ML20065N455

Forwards Response to 940407 RAI Associated w/NUMARC/NESP-007 EAL Submittal

ML20065N455
Person / Time
Site:	Callaway
Issue date:	04/21/1994
From:	Stiller M UNION ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20065N458	List: ML20065N455 ML20065N461 ML20065N483
References
ULNRC-2998, NUDOCS 9404270166
Download: ML20065N455 (13)

Text

g m Callaway Plant Pa:a Othce Box 620 Jul ton. Mmoun 65251 Union April 21,1994

'Euscnue 53 Document Control Desk Oflice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop Pl-137 Washington, DC 20555 ULNRC-2998 Gentlemen:

DOCKET 50-483 CALLAWAY PLANT NUMARC/NESP-007 EAL SUBMITTAL REOUEST FOR ADDIT!ONAL INFORMATION You will find attached one (1) copy of our response to your Request for Additional Information (RAl) associated with our submittal. Your RAI was transmitted to us in your letter TAC M88479 dated April 7,1994.

If you have any questions regarding these responses please call me at (314) 676-8212 or Mr. Mark flicks at (314) 676-8705.

Very Truly Yours, Manager, Nuclear Safety and Emergency Preparedness f td.:MWH:alr Enclosure cc: J. B. O'Brien, EP Specialist, U.S. Nuclear Regulatory Commission, w/a L. R. Wharton, Licensing Project Manager, Callaway Plant, w/a J. B. Martin, USNRC Regional Administrator, Region III, w/a B. A. Bartlett, USNRC Resident Inspector, Callaway Plant, w/a L. R. Greger, USNRC Region III - Chief, Reactor Projects Section HI A, w/a

- Manager, Electric Department, Missouri Public Service Commission, w/a 1

Shaw, Pittman, Potts & Trowbridge, w/a I i

~

6

l 1

RESPONSE

TO l REQUEST FOR ADDITIONAL INFORMATION (RAI) l DOCKET 50-483 UNION ELECTRIC ,

CALLAWAY PLANT

i l

l TABLE OF CONTENTS l

l

1. NUMARC EALs - Attachment 1 of EIP-ZZ-00101 l

2. EAL Bases l

3. Responses to the Request for AdditionalInformation j 4. Change s to Callaway's EAL Submittal l 5. Enclosure 1 - EDP-7Z-00005 l

6. Enclosure 2 - Critical Safety Function Status Trees l

7. Enclosure 3 - Radiological Consequences of a Waste Gas Decay Tank Rupture

8. Enclosure 4 - Technical Bases for P.C. Based Plume Phase Dose Assessment

9. Enclosure 5 - EIP-ZZ-00101 Examples of Emergency Coordinator Judgment

10. Enclosure 6 - FSAR Site Addendum - 3.5.2 l

l 1. Enclosure 7 - OTO-RK-00001, Loss of Control Room Alarms i

s

~

EIP-ZZ-00101 Rev.16 EMERGENCY ACTION LEVELS Group i ABNOR31AL RADIATION EVENTS Ofhite Events UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMCRGENCY A. B. C. D. l Any Unplanned Release of Any Unplanned Release of EAB Dose Resulting From an Actual or EAB Dose Resulting From an Actual or Radioactivity to the Emironment That Radioactivity to the Emironment That Imminent Release of Gascous Radioactivity Imminent Release of Gaseous Radioactivity Exceeds 2 Times the Radiological Exceeds 200 Times the Radiological Exceeds 100 mrem TEDE or 500 mrem Exceeds 1000 mrem TEDE or 5000 mrem Emuent Control Limits in the ODCM, Emuent Control Limits in the ODCM, CDE Thyroid for the Actual or Projected CDE Thyroid for the Actual or Projected l (APA-ZZ-01003) for 260 minutes. (APA-ZZ-01003) for 215 minutes. Duration of the Release. Duration of the Release.

