ML20003A413

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Forwards Draft Emergency Procedures for NRC Review.Bwr Owners Group Expected to Forward Revised Guidelines to NRC in Late Jan or Early Feb 1981
ML20003A413
Person / Time
Site: Grand Gulf  Entergy icon.png
Issue date: 01/27/1981
From: Dale L
MISSISSIPPI POWER & LIGHT CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8102030643
Download: ML20003A413 (50)
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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi kihkihblideE P. O. B O X 16 4 0 J A C K S O N, MISSISSIPPI 39205 January 27, 1981 NUCLEAR PRoOUCT1oN DEPARTMENT U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.

20555 Attention:

Mr. Ha rold R. Denton

Dear Sir:

SUBJECT:

Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 File 0260/0277/L-860.0/L-952.0 Transmittal of GGNS Emergency Procedures AECM-81/44 Attached are the Grand Gulf Nuclear Station (GGNS) emergency procedures (EP-1 through EP-9).

These procedures are based on the BWR Owner's Group Emergency Procedure Guidelines. We understand that the revised guidelines which include BWR-6 are to be formally submitted to the NRC by the Owner's Group in late January or early February, 1981.

Prior to the formal submittal mentioned above, we anticipate some improvements to the guidelines by the Owner's Group. Accordingly, there will be some changes made to the attached GGNS emergeacy procedures.

We, however, expect that the changes will be minor in nature and recommend that your review be based on the attached procedures.

Some curves and specified numerical values presented in the attached procedures are generic in nature and not GGNS specific. The GGNS specific information will be submitted when available.

I The emergency procedure pertaining to the Anticipated Transient Without Scram (ATWS) event is currently under preparation and is not i

l included in this package. This procedure will be submitted no later l

than January 30, 1981.

1 Please contact Mr. J. Richardson or myself for additional inf o rma tion.

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Yours truly, l

1

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L. F. Dale Nuclear Project Manager

/ /

JGC/LFD:Im Attachments:

(See Next Page)

~ h?I jh deer Middle South Utilities System

e MISSISSIPPI POWER & LIGHT COMPANY U.S. Nuclear Regulatory Commission AECM-81/44 Office of Nuclear Reactor Regulation Page 2 1

-Attachments:

GGNS Safety Related Emergency Procedures 1.

EP-1 Level Control Rev. A 2.

EP-2 Cooldown Rev. A 4

3.

EP-3 Containment Contro1*

Rev. A 4.

EP-4 Level Restoration Rev. A 5.

EP-5 Rapid RPV Depressurization Rev. B 6.

EP-6 Core Cooling Vithout Injection Rev. A 7.

EP-7 Core Cooling Without Level Rev. A Restoration 8.

EP-8 Alternate Shutdown Cooling Rev. B 9.

EP-9 RTV Flooding Rev. B

  • Attachment I to EP-3 will be provided later.

cc:

Mr. N. L. Stampley Mr. G. B. Taylor Mr. R. B. McGehee Mr. T. B. Conner Mr. Victor Stello, Jr., Director Division of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

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GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE PLANT OPERATIONS MANUAL 05-S-01-EP-1 Volume 5 Revision A Section 1 Date:

EMERGENCY PROCEDLRE LEVEL CONTROL SAFETY RELATED Date Prepared:

Reviewed:

Date Technical Review Reviewed:

Date Operations Superintendent Reviewed:

Date Nuclear Plant Quality Superintendent-4 Date-Approved:

Assistant Plant Manager.

PSRC:

Date 1

List of Effective Pages:

Page:

Revision:

1-2 Rev. A Attachment I Rev. A I

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GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE:

Level Centrol NO. 05-S-01-EP-1 REV. A PAGE 1 of 2 1.0 PURPOSE The purpose of this p. ocedure is to restore and stabilize RPV water level above the tcp of the active fuel (TAF).

2.0 ENTRY CONDITIONS

] Entry conditions are any of the following:

]

2.1 RPV water level below +10"

]

2.2 Drywell pressure above +1.75psig 2.3 Group I isolation 3.0 OPERATOR ACTIONS 3.1 Confirm initiation'of any of the'following which should have occurred:

]

3.1.1 Reactor Scram (from any scram signal)

]

3.1.2 Group I Isolation (from any Group I isolation signal)

]

3.1.3 ECCS (+1.75psig DW = HPCS, LPCS, LPCI & possibly ADS)

(-51" RPV level = HPCS)

(-150" RPV level = LPCI, LPCS & possible ADS)

]

3.1.4 D/G's Start (from any D/G start signal)

] 3.2 Initiate any of the action of 3.1 which should have initiated but did not.

] 3.3 Enter ONEP 05-1-02-I-1 (Reactor Scram) and execute if concurrently with this procedure.

] 3.4 Confirm or place the Reactor Mode Switch in REFUEL.

CAUTION Avoid RPV High Water Level Trip (+52") of RFPT's, RCIC, and HPCS injection valve (E22-F004).

l

[ 3.5 Restore and maintain RPV water level between +10" and +52" with one or i

more of the following systems:

1

]

3.5.1 Feedwater (1103 - O psig)

]

3.5.2 CRD (1103 - O psig)

]

3.5.3 RCIC (1103 - 50 psig)

-]

3.5.4 HPCS (1103 - O psig) l

]

3.5.5 LPCS (500 - O psig).

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GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Level Control NO. 05-3-01-EP-1 REV. A PAGE 2 of 2

[))

3.5.6 Condensate Booster (435 - O psig)

{ 3.5.7 Condensate (270 - O psig) [)) 3.5.8 LPCI (310 - O psig) [)) 3.6 If RPV water level cannot be restored and maintained above +10", maintain RPV water level above TAF. a. TAF = 0" as read on fuel zone instrumentation: (1) P601 - RHR Section - B21-R615 (2) P601 - RCIC Section - B21-R610 [)) 3.7 If RPV water level cannot be determined or maintained above TAR enter EP-4 (Level Restoration). {] 3.8 If SRV's are cycling, open ore SRV and reduce RPV pressure by at Isast 150psig to minimize SRV cycling. (Alternate SRV's to equalize suppression pool heating if.this step must be repeated.) NOTE SRV Low-Low Set should have activated at 1103 psig and reduced RPV pressure to 926 psig. This SRV will reopen at 1033 psig (B21-F051D @ 0 Azimuth). (()3.9 When the RPV water level has stabilized, enter EP-2 (Shutdown).

