ML20129G075

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Rev 0 to Station Operating Procedure GOP-0007, Scram Recovery
ML20129G075
Person / Time
Site: River Bend Entergy icon.png
Issue date: 09/28/1984
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20129E940 List:
References
GOP-0007, GOP-7, NUDOCS 8507170524
Download: ML20129G075 (12)
v • d • e


Text

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  • l. RIVER BEND STATION APPROVAL SEEET

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STATION OPERATINC PROCEDURES NO. GOP- 0007 TITLE SCRAM RECOVERY SAFETY RELATED TES NO TECHNICAL REVIEW REQUIRED TES X NO] ,,

REV. PAGES INDEP. TECH.

NO. ISSUED REVIEW REVIEW APPROVED BY EFFECT SIGNATURE /DATE SIGNATURE /DATE SIGNATURE /DATE DATE 9 1 THRU 10 gg @ f 09/28/84 LATER'S PAGE

. yo- L INFORMATION ONLY

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8507170524 PDR 850709 ADOCK 05000458 A PDR I

SOM-003

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l (LATER'S) l

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'l PROC. NO. GOP-0007 TITLE SCRAM RECOVERY REV. NO. O c:l The following is a list of " missing" and/or " tentative information" (

l -- (LATER'S) -- in this procedure. The responsible Section Supervisor

,^l shall update this procedure as the information becomes available.

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I l(LATER) LOCATION l

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lSECTION/ STEP PAGE BRIEF DESCRIPTION l

. l Attachment i, Manual or

  1. pl5.0/5.2 l 4 Procedure Number for Computer "l Attachment 1, l I

l5.0/5.3 4 Differential Temperature Setpoint l l Attachment 2, Manual or l l5.0/5.2 8 Procedure Number for Computer l l Attachn. nt 2- l l5.0/5.3 8 Differential Temperature Setpoint l 1

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_l SCRAM RECOVERY l l

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TABLE OF CONTENTS l

-l 1 l_ SECTION PAGE NO. l l 1

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1.0 PURPOSE l 2 l

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2.0 REFERENCES

2 l l- 1 l Attachment 1 - Performance Package; MSIV's Open l

, l ', 3.0 PRECAUTIONS 3 l yl7 4.0 LIMITATIONS AND ACTIONS 3 l

'l. -5.0 PROCEDURE NOTES 4 l 1 I

.l Attachment 2 - Performance Package; MSIV's Closed l

'l 3.0 PRECAUTIONS 7 l l 4.0 LIMITATIONS AND ACTIONS 8 l-l 5.0 PROCEDURE NOTES 8 l 1 I

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'l l I I I I I I I I I I l' I I ~l l I

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~l l I I I I I I I I I I I i l I i i l l I I I I I i i 1 l .

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I ll l l l l N/A l N/A ll GOP-0007 l REV 0 l PAGE 1 0F IO l l l ll l l 1

l l l 1.0 PURPOSE l -

l l 0*l To provide instructions,to the Operations Section Personnel for plant l l recovery following a reactor scram. It is assumed that all applicable l l sections of A0P-0001 " Reactor Scram" and, if necessary, E0P-0001 "RPV l l Control" have been completed prior to entry into this procedure. l 1 I

.I The actions specified in this procedure are intended to prepare the l l plant for a subsequent startup (GOP-0005) or Shutdown to HOT SHUTDOWN .J

'l (GOP-0003) or Cold Shutdown (GOP-0004). -~l l l l Administrative requirements are' contained in AD!i-0022 " Conduct of l l Operations". l

. l l l

2.0 REFERENCES

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'. l l l' 2.1 ANSI N18.7-196 Administration Controls and Quality Assurance for l l the Operational Phase of Nuclear Power Plants. I I I l 2.2 " Preparation of Operations Section Procedures", OSP-0007.

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I 2.3 River Bend Unit 1 Technical Specifications. l l l I 2.4 River Bend Station Final Safety Analysis Report. l l l l 2.5 " Development, Control and Use of Procedures", AD}!-0003. l l l l 2.6 System Operatitg Procedures: l 2.6.1 " Circulating Water", SOP-0006.

I 2.6.2 "Feedwatar", SOP-0009.

