ML19345F036
| ML19345F036 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/30/1981 |
| From: | Dale L MISSISSIPPI POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AECM-81-56, NUDOCS 8102060563 | |
| Download: ML19345F036 (11) | |
Text
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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B OX 164 0, J AC K S O N, MIS SIS SIPPI 3 9 2 0 5 January 30, 1981 NUCLEAR PRODUCTION DEPART %8ENT U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 Attention:
Mr. Harold R. Denton
Dear Sir:
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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 ATWS Event Procedure and Revised RPV Flooding Procedure AECM-81/56 In accordance with our letter to you, AECM-81/44, dated January 27, 1981, providing the Grand Gulf Nuclear Station (GGNS) emergency procedures (EP-1 through EP-9), we are submitting the off-normal event procedure pertaining to the Anticipated Transient Without Scram (ATWS) event. Attachment I to ATWS event procedure will be provided at a later date.
Recent changes to the BWR Emergency Procedure Guidelines have necessitated certain revisions to the GGNS procedure for RPV Flooding (EP-9) submitted in the above referenced MP&L letter. Revision C to EP-9 is attached. Attachment I (Revision C) to EP-9 will be provided at a later date.
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Yours ly, l
L. F. Dale Nuclear Project Manager JGC/JDR/LFD:Im
Attachment:
1.
ATWS Event Procedure, Revision 0 2.
RPV Flooding Emergency Procedure, Revision C l
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(See Next Page)
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Member Middle South Utilities System
MISSISSIPPI POWER & LIGHT COMPANY U.S. Nuclear Regulatory Commission AECM-81/56 Office of Nuclear Reactor 3egulation Page 2 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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PLANT OPERATIONS MANUAL Volume 5 05-1-02-I-7 Section 02 Revision 0 Date:
OFF-NORMAL EVENT PROCEDURE ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS)
SAFETY RELATED Prepared:
Date Reviewed:
Date Nuclear Plant Quality Superintendent Reviewed:
Date Technical Review Approved:
Date Operations Superintendent Concurrence':
Date Assistant Plant Manager List of Effective Pages:
Page:
Revision:
1-3 Rev. O
CRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE Anticipated Transient TITLE: Without Scram (ATWS)
NO. 05-1-02-I-7 REV. O PAGE 1 of 3 1.0 PURPOSE / DISCUS 8 ION 1.1 The purpose of this procedure is to provide the operator with recognition criteria such that the ATWS condition can be promptly identified. The procedure also deteribes the actions to be taken in the event of an ATWS that will bring the reactor to the full shutdown condition and mitigate the consequences of the transient.
1.2 The consequences of an ATWS may place the plant in a condition where one or more of the Emergency Procedures should be used in order to return the plant to a stable condition.
In addition, an ATVS constitutes an alert within the scope of the Emergency Plan. The actions described in EPP-3 Alert shall be carried out coincident with this procedure.
1.3 Prompt identification of the ATWS condition in conjunction with appropriate immediate operator action will minimize the effects of the transient. Another mitigating action will be the tripping of the Reactor Recirculation Pump at 1125 psig reactor pressure or -51 inches reactor water level.
If repeated atterp+.s to insert all control rods, as described below, have failed the operator will initiate the SCC system which will bring the reactor to a cold shutdown condition.
2.0 SYMPTOMS 2.1 The following symptoms would indicate a scram signal is present in th RPS system, but that a full scram has not occurred:
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2.1.1 The full core display rod position indicating lights show only partial or incomplete rod insertion following the receipt of one or more of the reactor scram annunciator alarms.
2.1.2 The APRM's indicate only a partial or incomplete downpower transient following the receipt of one or more of the reactor scram annunciator alarms.