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GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE PLANT OPERATIONS MANUAL Volume 5 05-S-01-EP-2 Section 1 Revision A Date: EMERGENCY PROCEDURE C00LDOWN SAFETY RELATED Date Prepared: Reviewedi Date Technical Review Reviewed: -Date Operations Superintendent Reviewed: Date Nuclear Plant Quality Superintendent Date Approved: l Assistant Plant Manager PSRC: Date l List of Effective Pages: Page: Revision: il - 5' Rev. A' l-t . Attachment I . Rev. A l~ l l' { l

B GRAND GUIS NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Cooldown NO. 05-S- 01-EP-2 REV. A PAGE 1 of 5 1.0 PURPOSE The purpose of this procedure is to depressurize and cooldown the RPV to cold shutdown conditions while maintaining RPV water level within a satisfactory range. 2.0 ENTRY CONDITIONS This proce. dure is entered from EP-1 (Level Control) after the RPV water level has beca stabilized. 3.0 OPERATOR ACTIONS ~ CAUTION IE While depressurizing the RPV, a high Drywell pressure (+1.75psig) ECCS ' initiation signal occurs or exists. THEN Prior to reaching their maximum injection pressures, prevent injection from those LPCS and LPCI pumps that are not required to assure adequate core cooling (keeping the core covered, or spraying onto the core). WHEN The high Drywell pressure (+1.75psig) ECCS initiation signal clears, restore LPCS and LPCI to the standby condition. CAUTION Do not place an ECCS in the MANUAL mode unless. by two independent indications: 1. misoperation in the AUTOMATIC mode is confirmed, or 2. adequate core cooling is assured. i IE An ECCS is placed in the MANUAL mode: 1. it will not initiate automatically. 2. make frequent checks of the initiating or controlling parameter.

i GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Cooldown NO. 05-S-01-EP-2 REV. A PAGE 2 of 5 CAUTION - Cont'd hE_2 Manual operatien is no longer required, restore the system to the AUTOMATIC / STANDBY mode if possible. ] 3.1 Maintain RPV water level between +52" and the TAF. TAF = 0" as read on fuel zone instrumentation: a. (1) P60.1 - RHR Section - B21-R615 (2) P601 - RCIC Section - B21-R6); i] 3.1.1 Use one or more of the following systems: a. Feedwater (1103 - O psig) ] b. CRD (1103 - O psig) ] (1) Operate two pumps if possible (2) Increase flowrate to maximum c. RCIC (1103 - 50 psig) ] (1) Maintain greater than 2000 RPM to ensure sufficient oil pressure by placing the RCIC FLOW CONTROLLER to MANUAL and adjusting RPM (2) Be aware that this system results in Suppression Pool heating d. HPCS (1103 - O psig) ] e. LPCI (500 - O psig) ] ] f. Condensate Booster (435 - O psig) g. Condensate (270 - O psig) ] ] h. LPCI (310 - O psig) If high Suppression Pool water level (18'10") or low Condensate ] 3.1.2 f Storage Tank le'el (2'0") occurs: Confirm automatic transfer of HPCS and RCIC suctions from ] a. the Condensate Storage Tank to the Suppression Pool. ] (1) HPCS - E22-F015 opens and then E-22-F001 closes. ] (2) RCIC - E51-F031 opens and then E51-F010 closes.

-GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Cooldown NO. 05-S-01-EP-2 REV. A PAGE 3 of 5 b. Manu lly transfer HPCS and RCIC suction paths if the ] automatic transfer fails to initiate as designed. 3.1.3 If the following limits are exceeded, proceed to EP-3 (Containment Control) and perform it concurrently with this procedure. a. Drywell pressure above +1.75psig ] b. Drywell temperature above 135 F ] c. Suppression Pool temperature above 95 F ] ] .d. Suppression Pool level above 18'10" Suppression Pool level below 18' 5.5" ] e. C f. Containment teuperature above 90 F CAUTION If RPV water level cannot be determined or maintained above TAF, enter EP-4 (Level Control). 1. TAF = 0" as read on fuel zone instrumentation: P601 - RHR Section - B21-R615 P601 - RCIC Section - B21-R610 C 3.1.4 If SRV's are cycling, manually open one SRV and reduce RPV pressure As150 psig below the lowest SRV lift pressure. l (880psig after low low set has actuated). l ]3.2 Depressurize the RPV and stintain cooldown rate below 100 F/hr. NOTE Cooldown rates greater than 100 F/hr may be required to: 1. Conserve RPV wat er inventory 2. Protect Primary Containment integrity 3. Limit radioactive release to the environment 3.2.1 Use one or more of the following systems: a. Main Condenser available ] ] (1) Main turbine bypass valves (preferred method)

i GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Cooldown NO. 05-S-01-EP-2 REV. A PAGE 4 of 5 ((] (2) RCIC (a) Maintain greater than 2000 RPM to ensure sufficient oil pressure by placing the RCIC FLOW CONTROLLER to MANUAL and adjusting RPM. (b) Maintain greater than 50psig RPV pressure unless motor driven pumps sufficient to maintain RPV level are running and available for injection. (c) Be aware that this system results in Suppression Pool heating. {}} (3) RHR (Steam Condensing Mode) [)) (4) Other steam driven equipment {)) (5)~ RECU (recirculatiou _s fe) {)) (6) Main Steam Line Drains {}} (7) RWCU (blowdown mode) {}} b. Main Condenser not available ((} (1) RCIC (a) Maintain greater than 2000 RPM to ensure sufficient oil pressure by placing the RCIC FLOW CONTROLLER to MANUAL and adjusting RPM. (b) Maintain RPV pressure greater than 50psig unless motor driven pumps sufficient to maintain RPV - water level are running and available for injection. (c) Be aware that this system results in Suppression Pool heating [)) (2) RHR (Steam Condensing Mode) [)) (3) RWCU (Recirculation Mode) l I)) (4) SRV's l (a) Each SRV actuation should be selected from the next steam line in order from the line selected ~ previously (B, D, A, C, sequence) to equalize Suppression Pool heating. l l (b) Fewer blowdowns with increased pressure reductions are desirable to minimize SRV cycle stresses. I