. .l' ' l 2.6.5 " Reactor Water Cleanup", SOP-0090. l x, I l Y

e.1 l

l 2.6.6 "Off Gas System", SOP-0092. l l

l 2.6.7 " Condensate Demineralizer", SOP-0093. I l I I 2.6.8 "> fain Turbine", SOP-0080. l I I I 2.7 Abnormal Operating Procedure, " Reactor Scram". A0P-0001. l I I I 2.8 Emergency Operating Procedures, "RPV Control", E0P-0001. l I I

! 2.9 GSU Operational QA Manual,Section XIV. l l I l' 2.10 Administrative Procedure AD11-0022, " Conduct of Operations". I I I l

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I I I i 11 l l l l

N/A I N/A II GOP-000/ I REV - 0 l PAGE 2 0F 10 l I I ll l l l

m 3 l

l ATTACHMENT - 1 PERFORMANCE PACKAGE; MSIV's OPEN A

l INITIATED ' COMPLETED ON: DATE ON: DATE AT: TIME l AT: TIME l

BY: NCO l BY: NCO l SS SS OTHER DOCUMENTS ATTACHED:

.)

REMARKS: -

1 i

3.0 PRECAUTIONS l

3.1 Following a reactor scram from high power levels there is an initial RPV level " Shrink" of 20 to 40 inches followed by a " Swell" of approximately 10 to 20 inches. The Feedwater Level Control System is programmed to

" ride out" this shrink and swell without overfilling the RPV. ;0 NOT attempt to take manual control of the level unless misoperation in automatic is obvious. <

3.2 If Reactor Recire Pumps should trip, they should be restarted on LFMG to assure adequate mixing of RPV Coolant and prevent stagnation of Cool Water in the bottom head region. Consult SOP-0003 for pump restart precautions.

3.3 If feedwater regulating valves leak excessively, close MOV's (IFWS-MOV27A, l 27B and/or 27C) to prevent overfilling the RPV. l l

4.0 LIMITATIONS AND ACTIONS l l

1 l 4.1 RPV level should be maintained between +35" and +45" on the Wide Range l Level Recorder, throughout this procedure unless specifically directed l otherwise.

l 1 l . l .

, ATrACHMENT - 1 PAGE 1 0F 4 GOP-0007 REV - 0 PAGE 3 0F 10

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I A'ITACHMENT - 1 PERFORMA:!CE PACKAGE; MVIS's OPEN (Continued)

I t 4.2 Limit the reactor coolant temperature change to less than or equal to 100*F when averaged over any one hour period (Technical Specifications 3.4.6.1).

I 4.3 When heat is being added to the suppression pool, maintain pool temperature- l per (Technical Specification 3.6.3.1).

4.4 Whenever the Condensate /Feedwater System is providing primary makeup to the RPV with the RPV water temperature greater than or equal to 212'F, condenser vacuum should be maintained between 23 Hg and 28 in. Hg to assure deaeration of the feedwater and reduce the possibility of Inter-Granular

. Stress Corrosion.

4.5 The Main Turbine must remain on Turning Gear whenever the Steam Seals are on.

4.6 Maintain Condensate Demin inlet temperature less than 130 F.

4.7 Complete administrative requirements in reference 2.9 before restarting the reactor.

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PROCEDURE NOTES 5.1 As feed flow is reduced, reduce on-line condensate demins per SOP-0093 to maintain flow through each demin between 1250 GPM and 2350 GPM.

l 5.2 Block the NSSS Computer P-1 Calculations per (LATER).

5.3 If RPV drain temperature to saturated steam temperature differential exceeds l 100*F then depressurize the RPV as necessary to maintain this differential temperature less than (LATER).

5.4 Anytime steam loads are reduced (such as when steam drains are closed ,

or steam driven equipment is shutdown) maintain RPV pressure control I with the Bypass Valves. '

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5.5 Except as specified, primary RPV level control will be with makeup from the Feedwater System with reject as necessary (to control increasing level) from RWCU Blowdown to the main condenser per SOP-0090.

5.5.1 Maintain condenser vacuum between 23" Hg and 28" Hg.

5.6 If the circulating water pumps trip and cannot be immediately started, close MSIV's and enter Attachment 2 of this procedure. 4 5.7 The reactor scram must be reset in order to restore normal CRD Hydraulic System operation.

