ML20132E547

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Rev 0 to Engineering Svc Procedure 42EN-ENG-011-OS, Scram/ Transient Reporting
ML20132E547
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 08/23/1985
From:
GEORGIA POWER CO.
To:
Shared Package
ML20132E487 List:
References
42EN-ENG-011-OS, 42EN-ENG-11-OS, NUDOCS 8510010114
Download: ML20132E547 (25)
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Text

GEORGI A -POWER COMPANY l DOCUMENT TYPE: l PLANT E.I. HATCH I ENGINEERING SERVICE PROCEDURE l PAGE 1 0F 24

' DOCUMENT TITLE: l DOCUMENT NUMBER: l REVISION NO:

SCRAM / TRANSIENT REPORTING l 42EN-ENG-011-OS l O EXPIRATION DATE: l APPROVALS: EFFECTIVE DATE:

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1.0 OBJECTIVE The objective of this procedure is to collect and document all pertinent information concerning a scram or significant transient and to analyze plant response at all levels to determine if corrective action is needed prior to returning the unit to service.

2.0 APPLICABILITY This procedure applies to commitments associated with scram and significant transient data collection and subsequent reporting requirements.

3.0 REFERENCES

3.1 40AC-REG-02-0 3.2 30AC-0PS-003-OS 3.3 Instrument Setpoint Indexes -A-16397 and' A-26497 3.4 Units 1 and 2 Technical Specifications - Limiting Safety System Settings and 2 Instrument Setpoints.

~ 3.5 Units 1 and 2 FSAR - Systems design basis and analysis for accidents and transients.

4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS N/A - Not applicable to this procedure.

4.2 MATERIAL AND EQUIPMENT N/A - Not applicable to this procedure.

4.3 SPECIAL REQUIREMENTS A report shall be completed as soon as possible whenever control rods are I scrammed in with more than one rod withdrawn and fuel in the vessel. (Does not  !

include scram time testing.)

5.0 PRECAUTIONS AND LIMITATIONS 5.1 PRECAUTIONS N/A - Not applicable to this procedure.

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GEORGIA POWER. COMPANY l l PLANT E.I. HATCH l l PAGE 2 0F 24 DOCUMENT TITLE: l DOCUMENT NUMBER: l REVISION NO:

SCRAN/ TRANSIENT REPORTING l 4?EN-ENG-011-0S l 0

LIMITATIONS U( ~.2 N/A - Not applicable to this procedure.

6.0 PREREQUISITES N/A - Not applicable to this procedure.

7.0 PROCEDURE 7.1 DATA COLLECTION 7.1.1 During any significant transient, control room perionnel, normally the Shif t Technical Advisor, should complete to the extent possible, the Scram / Transient Checklist shown as Attachment 1. The checklist is used to collect important system information to be used in the subsequent analysis.

Any abnormality should be recorded. Its significance can be determined during the analysis. Initial conditions should be recorded on a Conditions Prior to Event Form, similar to Attachment 3.

7.1.2 Attachments 4 through 9 contain items to be checked which confirm both logic system operations and integrated system response to a transient. In the first section of the analysis package, the reviewer will initially determine the rang of values for each parameter during the transient and then confirm that all intended actions did indeed occur. Any problems discovered should rm be recorded on a Deficiency Report. The Operations Supervisor On Shift

(\"') should be immediately notified of any safety related action that did not occur when the appropriate setpoint was reached. For items that cannot be verified, indicate so on the data sheet.

7.1.3 ~ The second part of the analysis involves comparing the system response to pred'cted or historical response. Where available, the parameters indicating the system response sections should be reviewed to determine if olant response was significantly different from the expected. Any abnormalities will be recorded on a Deficiency Report.

7.1.4 Any abnormalities discovered that might be a generic industry problem should be considered for posting on the NUCLEAR NETWORK system.

7.2 ANALYSIS 7.2.1 Once a transient has been brought under control, an analysis needs to be completed to determine if all systems performed as intended.

7.2.2 To perform an effective analysis, as much information as possible should be collected concerning plant response and system operation. This should include the Scram / Transient Checklist, Process Computer Print-Outs, items brought forward in a Personnel Observations Section, similar to that shown as Attachment 7, and the Control Room recorded traces. If deemed necessary by Management, a Post Event Debriefing should be held as soon as involved

-persons can be relieved from duty in the Control Room.