2.1.3 The CRD DISCH VOL HIGH WrR LEVEL TRIP annunciator does not alarm following a scram caused by another signal.
2.1.4 The SCRAM PILOT VLV AIR HDR PRESS HIGH-LOW ALARM annunciator does not alarm following a scram.
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2.2 The following symptoms would indicate a scram signal was not received or that the RPS system has failed to function and that a Limiting System Setting (LSSS) has been exceeded:
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2.2.1 Any of the following conditions are observed, either by annunciation or by actual local or remote indication, and are not accompanied by reactor scram indications (i.e., power level decrease, full rod insertion, annunciators):
a.
Scram discharge volume high water level (54 gallons)
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b.
Main steam line high radiation (3 x normal)
GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE Anticipated Transient TITLE: Without Scram (ATWS)
NO. 05-1-02-I-7 REV. O PAGE 2 of 3
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c.
MSIV closure
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d.
Reactor high pressure (1074 psig) (possible accompanied by safety / relief valve actuation) e.
Reactor low water level (10 inches) f.
Reactor high water level (52 inches) (possibly accompanied by main and/or RFP turbine trips) g.
Turbine stop valve and/or a control valve closure.
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(Accompanied by possible safety / relief valve actuation) h.
Neutron monitoring system trip
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Drywell high pressure (1.73 psig) 3.0 AUTOMATIC ACTIONS 3.1 The Reactor Recirculation Pumps shift to slow speed on an RPT signal and will trip on vessel low level (-51 inches) or high pressure (1125 psig).
4.0 IMMEDIATE OPERATOR ACTIONS 4.1 Inform Shift Supervisor / Shift Superintendent of plant conditions.
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4.2 If an LSSS has been exceeded and no scram signal has been generated perform the following steps in order listed:
a.
Manually scram the reactor, b.
Trip both Reactor Recirculation Pumps if they are not already tripped.
c.
Place the Reactor Mode switch in toe SHUTDOWN position.
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d.
Continue in accordance with the instructions in ONEP 05-1-02-I-l Reactor Scram.
e.
If an RTPS scram is still not initiated open the following breakers:
Power Supply Panel Breaker RPS Channel A IC71-P001 52-1C71102 RPS Channel C 1C71-P001 52-1C71108 RPS Channel B IC71-P002 52-1C71202 RPS Channel D 1C71-P002 52-IC71208
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f.
If an RPS scram is still not initiated perform the following:
(1) Initiate Standby Liquid Control (SLC)
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(2) Verify Reactor Water Cleanup (RWCU) isolates e
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GRAND GULF NUCLEAR STATION OFF-NORMAL EVENT PROCEDURE Anticipated Transient TITLE: Without Scram (ATWS)
NO. 05-1-02-I-7 REV. O PAGE 3 of 3 g.
Monitor reactor power indication and proceed to shutdown the plant in accordance with the integrated operating instruction.
4.3 If a scram has occurred, but all rods are not fully inserted perform the following:
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a.
Carry out the actions of ONEP 05-1-02-I-1 Reactor Scram or ONEP 05-1-02-I-2 Reactor Scram with Group I Isolation, b.
Attempt to insert all control rods as follows:
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(1) Reset the RPS system scram.
(2) Vent and drain the scram discharge volume for approximately 5 minutes.
(3) Manually scram the reactor.
c.
If rod motion is accomplished by performance of the above steps repeat them several more times until all rods are fully inserted.
d.
If rod motion is not accomplished by the actions of step b OR if all rods are not fully inserted after 20 minutes of the vent, drain and scram operation then perform the following:
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(1)
Initiate SLC
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(2) Verify the RWCU system isolates (3) Monitor reactor power indication and proceed to shutdown the plant in accordance with the integrated operating instructions.
4.4 If the safety / relief valves are actuating as a result of a reactor high pressure condition, place the RHR system in the suppression pool cooling mode. Operate the system to maximize suppression pool cooling.
5.0 SUBSEQUENT OPERATION ACTIONS 5.1 Ensure all of the sodium pentaborate solution is injected into the core-prior to serving the SLC system.
5.2 Continue to carry out the actions of the scram ONEP.
5.3 Continue to carry out the actions of EPP-3, alert.
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5.4 As soon as repairs can be made insert all control rods.
