AECM-84-0180, Rev 1 to Procedure 14-S-01-4, Training & Administrative Section Procedure

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Rev 1 to Procedure 14-S-01-4, Training & Administrative Section Procedure
ML20087N496
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 03/30/1984
From:
MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20087N487 List:
References
14-S-01-4, 14-S-1-4, AECM-84-0180, AECM-84-180, NUDOCS 8404030511
Download: ML20087N496 (44)
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Attachment 1 to AECM-84/0180 Emergency Assessment Training Examination 4

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.2-GRAND GtJLF NUCLEAR STATION TRAINING AND ADMINISTRATIVE SECTION PROCEDURE i' .

I 14-5-01-4 i Rev. 1 i

[~ QA Record,.Related Docu=ent # NA l Attachment VII l Page 1 of 1 1

\ No. of Pages ,Date , Initials 1

EXAMINATION (Stud 5ric Name)

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IXHEFl l l l DATE EXAM SCORE Total Points: 20.25 Actual Points:

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EAL-1 2 pts. 1. Considering u re fuel damage, indicate the appropriate Ea.

A. degraded core with loss of coolant geometry _

B. severe loss of fuel cladding .

C. fuel damage indication . T.

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D. loss of 2 of 3 fission product barriers with a potential 'Ji loss of the 3rd barrier ** . #A

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EAL-2 2 pts. 2. Considering " loss of 2 of 3" fission product barriers in ~'f'!!

1D sbove, wha: boundaries or parameters are used to define .a "ch this condition? y A. -4

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C. j' EAL-3 2 r,ts. 3. Indicate the appropriate EAL .

A. MSL break outside containment w/o(without) isolation -

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,. E B. MSL break inside containment with isolation C .' RCICsteamlinebreakoutsideofcontain=entw/oisolation]

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'N EkL-4 2 pts. 4 Consid ring major A.C. GlGctrical fcilurns, whit initiating c nditions would rcquira A. Site Emergency declaration?

B. Alert declaration?

. EAL-5 2 pts. 5. Conheering fire, vnat initiating condition "culd require .

A. Alert declaration?

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B. Sire Emergency declaration?

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EAL-6 2 p ts . *

6. Under what circumstatice would kn'overe5cposed and/or contaminated injured individual be considered and Unusual Event?

EAL-7 1.5 pts. 7. As an. Operator, how would you handle a security threat given to y.ou over the phone.?. What EAL would this require?

E.U.- ? 1 pt. 8. Unaer natural evenum, what natural events w'ould constitute declaring an Alert?

EAL-9 3.75 pts. 9. Under "other" catagories, list Iive(5) initiating conditions along with the for each._

EAL-10 2 pts. 10. Why'sh6ul'd abnormal Primary Coolant Chemistry limits as defined in EPP-1 constitu*e and, Unusual Event situccion?

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Attachment 2 to AECM-84/0180 o

Systems Training and Examinations 3.

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GRAND GULF NUCLEAR STATION SHIFT ADVISOR TRAINING GRAND GULF TECHNOLOGY I. INTRODUCTION

. This outline describes the systems training for shif t advisors. Systems training is a three week self-study course.

II. ?URPOSE '

The purpose of this' course is to cover the Grand Gulf Nuclear Station systems with an emphasis on safety systems and the differences between a 3WR-4 and a BWR-6.

-III. CONTENT Because the course is self-study, systems to be covered are assigned on a

(. weekly basis. Upon the completion of each week of systems, an exam of 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in length will be given. Systems assigned for each week of self-study are per the following list.

A. ' Week 11 Systems:

1. B13 Nuclear Boiler and Vessel Internals
2. B21 -Vessel Instrumentation
3. 333-1 Recirculation System
4. B33-2 Recirculation Flow Control System
5. Cll-1A Control Rod Drive Hydraulic System
6. Cll-1B Control Rod Drive Mechanism System
7. C11-2 Rod Control and Infor=ation System
8. C41 Standby Liquid Control Syste:
9. C51-1 Source Range Monitor System
10. C51-2 Intermediate Range Monitor System.
11. C51-3 Local Power Range Monitor System

-12. C51-4 Average Power Range Monitor Syste:

13. J11 Nuclear Fuel e
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3. Week 2 Systems:

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14 C71 Reactor Protection System

15. D17 Process Radiation Monitoring System
16. E12 Residual Heat Removal System
17. E21 Leu Pressure Core Spray System
18. E22 High Pressure Core Spray System
19. JE22-1 Automatic Depressurization System
20. 'E30 Suppression Pool Makeup System
21. E32 MSIV Leakage Control System
22. E38 Feedwater' Leakage Control System
23. E51 Reactor Core Isolation Cooling System
24. E61 ccabustible Gas Control System
25. G33/36 Reactor Water Cleanup System
26. G41/46 Fuel Pool Cooling and Cleanup System
27. T48 Standby Gas Treatment System C. Week 3. Systems:

r: 23. L11 Plant DC Sy-.em 4 29. M41 Containment Cooling System

-30. M41-1 Containment System

-31. M51 Drywell Cooling System

32. M71 CTMI and DW Instrumentation and control
33. N11 Main and Reheat Steam System
34. N19 Condensate System
35. N21 Feedwater System
36. U22/P60 Condensate and Suppression Pool Cleanup System
37. N32-2 Electro-Hydraulic Control Logic System
38. N62 Condenser Air Removal System
39. N64 Low Temperature Offgas System
40. N71 Circulating-Water System
41. P41 Standby Service Water System
42. P42 Component Cooling Water System
43. P44 Plant Service Water Sysrem
44. P75 Div. 1/II Standby Diesel Generators

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. 45. PSl Div. III. Standby. Diesel Generator

46. R20- Nor=al AC Pcwer System
47. R21 ESF. Power System IV. MATERIALS Each student is given' a copy of the Grand Gulf Nuclear Station System Lesson Notes for each of the' applicable systems. Additionally, a copy of the System Descriptions are made available for use as reference material.