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SCRAM / TRANSIENT REPORTING l 42EN-ENG-011-OS l 0 I

7.2.3 In this meeting, the event will be discussed to ensure that the collected

information'is correct, and to see if any abnormalities are readily discernable. A decision should be made at the end of the debriefing to either

' reconsnend a re-start of the unit or initiate specific investigation or corrective actions that are to be completed prior to re-start. For significant matters it may be necessary to initiate LCOs or take clearances on-equipment to ensure compliance. The minutes of the debriefing meeting should be recorded on a Debriefing Report, similar to that shown as Attachment 8.

7.2.4 In addition to the debriefing review, an in-depth analysis of plant response l will be conducted per Attachments 1 and 3 through 8. The. STA group has primary responsibility for performing the analysis; however, any department may be i requested to perform specific reviews or initiate investigation into system -

response or operation. For any item that cannot be ef fectively analyzed by

on-site personnel,-offsite support is to be requested.

! 7.3 CORRECTIVE ACTION 7.3.1 If any abnormalities are discovered during the debriefing or analysis, a Deficiency Report is to be used to document the findings and track any corrective action. To ensure that all required actions are completed prior to startup, an LCO or equipment clearance should be initiated.

i 7.3.2 The Manager of Operations, or his alternate, is responsible for reviewing the event and subsequent analysis and for making a recommendation to Management on the capability of resuming safe power operation.

7.4 . REPORTING l

. The STA group will complete a Narrative Event Report which includes a detailed sequence-of events, findings of the post-event analysis, and corrective actions i i that were initiated and/or completed.

1 7.5 DOCUMENTATION s l- Attachments 1 an'd 3 through 8, the pertinent process computer edits, and the final

. narrative report will be filed in Document Control. The event shall be logged and j assigned a sequential number, preceded by the unit number and last two digits of 4

the year. The Shift Supervisor shall keep a log using the form similar to that 4 shown as Attachment 2.

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i 4LE: SCRAM / TRANSIENT CHECKLIST l 1 0F 3 Scram / Transient No. Date: Time:

Ev:nt leading up to scram / transient:

RPS Sensor Causing Scram SCRAM Discharge Volume Hi Level Trip SCRAM Bus Lights Extinguished SCRAM Discharge Volume Vent and Drain Valves Close All Rods Verified Full In Isolations GP I Cause Reset Time r GP II Cause Reset Time t

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GP III Cause ___ Reset Time GP IV Cause Reset Time GP V Cause Reset Time Recirc Pump Trip A B No Cause Time Time Restarted A 8 9400 Needed Completed Turbine Trip Auto Manual Cause ADS Initiation All Valves Open HPCI Start Auto Manual Inject Trip Cause RCIC Start Auto Manual Inject Trip Cause CS A Start Auto Manual Inject Trip Cause n

8 Start Auto Manual Inject Trip Cause
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klE: SCRAM / TRANSIENT CHECKLIST 2 0F 3 LPCI A Start Auto Manual Inject Trip Cause LPCI B Start Auto Manual Inject Trip Cause LPCI C Start Auto Manual Inject Trip Cause LPCI D Start Auto Manual Inject Trip Caase SECS That Auto Started:

Fc:dpump A Trip Cause Restarted B Trip Cause Restarted Lev 21 Control (narrative)

Level Highest in. Source Lowest in. Source

- "~0ssure Control

( jrrative) v Pressure Highest psig Lowest psig SRVs tra? lifted: Auto Manual AC Electrical Busses Energized: 4160V A B C D E F G 600V A B C D AA BB DG A Start Auto Manual Tied Trip Cause DG B Start Auto Manual Tied Trip Cause DG C Start Auto Manual Tied Trip Cause All DC Electrical Busses Energized:

SBGT A Start Auto Manual SBGT B Start Auto Manual Abn:rmal alarms: Rad. Hon., Electrical, etc.

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g iLE: SCRAM / TRANSIENT CHECKLIST l 3 0F 3 N;tifications made: NRC Time Method Load dispatcher Management Other D;ficiency Report written by OPS (Y/N - N/A)

Misc. Notes, LCOs initiated, equipment, problems, etc.

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\__TTLE: CONDITIONS PRIOR TO EVENT l 1 0F 1 Shift Personnel Operations Supervisor Shift Supervisor 3 Shift Technical Advisor Plant Operator Assistant Operator 1 Assistant Operator 2 Plant Equipment Operator 1 Plant Equipment Operator 2 Plant Equipment Operator 3 Initial Conditions Mode Switch Position Power Level Thermal Elect Rx. Pressure psig Rx.~ Water level in Core Flow mlb/hr Steam Flow mlb/hr FW Flow mlb/hr Procedures in Progress Narrative Completed By: /

O Date ,

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SCRAM / TRANSIENT REPORTING l 42EN-ENG-011-OS l 0 ATTACHMENT 4 l ATTACHNENT PAGE:

l TLE: LOGIC CHECK SHEETS l 1 0F 4 I DRYWELL PRESSURE For each setpoint, insure that all required actions occurred and indicate maximum l and minimum values with a bar graph.