5.5 If SLC has initiated, refer to the normal shutdown integrated operating procedure for instructions on bringing the plant to the cold shutdown condition.
- GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE PLANT OPERATIONS MANUAL Volume 5 05-S-01-EP-9 Section 1 Revision C 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 i
List of Effective Pages:
Page:
Revision:
1-4 Rev. C Y
l Attachment I Rev. C
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GRAND GUIS NUCLEAR STATION EMERGENCY PROCEDURE TITLE: RPV Flooding NO. 05-S-01-EP-9 REV. C PAGE 1 of 4 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:
C 2.1 Temperature near the cold reference leg instrument vertical runs exceeds the RPV saturation limit.
O 2.2 Rev water level cannot be determined.
O 2.3 Containment pressure caonot he maintained heiow 13psig.
3.0 OPERATOR ACTIONS 3.1 If:
- at least three SRV's are open, or
- HPCS available for injection, or O
- condensate / condensate saaster Pu Ps avaitadte for injection Then:
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- close MSIv s
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- close Main Steam line drains
- isolate RCIC, RWCU, and RHR Steam Condensing O
3.2 Inject water into the RPV with all of the following:
O 3.2.1 APCS O
3.2.2 Condensate sooster Pumps O
3.2.3 tPCS 3.2.4 LPCI 3.2.5 Condensate Pumps 3.2.6 CRD C 3.3 If RPV water level is increasing, then continue in this procedure at paragraph 3.8.
3.4 If RPV pressure is stable, perform the following:
GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE
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TITLE: RPV Flooding NO. 05-S-01-EP-9 REV. C PAGE 2 of 4 3.3.1 Cycle one SRV closed and back open 3.3.2 Determine the RPV pressure rise (referred to as single SRV pressure rise).
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3.5 If the single SRV pressure rise exceeds the minimum single SRV pressure rise, continue in this procedure at paragraph 3.8.
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3.6 Inject water into tN
?V with all of the following:
l 3.6.1 Standby Se Water crosstie a.
Run mors n one pump if possible I
b.
Valves are operated from RHR section of 1H13-P601 0
3.6.2 Fire System a.
Fill any tank that can be pumped to the RPV.
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3.6.3 ECCS flush connections from the Condensate Transfer system.
3.6.4 SLC (test tank)
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CAUTION l
Defeating isolation interlocks may be required to accomplish this step.
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GRAND GULF NUCLEAR STATION EMERGENCY PROCEDURE TITLE: RPV Flooding NO. 05-S-01-EP-9 REV. C PAGE 3 of 4 3.7 If the Containment pressure exceeds 15psig, vent the primary containment in accordance with 04-1-01-M41-1 to reduce pressure below the primary containment pressure limit.
C 3.8 If the Containment pressure cannot be maintained below 15psig, initiate Containment Spray regardless of whether adequate core cooling is assured.
3.9 Fill all RPV level instrumentation reference columns.
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3.10 Continue injection until temperature near the c:Id reference leg vertical runs is below 212 F and RPV water level instrumentation is available.
3.11 If it can be determined that the RPV is filled, continue in this procedure at step 3.14.
3.12 Cycle one SRV closed and back open to determine the RPV pressure rise (referred to as single SRV pressure rise).
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iante sav pressure rise, return to paragraph 3.11.
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3.15 If RPV water level indication is not restored within the maximum acceptable core uncovery time as determined by the following figure, return to paragraph 3.2.
GRAND GULF NUCLEAR STATION EMERGENCY PROCEDUaE TITLE: RPV Flooding NO. 05-S-01-EP-9 REV. C PAGE 4 of 4 NOTE Core uncovery time as used in this figure commences when RPV injection is terminated.
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w e. k as_ h co_ wma 3.16 If RPV water level indication is_ restored within the maximum acceptable core uncovery time as determined in paragraph 3.15, proceed to EP-1 (Level Control) at paragraph 3.5.
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