ML20086J786
| ML20086J786 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/09/1983 |
| From: | Specter S ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17255A623 | List: |
| References | |
| PROC-831109, NUDOCS 8401250100 | |
| Download: ML20086J786 (12) | |
Text
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f GINNA STATION UNIT #1 COMPLETED DATE :-
ROCHESTER GAS AND ELECTRIC CORPORATIOu TIME :-
GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO.
SC-5 REV. NO.
7 EARTHQUAKE EMERGENCY PLAN TECHNICAL REVIST PORC REVIDI DATE lD'l h-k h
QC REVIEti PLANT SUPERINTENDENT OCT 181993 EFFECTIVE DATE QA k NON-QA CATEGORY 1.0 REVIE'iED BY:
THIS PROCEDURE CONTAINS 2
PAGES O
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SC-5,:1 SC-5 EARTHQUAKE EMERGENCY PLAN
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1.0 PURPOSE
1.1 To provide instructions for response to an earthquake tremor l
felt at the plant.
l 1.' 2 To provide instructions for appropriate notification to authcrities of the above in accordance with pre-established classifications.
2.O
REFERENCES:
2.1 NUREG 0654, Appendix I,
Emergency Action level Guidelines for Nuclear Power Plants.
3.0 INSTRUCTIONS
3.1 In the event an unexplained tremor or earthquake is experienced, evaluate and classify the condition per SC-100 Ginna Station Event Evaluation and Classification and implement applicable emergency procedure.
3.2 The Shift Supervisor shall dispatch an Auxiliary Operator to the Intermediate Building sub-basement to check the response 4
of the accelerograph.
3.2.1 Registration of a tremor greater than 0.01g is indicated by a red target on the action indicator at the bottom o f 1-the case.
3.3 If the above indication occurs perform the following:
3.3.1 The lA or 1B diesel generator shall be olaced in service using procedure T-27.4, Diesel Generator Operation.
3.3.2 The Shift Supervisor shall notify the Plant Superintendent and shall requast an I&C Technician to remove the film from the accelerograph.
3.3.3 The operators shall tour all plant areas and shall check i l all plant instrumentation, piping, equipment and structures j
with particular emphasis on the following:
3.3.3.1 Check turbine rotor displacement and eccentricity.
Verify turbine vibrations are within allowable limits.
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3.3.3.2 Check control rods for proper position and operability by performing the Periodic Test PT-1, Rod Control System.
NOTE:
Omit this step if reactor trip occurred.
i
-l 3.3.3.3 Check the radiation monitoring system panel for any increases in area radiation levels or process system activity levels.
3.3.3.4 Check for any increase in the makeup rate to the. primary system.
C 3.3.3.5 Check for an increase in the f requency of containment samp A pump actuation.
3.3.3.6 Chack the plant outside the containment, including the screen-house, turbine building structures and piping, the intermediate building, and the auxiliary building and all containment penetrations.
3.3.3.7 Check the letdown ahd charging lines that are accessible in the auxiliary building for leaks.
Inspect the component cooling system and spent fuel pit system.
3.3.3.8 Monitor auxiliary building sump pump actuations for increased frequency and monitor the level rise in the waste holdup tank.
I 3.3.3.9 The Shift Supervisor ~shall initiate a containment entry and inspection if leakage inside' containment is indicated.
The reactor coolant system, the main steam and feedwater systems, and other containc.ent piping and associated oenetrations shall be examined.
3.3.4 The accelerograph film shall be sent to the company photo lab for processing.
3.3.5 A thorough radiation survey shall be performed by the Health Physics Department of all plant areas.
3.3.6 If any damage to the primary system or safeguards systems is noted or the accelerograph indicates an earthquake of greater than.08G at the plant site, initiate unit shutdown.
3.3.7 If it is determined that tha reacter cannot be maintained in the hot shutdown condition, the reactor shall be placed in cold shutdown.
3.4 The Plant Operations Review Committee shall meet and decide on any further actions.
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o GINNA STATION pNIT #1 COM Ft.ETE D DATE :-
TIME :.
d ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION O
CONTROLLED COPY NUMBER C PROCEDURE NO.
SC-5 REV. NO.
TECHNICAL REVIEW PORC REVIEst DATE I I 6.3 hE l QC RPMIEW PLANT SUPER ()lTENDENT Nov s 1983 EFFECTIVE DATE QA h NON-QA CATEGORY 1.0 REVIEWED BY:
THIS PROCEDURE CONTAINS 3
PAGES l
SC-5:1 SC-5 EARTHQUAKE EMERGENCY PLAN
~
1.0 PURPOSE
1.1 To provide instructions for response to an earthquake tremor felt at the plant.
1.2 To provide instructions for appropriate notification to authorities of the above in accordance with pre-established classifications.