9 a GRAND GUIS NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Cooldown NO. 05-S-01-EP-2 REV. A PAGE 5 of 5 (c) If the continuous SRV pneumatic supply is or becomes unavailable, depressurize with sustained SRV opening. ] (5) RWCU (Blowdown Mode) U 3.2.2 When the RHR shutdown cooling interlocks clear, initiate the shutdown cooling mode of RHR. l CAUTION I If RPV cooldown is required but cannot be accomplished, proceed to EP-8 (Alternate Shutdown Cooling). If the RHR shutdown cooling mode cannot be established and a. further cooldown is required, continue to cooldown with the systems listed in substep 3.2.1.a or 3.2.1.b as applicable. b 3.2.3 Proceed to Cold Shutdown in accordance with 101 (Lat r). %%:, pfM \\$cc.

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- = -. i i i j GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE PLANT OPERATIONS MANUAL 1 Volume 5 05-S-01-EP-3 l Section 1 Revision B 4 Date: l 1 EMERGENCY PROCEDLTE CONTAINMENT CONTROL SAFETY RELATED Prepared: Date i Reviewed: Date Technical Review Reviewed: Date Operations Superintendent Reviewed: Date Nuclear Plant Quality Superintendent Approved: Date Assistant Plant Manager PSRC: Date List of Effective Pages: Page: Revision: 1-7 Rev. B Attachment I Rev. B

i GRAND GUI.F NUCI. EAR STATION EMERGENCY PROCEDURE TITI.E: Containment Control NO. 05-S-01-EP-3 REV. B PAGE 1 of 7 1.0 PLTPOSE The purpose of this procedure is to control primary containment temperatures, pressure and level. This procedure will be performed concurrently with the procedure from which it was entered. 2.0 ENTRY CONDITiuNS The entry conditions for this procedure are any of the following: i Paragraph 2.1 Drywell pressure above +1.75psig 3.3 ] 2.2 Drywell temperature above 135 F 3.2 ] 2.3 Suppression Pool temperature above 95 F 3.1 ] ] 2.4 Suppression Pool leveT above 18'10"- 3.4 [ 2.5 Suppression Pool level below 18' 5.5" f 3.4 ] 2.6 Containment temperature above 90 F l 3.5 NOTE Enter the paragraphs of thi. procedure as required by the entry condition. The paragraphs can and should be performed concurrently with each other as the entry conditions dictate. 3.0 OPERATOR ACTIONS 3.1 Monitor and control suppression pool temperature. i ] 3.1.1 Attempt to close any stuck open SRV. If any stuck open SRV cannot be closed within two minutes, ] a. Scram the reactor. ] 3.1.2 Operate available suppression pool cooling when both: adequate core cooling does not require that RHR pumps be ] a. continuously operated in the LPCI mode ] b. suppression pool temperature reaches 95 F ] 3.1.3 If suppres'sian pool temperature reaches 110 F, scram the reactor. ] 3.1.4 If suppression pool temperature ' car.not be maintained below the heat capacity temperature limit, maintain RPV pressure below the limit.

EMERGENCY PROCEDURE GRAND GUIJ NUCLEAR STATION TITLE: Containment Control No. 05-S-01-EP-3 REV. B PAGE 2 of 7 CAUTION Do not depressurize the RPV below 50psig (RCIC lot, pressure isolation a. setpointi unless motor driven pumps sufficient tre maintain RPV water level are running and available for injection. b. Observe NPSH requirements for pumps taking a suction from the suppression pool l SL7PRESSION POOL PUMPS IMAXIMUM TEMPERATURE MINIMUM LEVEL IECS, LPCS, RHR 212 F 14'6" RCIC 140 F 14'6" NOTE Cooldown rates greater than 100 F/hr mir be required to accomplish this step. / 212 m 203-I f i 160

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g Heat Capacity / } TemperatureLimit e 122- \\ N I s s y N., 'o 135 240 1020 RFV Fressure (psig) [i 3.1.4 If suppression pool temperature and RPV pressure cannot be ~ restored or maintained below the heat capacity temperature limit, proceed to EP-5 (Rapid RPV Depressurization). 3.2 Monitor and control dryvell, temperature. 3.2.1 Operate available drywell cooling when drywell temperature exceeds 135 F.

GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Containment Control No. 05-S-01-EP-3 REV. B PAGE 3 of 7 R 3.2.2 khenever temperature near the cold reference log vertical runs exceeds the temperature in the following table, the actual RPV ~ water level may be anywhere below the elevation of the lower instrument tap when the instrument reads below the indicated level in the table. CAUTION If the temperature exceeds the temperature in the table and the level reads the indicated level in the table, disregard the instrument for further reliability.. Indicated Instrumant Temperature Level Ty'pe Range Number 1 any 114 in. Shutdown 0" to +400 in. B21-LR-R605 8 ^ 98 F -115 in. Wide Range -160" to +60 in. I[ [ g B1]L-6A,B&C 314 F 19 in. Narrow Range 0" to +60 in. 1~ 380 F -107 in. Fuel Zone -150" to +50 in. 1 R6 0 CAUTION Shutdown Reactor Recirculation pumps and Drywell coolers: B001A and B002A - P870 - Section 4 - location - Drywell 93' elevation, B001B and B002B - P870 - Section 10 - location - Drywell 93' elevation, prior to l spraying the Drywell. l 3.2.3 Spray the drywell before the drywell reaches 330 F. a. Spray the drywell with the Fire Protection System [ (1) Open SP64-F238 on Panel P862. (a) The fusible links should have melted at 165 F. l [ (2) If the Auxiliary Building has isolated, the Drywell Fire Protection System can be activated by: l (a) Opening SP64-FA10A or SP64-FA10B (Auxiliary l Building Isolation Bypass Unit 1), or_ l (b) Resetting the Auxiliary Building Isolation Bypass Div I and Div II switches on panel 1H13-P870 sections 3 and 9. [ 3.2.4 If temperature near the cold reference leg instrument vertical runs reaches the RPV saturation limit, proceed to EP-5 (Rapid RPV Depressurization).

GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Containment Control NO. 05-S-01-EP-3 REV. B PAGE 4 of 7 \\\\N 550 21 .- E. \\ RPV. saturation {t g ti=It j:" N '27 N EU$ 5.5

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APv Pressure (pseg) 1000 C 3.2.5 If drywell temperature cannot be maintained below 330 F, proceed to EP-5 (Rapid RPV Depressurization). 3.3 Monitor and control drywell and primary containment pressure with the ] following systems, as required: Containmgnt Cooling System - Containment purge mode - if less [ 3.3.1 than 212 F in the Containment. Refer to SOI 04-1-01-M41-1. CAUTION Elevated suppression chamber pressure may trip the RCIC turbine on high exhaust pressure. Congainment Cooling System - Drywell purge mode - M less than [ 3.3.2 212 F in the Drywell. Refer to SOI 04-S-01-M41-1. CAUTION Shutdown Reactor Recirculation pumps and Drywell coolers: B001A and B002A - P870 - Section 4 - location - Drywell 93' elevation B001B and B002B - P870 - Section 10 - location - Drywell 93' elevation, prior to spraying the D/W. t] 3.3.3 Drywell Spray (Fire Protection System)

GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Containment Control NO. 05-S-01-EP-3 REV. B PAGE 5 of 7 Initiate Drywell spray using the Drywell Fire Protection a. System before drywell pressure reaches 20psig. (1) Open SP64-F238 on panel P862 (a) The fusible links should have melted at 165 F. ] (2) If the Auxiliary Building has isolated, the Drywell Fire Protection System can be activated by: (a) Opening SP64-FA10A or SP64-FA10B (Auxiliary Building Isolation Bypass Unit 1), or (b) Resetting the Auxiliary Building Isolation Bypass Div I and Div II switches og panel 1H13-P870 sections 3 and 9. ] 3.3.4 Scram the r'dactor when Drywell pressure reaches'+1.75psig. 3.3.5 If the Containment pressure cannot be maintained below 15psig, [ proceed to EP-5 (Rapid RPV Depressurization). i ] 3.4 Monitor and control suppression pool water level. [ 3.4.1 Maintain suppression pool water level between 18'10" and 18' 5.5". b M high suppression pool water lvel (18'10") g low a. Condensate Storage Tank level (2'0") occurs: (1) Confirm automatic transfer of HPCS and RCIC suctions from the Condensate Storage Tank to the Suppression Pool. (a) HPCS - E22-F015 opens and then t E-22-F001 closes. j (b) RCIC - E51-F031 opens and then i E51-F010 closes. CAUTION t I i Observe NPSH requirements. for pumps taking a suction from the Suppression l ! Pool. ~ l l Suppression Pool j Pumps

Maximum Temperature i Minimum Level l

14'6" HPCS, LPCS, RHR 212 F i l RCIC 140 F 14'6" l

GRAND GUIS NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Containment Control NO. 05-S-01-EP-3 REV. B PAGE 6 of 7 3.4.2 If normal suppression pool makeup cannot maintain suppression pool water level above 18' 5.5", scram the reactor and initiate SPMS by alternately opening and closing the upper containment pool dump valve to makeup to the suppression pool as required, a. If ECCS auto initiation signal is present, initiate the Suppression Pool Makeup System if not initiated automatically. 3.4.3 If suppression pool water level cannot be maintained above the Heat Capacity Level Limit, proceed to EP-5 (Rapid RPV Depressurization). NOTE The purpose of step 3.4.3 is to assure that unstable steam condensation of steam discharged through the SRV's at some point following an ADS actuation does not occur and to assure minimum top vent coverage in the event of a LOCA. 18.5' ] eat capacity Level Limit C $T l.$ 'f a k &3 16.1' ~ / l l T l g HC l AT = Heat capacity Temperature Limit Minus Suppression gg Pool Temperature (Quantitative Temperature Axis to be Provided Later) i 3.4.4 If suppression pool water level cannot be maintained below 18'10": If adequate core cooling is assured, terminate injection a. into the RPV from sources external to the primary containment.

