ML20056F307
| ML20056F307 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/08/1993 |
| From: | Gordon D CENTERIOR ENERGY |
| To: | |
| References | |
| HS-EP-02820, HS-EP-2820, NUDOCS 9308260351 | |
| Download: ML20056F307 (15) | |
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Page 1 of 12 O i Davis-Besse Nuclear Power Station EMERGENCY PLAN OFF NORMAL OCCURRENCE PROCEDURE HS-EP-02820 (Supersedes R2) EARTHOUAKE REVISION 3 1 0 ( , Prepared by: [f e, a
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7ii<'7 i3 r; 1 Date Sponsor: [g#fd,/4gn, 7// 5/f_3 Manager - Erdergency Preparedness 'Date
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T , > b b/d/ ~?C k Director - Technical /5ervice's ' Date' 4_ Approved by: b 94 Date
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AUG 2 01993 Effective Date: Procedure Classification: X Safety Related Quality Related Non-Ouality Related O
i EARTHOUAKE 2 HS-EP-02820 R3 LIST OF EFFECTIVE PAGES I I I I I I I I I Change No. l l Fage l Change No. l l Page Change No. l l Page i I I I I I I I I 1 - 1 I ! I I I : I I I I I I I 2 - 1 I i I I , I ; I I I I I I I 3 I 1 I i i I I I I I I I I i I - i 4 - I i i l 1 r I I I I I I I - 5 I 1 I I I I 1 i i l l I I I I 6 ! 1 I I I I I I I I I I I 7 - 1 I I I I
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.- EARTHOUAKE 3 HS-EP-02820 R3 l
TABLE OF CONTENTS
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Page ) 1.0 PURPOSE 4 i
2.0 REFERENCES
4 j 3.0 DEFINITIONS 4 ! 4.0 RESPONSIBILITIES 5 , 5.0 INITIATING CONDITIONS 5 i i 6.0 PROCEDURE 6 f 6.1 Immediate Operator Action 6 l l 6.2 Supplementary Actions 6 l t 7.0 FINAL CONDITIONS 10 1 8.0 RECORDS 11 , t COMMITMENTS 12 l i t I i i i i 4 i
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4 HS-EP-02820 EARTHQUAKE R3 1.0 PURPOSE lf This procedure describes the actions to be taken in the event of a seismic i event.
2.0 REFERENCES
2.1 Developmental l 2.1.1 10 CFR 100, Appendix A, Seismic and Geologic Siting Criteria For Nuclear Power Plants 2.1.2 Davis-Besse Nuclear Power Station Emergency Plan 2.1.3 USAR 9.2.1.2 and 9.2.5.1, Loss of Ultimate Heat Sink 2.2 Implementation 2.2.1 DB-0P-00002, Operations Section Event / Incident Notifications and Actions 2.2.2 DB-OP-02000, RPS, SFAS. SFRCS Trip or SG Tu'oc Rupture 2.2.3 DB-0P-02504, Rapid Shutdown 2.2.4 DB-0P-02511, Loss of Service Vater Pumps / System 2.2.5 DB-0P-06414, Seismic Monitoring System 2.2.6 DB-SC-03070, Emergency Diesel Generator 1 Monthly Test 2.2.7 DB-SC-03071, Emergency Diesel Generator 2 Monthly Test 2.2.8 ST-5013.04 (DB-SC-03272), Control Rod Exercising Test 2.2.9 DB-SP-03356, RCP Seal Leakage (Monthly) 2.2.10 HS-EP-01500, Emergency Classification 3.0 DEFINITIONS 3.1 SAFE SHUTDOVN EARTHOUAKE (SSE) - The SSE as defined in 10 CFR 100 Appendix A, is that earthquake which is based upon an evaluation of the maximum earthquake potential considering the regional and local geology and seismology and specific characteristics of local subsur-face material. It is that earthquake which produces the maximum vibratory ground motion for which certain structures, systems, and components are designed to remain functional. These structures, sys-tems, and components are those necessary to assure: 3.1.1 The integrity of the reactor coolant pressure boundary 3.1.2 The capability to shut down the reactor and maintain it in saie shutdown condition, or l l l
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EARTHOUAKE 5 HS-EP-02820 i l R3 l 3.1.3 The capability to prevent or mitigate the consequences of , accidents that could result in potential offsite exposures. i 3.2 OPERATING BASIS EARTH 00AKE (OBE) - The OBE as defined in 10 CFR 100, Appendix A, is that earthquake which, considering the regional and local geology and seismology and specific characteristics of local subsurface material, could reasonably be expected to affect the plant -{ site during the operating life of the plant; it is that earthquake j vhich produces the vibratory growth motion for which those features of l the nuclear power plant necessary for continued operation vithout undue risk to the health and safety of the public are designed to , remain functional. , i 4.0 RESPONSIBILITIES i The Shift Supervisor shall be responsible for directing the operating shift j in the utilization of this procedure. 5.0 INITIATING CONDITIONS The following conditions shall initiate the use of this procedure: , 5.1 The Strong Motion Recording System and Seismic Monitoring Equipment are actuated and record a seismic disturbance. 5.2 As directed by Station management. O 4 [ i, h h s
EARTHOUAKE 6 HS-EP-02820 R3 6.0 PROCEDURE 6.1 Immediate Operator Action 6.1.1 The Shift Supervisor shall:
- a. Order all fuel handling operations suspended.