2.0 REFERENCES
2.1 NUREG 0654, Appendix I,
Emergency Action level Guidelines for Nuclear Power Plants.
3.0 INSTRUCTIONS
3.1 In the event an unexplained tremor or earthquake is experienced, evaluate and classify the condition per SC-100 Ginna Station Event Evaluation and Classification and implement applicable emergency procedure.
3.2 The Shift Supervisor shall dispatch an Auxiliary Operator to the Intermediate BLailding sub-basement to check the response of the accelerograph.
3.2.1 Registration of a tremor greater than 0.01.g is indicated by a red target on the action indicator at the bottom of the case.
3.3 If the above indication occurs perform the following:
3.3.1 The 1A or 18 diesel generator shall be placed in service using procedure T-27.4, Diesel Generator Operation.
3.3.2 The Shift Supervisor shall notify the Plant Superintendent and shall request an IEC Technician to remove the film from the accelerograph.
3.3.3 The operators shall tour all plant areas and shall check all plant instrumentation, piping, equipment and structures with particular emphasis on the following:
3.3.3.1 Check turbine rotor displacement and eccentricity.
Verify turbine vibrations are within allowable limits.
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SC-5:2 3.3.3.2 Check control rods for proper position and operability by performing the Periodic Test PT-1, Rod Control System.
NOTE:
Omit; this step if reactor trip occurred.
3.3.3.3 Check the radiation monitoring system panel for any increases in area radiation levels or process system activity levels.
3.3.3.4 Check for any increase in the makeup rate to the primary system.
3.3.3.5 Check for an increase in the frequency of containment eump A pump actuation.
3.3.3.6 Check the plant outside the containment, including the screen-house, turbine building structures and piping, the intermediate building, and the auxiliary building and all containment penetrations.
3.3.3.7 Check the letdown and charging lines that are accessible in the auxiliary building for leaks.
Inspect the component cooling system and spent fuel pit system.
3.3.3.8 Monitor auxiliary building sump pump actuations for increased frequency and monitor the level rise in the waste holdup tank.
3.3.3.9 The Shift Supervisor shall initiate a containment entry and inspection if leakage inside containment is indicated.
The reactor coolant system, the main steam and feedwater systems, and other containment piping and associated penetrations shall be examined.
3.3.4 The accelerograpn film shall be sent to the company photo lab for processing.
3.3.5 A thorough radiation survey shall be performed by the Health Physics Department of all plant areas.
3.3.6 If any damage to the primary system or safeguards systems is noted or the accelerograph indicates an earthquake of greater than.08G at the plant site, initiate unit shutdown.
3.3.7 If it is determined that the reactor cannot be maintained in the hot shutdown condition, the reactor shall be placed in cold shutdown.
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SC-5:3 3.4 If an earthquake is reported by radio or other news media to be equal to or greater than 6 on the Richter scale within 30 miles or 7 on the Richter scale within 90 miles of the plant, an inspection of the steaam generator tubes per QA
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Manual Appendix B shall be performed..
3.5 The plant Operations Review Committee shall meet and decide on any further actions.
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GINNA STATION
, UNIT 41 COMPLETr0 ROCHESTER GAS AND ELECTRIC CORPORATION DATE :-
GINNA STATION TIME :-
CONTROLLED COPY NUMBER PROCEDURE NO.
SC-100 REV. NO.
3 t
GINNA STATION EVENT EVALUATION AND CLASSIFICATION TECHNICAL REVIEi PORC REVIE;l DATE
[O-/M-8b
\\
QC REVIEi PLAtfT SUPERINTENDENT OCT 181983 EFFECTIVE DATE GA V NON-QA CATEGORY 1.0 REVICIED BY:
THIS PROCEDURE CONTAINS 4
PAGES A
=
s SC-100:1 SC-100 GIMNA STATION EVENT EVALUATION AND CLASSIFICATION
1.0 PURPOSE
4 1.1 The purpose of this procedure is to provide guidance to personnel in evaluating situations which may require activation of the SC-1 Emergency Plan and direct them to appropriate implemer. ting procedures.
Prompt recognition and classification is necessary to ensure the timely activation of' support functions and notification of OFF-SITE organizations.
2.0 REFERENCES
2.1 10CFR50 Appendix E 2.2 NUREG-0654 2.3 NUREG-0696 2.4 SC-1
3.0 INSTRUCTIONS
3.1 In the event of an abnormal condition the Control Room Personnel will:
3.1.1 perform the immediate responses defined in the appropriate plant procedures.
