, C2 123-20 12 CONT. SPRAY PMP DISCHARGE VA 32105 1KA2

, C3 123-16 12 CONT. SPRAY PMP SUCT FROM RSDL HT EXGR 32097 1KA2

, C4 123-17 12 CONT. SPRAY PMP SUCT FROM RFLG WTR TNK 32099 1KA2 #

, D1 123-34 RESIDUAL HEAT REMOVAL TO 12 SAF INJ PM 32207 1KA2

, D2 123-23 11 REAC CLNT LP B HOT LEG SMPL ISOL MV B 32405 1KA2

, D3 123-27 12 SAFETY INJ PUMP SUCTION ISOL VA 32163 1KA2 l

, El 123-30 12 COMP CLG HT EXGR OUTLET VA 32121 1KA2 '

, E2 123-31 12 COMP COOLING PUMP SUCTION VA 32201 1KA2 i

, E3 123-21 1B STEAM GEN BLOWDOWN & DRAIN HEADER VA 32058 1KA2

..... END REPORT .....

2. M 7 CdLL MCrrUR NtJ il iti MV NUMEhR

(*) 223-23 21 REAC CLNT CP E S'OT LEG SMPL ISOL MV B 32411 223-5L 22 COMPONENT CGOLING PUMP COOLING FANS

- 223-52 23 CHARGING PUMP COOLING FANS 223-53 21 CHARGlhG PUMP COOLING FANS 223-54 22 CONTAINMENT SPRAY PUMP CCOLING FANS 223-55 22 5 AFET Y ]NJ PUMP CLG FANS

- 223-56 202 SW GR RM CCOLING FANS 223-57 21 CHARGING FUMP ROOM EXHAUST FAN 223-56 23 CHARGING PUMP ROOM EXHAUST FAN Al 223-3C 22' COMP CLG HT EXGR OUTLET VA 32123 AZ 223-31 22 COMP COOLING PUMP VA 32212 A3 223-38 2A. STEAM GEN ELOWOOWN & DRAIN EbADER VA 32051 A4 223-30 26 - STEAM GEN bt0WDOWN 6 DRAIN HEADER VA 32059 51 223-27 22 ' dAFETY INJ PUMP SUCT ION ISOL VA 32191 b2 223-34

  • COMP CLNT HOR TO WST DSPL SYS NT EXGnS VA 32106 B3 223-3T '

FEEDWATER TO 22 STEAM GEN ISCL VA 32029 C1 223-33 sRESIDUAL HEAT REMOVAL TO 22 SAF INJ PMP VA 32209 C2 223-4G 42 , CONT. SPRAY PMP DISCHARGE VA 32116 C3 223-lo 22 CONT. SPRAY PMP SUCT FROM kSCL HT EXbR VA 32109 C* 223-17 22 -CON T .SP RAY PMP SUCT FROM RFLG WTR TNK V A 32111 D1 223-28 21

  • CONTAINMENT SUMP B ISCL VA A2 32179 D2 223-29 21 ' CONTAINMENT SUMP B ISOL VA B2 32181 03 223-35 21 ' AUX BLOG CLG WTR RET HOR VA 32329 E2 223-19 LSAF INS TE ST TO 2) RFLG WTR STRG TNK VA B 32205 E3 223-50 CAC LISTRIeUTION T NEL 235.

32183 E6 123-26 4 REFUELING wTR TCf SAF INJ FMPS HOR 150L VA B 32185 ES 223-2$ #80RIC ACIO SPLY TO SAFETY INJ PMPS I SCL V A B

g. .wew .e44 e v- - Eh

~~~

ATIACHMENT 8 i

l

NF - 4 0190-8 ; 000-68808-73 w- _-

h5hF-Abbb6 a

?

" " ' " " "'MV NUMBER"MCC"

' 2"' CELL ~ MOTOR #~~~ TITLE DIESEL ~ " " "CLG

" " "WTR

~"~ PMP" ~121OIL STG TK PMP 1AB1

- 112-51 1AB1

- 112-52 121 SCREEN DIFF CONTROL PANEL 1AB1 FIRE PUMP 121 OIL STORAGE TK PUMP

- 112-12 - 1AB1 121 COOLING WTR TRAVELING gATER SCREEN

, A1 112-10 1A81

' A2 112-15 12 COOL WTR PUMP LEFT WATER JACKET HTR 1AB1 AC OIST PANEL 136 FEEDER

, A3 112-50 - 1A81

, A5 112-26 12 , COOLING WTR PUMP LUBE OIL PUMP 32034 1AB1

, Si 112-9 121 COOLING WTR PUMP OISCH HEADER VA A 32036 1A81

, B2 112-8 121 COOLING WTR PUMP OISCH HEADER VA C 1A81

, 84 112-14 12 COOL WTR PUMP RIGHT WATER JACKET HTR 1A81 C1 112-21 11 COOLING WATER STRAINER 1AB1 C2 112-22 21 COOLING WATER STRAINER 1AR1 C3 112-27 12 COOL WATER PUMP START AIR COMPRESSOR 1AB1

, CA 112-24 11 SCRNHSE VERT WTR PMP MTR CLG SPLY FAN 1A81 C5 112-23 11 SCREENHOUSE DIESEL COOL SPLY FAN 1AB1

.2/ ,

,il ,C6 112-25 11 ROOF EXHAUST FAN

..... END REPORT .....

9 9

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