- b. If fuel is being supported from a crane or a bridge, then order that it be lowered into a secure location.
- c. Evaluate control rod position, reactor power, and other pertinent variables to verify that no change has occurred in core reactivity.
6.2 Supplementary Action 6.2.1 The Control Room Operators shall:
- a. Monitor the control panels to determine the effect of the earthquake, if any, on instrumentation, controls or station operations.
- b. Notify the Shift Supervisor of any abnormal indica-tions.
- c. Verify that there is no abnormal sump pump operation and that tank levels are stable.
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- d. Verify the operability of systems or components not running at the time of the earthquake before relying upon them,
- e. If the unit has been shutdown by automatic protection systems, then place the unit in a safe shutdown condi-tion.
6.2.2 The Shift Supervisor shall:
- a. If the unit has not been shutdown, and no apparent dam-age has occurred, then maintain the unit in its opera-ting status.
- b. Assign personnel to verify the authenticity of the Seismic / Instrumentation alarm.
If the seismic monitoring system is inoperable, then contact the Engineering Department for further guidance.
EARTHOUAKE 7 HS-EP-02820 R3
) c. Utilize HS-EP-01500, Emergency Classification, to determine proper emergency classification and take actions accordingly.
- d. If OBE or SSE levels have not been exceeded, then analyze the magnitude of the earthquake utilizing DB-0P-06414, Seismic Monitoring System. Assistance in analyzing the graphic record of the event may be required from the Engineering Department, or from other knowledgeable personnel responding to the Emergency Plan activation.
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- e. Order an inspection of the station looking for 1eaking fluids deformed structures, particularly those spanning seismic joints broken gauge glasses any physical damage.
Particular attention shall be directed to the following systems:
- 1. Emergency Core Cooling Systems, including the Borated Vater Storage Tank
- 2. Nuclear Steam Supply System (f
- 3. Auxiliary Feedvater
- 4. Component Cooling Vater
- 5. Service Water
- DB-OP-02511, Loss of Service Vater Pumps /
System, contains a Service Vater Non-Seismic Line Rupture section
- 6. Makeup and Purification Systems
- 7. Boric Acid Storage Tanks and associated piping
- 8. Radvaste Systems
- 9. Spent Fuel Pool and Spent Fuel Pool Cooling System
- 10. New Fuel Storage
- 11. Containment Integrity
- 12. Intake Canal and Intake Forebay
EARTHOUAKE 8 HS-EP-02820 R3
- f. Verify the Aux Feed Pump turbines case drains and drip leg drains have not been blocked by the Seismic Event. y If the Aux Feed Pump turbines case drains and drip leg drains can not be verified clear, then perform either of the following two steps within two hours after receiving the seismic alarm:
- 1. Start the Aux Feed Pump Turbines in accordance with DB-0P-06233, Aux Feedvater System Procedure
- 2. Drain the Aux Feed Pump turbine case drains and drip legs every two hours.
- g. If the Seismic event results in a break of the Cooling Tower makeup line, then perform the following:
- 1. Verify Service Water returns lined up to the Forebay or Intake Structure.
- 2. Verify Service Vater returns to the Cooling Tower isolated within 3 hours. Refer to DB-0P-02511, Loss of Service Water Pumps / System.
- h. If the seismic event results in loss of the supply pipe from Lake Erie to the intake canal (collapse of the dike) then perform the following:
- 1. Perform a rapid shutdown of the reactor, refer to DB-0P-02504, Rapid Shutdown.