Confirmation Bar Graph Setpoint (psi) Action (Y/N or NA) 1.8 (U1) Reactor Scram 1.63 (U2) Group II Isolation HPCI Initiation RHR Pump Starts A B C D CSS Pump Starts A B Stdby. D/G Starts A B C Control Room Vent to Mode II CRD Pump Trips Drywell Chillers Trip 7A 7B 8A 88___

9A 9B SBGT Starts ADS Perm Alarm 1.5 (U1) .65 (U2) Ala rm REACTOR WATER LEVEL For each setpoint, ensure that all required actions occurred and indicate maximum

('_'; and minimum valves with a bar graph.

\m / (inches above Confirmation Bar Graph Setpoint instr. zero) Action (Y/N or NA)

+ 54.5" Main turbine trip RFP Turbine Trip

+ 51.7" HPCI Turbine Trip RCIC Turbine Trip

+ 42. " High Level Alarm

+ 32. " Low Level Alarm Runback (if any FWP < or = 20%)

+ 9.9" Reactor Scram Group II Isolation Group V Isolation SBGT Initiation

- 30. " Group I Isolation (U1)

- 50.3" RCIC Auto Initiation HPCI Auto Initiation Recirc Pump Trip A B Control Room Vent. to Mode II

-116. " RHR Pumps Start A B C D CSS Pumps Start A B Stdby. D/G Start A B C PSW to Turb Bldg Isolates Div I Div II

/S Control Room Vent to Mode II

() Group I Isolation (U2)

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SCRAM / TRANSIENT REPORTING l 42EN-ENG-011-0S l 0 ATTACHMENT 4 l ATTACHMENT PAGE:

l iLE: LOGIC CHECK SHEETS l 2 0F st CORE AVERAGE FLUX For the following values of power, on the appropriate neutron instrumentation, confirm the below listed automatic actions occurred. Indicate highest level reached with a bar graph.

Bar Graph -Setpoint (APRM) Action Confirmation (Y/N or NA) 117. % Reactor Scram 115. % (U1) (fixed) 113.5 % (U2) Reactor Scram (Flow Biased, Clamped)

.58W + 59% Reactor Scram (Flow Biased)

.13% Reactor Scram (When Not In Run) 3% Reactor Scram (with Comp. IRM Hi or IN0P in Run Mode)

Setpoint (IRM) Action Confirmation (Y/N or NA) 115/125 of Scale Reactor Scram (When Not in Run)

Setpoint (SRM) Action Confirmation (Y/N or NA) 3 x 105 cps Reactor Scram (When Shorting Links Removed)

REACTOR PRESSURE (Unit 1 Only)

For each setpoint confirm that all actions occurred and indicate maximum and minimum values with a bar graph.

Bar Graph Setpoint (psig) Action Confirmation (Y/N or NA) 1085 ATWS Recirc Pump Trip A B 1100 +/- 11 3.SRVs Lift B C J

1090 +/- 10.9 4 SRVs Lift D F H K 1080 +/- 10.8 4 SRVs Lift A E G L 1034.75 Rx Scram .

1042 High Pressure Alarm 863 Group I When in Run D

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l iLE: LOGIC CHECK SHEETS l 3 0F 4 Confirmation Bar Graph Setpoint (psig) Action (Y/N of NA) 449 ~ Permissive for Opening CS & RHR Injection Valves 360 Recirc Discharge Valve Close A B 138 SDC Isolation 106 HPCI Isolation 77.5 RCIC Isolation REACTOR PRESSURE (Unit 2 Only)

For each setpoint confirm that all actions occurred and indicate maximum and minimum values with a bar graph.

Bar Graph Confirmation Setpoint (psig) Action (Y/N of NA) 1085 ATWS Recirc Pump Trip A B 1100 +/- 11.1 3 SRVs Lift H E L

1100 +/- 11.0 4 SRVs lift D M A K 1090 +/- 10.9 4 SRVs Lift B C G F

,- s 1044 Activate low-Low Set logic if any

( ) SRV is Opened (See Below)

' - ' 1045 Rx. Scram 1025 High Pressure Alarm 855 Group I When in Run 449 Permissive for Opening CS & RHR Injection Valves 360 Recirc Discharge Valve Close A B 138 SDC Isolation 115 HPCI Isolation 70 RCIC Isolation If Low-Low Set is activated, the following SRVs should cp:n and close at the specified values of Reactor Pressure.