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_ ATTACHMENT - 1 PAGE 2 0F 4 l G0P-0007 l REV - 0 l PAGE 4 0F 10 I I I l

r I I I I A'ITACHMENT - 1 l PERFORMANCE PACKAGE; MSIV's OPEN (Continued) I STEP INITIAL

1. l Verify / establish on-scale neutron monitoring on the SRM's and IRM's l l l l l t I ~ .. i
2. " l Maintain RPV pressure at approximately 950 Psig using cay of the l l l following: l l
a. Main Turbine Bypass Valves per SOP-0080. l
1) On automatic pressure control l l, 2) With bypass valve opening jack l l l b. Normal plant steam loads.

'l 1) SJAE per SOP-0025

2) Steam seals per SOP-0015 l

'3 ) Radwaste reboiler per SOP-0026 l

4) Off gas preheater per SOP-0092 l l
5) MSL drains per SOP-0011 l l l c. RCIC per SOP-0035. l l l l l 1 I I
3. I Verify Main Turbine Steam Seals are being maintained at l l l approximately 4 Psig. l l 1 I I l l l
4. l Maintain RPV level usiag condensate /feedwater as follows: l l l a. Transfer level control to single element as follows; l l

?. '1) Verify RPV level is stable at the MASTER LEVEL' CONTROL l l L

[C33-R600) setpoint (will be in "Setdown"). I l

2) Verify steam flow and feed flow are approximately equal. l l
3) Select the 1 pushbutton on the ELEMENT 1 OR 3 SELECT. l l l 4) Depress the level "Setdown" reset pushbutton as necessary l l l to restore RPV level setpoint to 35" to 38". l l l b. Shutdowu condensate pumps and feedpumps as necessary to have l l l one condensate and one feedwater pump running. l l c. If necessary, start RCIC per SOP-0035. l l d. Use RWCU blowdown per SOP-0090 if RPV level increases to +50". l l l _I I I l l S. l If tripped, restart reactor recirculation pumps on LFMG per SOP-0003l l l a. Open flow control valves to the full open position (see Tech l l l Spec 4.4.1.4). l l 1 l l 6.

I I_ I l Verify the HCU scram accumulators have been recharged, by observing l l l the ACCUM FAULT indicating lights on 1H13-P680 are out. l l 1 I I

7. Shutdown both heater drain pumps per SOP-0010. l h j l

l l l 1

8. l Open/verifv open main steam drain valves [1B21-MOVT021 and F0681 l___ l t .I I . I I .

4 ATTACHMENT - 1 l PAGE 3 0F 4 l GOP-0007 l REV - 0 PAGE 5 0F 10

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A'ITACHMENT - 1 PERFORMANCE PACKAGE; MSIV's OPEN (Continued) i 1 0 1

i STEP l INITIAL l .l
9. , Shutdown feedwater heaters extraction steam per SOP-0010. l l

I Consistent with decay heat availability, open the following drain

10. '

l valves to the rnain condenser; i l

a. Main Stop nefore Seat [1DDI-MOVSV1, SV3, SVS, SV7] l l
b. SJAE Supply Line [1DTM-MOV175] l l
c. Main Steam Header [1DDI-MOV12A and 12B] l l
d. Main Steam Line [1B21-MOVF066A-D] l l
e. Main Steam Line [1B21-MOVF070] l l
f. Main Steam Line Drain Header [1B21-MOVF015, F016, F085] l l
g. MSIV Before Seat [1B21-MOV068, 1DR1-MOV199] l l
h. Reheater Steam Supply [1DTM-MOV51A and B, 54A and B] l l
i. Crossaround Piping [1DDI-MOVCA1-CA6] l l
j. Extraction Line [1DDI-A0V32A, 32B, 35A, 35B, 41A, 41B] l l l

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11. l Start air removal pumps'per SOP-0025, if required (SJAE inadequate) l l l a. Maintain vacuum between 23" Hg and 28" Hg l l l l l l l
12. Shutdown moisture separatsr/ reheaters and establish steam blanketing l per SOP-0010. l 1 I l
13. Complete the Scram Report and Post Trip Review Checklist (in l l reference 2.9). l l l I
14. If Plant Shutdown is desired, notify System Dispatcher and enter l ,

GOP-0003 or GOP-0004. l }

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15. If it is desired ta startup the Plant, perform the following:

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a. Verify the cause of the scram is known and no longer exists. I
b. Verify that the necessary maintenance actions and post-main- l tenance tests to correct any malfunction that caused or con- l tributed to the scram have been corrected. l l l c. Enter GOP-0005. g i l i I I I I
16. Submit the completed Scram Report, Post Trip Review Checksheet and j this attachment to tta. Operations Supervisor for review. l l l l 1 I I i l i i i il I . I -

ATTACHMENT - 1 l PAGE 4 0F 4 l GOP-0007 l REV - 0 l PAGE 6 0F 10 l l I l

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I I 1 1 I ATTACHMENT - 2 l PERFORMANCE PACKAGE; MSIV's CLOSED '

l l I

, ' INITIATED l COMPLETED I

ON: DATE l ON: DATE I

AT: TIME l AT: TIME BY: NCO BY: NCO SS SS OTHER DOCUMENTS ATTACHED:

' ~

REMARKS:

3.0 PRECAUTIONS 3.1 Following a reactor scram from high power levels there is an initial RPV level " Shrink" of 20 to 40 inches followed by a " Swell" of approximately 10 to 20 inches. The Feedwater Level Control System is programmed to

" ride out" this shrink and swell without overfilling the RPV. DO NOT attempt to take manual control of the level unless misoperation in l l automatic is obvious. l 3.2 If Reactor Recirc Pumps should trip, they should be restarted on LFMG to assure adequate mixing of RPV Coolant and prevent stagnation of Cool Water in the bottom head region. Consult SOP-0003 for pump restart.

precautions.

3.3 If feedwater regulating valves leak excessively, close MOV's (1FWS-MOV27A, 27B and/or 27C] to prevent overfilling the RPV.

3.4 One loop of RHR should be left available for shutdown cooling or suppression pool' cooling (B loop is preferred).

ATTACHMENT - 2 PAGE 1 0F 4 GOP-0007 REV - 0 PAGE 7 0F 10

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I l ATTACHMENT - 2 l PERFORMANCE PACKAGE; MSIV's CLOSED (Continued)

J l 4.0 LIMITATIONS AND ACTIONS l 4.1 RPV lovel should be maintained between +35" and +45" on the Wide Range l Level Recorder, throughout this procedure unless specifically directed 1 otherwise. -

4.2 Limit the reactor coolant temperature change to less than or equal to 100*F/hr when averaged over any one hour period ('Inchnical Specifications 3.4.6.1).

4.3 When heat is beging added to the suppression pool, maintain pool temperature 1 per (Technical Specifications 3.6.3.1).

4.4 Whenever the Condensate /Feedwater System is providing primary makeup to the RPV with the RPV water temperature greater than or equal to 212*F, condenser vacuum should be maintained between 23 Eg and 28 in. Hg. to assure deaeration of the feedwater and reduce the possibility of Inter-Granular Stress Corrosion.

I 4.5 The Main Turbine must remain on Turning Gear whenever Steam Seals are on. l l

4.6 Maintain Condensate Demin inlet temperature less than 130 F. l 4.7 Do not shutdown one Decay Heat Removal mode unless a second mode is in l service and demonstrated adetuate.

4.8 Complete administrstive requirements in reference 2.9 before restarting the reactor.

5.0 PROCEDURE NOTES 5.1 As feed flow is reduced, reduce on-line condensate demins per SOP-0093 to maintain flow through each demin between 1250 GPM and 2350 GPM.

5.2 Block the NSSS Computer P-1 Calculations per (LATER).

5.3 If RPV drain temperature to saturated steam temperature differential exceeds 100*F, then depressurize the RPV as necessary to maintain this differential temperature less than (LATER). i l

5.4 Except as specified, primary RPV pressure control will be with RCIC l initially, with RHR Steam Condensing Mode placed in service as soon as possible. If necessary, SRV's will be used to supplement / augment RCIC/RHR. l l

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I ATTACHMENT - 2 PAGE 2 0F 4 G0P-0007 REV - 0 PAGE 8 0F 10

l l AiTACHMENT - 2 PERFORMANCE PACKAGE; MSIV's CLOSED (Continued) l

, I j 5.6 RHR should be operated in Suppression Pool Cooling anytime heat is being I added to the suppression pool.