V. FSAR RE0t*IREMENTS The FSAR does not address training for. Shift Advisors, so no FSAR requirements are met by this course.

VI. Successful' completion of this course meets the commitment for- Systems Training for Shif t . Advisors per. the ' [[letter::AECM-83-0754, RO 83-103/0:on 831017,fire-rated Penetrations CE 230D,CE 205D & CE 153D Opened to Implement Design Change Package. Fire Watch Established Until Penetrations Resealed on 831102|November 23, 1983 letter]], AECN-63/0750. to the NRC.

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SHIFT ADVISOR TRAINING Grand Guif Technology Exam GGT 8405-02 Week 1 B13/21-19 (3.0 pt)' 1. Label the attached drawir.g B13/21-19A.

B13/21-29 (1.5pt) 2. What.is the function o.f the steam line flow restrictor? To what value is steam flow limited?

B13/21 (1.5 pt) 3. Will a level indicator calibrated for operating conditions give an accurate reading as the vessel water cools down?

Explain your answer.

B13/21-27 (3.0 pt) 4 List the five (5) ranges of vessel level instrumentation. Give tne ranges referenced to instrument zero and state the Rx' condition each is us.ed for.

833-23 (3.'0 pt) 5 .' Preparing for a Rx startup, the operator pushes the start button on CB-5 for Recirc Pump A. Feedwater flow is less"than 30%

ano all other interlocks are met.

Basically describe what will happen.

-333-24 (3.0 pt) 6. a) List the indications you would receive if Recirc Pump A-#2 seal completely failed.

b) Would you expec.t to receive any other drywell or containment alarms shortly afterward?

B33-25 (2.0 pt) 7. What are the vessel thermal shock interlocks? List the setpoints and where they are measured.

B33-26 (2.0-pt) 8. List three (3) things that will cause the recirc pumps to dcwn shift hi to lo speed.

List setpoints.

J11-31' (2.0 pt) 9. List five (5) ways to determine proper '

fuel assembly orientation in the core.

J11-33 (2.0 pt) 10. Where are the fuel assembly water rods located? How many are tnere in each assembly, and what is tr.eir purpose?

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. SHIFT ADVISOR TRNG-GGT Exam GGT 8405-02 Page 2 C11-H-33 _( 1.5 pt) 11. What is the purpose of the stabilizing valves in the CR0 Hydraulic System? How many valves are there and how many activate on an insert signal?

C11-H (1.0 pt) 12. What is the purpose of the restricting orifice in the CRD Hydraulic System charging water neacer? Why is a check valve included in tne header?

C11-M-06 (1.0 pt) 13. What is the purpose of the CR velocity limiter?

C11-M-17 (1.0 pt) 14. What is the purpose of the ball check valve in tne CRDM? When coes it function?

C11-R-15 (1.5 pt) 15. With regard to the RC&IS System,.wnat'is the significance of the LPSP, LPAP, HPSP.

Give setpoints and limits (not rod pattern limits).

C41-15 .(2.0pt)'16. List when SLC must te injectec oy Plant Procedures.

C41-16 (2.0 pt) 17. Describe tne operation of SLC System upon initiation and. include how :ne operator verifies SLC is injecting into the RPV after initiation.

C51-AV-14 (2.5 pt) 18. Answer the following for each of the subsystems of the neutron monitoring system (SRM, IRM, LPRM, APRM):

a)' number of detectors or channels b) type of detector c) method used.to determine power d) method usec to compensate for gammas e) units (cutput) f) scale (output)

C51-5-15 (2~0 pt)

. 19. What conditions in the SRM monitor cust the operator verify before Rx startup?

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a SHIFT ADVISOR TRNG-GGT Exam GGT 8405-02 -

Page 3 C51-IR-16' -(1.0 pt) 20. What are the purposes of tne Mean Scuare Analog Unit in the IRM System?

-C51-LPRM-13 .(2.0 pt) 21. How can the LPRM System give ,

representative values of heat flux (w/cm-)

at every uncontrolled gap? Give the LPRM core axial locations referenced to BAF.

C51-AV-15 (1.5pt) 22. What minimum LPRM inputs are required to an APRM channel to keep it from being declared inop?

C511 T-7' (2.0pt) 23. Name the major components of tne TIP System and briefly describe the purpose of each.

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EXAMINATION r

ic- SHIFT ADVISOR TRAINING GGT-3405-02 WEEK 2 C71-3 1.0 pt. 1. What is the function.of the " Scram Discharge Volume"?

C71-4 2.0 pts. 2. According to Technical Specifications, what is the purpose of the reactor protection system? (T.S. Basis)

.s D17-2 2.0 pts. 3. List the processes that are monitored by the Process Radiation Monitoring System.

D17-4 12.0 pts. 4. List the Liquid Process Radiation Monitors. Include any automatic actions which function to safeguard the environment.

E12-2 2.0 pts. 5. What are five basic codes of operation of the RER

.Syste=?

E12-9 1.5 pts.- 6. When would the Steam Condensing Mode of the RHR System be used? Describe the flowpath for the Steam Condens'ing Mode.

.- E21-6 2.5 pts. 7. What actions take place on a LPCS initiation?

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v E21-5 1.0 pt. 8. Why is there a jockey pu=p in the LPCS Systes?

E22-7 2.0 pts. .9. How is a =ini=us volume -of water insured for the HPCS

System? .W hat would happen if all this water was used?

-E22-4 -1.5 pts. 10. What will c.ause initiation of the HPCS?