(U1) (U1) (U2) (U2) 1033 Open C 997 Open B 887 Close C 851 Close B 1023 Open G 1036 Open D 877 Close G 890 Close D 1008 Open A 1027 Open F

, 862 Close A 881 Close F 983 Open H 1012 Open G 847 Close H 866 Close G LLS LOGIC RESET l

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l TLE: LOGIC CHECK SHEETS 4 0F

( l 4 REACTOR PROTECTION SYSTEM (RPS) l Action Confirmation (Y/N or N/A)

1. All rods go in
2. Scram discharge volume trip
3. Manual scram
4. Mode switch to shutdown scram RECIRCULATION SYSTEM Rurback to No. 2 Limiter Runback to No. 1 Limiter Pump Trip if Turbine Trip 30% Power A B TURBINE Confirmation (Y/N or N/A)

Turbine tripped Manual Auto Cause tN TSV Scram Annunciated

()g (if > 30% power) Computer lift Pumps Auto Start Standby EHC Auto Start Turning Gear Auto Start Motor Suction Pump Auto Start Turning-Gear Oil Pump Auto Start Emergency Bearing Oil Pump Auto Start I (if turning gear oil pump didn't)  !

l Bypass Valves Controlled Pressure at psig '

Setpoint at psig Completed by: /

Date l

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l ITLE: CONDENSER VACUUM CHECK SHEET l 1 0F 1 For the following values of condenser vacuum, confirm that the listed automatic actions occurred. Indicate minimum values of vacuum during the event with a bar graph.

Confirmation Bar Graph Setpoint (Hg) Action (Y/N or N/A) 10

  • Group 1 Isolation Bypass Valve Closure 22.3 (U2) 20 (U1) Reactor Feed Pump Trip 22.3 (U2) 22.23 (U1) Main Turbine Trip 24.73 Low Level Alarm 27 to 29 Normal Vacuum
  • - Confirm closure of: all MSIVs (1/2821F022 and 28(A-0); Main steamline drain isolation valves (1/2B21F016, F019); Reactor water sample isolation valves (1/2831F019, and F020); Torus water cleanup and makeup isolation valves (1/2G51-A0V-F013 & F021,1/2G51-A0V-F011 & F012)

Completed by: /

7-~ Date

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I LE: PLANT RESPONSES l 1 0F 7 CONTAINNENT PARAMETERS f

Maximum Drywell Pressure Maximum Torus Pressure Drywell Temperatures for Unit 1 T1 : IT47-R611 Pt. 8 T2: 1T47-R612 Pt. 8 T3: 1T47-R611 Pt . 10 T4: 1T47-R612 Pt. 10 TS: 1T47-R612 Pt. 9 T6: 1T47-R611 Pt. 13 T7: 1T47-R611 Pt. 9

/~'s T8: 1T47-R612 Pt. 12 Average Volumetric D/W Temperature T1 + T2 + T3 + T4 (0.63) + T5 + T6 (0.22) + T7 + T8 (0.15) =

4 2 2 Drywell Temperatures for Unit 2 T1: 2T47-R626 Pt. 10 T2: 2T47-R626 Pt . 12 T3: 2T47-R627 Pt. 11 T4: 2T47-R626 Pt. 8 TS: 2T47-R626 Pt. 9 T6: 2T47-R626 Pt. 13 T7: 2T47-R620 T8: 2T47-R621 T9: 2T47-R626 Pt. 9 7,

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LE: PLANT RFSPONSES 2 0F 7 Average Volumetric D/W Temperature (T1 + T2 + T3 + T4)(.825) + T5 + T6 (.025) +

4 2 (T7 + T8 + T9 + T10)(.15) =

4 Maximum Torus Water Temperature Causes for Significant Increases in any of above:

Drywell Leak Rate Equipment Drain gpm

,- Floor Drain gpm

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Any system behavior indicative of unusual leakage into drywell?

Hydrogen Level Before  % After  %

0xygen Level Before  % After  %

Explanation for any change:

Torus Level Max in. Min in.

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TLE: PLANT RESPONSES 3 0F 7 REACTOR WATER LEVEL Answer the following questions concerning the plant water level response.

1. Was initial transient in the expected direction? (If no, explain)
2. Did the magnitude of the change deviate significantly from expected values?

(If yes, explain)

3. Did level recovery systems (HPCI, RCIC Feedpumps, etc.) function to regain and control reactor water level in a manner consistent with system design

, characteristics? (If no, explain)

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REACTOR PRESSURE RESPONSE Answer the following questions concerning plant pressure response.