I STEP INITIAL

1.  ! Verify / establish on scale neutron monitoring on SRM's and IRM's. j l
2. . Maintain RPV pressure; use the following systems as needed (listed

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I in order of perference):

a. RCIC'in CST to CST recire per SOP-0035.

[ b. Steam condensing mode of RHR SOP-0031.

l c. SRV's per SOP-0029. Alternate opening SRV's as necessary to l equalize suppression pool heating, u d. Steam line drains (if. condenser is available).

l l

3. Maintain RPV level; use the following systems as needed (listed in '

l order of perference):

l a. Condensate /feedwater; transfer to single element as follows; l 1) Verify RPV level is stable at the MASTER LEVEL CONTROL

[C33-R600] setpoint (will be in "Setdown").

2) Verify steam flow and feed flow are approximately equal.
3) Select the i pushbutton on the ELEMENT 1 OR 3 SELECT.
4) Depress the level "Setdown" reset pushbutton as necessary to restore RPV level setpoint to 35" to 38".
5) Shutdown condensate pumps and feed pumps as necessary to l l have one of each running. l l
b. RCIC in normal RPV inject mode per SOP-0035. l
c. HPCS per SOP-0030. l 1 1 1
4. If necessary to reduce RPV level, operate RWCU in the blowdown mode  ;

per SOP-0090:

a. Reject to hotwell is preferred.

l b. Reject to radwaste if necessary.

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5. If tripped, restart reactor recirculation pumps on LFMG per GOP-0003l
a. Open flow control valves to the full open position. l 1
6. Verify Steam Seals are being supplied by auxiliary boiler.

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7. Start air removal pumps per SOP-0025
a. Maintain condenser vacuum between 23" Hg and 28" Hg.

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ATTACHMENT - 2 l PAGE 3 0F 4 GOP-0007 REV - 0 PAGE 9 0F 10 l I I' I L _

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ATTACHMENT - 2 l PERFORMANCE PACKAGE; MSIV's CLOSED (Continued) i I l

STEP INITIAL j i l l I

8. Verify that the HCU scram accumulators hav9 been recharged by l observing the ACCUM FAULT indicating lights on 1H13-P680 are out. l l

l

9. Shutdown or verify shutdown, the heater drain pumps per SOP-0010: l l a. Verify #3 feedwater heaters dump valves to the condenser open l l to control level. l l

l If all isolation sigrials are clear, open/ verify open Main Steam 10.

Drain Valves [1B21-MOVF021 and F068]. l 1

11. Shutdown feedwater heaters extraction steam per SOP-0010. ~

l l

12. Open the following drain valves to the main condenser: l "l a. Main Stop Before Seat (1DTM-MOVSV1, SV3, SV5 and SV7] l i
b. SJAE Supply Line [1DTM-MOV175] l
c. Main Steam Header [1DTM-A0V12A, 12B] l
d. Main Steam Line [1B21-A0VF06( . - D] l
e. Main Steam Line [1B21-A0VF070] l
f. Main Steam Line Drain Header [1B21-MOVF015, F016, F085] l l
g. MSIV Before Seat [1B21-MOV068, 1DTM-MOV199] l l
l h. Reheater Steam Supply [1DTM-MOV1A and 1B, 54A and B] l l
1. Crossaround Piping [1DTM-MOVCA1-CA6] .

l l

j. Extraction Line [1DTM-A0V32A, 32B, 35A, 35B, 41A, 41B] l l l l l l
13. Shutdown moisture separator / reheater and establish steam blanketing l l per SOP-0010. l 1 l

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14. Complete the SCRAM report and Post Trip Review Checklist (in l reference 2.9). l I I l l
15. If plant shutdown is desired, enter GOP-0003 or GOP-0004. l l

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16. I If it is desired to start up the plant, perform the following: l
a. Verffy the cause of the scram is known and no longer exists. l l b. Verify that the necessary maintenance actions and post-main- l

, l tenance tests to correct any malfunction that caused or con- l l tributed to the scram have been completed. l l

c. Enter GOP-0005. l l 1 i
17. Submit the completed scram report, Post Trip Review Checklist, and l .

l this attachment to the Operations Supervisor for review. l ll Il l l l ATTACHMENT - 2 PAGE 4 0F 4 ll GOP-0007 l REV - 0 PAGE 10 0F 10 l l 11 1 I

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