GRAND GULF NUCLEAR STATIO.i EMERGENCY PROCEDURE TITLE: Containment Control NO. 05-S-01-EP-3 RIV. B PAGE 7 of 7 ] 3.4.5 When Primary Containment water level reaches feet at Opsig, terminate injection into the RPV from sources external to the primary containment regardless of whether adequate core cooling can be assured. 3.5 Monitor and control Containment temperature 3.5.1 Whenever temperature near the cold reference leg vertical runs exceeds the temperature in the following table, the actual RPV water level may be anywhere below the elevation of the lower instrument tap when the instrument reads below the indicated level in the table. CAUTION , If the temperature exceeds the temperature in the table and the level reads the indicated level in the tabTe; disregard the instrument for further reliability. Indicated Instrument Temperature Level Type Range Number any 114 in. Shutdown 0" to +400 in. B21-LR-R605 B ^ 98 F -115 in. Wide Range -160" to +60 in. B1] 4 314 F 19 in. NarrowRangel0"to+60in. 6A, B&C -150" to +50 in.f I [f6 380 F -107 in. Fuel Zone l-l I 3.5.2 Operate available containment cooling when containment temperature exceeds 90 F. l CAUTION Do not divert RHR pumps from the LPCI mode if continuous LPCI is required l for adequate core cooling. l l ] 3.5.3 If Containment temperature reaches 185 F, initiate Containment sp ray. 1 il 3.5.4 If Containment cannot be maintained below 185 F, proceed to EP-5 I l (Rapid RPV Depressurization). ~ l WT.ohpw M O. l l t

GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE PLANT OPERATIONS MANUAL Volume 5 05-S-01-EP-4 Section 1 Revision A Date: EMERGENCY PROCEDURE LEVEL RESTORATION SAFETY RELATED Prepared: Date Reviewed: Date Technical Review Reviewed: Date Operations Superintendent Reviewed: Date Nuclear Plant Quality Superintendent Approved: Date Assistant Plant Manager PSRC: Date List of Effective Pages: Page: Revision: 1-3 Rev. A Attachment I Rev. A

GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Level Restoration NO. 05-S-01-EP-4 REV. A PAGE 1 of 3 1.0 PURPOSE The purpose c' this procedure is to restore RPV water level to above TAF. 2.0 ENTRY CONDITIONS Enter this procedure from EP-1 (Level Control) or EP-2 (Cooldown) when RPV water level cannot be maintained above TAF. NOTE TAF = 0" as read on fuel zone instrumentation: 1. P601 - RHR Section - B21-R615 2. P601 - RCIC Section - B21-R610 3.0 OPERATOR ACTIONS i 3.1 Lineup for injection and start pumps in two or more of the following ((] injection subsystems: _l 3.1.1 Condensate ~ ((] 3.1.2 HPCS I'l 3.1.3 LPCI A ((] 3.1.4 LPCI B 1,_j 3.1.5 LPCI C ((] 3.1.6 LPCS j 3.2 If less than two injection subsystems (Paragraph 3.1) can be lined up, ((] commence lining up as many of the following alternate injection subsystems j as possible: 3.2.1 Standby Service Water crosstie (150 - O psig) 7 Run more thac one pump if possible a. b. Valves are operated from RHR section of 1H13-P601 ((} 3.2.2 Fire System i Fill any tank that can be pumped to the RPV a. 3.2.3 - ECCS fli'.sh' connections from the Condensate Transfer System [)) [] 3.2.4 SLC (test tank) I"] 3.2.5 SLC (boron tank) -,~ms-e n .e

GRAND GULF NUCLEAR STATZON EMERGENCY PROCEDURE TITLE: Level Restoration NO. 05-S-01-EP-4 REV. A PAGE 2 of 3 3.3 Monitor RPV pressure and water level 3.3.1 Continue in this procedure at the step indicated in the following table: i RPV LEVEL t INCREASING DECREASING 1 HIGH Step 3.3.2 (500psig) Step 3.3.5! IMMEDIATE Step 3.3.3 l (50psig) (50psig) j l LOV Step 3.3.4 Step 3.3.6 500psig = LPCS Shutoff Head 50psig = RCIC Low pressure isolation setpoint CAUTION IF RPV water level cannot be determined and at least one subsystem with at least one pump running is: l 1. line up for injection - proceed to EP-5 f (Rapid RPV Depressurization) 1 r i 1 2. not lined up for injection - proceed to EP-6 i 1 (Core Cooling Without Injection). NOTE If at any time the RPV water level trend reverses or RPV pressure changes I region, return to step 3.3.1. ( [-] 3.3.2 Proceed to EP-1 (Level Control) at paragraph 3.5. [)) 3.3.3 Determine RCIC availaoility: a. If RCIC.is not available and: { {}} (1) RPV pressure is increasing - proceed'to EP-5 (Rapid RPV Depressurization) i L_.I (2) RPV pressure is not increasing - proceed _to EP-1 (Level Control) at paragraph 3.5. b. If RCIC is available and RPV water level increases to +10",. ]"] proceed to EP-1 (Level Control) at. paragraph 3.5. l i ~

GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: Level Restoration NO. 05-S-01-EP-4 REV. A PAGE 3 of 3 ] 3.3.4 Determine RPV pre sure: If RPV pressure is_ increasing, proceed to EP-5 (Rapid RPV a. Depressurization). b. If RPV pressure is not increasing, proceed to EP-1 (Level Control) at paragraph 3.5. 3.3.5 With RPV water level decreasing: If RCIC is not operating, restart RCIC. ] a. b. If CRD is not operating and: ] (1) No injection subsystem is lined up for injection with pumps running, start pumps in alternate injection subsystem which are lined up for injection (Systems ' 1Tsted in paragraph 3.2) OR ] (2) At least two injection subsystems are lined up for injection with pumps running, proceed to EP-5 (Rapid RPV Depressurization) c. When RPV water level drops to TAF: ] NOTE TAF = 0" as read on fuel zone instrumentation: 1. P601 - RRR Section - B21-R615 2. P601 - RCIC Section - B21-R610 [ (1) If CRD is not operating and no injection or alternate injection subsystem is lined up with at least one pump running, proceed to EP-6 (Core Cooling Without j Injection). i [ (2) Otherwise, proceed to EP-5 (Rapid RPV Dep res suriza tic.d. C 3.3.6 If no injection subsystem is lined up for injection with at -least one pump running, start pumps in alternate injection subsystems which are lined up for injection. (Systems listed ia l paragraph 3.2) If RPV pressure M increasing, proceed to EP-5 (Rapid RPV ] a. l Depressurization). I f C b. If RPV is not increasing, when RPV water level decreases to l TAF, proceed to EP-7 (Core Cooling Without Level Restorat.f on). l 1 l