3.1.2 Classify the situation using the guidelines of Appendix I.
3.1.3 Implement applicable Emergency Plan proceduros based on Appendix I guidelines.
3.1.3.1 UNUSUAL EVENT SC-201 3.1.3.2 ALERT SC-202 3.1.3.3 SITE EMERGENCY SC-203 3.1.3.4 GENERAL EMERGENCY SC-204 A
1.PPFNDIX I (AJIDELINES SITE IMEMiNCY GENERAL HiEMeaCY
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AIEJR PARAMETFR (D 'IO SC-202 PARAMETERS (D '10 PARAMETER (D 'IO INITIATING UNUSUAL FNDR PARAMETER i
00mITION 00 'IO SC-201 SC-203 SC-204 REACIOR
- a. Safety Injection Initiated ard
- a. 0hexplained charging pump flow
- a. Depressurization i
C00 LAIR flow on FI-924 or FI-925
> 50 gpa, FI-128 with accumulator IEAKAGE
- b. Unidentified leakage > 1 gpn
- b. ?.afety injection flow > 50 gpn discharge.
t
- c. Identified leakage > 10 gpn M-924,925
- d. S/G 1eakage >.1 gpn LI-934, 938 l
R-15/19 alarm PR-420
- e. Pipe, vessel, or valve body leak..
FUEL
- a. Sampling indicates coolant
- a. (bolant activity I 131)
- a. 'Ibchnical staff CIADDING activity > 84/E 300 uCi/cc evaluation of DEGRADA-
- b. R-9 increase of 500 mr/hr
- b. R-9 increase of 4000 mr/hr reactor conditions 1
TICN in 30 minutes.
or reading 10,000 mr/hr.
indicates a c.
Fuel damage accident with degraded core i
release of activity.
with loss of j
cooling.
i SECONDARY
- a. Rapid depressurization of
- a. Steam line break with Irimary
- a. Steam line break
- a. Maltiple S/G SYSTEM Steam or Feedwater system to secondary leakage greater with primary t.;
Tube rupture indicated on PT-468, 469 or than T.S.
secondary leakage with unisolaole 484
- b. Steam Generator Tube leakage
> 50 qpn ard R-9 secondary
> 100 gpn, flow > 120 qpa en
> 500 mr/hr.
relief valve FI-128, with Icos of offsite
- b. S/G Tube leak failed cpen.
power.
greater than 1000 qpm.
00 TRAIN-
- a. Ioss of containment integrity,
- a. IR/hr an containment area a.10,000 IVhr on
- a. Ioss of 2 of 3 1
MDR as indicated by report of mnitors, R-2 or R-7, except containment area fission barriers SYSTEM malfunctioning valves, hatches during flux napping.
manitor.
with p>tential or other equipnent.
- b. Containment noni-loss cf third:
tor readirn 100
- 1. Fuel Claddirg j
R/hr with contain-
- 2. Reactor cool-ment Eressure > 28 ant System psig.
- 3. Containment
~EFFI1JDR
- a. Exceeding Tech Spec. limit for
- a. Greater than 10 times Tech.
- a. Offsite teams
- a. Offsite Strvey RELEASE liquid or gaseous release.
Spec limit for liquid or report > 50 mR/hr Teams report (TS-3.9) gaseous release.
whole body for 1/2 1 IVhr diole R-11 > 5.0 x 104 cpn.
- b. R-11 > 5.0 x 105 cpm.
hr. or 2 hr.
body or 2 hr R-12 > 4.0 x 104 cpn.
R-12 > 4.0 x 105 cpn..
thyroid dose >
thyroid dose 8
R-13 > 2.0 x 104 R-13 > 2.0 x 105 500 mrem
> 5 rem.
J. 6 cpn.
cpm.
R-14 > 1.1 x 104 R-14 > 1.1 x 105
- b. R-11,12,13,14 8
cpu.
can.
- b. R-18 > 6.0 x 1(P cpn.
R-18 >}.0 x 106 cpn.
18 off scale.
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APPEIGIK I CUIDE*.IFj"l l
SITE DERGENCY CENERAL BERGENCY f
INITIATING UNUSUAL EVENT PARAMETER AI.ERT PARAMETEP CD 10 SC-202 PARAMETERS GD PARAMETER G) TO CONDITION CO 10 SC-201 TO SC-203 SC-204 LOSS OF
- a. less of Offsite Power,
- a. Imse of Of fsite Power and loss
- a. Ioss of Of fsite l'
POWER of both diesel generators.
