ML20092F736

Training Lesson Plan to Rev 4 to LO-LP-60315-04-C, Loss of Rhr

ML20092F736
Person / Time
Site:	Vogtle
Issue date:	09/01/1989
From:	Fitzwater L GEORGIA POWER CO.
To:
Shared Package
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References
CON-IIT05-002-131A-90, CON-IIT05-191-000D-90, CON-IIT5-191-D-90, CON-IIT5-2-131A-90, RTR-NUREG-1410 LO-LP-60315-04, LO-LP-60315-4, NUDOCS 9202190482
Download: ML20092F736 (12)

Text

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GEORGIA POWER POWER GENERATION DEPARTHENT y

VOCTLE ELECTRIC GENERATING PLANT 4t TRAINING LESSON PLAN TITLE:

LOSS OF RESIDUAL HEAT REMOVAL NUMBER:

LO-LP-60315-04-C PROGRAM LICENSED OPERATOR TRAINING REVISION:

4 AUTHOR:

L. FITZWATER DATE:

0/9/69 APPROVED:

1 DATEi (l'

INSTRUCTOR GUIDELINES:

I. Lesson Format:

A-Lecture With Visual Aids II.

Materialst A.

Overhead Pro.jector B.

Transparencies C.

White Board With Markers 111.

Evaluation:

A.

Written or Oral exam in conjunction with other Lesson Plans IV.

Rexarks A.

Performance-based instructional units (IUs) are attached to the lesson plan as student handouts.

Af ter the lecture on Loss of Residual Heat Removal. the student should be given adequate self-study time for the IUs. The instructor should direct self-study activities and be available to answer questions that may arise concerning the IU material.

After self-study, the student will perform, simulate. observe, or discues (as identified on the cluster signoff criteria listi unit in the presence of an evaluator.the task covered in the instructional MAS"a COPY

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PURPOSE STATEMENT:

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FOLLOWING COMPLETION OF THIS LESSON. THE STUDENT WILL POSSESS THOSE KNOWLEDGES SYSTEMATICALLY IDENTIFIED FOR THE PERFORMANCE OF LOSS OF RESIDUAL HEAT REMOVAL TASKS 11.

LIST OF OB.iECTIVES:

1.

Describe factors that can lead to a loss of RHR.

2.

State the possible consequences of a sustained loss of.RHR.

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e LO-LP-60315-06-c

REFERENCES:

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1.

Plant Vogtle Procedures

-18019. " Loss of Residual Heat Removal" 2.

. Technical Specifications: None 3.

Vogtle Training Text None 4.

Plant Manual: None 5.

Design Manuait None 6.

P& ids. Logics and other Drawings: None 7.

Vendor Manuals and other Referencess None 8.

FSAR: None 9.

Commitments and other Requirements:

IEN-87.023 Diablo Canyon Loss of RHR IEN-86.101 Loss of RHR due to Loss of Fluid Levels in RCS OKR 3L4 CCW Inventory Losses Resulting in Loss of RHR CL-88.017 hRC Concerns and Actions on Loss of RHR SOER 88.003 Losses-of RHR with reduced water level at PWRs 10.

Transparencies LO-TP-60315-001, objectives 11.

Instructional Units LO-10-60315-001 Respond to Loss of RHR 12.

Handouts LO-HO-60315-001 Industry Event Summaries I

(SOER 88.003) l t

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111.

LESSON OUILINE:

NOTES I.

INTRODUCTION A.

The loss of Residual Heat kemoval Procedure AOP-18019-C is to identify and correct a loss of RHR capability B.

Procedure covers Loss et RHR in:

1.

Modes 4 and 5 2.

Mode 6 (head removed)

C.

Present Lesson Objectives LO-TP-60315-001 II.

PRESENfATION A.

Symptoms:

1.

Unexplained decrease in RHR flow or discharge AOP-18019 pressure 2.

Detected RHR system excessive leakage while AOP-18019 RHR in operation 3.

Any unexplained raise in RCS te:nperature while AOP-18019 RHR in operation 4.

Any observed loss of RHR capability while RHR in operation AOP-18019 5.

CL 88.014 lists the following conditions in which entry to Loss of RHR Procedures may be required Accidental loss of a system that is oper-a.

ating to cool the RCS b.

Unsuccessful attempt to start a system when the system was to be used for RCS cooling and the RCS was not being actively cooled by~another DHR system Uncontrolled and significant loss of RCS c.

inventory d.