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1 GRAND GLU NUCLEAR STATION EMERGENCY PROCEDURE l PLANT OPERATIONS MANUAL Volume 5 05-S-01-EP-5 Section 1 Revision B Date: EMERGENCY PROCEDURE 1 RAPID RPV DEPRESSURIZATION i SAFETY RELATED Prepared: Date t Reviewed: Date Technical Review Reviewed: Date Operatiot s Superintendent i Nuclear Plant Quality Superintendent t Approved: Date Assistant Plant Manager PSRC: Date i l I List of Effective Pages: Page: Revision: j l 1-4 Rev. B Attachment I Rev. B t i i l. ..... -, -, -,. -.. - ~. - -

GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE Rapid RPV TITLE: Depressurization NO. 05-S-01-EP-5 REV. B PAGE 1 of 4 1.0 PURPOSE The purpose of this procedure is to rapidly depressurize the RPV tc allow injection systems to inject and restore RPV water level to an acceptable level above TAF. 2.0 ENTRY CONDITIONS This procedure is entered from the following Emergency Procedures: 2.1 EP-3 (Containment Control) when: 2.1.1 Suppression Pool temperature and RPV pressure cannot be maintained below the heat capacity temperature limit. (EP-3 step 3.1.4) []} 2.1.2 Drywell temperature near the cold reference leg instrument vertical luhs has increased to the RPV saturation limit. (EP-3 step 3.2.4) [-] 2.1.3 Drywell temperature cannot be maintained below 330 F. (EP-3 step 3.2.5) [-] 2.1.4 Containment pressure cannot be maintained below 15psig. (EP-3 step 3.3.5) fl 2.1.5 Suppression Pool Water level cannot be maintained above 107'0" or above the heat capacity level limit (EP-3 step 3.4.3). [)) 2.1.6 Containment temperature cannot be maintained below 185 F. (EP-3 step 3.5.4) 2.2 EP-4 (Level Restoration) when: ~)) 2.2.1 RPV water level cannot be determined and at least one injection l I alternate injection subsystem is lined up with at least one l ot pump running. (EP-4 paragraph 3.3 CAUTION) l Il 2.2.2 RPV water level is incre. sing, RPV pressure is between 50 psig and 500 psig and is increasing, and RCIC is not available (EP-4 ~-~ l step 3.3.3). ~~} 2.2.3 RPV water level is increasing, RPV pressure is less than 50 psig and RPV pressure is increasing (EP-4 step 3.3.4). 1 l l [_j 2.2.4 RPV water level is decreasing, RPV pressure is greater than 50 l psig, CRD is not operating and at least two injection subsystems l are lined up for injection with pumps running (EP-4 step 3.3.5). [-] 2.2.5 RPV water level is decreasing, RPV pressure is'less than 50 l psig, any injection or alternate injection subsystes is lined up l with pumps running and RPV pressure is increasing (EP-4 step l 3.3.6). J

GRAND GULF NUCLEAR STATION EMEhrfNCY PROCEDURE Rapid RPV TITLE: Depressurization No. 05-S-01-EP-S REV. B PAGE 2 of 4 1.3 EP-6 (Core Cooling Without Injection) when low pressure injection subsystems (or alternate injection subsystems) are lined up for injection with at least ene pump running. (EP-6 paragraph 3.3) 3.0 OPERATOR ACTIONS [)) 3.1 Open all ADS valves. l CAUTION i i a. Do not depressurize the RPV below 50 psig (RCIC low pressure isolation setpoint) unless motor driven pumps sufficient to maintain RPV water level are running and available for injection. b. Observe NPSH requirements for pumps taking* a suction from the Suppression Pool. I SUPPRESSION POOL Pumps i Maximum Temnerature Minimum Level HPCS, LPCS, RHR 212 F l 14'6" RCIC 140 F 14'6" NOTE Cooldown rates greater than 100 F/hr may be required to accomplish this step. ((] 3.2 If not all ADS valves can be ope 9ed, open other SRV's until 11 valves are open. ((] 3.3 If less than three SRV's can be opened, rapidly depressurize the RPV using one or more of the following systems: NOTE 1. Defeating isolation interlocks may be required to complete this step. 2. Minimize radioactive release to the l environment. ((} 3.3.1 Main Condenser ((} 3.3.2 RHR (Steam Condensing Mode) ((] 3.3.3 Other Steam Driven Equipment () 3.3.4 Main Steam Line Drains

GRAND GUIJ NUCLEAR STATION EMERGENCY PROCEDURE Rapid RPV TITI.E: Depressurization NO. 05-S-01-EP-5 REV. B PAGE 3 of 4 3.3.5 RWCU (Blowdown Mode) [ 3.3.6 RCIC Steam Line ] 3.3.7 Head Vent ] 3.4 If RPV water level cannot. be determined, proceed to EP-9 (RPV Flooding). 3.5 If Containment pressure reaches 7.5psig, divert one LPCI pump flow to the CONTAINMENT SPRAY MODE for a period of time sufficient to reduce Containment pressure. NOTE Containment spray will initiate automatically at 9psig. [ 3.6 If' Containment pressuYe'cannot be maintained below 15psig; proceed to EP-9 (RPV Flooding). [ 3.7 If temperature near the cold reference leg instrument vertical runs reaches the RPV saturation limit as determined from the following figure, proceed to EP-9 (RPV Flooding). f s. E em_:: \\N 9; %. ,,,.s.....~ limit j!! N 237 N E35 5