E22-1-ll 1.0 pt. 11. What would the consequences be if the ADS control switch (keylock) was lef t in the "off" position on Panel 601?

E30 5.0 pts. 12. What will cause the Suppression Pool Makeup Subsystems A and 3 to auto =atically initiate? Manual initiation?

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E30 2.0 pts. 13. What are the interlocks associated with the Suppression

? col Makeup System valves F001 A/S and F002 A/3 and give the purpose of the interlocks.

E32/38-4 2.0 pts. 14. What happens when the outbd >$IV leak control system is initiated (Include interlocks).

E32/38-5 2.0 pts. 15. What happens when the Feedwater leakage control syste= is initiated? (Include interlocks) t N.

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SHIFT ADVISQR.IRAINING GGT-8405-02 Page 2

+ .EyU ISATION ~ WEEK 2-i s31-3 1.0 pt. 16'. What will cause RCIC system to initiate?

E51-4. 3.6 pts. -17. 5' hat will cause the RCIC turbine to trip?

E61-2. 1.5 pts. 18. What are.the three subsystems of the Co=bustible Gas

. Control System that will reduce the percent of H2 in the containment?- How does each reduce the H3 concentration?

G33/36-8 2.0 pts. 19. What conditions will cause-an automatic trip of the ERCU pu=ps?

G33/36-9 1.0 pt. 20. Explain the advantage of using the " Post-Pump" mode of operation.-

G41/46-1 1.0 pt. 21. What are the trips of the Fuel Pool Cooling pu=ps?

.G41/46-6 2.0 pts. 22. What supplies cooling water to fuel pool heat ex-changers during normal operations? During loss of normal power operations? Provide detailed explanation.

..i-12 2.0 pts. 23. What conditions will automatically initiate the S3GTS?

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SHIFT ADVIS0F. TRAINING EXA'4 GGT 8405-02 Week 3 Lil-04 (1.0 pt) 1. How is the 250V Battery Syste= different than any.one of the 125V Lattery Syste=s?

M41-ll (1.5 pt) 2. What are the functions of the suppression pool?

M41-28 (1.0 pt) 3. a) What are the design temperature and pressure for the drywell?

b) for the containment?

M71-03 (3.0 pt) 4. Describe the Drywell Air Monitoring System.

M71-12 (2.0 pt) 5. a) List the signals that will cause an auto isolation of the Containment and Drywell Isolation Subsystem, b) List the signals that will cause an auto isolation of the Auxiliary

{ ; Building Isolation Subsystem.

Nil-04 (1.5 pt) 6. What is the purpose of the =ain steam

=oisture separator / reheaters? How do they work?

N19-13 (1.0 pt) 7. a) What will cause an autonatic isolation of Low Pressure Heater String?

b) Why is this isolation provided?

N19-17 (1.0 pt) 8. List at least 5 loads that are supplied directly from the Condensate Makeup /Rej ect

. Header.

521/C34-04 (1.0 pt) 9. Describe the interlocks associated with the (F029 A/3).RTP suction valves.

N21/C34-12 (2.0 pt) 10. Concerning the progra==ed level of the Feedwater Centrol Systen:

a) What is the purpose?

b) Describe hev this is accc plishec.

2 SHIFT ADVISC?. TP5G EXAli 1 GGT-3405 week 3 Page 2 N22-G4 (1.5 pt) 11. Condensate flow through the various in service decineraliters is regulated by a flow balancing system:

a). What is the purpose of the flow balancing system?

b) .Why do we need'a flow balancing system?

N32-01 (3.0 pt) 12. Describe.the effects of increasing Rx pressure on a direct cycle BWR.

N32-04 (1.0 pt) 13. What is the purpose of the bypass control 4

unit-of the EHC System?

N62-04 (1.5 pt) 14. a) What is the normal and backup steam supply the SJAEs?

b) What actions auto =atically occur -

a low steam flow from the air ejector normal supply?-

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N64-20 (1.0 pt) . 15. List in order of flow p th the major components of the OFF wAS.

N71-01 -(2.0 pt) 16. What are.the starting interlocks for the circulating water pumps?

P41-04 (2.0 pt) 17. What are the start signals which will start-up the A Standby Service Water System?

P42-06 (2.0 pt)- 18. a) How does the CCW System respond to a loss of offsite power-during a LOCA?

b) What loads can be supplied?

-P44/47-01 (2.0 pt) 19. List at least 10 leads served by the Plant- ,

Service Water System. 1 R21-27 (1.5 pt) 20. List three (3) DG trips that are bypassed when the' diesel starts due to an ECCS signal.

P.21-31 (1.5 pt) 21. List the signals cnd the oesociated

, setpoint that will autocatically start the HPCS Division III Diesel Generator.

. SHIFT ADVISOR,TPSG F101' GGTf5405 Week 3 Page 3 R21-35: (1.0 pt) 22. What is the minimus day tank fuel capacity as required by' Tech Specs fet the EPCS DG?

R20-13 (1.0 pt) 23. . What are the voltage level designations for the normal AC Power Distribution System?.

' R21-03' (1.0~pt) 24. What components supply power to the ESF buses and how many of the ESF buses can each supply?

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. Attachment 3 to AECM-84/0180 L ,

b I Simulator,

.-Administrative, Procedure, 4

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Mitigation of Core Damage Training j and Examinations

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GRAND GULF NUCLEAR STATION Sh1FT ADVISOR TRAINING I. INTRODUCTION This outline describes the four parts of a progra of training for shift advisors. The program included training in the following areas: Simulator, Administrative Procedures, Technical Specifications, and Pdtigated Core Damage. The duration of the program was 7 days.