- 2. Close CT 840, Cooling Tower Blowdown Valve.
- 3. Verify service water returns are aligned to the intake forebay or the intake structure.
- 4. If the dilution pump is running in the dilution mode, shutdown the dilution pump.
- 5. If forebay vater level decreases to 564' IGLD,
- a. Trip the reactor.
- 5. Initiate AFV flow and isolation using HIS 6403 and HIS 6404.
- c. Reduce SV loads as directed by the Shift Supervisor.
- d. Begin a cooldown to Hot Shutdown using the Aux Feedvater pumps using CST's if available.
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4 EARTHOUAKE 9 HS-EP-02820 R3
- e. Maintain cooling from AFV until directed by the Emergency Director to transfer to the Decay Heat Removal System. This decision vill be based on available forebay cooling.
- 1. Notify the Plant Manager and/or the Operations Superintendent of the results of the physical inspection of the Station.
CAUTION 6.2.2.J. A plant shutdown following an earthquake shall pro-ceed slowly enough to allov evaluation of the operation of systems used to support the shutdown.
- j. A carefully controlled shutdown of the unit shall be initiated whenever the following conditions exist:
Valid OBE or SSE Alarm, with ground motion felt S
- 1. An Engineering Department's evaluation of the l spectrum analysis of the earthquake utilizing O, DB-OP-06414, Seismic Monitoring System, requires a shutdown EE
- 2. A significant radiological release exists due to the event 4
SE
- 3. System or equipment damage prevents further plant operation SE
- 4. Technical Specifications require a plant shutdown due to inoperability of systems as a result of the earthquake.
6.2.3 operating personnel shall perform the following tests as deemed necessary by the Shift Supervisor:
- a. DB-SP-03356, RCP Seal Leakage (Monthly).
- b. DB-SC-03272, Control Rod Exercising Test.
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10 HS-EP-02820 EARTHOUAKE R3
- c. DB-SC-03070, Emergency Diesel Generator 1, Monthly Test.
- d. DB-SC-03071, Emergency Diesel Generator 2, Monthly Test.
6.2.4 The Plant Manager shall:
- a. Notify the on-call Vice President Nuclear of the earthquake.
- b. Notify the NRC in accordance with DB-0P-00002, Operations Section Event / Incident Notifications and g I
Actions.
- c. Vith the assistance of the plant operating shift and staff personnel, convene the SRB to evaluate the reports, records, and recordings for any possible earthquake damage to equipment and structures. Deter-mine if any of the engineered safety features have been damaged.
- d. If a seismic event inhibits the use of Lake Erie as a water source, the Engineering Department shall be notified so that temporary pumping the intake forebay can be established before t. end of the 30-day stored water cooling period.
- e. If a seismic event greater than OBE has occurred, con-duct an unscheduled inservice inspection of the steam generators during the subsequent shutdown in accordance with Technical Specification 4.4.5.3.c.2. ,
l f. Order an inspection of hydraulic and mechan. cal i snubbers in accordance with Technical Specification 4.7.7.1.e.
- g. Order restoration of the seismic monitoring instrumen-tation in accordance with Technical Specification 4.3.3.3.2.
7.0 FINAL CONDITIONS The plant is in a stable condition and it has been determined that no classifiable emergency has occurred. I t 9
i 4 .j w EARTHOUAKE 11 HS-EP-02820 R3 8.0 RECORDS 8.1 The following quality' assurance records are completed by this procedure and shall be listed on the Nuclear Records List, captured, and submitted to Nuclear Records Management in accordance with , NG-PS-00106: j 8.1.1 None j 8.2 The following non-quality assurance records are completed by this procedure and may be captured and submitted to Nuclear Records Management, in accordance with NG-PS-00106: 8.1.2 None [ l
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i EARTHOUAKE 12 HS-EP-02820 R3 COMMITMENTS Section Reference Comments 6.2.4.e. PCA0R 86-0519 OTSG inspection 6.2.4.g. Tech. Spec. Verification Seismic monitoring instruction Program Entire Procedure TERMS 0 00070 Acts of nature procedure 6.2.2.e.5 Safety Evaluation 88-0189 Service water concerns in the event of an earthquake 6.2.2.g USAR Section 9.2.1.1 Break in non-seismic line to cooling tower 6.2.2.h USAR Section 9.2.5.1 Loss of Intake Canal O, em O END}}