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. -. - = = _ -. .. ~ _ i GRAND GUIJ NUCLEAR STATION EMERGENCY PROCEDLM 1 Rapid RPV TITLE: Depressurization NO. 05-S-01-EP-5 REV. B PAGE 4 of 4 [ 3.8 If the Soppression Pool water level is less than 16'1", initiate the i Suppression Pool Makeup System. i P870 - Sections 4 and 10 - E30-LR-R600A and B a. 4 i b. P870 - Sections 4 and 10 - Manual Initiate Pushbuttons I 3.9 Proceed to EP-1 (Level Control) at paragraph 3.5 l e i I t o ' l 4 4 4 5 l b ' i f i i l t r b i ~ i r l s m i _.-__.~,,,,..;_..,.,...,,--..,-..,_m , r.. :.-..._ - _..-.._,__.._.a.. ._.-a,

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GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE Core Cooling TITLE: Without Injection NO. 05-S-01-EP-6 REV. A PAGE 1 of 2 1.0 PURPOSE The purpose of this procedure is to cool the reactor core with steam sufficiently to maintain peak cladding temperature (PCT) below 2200 F. 2.0 ENTRY CONDITIONS Entry Conditions consist of the following canditions occuring simultaneously: ] 2.1 RPV water level has decreased to 0" (TAF) on the fuel zone instrumentation: 2.1.1 P601 - RHR Section - B21-R615 2.1.2 P601 - RCIC Section - B21-R610 ] 2.2 CRD is not operating. ] 2.3 No injection or alternate injection subsystem is lined up with at least one pump running. 3.0 OPERATOR ACTIONS ] 3.1 Open one SRV _i_f either: C 3.1.1 RPV water level is unknown, or 3.1.2 RPV water level decreases to core midplane (-75" on fuel zone instrumentation). a. P601 - RHR Section - B21-R615 b. P610 - RCIC Section - B21-R610 3.2 As RPV pressure decreases, open additional SRV's as required by the fol. lowing table: i TOTAL NUMBER OF RPV PRESSURE (psig) SRV's OPEN above 800 1 ] ] between 800 and 500 2 ]' between 500 and 350 3 4 between 350 and 250, between 250 and 175 5 ] between 175 and 125 6 ] below 125 7

GRAND GUIS NUCLEAR STATION EMERGENCY PROCEDURE Core Cooling TITLE: Without Injection NO. 05-S-01-EP-6 REV. A PAGE 2 of 2 C 3.3 When an injection or alternate injection subsystem is lined up for injection with at least one pump running, proceed to EP-5 (Rapid RPV ~ Depressurization). Gb l t l l l l l I I i i l

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GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE Core Cooling Without TITLE: Level Restoration NO. 05-S-01-EP-7 REV. A PAGE 1 of 2 1.0 PURPOSE The purpose of this procedure is to cool the reactor core with spray flow. 2.0 ENTRY CONDITIONS This procedure is entered from EP-4 (Level Restoration) when both: 2.1 RPV level cannot be restored and maintained above 0" (TAF) as read on the fuel zone instruaentation: 2.1.1 P601 - RHR Section - B21-R615 2.1.2 P601 - RCIC Section - B21-R610 and [)) 2.2 RPV pressure is less than 50psig (RCIC low steam pressure isolation setpoint). 3.0 OPERATOR ACTIONS 3.1 Open all ADS valves. 1, h CAUTION Observe NPSH requirements for the HPCS and LPCS pumps as indicated, when taking a suction on the Suppression Pool. I SUPPRESSION POOL PUMPS MAXIMUM TEMPERATURE MINIMbH LEVEL HPCS 212 F 14'6" LPCS 212 F 14'6" NOTE Cooldown rates greater than 100 F/hr may be required to accomplish this step. 3.2 If not all ADS valves can be opened, open other SRV's until 11 valves are open. ([] 3.3 Operate HPCS and LPCS systems with suction from the Suppression pool. [)) 3.4 When - HPCS and/or LPCS syster(s) are operating with suction from the Suppression Pool and RPV pressure is less than 310 psig Then - Terminate injection into the RPV from sources external to the primary containment. t

GRAND GUIS NUCLEAR STATION EMERGENCY PROCEDURE Core Cooling Without TIT 1E: Level Restoration No. 05-S-01-EP-7 REV. A PAGE 2 of 2 3.5 If RPV water level is restored to 0" (TAF) on the fuel zone instrumantation as read en Panel P601: 3.5.1 level recorder B21-R615 - RHR Section 3.5.2 level indicator B21-R610 - RCIC Section Then - proceed to EP-1 (Level Control) at paragraph 3.5. I i j 1 6 1 4 l i

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GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE PLANT OPERATIONS MANUAL Volume 5 05-S-01-EP-8 Section 1 Revision'B Date: EMERGENCY PROCEDURE ALTERNATE SHUTDOWN COOLING SAFETY RELATED Prepared: Date Reviewed: Date Technical Review Reviewed: Date - Operations Superintendent Reviewed: Date Nuclear Plant Quality Superintendent Approved: Date Assistant Plant Manager PSRC: Date List of Effective Pages: Page: Revision: 1-3 Rev. B Attachment I Rev. B-

l GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE Alternate Shutdown TITLE: Cooling NO. 05-S-01-EP-8 REV. B PAGE 1 of 3 1.0 PURPOSE The purpose of this procedure is to establish an alternate means for cooling down the RPV when the RHR Shutdown Cooling Mode is not available. 2.0 ENTRY CONDITIONS This procedure is entered when the following occur concurrently: f-] 2.1 RHR Shutdown Cooling Mode cannot be established and ((] 2.2 The RPV can no longer be cooled down by depressurization and Il 2.3 RPV temperature must Be' reduced and/or the RPV must be' maintained in a ~"" cold shutdown condition. 3.0 OPERATOR ACTIONS 3.1 Initiate Suppression Pool Cooling 3.2 Close the following if open: [-] 3.2.1 RPV head vents B21-F001 B21-F002 B21-F005 [-] 3.2.2 MSIV's ((] 3.2.3 Main Steam Line Drains ((] 3.3 Place the control switch for one SRV to OPEN. ((] 3.4 Slowly increase RPV water level (establish a flow path ~through the open SRV back to the Suppression Pool). ([) 3.5-Start one LPCS or LPCI pump taking a' suction from the Suppression Pool. [i 3.6 Slowly increase LPCS or LPCI flow to the maximum single pump flow for the pressure at which the RPV stabilizes. wvw w s s. ,s ,aw m, er-- w-+ -, gn- - - -, ---,mr