II. PURPOSE .

The purpose of this course was to provide faciliarizaticn training for GGNS plant specific items. The guidelines for this course were listed in =emo IPC 83-10,448. The GGNS Systens Course and Energency Assess =ent Training addressed in the me=o wer.e covered in separate ccurses and are documented in separate course packages.

-, III. CONTENT This training program covered four areas. Each area is discussed in the order in which training was conducted.

A. Simulator Siculator training was 2 days in length. No performance exams were given. The following is a su= mary of the training conducted.

1-23-84

- Conducted a panel walkdown of all simulator panels discussing equip =ent layout and system operation.

- As an introduction to simulator training, inserted a spuricus reactor scran and took no operator action. Discussed plant response. In-serted another spurious reactor scra: and carried out i= mediate and subsequent cperator actions. Discussed plant response. .;

- Discussef feedwater and feedwater control systems. Perfor:ed severa'l feedwater control canipulations including single RFP trips, RFP s.artups. RFP controlled shutdcuns. shifting feedwater ccatrollers, and transferring level control to and fran the sta-tup level control valve.

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. . GRAND GULF XUCLEAR STATION Page 2 e

SHIFT ADVISOR TRAINING ll - Discussed Recire System and Recirc Con:rcl. Perferred several Recire Sys:e =anipulations including FCV runbacks, rese::in; FCV runbacks, trip of one recire pump. trip of he:h re:irc pumps, as-sociated :echnical specification LCO's, recire pu=p star:s, recire pump downshifts, and shifting recire controllers.

1-24-84

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- Discussed the main turbine and EHC Syste including EHC logic.

Perfor=ed a main turbine startup including rolling the :urbin: to 1800 RPM and loading the turbine to 300 MWe. Discussed main turbine startup limitations and TSE interface.

- Initiated and discussed plant response to the fellowing malfunctions (casualties): .

1. recirc loop suction pipe rupture; perfer:ed this several times to analyce the effects of varicus size ru :ures.
2. Steam line rupture in the drywell.
3. Feedwater line rupture outside containrent.

,. Fuel cladding leak.

5. Steam line rupture in turbine building.
6. Loss of feedwater flow - trip of both RFP's.

T. ATWS: discussed EF-10, " Reactivity Control".

S. Pressure control failure - Various combinations of bypass stop and control valve failures and =ain turbine stop and control valve failures.

9. Loss of electrical buses.

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10. Main turbine trip.

- As a final evolution, discussed'the steam condensing mode of RHR and placed the A loop of RHR in the steam condensing mode.

i B. Administrative Procedures w The administrative procedure training was one day in length and covered selected portions of the following administrative procedures:

1. 01-5-01-1, Grand Gulf Suelear Statica Organica:icnal Structure ll 2. 01-S-01-4, Operations Section Organizational S:ructure 2i r.~M. -

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GRAND GULF SUCLEAR STATION Pace 3 SHIFT ADVISOR TRAINING

3. 01-5-02-2, Centrol and Use of the GO::S 0;e:2:icns '!anual

. 01-S-03-1, GG55 Quality Progra:

5. 01-S-03-4, GGNS Quali:y Classifications
6. 01-S-06-1, Protective Tagging Sys:en
7. 01-S-06-2, Conduct of Operations
8. 01-S-06-3, Control of Te:porary Alterations
9. 01-S-06-4, Access and Conduct in the Control Roc:

01-5-0o,-2,

.0. . incident Reports /n,eportacie svents

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11. 01-S-06-7, Contain=en: and Drywell Access Ccntrol
12. 01-5-06-12, GGNS Surveillance Pr:gra:
13. 01-5-06-14, Cc==unica:icns Plan
14. 01-S-07-1, Contro; cf ?:ork en Plan Ecuipment and Pacilities
15. 01-S-07-2, Test and Reces: Centrol
16. 01-S-07-4, Plan: Changes and Modificaricas
17. 01-5-0$-1, Ad=inistratien of the CO5S Health Physics Progra:
18. 01-S-06-2, Expcsure and Contamination Control
19. 01-5-05-3, Personnel Monitoring
20. 01-S-05-8, Alara Progra: .
21. 01-S-10-1, Fire Protection Plan
22. 02-S-01-3, Responsibilities and Authori:ies of Operations Shift Personnel
23. 02-S-01-4, Shift Relief and Turnover 24 02-S-01-5, Shift Logs and Records
25. 02-S-01-S. Componen: Identifica:icn and Labeling
26. 02-S-01-9, Key Centrc;
27. 02-S-01-12. S:stien 076 atin! Orders
23. 02-5-01-17. Con rcl of limitin: Cenci:icas fer 0;eratica 3s--

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~~ . G 2' u Upon conpletion of the above training, an exar af 1 :: 1 c.aurs in length was given.

C. -iecnnical Speci:1 cations The Technical Specifications training was $ 2 days in leng:n and covered all of Technical Specifica:icns with :he excep:icn of sec:ica 4 (surveillance recuirements) and the bases. Of those areas, only selected porticas were covered. Upon ec pleticn of :he above training, an exa of 1 tc 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in length was given.

D. 3Etigated Core Damage Mitigated Core Damage training was 11: days in length and placed special e=phasis on GONS plant specifics. Upcn cer;1etien cf this training, an exa cf 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in length was given.

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,.M i L.. lam b The Simula:cr Training recuired no materials. For :he Administrative Procedure training, a copy of all 2d procecures was ;1ven :c -each student .

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Fcr the Technical Speci:ication training, a copy c: .ecnnicaz .pec  :: cations updated through amend =en: 11 was given :o each student. - .Fer the Mitigated .

Core Damage training, a copy c:. tne Granc.ou . . : ,...uclear ::a:1cn Lesson Notes ccvering Mitigated Core Damage was given to each student.