1. Did' peak pressure deviate significantly from expected values? (If yes, explain)
2. Did overpressure. period extend significantly past what is normally expected?

(If yes, explain below)

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LE: PLANT RESPONSES 4 0F 7

3. Did bypass valves (If MSIVs open) control pressure at EHC pressure setpoint?

(If No or N/A, explain below)

4. Did safety relief valves (if MSIVs closed) lift to control pressure at the appropriate setpoints? (Yes/No) (N/A) (If No or N/A, explain below)

STEAM FLOW Answer the following questions concerning steam flow, n

( 1. Did steam flow react as expected for the transient.

2. Did steam flow react as expected for a scram? (If no, explain below)
3. Did steam flow react as expected for a turbine trip? (If no, explain below)

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LE: PLANT RESP 0FSES 5 0F 7

4. Did steam flow react as expected for a Group I isolation?

(If No, explain below)

5. Did steam flow react as expected for an SRV actuation?

(If No, explain below)

6. Did steam flow react as expected for HPCI/RCIC operation?

(If No, explain below) p

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7. Did steam flow react as expected for bypass valve actuation?

(If no, explain below)

RADIATION VALUES Answer the following questions concerning plant radiation monitors.

1. Did MSL rad monitors drop to expected values?

(If No, explain below) l

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2. Did ARMS drop or remain at expected values?
3. Did containment radiation monitor readings remain at expected values?

(If No, explain below)

4. Did the FPM readings drop to expected values?

(If No, explain below)

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5. Did stack readings remain at expected values?

(If no, explain below)

6. Did RBCCW radiation values remain at expected values?

(If No, explain below)

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SCRAM / TRANSIENT REPORTING l 42EN-ENG-011-05 1 0 ATTACHMENT 6 l ATTACHMENT PAGE:

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.LE: PLANT RESPONSES l 7 0F 7

7. Did PWS radiation values remain at expected values?

(If No, explain below)

8. Did reactor building vent radiation values remain at expected values?

(If No, explain below)

ELECTRICAL Did any AC bus not transfer as intended?

I  ? If Not, give specifics and actions taken Was power lost to any DC bus?

If so, give specifics and actions taken Completed by: /

Date

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ENG-0087 Rev. 0 42EN-ENG-011-OS MGR-0009 Rev. 1 [fgl,{y g n -

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V GEORGIA POWER COMPANY l l PLANT E.I HATCH I l PAGE 21 0F 24

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SCRAM / TRANSIENT REPORTING l 42EN-ENG-011-0S l O ATTACHMENT 7 l ATTACHMENT PAGE:

l LE: PERSONNEL OBSERVATION REPORT l 1 0F 1 Did any system not operate as you expected?

Did any procedure prwe inadequate to operate a system or to ensure effective corrective action?

Were there any difficulties in diagnosing a condition due to poor system layout or

,m inaccurate indication or annunciation?

)

Were any deficiencies noted that could be improved by changes in Training Program?

(List AIT No.)

Completed By: /

Date

/

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I SLE: POST EVENT DEBRIEFING MINUTES _

l 1 0F 2 Event Date Time Lccation P;rsons Present Title

's (x- )

Items Brought Forward:

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. PLANT.E_I. HATCH l [ PAGE 23 0F 24 DOCUMENT TITLE: l DOCUMENT NUMBER: l REVISION NO:

SCRAM / TRANSIENT REPORTING l 42EN-ENG-011-0S I O ATTACHMENT 8 l ATTACHMENT PAGE:

l LE: f'OST EVENT DEBRIEFING MINUTES I 2 0F 2 C:rrective Actions Proposed:

Prerequisites for Startup:

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"W Recorded By: /

Date Approved By: /

Date

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GEORGIA POWER. COMPANY l l l PLANT E I HATCH l l PAGE 24 0F 24 l DOCUMENT TITLE: l DOCUMENT NUMBER: l REVISION NO: I SCRAM / TRANSIENT REPORTING l 42EN-ENG-011-OS l O ATTACHMENT 9 l ATTACHMENT PAGE:

l iLE: ABNORMALITIES DISCOVERED IN ANALYSIS l 1 0F 1 Function or Operation in Question Instrumentation in Question /Setpoint /Value /Last Cal./or FT

/ / / /

Completed By:

Corrective Action Requirements Need Investigation Need Resolution Prior to Startup/LCO No.

Completed By:

Tracking Mechanism (DCR, MR, MWO, Deficiency ' Report No., etc)

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Completed By: /

Date Reviewed By: /

Date Approved By: /

Date

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