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GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE Alternate Snutdown TITLE: Cooling NO. 05-S-01-EP-8 REV. B PAGE 3 of 3 ((} 3.6.2 If RPV pressure does not stablize below As psig, open another SRV. [)) 3.7 Monitor SRV tailpipe temperature. 3.7.1 SRV tailpipe temperature will vary with RPV temperature if flow has been established through the open SRV. ((] 3.8 Monitor Suppression Pool level. 3.8.1 A constant Suppression Pool level will indicate that conditions are stable. 3.8.2 A decreasing Suppression Pool level will indicate an abnormal system lineup or that the SRV line has failed. NOTE A steady SRV tailpipe temperature with a varying RPV temperature accompanied by a decreasing Suppression Pool level is indicative of an SRV line break in the Drywell. 3.9 If the cooldown rate exceeds 100 F/hr, reduce LPCS or LPCI injection flowrate into the RPV until the cooldown rate decreases to less than. 100 F/hr if possible. 3.10 Control Suppression Pool temperature to maintain RPV water temperature above 70 F. ((] 3.11 Proceed to cold shutdown in accordance with IOI-sE kMG l l l l

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GRAN'D GULF NUCLEAR STATION EMERGENCY PROCEDURE PLANT OPERATIONS MA.WAL Volume 5 05-S-01-EP-9 Section 1 Revision B Date: EMERGENCY PROCEDURE RPV FLOODING SAFETY RELATED Prepared: Date Reviewed: Date Technical Review Reviewed: Date Operations Superintendent Reviewed: Date Nuclear Plant Quality Superintendent Approved: Date Assistant Plant Manager PSRC: Date List of Effective Pages: Page: Revision: 1-3 Rev. B Attachment I Rev. B f 1

GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: RPV Flooding NO. 05-S-01-EP-9 REV. B PAGE 1 of 3 1 1.0 PURPOSE The purpose of this procedure is to flood the RPV using all the available injection subsystems. 2.0 ENTRY CONDITIONS This procedure is entered from EP-5 (Rapid RPV Depressurization) if any of the following occur: 2.1 Temperature near the cold reference leg instrument vertical runs exceeds ((] the RPV saturation limit. 2.2 RP7 water level cannot be determined. 2.3 Containment pressure cannot be maintained below 15psig. 3.0 OPERATOR ACTIONS 3.1 If: - at least three SRV's are open, or - HPCS available for injection, or ((] - Condensate / Condensate Booster pumps available for injection Then: ["] - close MSIV's ["] - close Main Steam line drains ((] - isolate RCIC, RWCU, and RHR Steam Condensing ("] 3.2 Inject water.into the RPV with all of the following: ((] 3.2.1 HPCS ((] 3.2.2 Condensate Booster Pumps l [ --.[_j 3.2.3 LPCS l ("] 3.2.4 LPCI [")

3..l. 5 Condensate Pumps

["} 3.2.6 CRD ((] 3.3 If it can be determined that the RPV is filled, then continue in this l pre cedure at paragraph 3.6. [) 3.4 If RPV pressure stablizes within seven minutes (maximum acceptable core j uncovery time), perform the following: l l

o .s GRAND GULF NUCZ. EAR STATION EMERGENCY PROCEDURE TITLE: RPV Flooding No. 05-S-01-EP-9 REV. B PAGE 2 of 3 [ 3.3.1 Cycle oce SRV closed and back open ] 3.3.2 Determine the RPV pressure rise (referred to as single SRV pressure rise). ] 3.5 If RPV pressure does not stablize within seven minutes (maximum acceptable core uncovery time) or if the single SRV pressure rise is less than M psig (minimum single SRV pressure rise), inject water into the RPV with all of the following: [ 3.5.1 Standby Service Water crosstie a. Run more than one pump if possible b. Valves are operated from RHR section of 1H13-P601 C 3.5.2 Fire System Fill any tank that can be pumped to the RPV. a. C 3.5.3 ECCS flush connections from the Condensate Transfer system. [ 3.5.4 SLC (test tank) C 3.5.5 SLC (boron tank) O 3.6 If the Containment pressure exceeds 15psig, vent the primary containment in accordance with 04-1-01-M41-1 to reduce pressure below the primary l l containment pressure limit. [ 3.7 If the Containment pressure cannot be maintained below 15psig, initiate Containment Spray regardless of whether adequate core cooling is assured. C 3.8 Fill all RPV level instrumentation reference columns. 3.9 Continue injection until temperature near the cold reference leg vertical runs is below 212 F and RPV water level instrumentation is available. i l [ 3.10 If it can be determined that the RPV is filled, continue in this procedure at step 3.12.1. [ 3.11 Cycle one SRV closed and back open to determine the RPV' pressure rise (referred to as single SRV pressure rise). ] 3.12 If the single SRV pressure rise is at least 4 psig (minimum single SRV pressure rise) g if can be determined that the RPV is filled: -] 3.12.1-Terminate all injection into the RPV. l ] 3.12.2 Reduce RPV water level until RPV water level indication is restored. If RPV water level indication is not restored within seven a. minutes after injection into the RPV was terminated, return to paragraph 3.2 of this procedure. bobc.gda.A \\tGa.c. 1

GRAND GULF NUCLEAR STATION EMERG3*CY PROCEDURE TITLE: RPV Flooding NO. 05-S-01-EP-9 REV. B PAGE 3 of 3 b. If RPV water level indication is restored within seven minutes (maximum allowable core uncovery time), after injection into the RPV was terminated, proceed to EP-1 (Level Control) at paragraph 3.5. O G 6

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