.. r S ,a r c0,a.. .-c s. _:.,u..S The FS AR does not address training for Shift Advisors, so no FSAR require-ments are ce: by this course.

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TECHfilCAL SPECIFICATI0 tis EXAM

(~. Shift Advisor Training SAT 8420 TS-01 (1.0 pt) 1. Define Identified Leakage.

TS-02 (1.5 pt) 2. What defines control rod coerability?

TS-03 (1.0 pt) 3. When must Standby Liquid Control be operable?

TS-04 (3.0 pt) 4. a) Define Safety Limit.

b) What are the Grand Gulf Safety Limits?

TS-09 (3.0 pt) 5. What AC electrical power sources must be operable during operating conditions 1, 2, and 3?

TS-22 (1.5 pt) 6. Define Drywell Integrity.

TS-20 (2.5 pt) 7. Complete. the following table:

flode Switch Average Reactor Condition ?osition Coolant Temoerature 1.

2.

3.

4.

5.

TS-29 (1.0 pt) 8. What is the basis of the high Rx water level scram?

TS-13 (1.5 pt) 9. What is the minimum shift crew composition during operating conditions 1, 2, and 3?

TS-30 (2.0 pt) 10. What are the tine interval requirements, including extensions, for surveillances?

TS-36 (2.0 pt) 11. Recirculation loop flow mismatch shall be maintained within what limits? .;

TS-48 (1.0 ;t) 12. Where does the Rod Witndrawal Limiter input power signal originate?

~5-63 (2.5 pt) 13. What is the basis for the limitation of 135*F on drywell avar ge aw temperature?

TS-67 (1.0 pt) 14. a) h' hat is Int Exclusion Aret racius ?

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What is the Lcw Pcculation Icr.e radi .s?

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( TECHiilCAL SPECIFICATION EXAM Shift Advisor Trng - SAT 8420 Page 2 TS-75 (1.0 pt) 15. Define Core Alteration.

TS-74 (1.0 pt) 16. Define Critical Pcwer Ratio.

TS-76 (2.0 pt) 17. a) When must the Standby Gas Treatment System be operable?

b) How long can one Standoy Gas Treatment subsystem be inoperable before action must be taken?

TS-77 (2.0 pt) 18. a) What is the Minimum Critical Power Ratio (l'CPR) limit at rated concitionr?

b) What two parameters dictate the MCPR limit?

c) What is tne Linear Heat Generation Rate (LHGR) limit?

TS-79 (2.0 pt) 19. WP . are the Tech Specs requirements for

( starting an idle recirc pump with:

a) both recirc loops idle?

o) one recirc loop idle?

TS-80 (2.0 pt) 20. Concerning the suppression pool temperature limits:

a) what is the normal limit?

b) what is the limit during testing which adds heat to the supp"ession pool?

c) at what temperature must the Rx be scrammed?

d) at what terperature must the RPV be I depressurized to < 200 psig within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />? -

TS-81 (2.0 pt) 21. Define Shutdown Margin and list the Tech Specs limit (s).

TS-84 (2.0 pt) 22. What are the terpfra!ure anc ? eve? req irements fcr the ege c Tues s:crase pool i. hen it

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TECHNICAL SPECIFICATION EXAM

( Shift Advisor Trng - SAT 8420 Page 3 TS-85 (1.5 pt) 23. 'What are the Tech Specs surveillance requirecents for Linear Heat Generation Rate when thermal power is 125'a of rated (i.e.,

when shall LHGR be determined)?

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. MITIGATION OF CORE DAMAGE EXAM

(~. Shift Advisor Training '

SAT 8420 MCD-01 (1.5 pt) 1. H2 Production created concern for days at TMI-2:

a) list all sources of H2 production following a LOCA with a.severly damaged core.

b) why is H a problem?-

2 .

c) what ways does Grand Gulf have to mitigate and control the production of H2? .

MCD-02 (1.0 pt) 2. Define " Adequate Core Cooling" with respect to your Administrative Procedures. -

MCD-05 (1.0 pt) 3. ADS is a high pressure ECCS System:

(, a) -what functions does ADS 5erve?

b) under what conditions would you manually-initiate ADS?

MCD-09 ,(1.5 pt) 4. Define:

a) Conduction b) Convection

~

c) Radiation .,

MCD-12 (1.5 pt) 5.. List the following limits:

a) Steady - state 100% power,100% flow MCPR .._.

b) Transient CPR limit t.

c)' ' Maximum LHGR MCD-17 (2.0) 6. What is meant by the term " reference leg flashing"?

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liitigation of Core Damage Exam

(_ SAT 8420 Page 2 MCD-18 (5.0pt) 7. List the ranges of all Rx water level instruments. Incluce the calibration conditions and where the instrument is located in the control room.

MCD-25 (1.0) 8. Why does the fuel zone level instrument have a different variable leg tap than the other level instruments?

MCD-27 (1.0pt) 9. List the four (4) classes of emergencies at GGNS.

MCD-29 (1.5 pt) 10. Define the following:

a) Laminar flow b) Subcooled nucleate boiling c) Slug flow (1.0 pt) A saturated Geiger-Meuller tube will have

( MCD-42 11 (max output, zero output) Select one.

MCD-45 (1.0 pt) 12. What is the purpose of the Hydrogen Igniter System?

MCD-46 (1.0pt) 13. True or False a) There are only 4 ranges of level ~

instrumentation at Grand Gulf.

b) Level instruments are calibrated at the temperatures and pres'sures in J.

which they are to operate.

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c) All Grand Gulf Rx vessel instruments are referenced to instrument zero, 533" above vessel zero.

d) Water density has an effect on indicated vs. actual level.