Uncontrolled and significant break in the RCS coolant boundary Any valid symptom of loss of control of the e.

state of the RCS. such as uncontrolled temp-erature increase uncontrolled pressuriza-tion. or the attainment of values of these 4

c._.____-__

LO-LP-60315-04-C i

121, LESSON OUTLINE:

NOTES parameters Ehich are sufficiently high that action is required that is not contained within normal procedures f.

Significant core damage expected Any valid symptom of significant core damage g.

obse rved B.

Factors that can lead to a loss of RHR l.

Improper valve lineups Many projects / evolutions occurring a.

simultaneously b.

Loss of control Personnel in plant not keeping control or c.

informed of changing conditions d.

Lack of coordination 2.

System leakage Improperly seated valves a.

b.

Improper valve lineups i

Operator not familiar with valve position c.

verification methods for reach rod operated valves d.

[

Loss of control of evolutions Inadequate tagging orders e.

f.

Normal system leakage not considered 3.

Deficient procedures Infrequently or first time used procedures a.

- untested b.

Abnormal conditions requiring special procedures or temporary procedures 4.

Opening RCS or related systems a.

50 manway removal b.

Reactor vessel head e

• sil

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a

T LO-LP-60315-04-C III.

LESSON OUfLINE:

NOTES

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Reactor coolant pump seal replacement c.

d.

Installation of local reactor vessel level standpipe e.

Venting CRDH's 5.

Starting idle RHR loop Idle loop partially drains while shutdown a.

due to gas coming out of solution and accumulating in unvented high points b.

Gas pocket shifts to pump suction - pump cavitation results i

c.

Gas pocket shifts to reactor vessel with subsequent de rease in level d.

Gas pockets shift to atmosphere through open reactor vessel or other system components, with a subsequent decrease reactor vessel level to fill the void left by the gases 6.

Poor communications l

a.

Inadequate / incomplete shif t turn over b.

Information on phone system not clear, no i

repeat backs. misunderstood / wrong l

interruptions i

c.

Distracting activities in control roon and/or other critical areas d.

Inadequate / improper documentation of problems or evolution during shift 7.

Changing plant conditions a.

Pressure reduction

1) Gases coming out of solution b.

Lowering reactor vessel level for reactor head removal /other maintenance Opening reactor cavity refueling transfer c.

gate valve d.

Surveillance is in progress 6

9 LO-LP-60315-04-C III4 LESSON OUTLINE:

NOTES e.

Pressurization of RCS

1) Caused by steam formation in unvented reactor vessel

2) Inappropriate use of SG nozzle dam can lead to core voiding within 15-20 min-i utes following loss of RRR

3) Cold leg opening can allow water to be eje ~.ed from vessel following loss of RHR until sufficient water is lost that

4) Steam is relieved by clearing the crossover pipes 3)

Pressure difference within RCS may pre-vent water from reaching the RV

6) Rapid RCS pressurization may prevent gravity feed from tanks anticipated to be available

7) Rapid pressurization may cause instru-ments to malfunction or provide mis-1eading indications l

8) Rapid pressurization may cause the RCS to respond in unanticipated ways

9) Small RCS openings (vents and drains) may lead to instrument malfunctions or unanticipated RCS responses

10) Large RCS pressure boundary openings j

(SG manway. RCP seals. pressurizer man-l ways) may lead to instrument malfunc-tion or unanticipated RCS responses

11) SG secondary side inventory and opening may influence RCS behavior f.

Vortexing

1) Small amount of air into RHR' pump suc-tion may lad to subtle changes that occur ove3 a time of minute to an hour i

or more

2) Large amounts of air may cause immedi-ate loss of RER 7

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LO-LP-60315-Oo-C I

III.

LESSON OUfi?1NE:

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I NOTES

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3) Vortelst'ng may occur at levels higher than anticipated

4) Vortexing may not be reflected by pump current and flow rate instruments until it is sufficiently severe to cause a loss of RRR

3) Vortexing may cause RCS level indien-tion errors g.

SG tube draining

1) Draining SC U-tube is frequently done by draining the RCS to the point where vortexing could occur h.

RCS level differences-

1) Critical level parameter is in hot leg where RRR takes suction

2) Level instruments connected at other points

3) Level differences exist between level indicator and hot leg EE.1 connection i

point'(may be several inches difference) i.

RER system effects 1)

I Shif ting from one train to anothericay l

cause level changes due to differences in actual size etc.