Power and loss of
- b. Ioss of both diesel I A & IB Diesel generators
- b. Ioss of both bat t atries.
Generators for 15 minutes.
- b. loss of both sta.
batteries for 15 min.
[
OTHER
- a. Shif t Super /Emerg. Coord. dis-
- a. Shift Super /Emers. Coord, dis-
- a. Shift Supe r/Eme rs, s. Shift Super /
CONDITIONS cretion. Plant conditions cretion. Plant condition that Coord. discretion.
Emerg. Coord.
that warrant increased aware-w evant activation of TSC; EOF, Plant conditions that discretion.
neas on the part of the state or ESC.
warrant activation of Flant condition
,t' and counties, emergency Centers &
that could lead.
i precautionary public to large radio.
not.i ficat ion logical release.
LOSS OF
- a. Loss of Indication Alarms
- a. Most annunciators lost,
- a. Most or ALL INDICATORS requiring a plant shutdown.
Annunciators and indicators lost.
ANNUNCIA-4 TORS, Od during unplanned transient.
ALARMS i
t CONTROL
- a. Control Room Evacuation
- a. Control Room Evacuation with
{;
ROON Iocs1 shutdown EVACUATION stations not established within 15 minutes.
LOSS OF
- a. ' Exceeding a limiting condition
- a. Inability to achieve cold
- a. Inability to ENGINEERED for operation on a safety shutdown.
achieve hot shut-SAFETY system requiring a plant shut-do w...
FEATURES down.
- b. Safety injection system o
relief valve fails, t
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--;_;.s.w APPDOIX I GIID3 LINES SITE IDEUGENCY GBEERAL BEtIGBICY INITIATING UNUSDAL EVDit' PARAMETER ALERT PARAML"rER (D 'IO SC-202 PARNEt1ERS (D PAIUlfECTER G) 10 NMUIRL
- a. Earthquake felt in plant or
- a. Earthquake >.08 but <.2 as Plant rair in cold SC-204 (DE)ITI(E m) '10 SC-201
'10 SC-203.
1 PHENOW NON detection m plant seismic registered on plant accelograph shutdown ani:
i,
BEING instrtamentation.
Red target on action indicator
- a. Earthquake >.2 l EXPlut-
- b. take level above 252 ft.
unich actuates ') 0.01g.
as registered m
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- c. Lake level below 242 ft.
- b. Lake level above 253 ft.
IENCED plant accelograph.
- d. Deer Creek flooding over
- c. Lake level below 241 ft.
- b. Winds or Flood or entrance road bridge.
- d. flood or large waveCs) which large wave (s)
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- e. Iarge sesve(s) causing water bring water into the plant.
which threaten to push over armor stone.
- e. Tornado striking plant buildin9 g ipment required
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- f. 'Ibenado on site / hurricane
- f. Hurricane winds)70 mph.
for cold shutdown.
)
warnings.
(st eady)
HAZARDS
- a. Aircraft crash on site
- a. Aircraft crash into site Plant IDF in cold i.
- BEING
- b. Near or ansite explosion.
building.
shutdown and:
EXPER-
- c. Near or malte toxic or flasua-
- b. Ernlosion affecting plant
- a. Aircraft crash in-l IEN3D (R able gas release.
operation.
to vital area.
PinJBC'IED d. 'Ibrbine rotating ocuponent
- c. Ehtry of moontrolled toxic or
- b. Explosion or i
failure causing shutdown.
flanunable gas into building.
missile damaging
- d. 'Ibrbine failure causing casing safety equipment.
- e. Missile striking building.
j PIRE #@
- a. Fire lastina 10 minutes.
- a. Fire potentially affecting
- a. Fire causing loss FIRE
- b. Fire department called.
safety systems.
of a safety systen t
PIDIECTION c. Exceeding a limiting condition i
i FEA'IUIE.S for operation on the fire sys.
requirirv) a plant shutdown.
COffAM-
- a. 'Itansportation of contaminated INMED patient to a hospital.
IlOllRY sF2.URITY
- a. Attenpted entry to site
- a. On-going Security compronaise
- a. Inuninent loss of
- a. Ioss of griysical l,
i
- c. Security threat (Pickets,
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physical control control of the
![
- b. Attenpted sabotage
- b. (bntinuing Security threat of the plant plant' Denonstration).
i.
KitORMAL
- a. Exceeding a limiting condition 0000ANF for cperation for heatup or TFM. AND/
cooldown.
OR PRESS.
- b. Exceeding a safety limit.
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