MCD-50 (2.0 pt) 14. Define the following:

a) Exclusion Zone Low Population Zone

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Mitigation of Core Damace Exam

( SAT 8420 Page 3 MCD-54 (2.0 pt) 15. Mat $hthefollowing: Answers may be used more than once.

1) Main steam line monitors a) Geiger Meuller Tube
2) Liquid process monitors b) Ion chamber
3) Off Gas monitor c) Scintillation detector
4) Vent' release monitors d) none of the above
5) Carbon Ded vault monitor
6) Ventilation System monitors -
7) Area raciation monitoring
8) Hi range accident monitors MCD-21 (4.0 pt) 16. a) On the attached graph, identify the region or points labled A - E.

b) Define or describe the above regions / points A - E.

c) Discuss which region a BWR normally operates in.

MCD-33 (2.5pt) 17. Name five (5) types of corrosion discussed in this course.

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SHIFT ADVISOR TRAINING EXAM

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ADMINISTRATIVE PROCEDURES SAT 8420.

ACRS-03 (2.0pt) 1. What tags issued under the protective tagging system require independent verification? .

ACRS .(1.0pt)

. 2. What activities and/or functions does the Operational.QA Program apply to?

ACRS-06 (1.0 pt) 3. Who has direct responsibility for conduct'

, and access to the Control Room?

'(2.0 pt)

ACRS-19 4. Define adequate core cooling. ,

.ACRS-23 (2.0pt) 5. Describe the requirements and procedure for implementing TCNs. -

ACRS-78 (2.0 pt) 6. . List the Federal and GGNS quarterly exposure limits. ,

ACRS-43 (1.5pt) 7. What are the 3 types of RWPs used at GGNS?

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ACRS-49 (2.0 pt) 8. What is the difference between a Red equipment clearance and a Brown equipment clearance?

ACRS-S2 (1.0 pt) 9. Under what condition (s) is the manipulation of controls at GGNS by a person who is not a Licensed Reactor l: Operator or a Senior Reactor Operator permitted?

'ACRS-53 (1.0 pt) 10. Who has the responsibility and the authority for shutting down the reactor when it is detemined that the safety of

, the reactor is in jeopardy, or when a l safety limit is exceeded, or when operating parameters exceed any portion of the Raactor Protection System logic setpoints and automatic shutdown does not ~'

occur?

ACRS-59 (1.0pt) 11. What are the color codes for electrical equipment in ESF supplied systems?

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e N-SAT 8420 Exam Admin Proc Page 2

- (r ACRS-67 (2.0pt) . 12. When used in a directive, the following shall be construed to nave the special definitions given; define the following:

a) shall/will b) should -

c) may .

d) must ACRS-70 (1.5 pt) 13. The term " safety related" shall be applied

. to those structures, systems, components, services, activities and directives that are necessary to ensure what?

ACRS-71 (1.5pt) 14. The Surveillance Program implements the . .

sur'veillance requirements of the Technical Specifications into a monitoring program consisting of 3 sub-programs. What are

(' the 3 sub-programs?

ACRS-72 (1.5 pt) 15. While doing a surveillance there are 3 types of notes for personnel to be ' aware of.' They are NOTE, CAUTION, and WARNING.

- Describe what each means.

ACRS-76 (1.0pt) 16. An ALARA connittee review is required for c' jobs expected to require a total man-rem exposure of? 37 s.a ACRS-36 (1.0pt) 17.' What is a Temporary Alteration?  ;).

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- Attachment 4 to AECM-84/0180 7,

Power Ascension Testing. Procedure Training and Plant Transient Recovery

-Simulator Training and 1

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Examination Summaries-W i ,e

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- a' '. MEMO T0i Terry Mayfield" ,

' FROM: Gary'lhamon,' Operations Training SupervisorS -

SUBJECT:

Simulator Training for Shift Advisors f-We have committed to provide the Shift Advisors with rwo additional weeks of simulator training.

It'is requested, therefore, that you and/or the other si=ul'ator instructors- formulate the program using the following guide]ines:

1. 1st WEEK
a. Procedures used during start-up program (>5% power). .
b. Transients likely to occur during the start-up test program.
c. Each advisor must manipulate the controls er.d align equipment IAW procedures.
d. Performance exam administered by M. Shelly or uyself to assure sufficient _ specific plant knowledge to properly perform their advisory function. -
2. '2nd WEEK
a. Training to ins e proper ide'ntification response and recovery from p ant. transients.

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b. Focus on Emergency Proceduresy ONEP's and Accident Response.

. c. .Each advisor must manipulate controls. _

d. Performance exam again administered by M. Shelly or myself to verify the above. .

The course is currently scheduled f or the weeks of Febru?.ry 27 and March 5. _ There should be 5 or possibly 6 advisors attending. The package needs to be ready and approved before the start of tri.ining.

Please contact me if you have any questions.

Thank you.

.? J-G. D. Ula=en J

2/14/84 .

GDLidaw G(_j cc: J."R. Yelverton D. L. Hunt M. Shelly 3..G. Jones File

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t POWER ASCENSION TESTING TRAINING COURSE OUTLINE I. Scope / Purpose ,

A. Familiarize Shif t Advisors with the overall scope of the Power Ascension Testing training program.

II. General Description A. Generally, the day will start out with a brief description of the days activities on the simulator. As the days progress, the classroom portion will involve a detailed discussion of the transient tests performed, including the actions to be taken during the test. Generally, static tests will be discussed, but not performed.

B. All procedures and actions normally used during the actual power ascension will be used throughout the Power Ascension Testing program. This includes, but is not limited to:

1. Integrated Operating instructions V

'2. System Operating Instructiona

3. Startup Test Instructions
4. Technical Specifications III. Outline Day 1 Overview of Power Ascension Tests Phase 1, II, III complete Emphasis on Phase IV and V Discussed TC 1 to 6 and level criteria

[

[" TRAINING COURSE OUTLINE Power Ascension Testing Page 2 1

Day 1 1-E51-SU-14-1-1 RCIC

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V

. Sections.