2) Starting one size while another is run-ning can increase total flow thus in-crease sortexing i

3) Operator response to loss of one PHR l

pump by starting the second pump may result in the loss of the second pump l

also if started without correcting the l :.

cause of the loss of the first pump-i j.

4) Stopping or starting RRR may cause RCS i

level change due to partially filled systera or air inductio1 into the RHR system j.

Instrumentation i

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LO-LP-60313-06-C III.

LESSON OUTLINE:

NOTE 5'

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1) May be 'in error by half a foot or more without detection of inaccuracles

2) Flow dynamics, entrapped air, and pres-surization may affect level indication.

individua.11y or all indicatorn simultaneously

3) Many normal instruments disconne:cted during RV head removal etc.

4) Remaining instruments may be insdequate 8.

Loss of CCW Begin OMR 324 Loss could be from impreper clearance on a.

one RER heat exchanger that comprises the operable heat exchanger b.

Loss of CCW to heat exchanger prevents heat removal from RCS Care should oe taken when tagging one heat c.

exchanger so as not to compromise remaining heat exchanger End DMR 324 C.

Consequences of Loss of IUiR l

l.

Core damage h

1 Loss of core cooling a.

f 2.

Radioactive releases to the environment t

Open RCS with contalament open to

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a.

atmosphere

,A 3.

RCS overpressurization due to heat up from M

decay heat 1

-e 4.

Contamination of personnel i)

U f

5.

Activation of emergency plan f

D.

Loss of RHR in Modes 4 or 5 1.

Use ADP 18019 to discuss this event Ensura students pay particular nttention a.

to:

1) Caution statemfat at beginning of 9

LO-1.P-60315-04-C III.

LESSON OUTLINE:

N0'fES Section A

2) The' statement thac steps Al thru A3 are to be performed continuously until exit frota this procedure

3) Note before Step Al Discuss each of these figures with the class

4) Note statement before step A3

5) Indications of RHR pump cavitation Quiz selected student to ensure the class has an understanding

6) Note statement before step A5

7) Note statement before step A6

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8) Note statement before step A7 b.

The procedure establishes the priorities ns:

1) Honitor/Haintaining coro cooling

2) Monitor / Reestablishing adequate RCS inventory

3) Restore RER

4) Deteristne/ establish alternate RCS rooling

5) Fix problems

6) Return to normal ops E.

Loss of RER - Modes 6 1

Use AOP 18019 to discuss th4.5 event This procedure provides the following a.

priorities

1) RCS level above Rx vessel flange

2) Suspend boron reduction

3) Verify RRR pump flow path

4) Level greater th<n :1 feet above Rx 10 l

1 LO-LP-bO313-06-C III.

LESSON 'dUTLINE :

NOTES vessel flange

5) No loss of inventory has occurred (If it has must return to Section A of 18019)

6) Repair problems i

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7) Be prepared to secure the RER train that may be subsequently lost i

8) Rectore RHR

9) Initiate alternate cooling F.

Industry Events TEN 07.023 1.

Diablo Cusyon IEN 87.101 GL 88.017 Loss of both RHR tra'ns while in Mode 5 Event included in a.

LO-80-60313-Oc1 b.

RHR out for 1 - 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> SOER 88.003 Containment equipment hatch was removed c.

d.

S/G manway receval was in progress with-RCS inv. at mid-loop level of Th RCS temp increased from 87 F to boiling e.

(212"F) f.

Steam was vented from Rx vessel head l

Water spilled' f rom partially removed aanway g.

l to containment t'loor h.

Containment radiogas level begins to increase

i. RER restored J.

Potential problems

1) Core damage due to boiling out RCS inv.

2) Rad release to evir.

III.

SUKHARY A.

Review Objectives 11

r LO-LP-60315-04-C III. LESSON OUTLINE:

NOTES t

1.

DESCRIEE FACTORS' TRAT CAN LEAD TO A LOSS OF RHR a.

Improper valve lineup Refer to LP Section II.3 for examples b.

System leakage and discussion c.

Deficient procedures d.

Opening RCS or related systems e.

Starting Idle RHR loop f.

Poor communication g.

Changing plant conditions 2.

STATE THE POSSIBLE CONSEQUENCES OF A SUSTAINED LOSS OF AHR a.

Core danage b.

Radioactive release to environment c.

RCS overpressurization d.

Personnel contamination l

Activation of the emergency plan e.

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