3.4/4.4 1-000-S U-2 3-1 Feedwater Sections.

3.1/4.1 1-B33-SU-29-1 Recire Sections.

3.1/4.1 1-E12-SU-71-1 RHR Sections.

3.1/4.1 Steps 4.1.1 to 4.1.47 Loss of T.G & Offsite Power

..V Day 2- 1-000-SU-31-2

! Sections.

i 3.1/4.1 1-000-SU-28-2 SD from RSD Panel Sections.

3.1/4.1 3.2/4.2 1-B33-SU-30-2 Recire

, , Sections.

3.1/4.1 1-B21-SU-26-2 Relief Valves Sections.

3.1/4.1 'One Valve

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L! ' l-E51-SU-14-2 RCIC Lw ions.

3.1/4.1 3.2/4.2 e- ' ~4- , _ . _ _ _ . _ _

e TRAINING COURSE OUTLINE Power Ascension Testing Page 3 Day 3 1-B33-SU-30-3 Reactor Recirc (mmN Sections.

3.5/4.5 3.8/4.8 3.9/4.9 3.10/4.10  :

1-000-SU-23-2 Feedwater System Sections.

3.2/4.2 3.5/4.5 1-000-SU-27-3 Turbine Trip '

c Sections.

3.1/4.1 1-M22 SU-22-4 IPC Sections.

, .tv'i 3.1/ 's .1 1 3.2/4.2 1-000-SU-23-6 Feedwater Sections. [

3.2/4.2 3.4/4.4 3.5/4.5 3.6/4.6 3.7/4.7 1-000-SU-24-6 Turbine Valve Surv.

Sections.

3.1/4.1 1-N32-SU-22-6 IPC Sections.

3.4/4.4

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.*.. TRAINING COURSE OUTLINE Power Ascension Testing Page 4 Day 3 1-000-SU-2 7-6 Gen. Load Reject Sections.

3.1/4.1 Day 4 1-B33-SU-30-6 Recirc Sections.

3.6/4.6 3.8/4.8 1-B21-SU-25-6 MSIV's Sections.

3.4/4.4 3.5/4.5 Review Day 5 Review And h Exam t , _ _ . _ . . _ _ . _ - _ -

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. PLANT TRANSIENT RESPONSE AND RECOVERY TRAINING COURSE OITILINE

.I . Scope / Purpose A. Familiarize Shift Advisors with the overall scope of response and recovery to plant transients.

II. General bescription

' A.

The day will start out with a general description of the plant condition, as malfunctions are placed into the simulator the individuals will per-form as the situation requires. After each scenario is over, a critique will be given to the individuals involved.

- B. .All actions and procedures used during the Transient Response and Recovery Training will.tne in accordance with, but not limited to:

1. System Operating Instructions (v, ' 2. Emergency P'ocedures r
3. Emergency Plan Procedures .

'4 ~. Off-Normal Event Procedures

5. Technical Specifica$ ions L6. Integrated Operating Instructions III. - Outline DAY l-101-1 .from- 850#

IC-10 850# H/U seq. A step 6B Turbine roll

~ Increase power to 50%

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  • PLANT TRANSIENT RESPONSE AND RECOVERY Page 2 n DAY 2

(_)

IC-16 100% power, Xenon equilibrium, Group 10-4 06 to 08 Malf. # 72 Main Steam Line High Radiation IC-16 Malf. # 59 Main Steam Relief Valve 51D Fails Open IC-16 Malf. # 62 Instrument Line Leak Malf. # 76 Failure to Scram (Manual Scram Function Operable)

IC-16 Malf. # 69 Instr.eaent Line Leak Outside Containment DAY 3 e' IC-16 j)

(_/ Insert Malfunction # 24, 8 times Control Rod Accumulator Trouble Malfunction # 25 Scram Control Rod Malfunction # 21 Control Rod Drift in Fb1 function # 75 Failure to Scram Malfunction # 110 A or B SJAE - Steam Supply Failure (Total)

Fblfunction # 121 A or B Feedwater Pump Signal Failure Fb1 function # 123 A and B Feedwater Pump Turbine

') ' Overspeed Trip b

O PLANT TRANSIENT RESPONSE AND RECOVERY Page 3 DAY 3 CONTINUED 1C-16

()

b/

Malfunction # 1 & IB Feedwater Pump Signal Failure Malfunction # 125 Failure of Steam Flow Signal to FW Control Fulfunction # 159A Mechanical Seizure of Selected F0V E22-F004 HPCS Injection Malfunction # 13A Recirc Pump Motor Hi Temperature Malfunction # 14A -

Recire Pump Hi Vibration Malfunction # 17B Recirc Loop Flow Control Valve Signal Failure

(~') tb1 function # 126B

'~' Feedwater Control Vessel Level Sensor Failure Mc1 function # 44-RCIC Turbine Speed Control Failure Malfunction # 73E Main Steam Isolation Valve Fails Shut Malfunction # 76 Failure to Scram (Manual Scram Function Operable) lblfunction # .159A MOV Failure HPCS Injection Valve Malfunction # 123 A and B Feedwater Pump Turbine Overspeed Trip

,7.-

\.)

PLANT TRANSIENT RESPONSE AND RECOVERY Page 4

. DAY 4 p

() IC-16 Malf. # 83A Turbine Bypass Control Valve Fails Open Malf. # 12A Reactor Recirculation Pump Trip lbif. # 22 Control Rod Twice Stuck Malf. # 76 Failure to Scram (Manual Scram Function Operable)

Malf. # 12B Reactor Recirculation Pump Trip Malf. # 13A Recirc Pump % tor Hi Temperature

\_.)

Malf. # 14A Recire Pump High Vibration Malf. # 123A Feedwater pump Turbine Overspeed Trip Malf. # 15A, ISB Recirc lst, 2nd Stage Seal Failure Malf. # 63 Recirc Loop Rupture (Variable)

Malf. # 89A, C Turbine Control Valve Servo Failure (Variable)

Malf. # 12B Rec. Dump Trip

,c--s Malf. # 21

(,,) - Control Rod Drift in

s .

PLANT TRANSIENT RESPONSE AND RECOVERY Page 3 DAY 4 CONTINUED .

, ')

IC-16 Malf. # 83A, B Turbine Bypass Control Valve Fails Open Malf. # 76 Failure to Scram (Manual Scram Function Operable) tblf . # 9A ,

APRM Chn.nnel fullscale Malf. # 151A Component Cooling Water Pump Trip Malf. # 148A, B Standby Service Water Pump trip Malf. # 121A Feedwater Pump signal failure

( '

i Malf. # 53 Spurious HPCS initiation Fblf. # 103 Generator Trip Malf. # 22 Control Rod stuck DAY 5 Review & Exam

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SUMMARY

OF SIMULATOR PERFORMANCE EXAM Week One - Power Ascention 3/2/84 l Initial Conditions .In startup test procedure SU-22-4, Section 4.1 -

Pressure' Control Step Change- Stability testing.

Problem . Failure of EHC control of turbine with load at 50%.

- Grade.on: 11) ; Manipulatory Skills.

,2) Expected response to overall' test.

3), Effects on power with Recirculation Flow Control in Manual?

Automatic?

4) -Interrelationships between various turbine control modes,

, - i.e. Speed demand, load demand, speed setter and starting device.

' 5)' 'Feedwater' Motor _ Speed Control vs. Electro-automatic positioner.

6)_ Sensing point for 30% feedflow automatic-recirculation' downshift.

7) Explanation of Cavitation and how to detect on Recirculation

- <' system using P680 indications.

8) When EHC failed, was positive action taken to control turbine?

- 9) . How are'EHC circuits removed to allow further turbine load

, increase?!

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OF SIMULATOR PERFORMANCE EXAM

+ Week Two - Transient Response 3/9/84 initial Conditions: ' About .95% power - normal operating line-v,. Operating per Power Operations procedure. Hypothesizes special test instruction for

, testing of one SRV.

~

Problim: Failure of:SRV to reseat completely - after recognized by student

~and proper action taken, followed in 2 minutes by failure of SRV in full open position.

Grade on: 1

1)
  • Recognition of problems with testing SRV at high power.
2) Recommending appropriate precautions to Shif t Supervisor.

3)' Manipulation of Turbine. By-pass' valves.

4) Technical Specifications 1 associated with open bypass valves.
5) . Recommending proper action with respect to personnel in con -
  • J tainment' prior 'to SRV actuation. I
6) Manipulation'of SRV.

i

, 7) : Manipulation of.RHR for' Suppression Pool Cooling.

7, - ,8) . Recognition'of Leaking SRV.

9) Recommending proper action toL eorrect SRV leaking.

. ~10) Referringito proper. procedures'for lea' king SRV.

11). Recognition'of Failing Open SRV.

12).. Consulting proper ONEP's.

13)1. Carrying out proper action on' Scram' and Manipulations. -

~14) . Consultation of Emergency Procedures and' Emergency Plan Procedures.

  • ~ 15) Recommending-long-term action to Shift Supervisor.

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e Attachment 5 to AECM-84/0180 Summation of OTEC Orel Board Questions i

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.i SUMMATIN OF WAL BOARD QUESTIONS

' given by OTEC 2/23/84 for Shift Advisor Certification

1. State the purpose of the ADS system.
2. What are the indications of a leaking SRV?

~

13. What is the air supply to ADS?

.4. ' Discuss the operation of an SRV.4

^ ~

~ 5. What 'other ECCS systems do we have at GGNS?

6. - What is th'e initiation setpoints for each of these (ECCS) systems?

~

' 7. ; Discuss the design for the containment and suppression pool- Design valves.

8. Discuss the operation of containment spray - include setpoints,

- , interlocks, etc.

9. What are the first indications of fuel damage?
10. By what means can we determine if we have fuel damage and extent of fuel damage?
11. -Discuss-the Design Basis Accident (Recirculation line break).

12.. Define adequate core cooling.

13.- Discuss Thermal limits including how chtained, and actual limit.

! 14. Discuss condition each thermal' limit is designed to prevent.

15. How do we determine if there is a break' in the LPCS line, inside or-y outside vessel.

Condition - h scram in on 1 trip system, 1 fuse supplying scram solenoids

~

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on other trip system blows. What is the result? What would happen?
How would you. recommend to the Shift Supervisor that he recover?
17. What are some of your immediate concerns with the above (16)?

, 18. - What would-you.do'if Shift. Supervisor refused to follow your recommen-dations'above-(17)?- Suppose you have. a genuine safety concern, what would~you do?-

19.- How does' initial power vary with flow.

20. : Define a radiation area here at GGNS._ Define a High' Radiation Area.

~

?21...What are the GGNS' exposure' limits?. What are the emergency ~ exposure limits?

22. -Explain the operation of a G-M tube. What are some of its advantages

'and disadvantages?

23. 'What are'the Technical Specification-Limits on Suppression Pool Temperature?

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' Basis?

- 24. ..What are the Technical Specification Thermal Limits?

~

25.. Discuss.what you feel is your role as a Shift Advisor.

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