MODES: At AllTimes MODES: At AllTimes MODES: At AllTimes MODES: At AllTimes Indicators Indicators Indicators Indicators

1. All of the following: 1. All of the following: Anv of the following: Any of the following:

a. A valid alarm and reading on a. A valid alarm and reading on any emuent monitor: any emuent monitor: *l. A valid reading on the Unit Vent *l. A valid reading on the Unit Vent monitor, GT-RE-21B (Channel 213) monitor GT-RE-21B (Channel 213)

HB-RE-18 (Channel 186) HB-RE-18 (Channel 186) >8.lE+5 Ci/sec for 15 minutes. > 8. IE+6 Ci/sec for 15 minutes.

GT-RE-21B (Channel 213) GT-RE-21B (Channel 213)

GH-RE-10B (Channel 103) GH-RE-10B (Channel 103) 2. A valid dose projection indicates >100 2. A valid dose projection indicates mrem TEDE or >500 mrem CDE >1000 mrem TEDE or >5000 mrem

b. The valid reading is 2 times b. The valid reading is 200 times thy roid dose at the EXCLUSION CDE thyroid dose at the the Hi Hi alarm setpoint (trip the Hi Hi alarm setpoint (trip AREA BGUNDARY using inplant EXCLUSION AREA BOUNDARY setpoint) value. setpoint) value. rad data or field monitoring team using inplant rad data or field

c. The release cannot be c. The release cannot be survey results. monitoring team survey results.

terminated within 60 minutes terminated within 15 minutes of the alarm actuation. of the alarm actuation. 3. Field survey results at the EAB 3. Field survey results at the EAB OR OR corresponding to > 100 mrem /hr corresponding to > 1,000 mrem /hr

2. Both of the following: 2. Both of the following: TEDE for I hour (or expected to TEDE for I hour (or expected to

a. Confirmed sample analysis a. Confirmed sampic analysis continue for I hour) or > 500 mrem /hr continue for I hour) or indicates that a release indicates that a release CDE thyroid for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ofinhalation. > 5,000 mrem /hr CDE thyroid for I exceeding 2 times the exceeding 200 times the hour ofinhalation.

applicable vala of the applicable values of the ODCM (APA-ZZ-01003), has ODCM (APA-ZZ-01003), has

• Declare the event using this indicator occurred. occurred. only if an actual dose assessment per

• Declare the event using this indicator

b. The release cannot be b. The release cannot be Indicator 2 cannot be performed in 15 on_ly if an actual dose assessment per terminated within 60 minutes. terminated within 15 minutes. minutes. Indicator 2 cannot be performed in 15 minutes.

Page 1 of 10 ATTACHMENT 1 l.

/

EIP-ZZ-00101 Rev.16 EMERGENCY mTION LEVELS Group 1 ABNORMAL RADIATION EVENTS Onsite Esents UNUSUAL EVENT ALERT ALERT E* F* G.*

An Unexpected Increase in Plant Radiation. Major Damage to Irradiated Fuel or Loss of Water Level Release of Rad Material, or an increase in Rad Lestl That Has or Will Result in the Uncovering of Irradiated that Either Impedes Safe Operations or the Ability to Fuel Outside the Reactor Vessel. Establish or Maintain Cold Shutdown.

MODES: At AllTimes MODES: At AllTimes MODES: At AllTimes Indicators Indicators Indicators Any of the following: Any of the following: Arty of the following:

1. Spent Fuct Pool testi is decreasing on 1. A VALID Hi-Hi Alarm on Fuel Building exhaust 1. Valid (confirmed by HP) reading on SD-33 (Control EC-L1-0039A with Normal makeup being added, monitors GG-RE-27 or 28 (Channel 273 or 283) Room) >l5 mr/hr.

and all irradiated fuel assemblies remain covered. of 1.46 E-3 Ci/cc.

2. Valid (confirmed by HP) reading on the following

2. Refueling Pool level is decreasing on BB-LI-0053A 2. Containment refueling bridge area radiation Safe Shutdown Area ARMS:

or B with Normal makeup being added, and all monitor (SD-41) 2150 nu/hr. SD-26 PC Changeout Area i irradiated fuel assemblies remain covered. SD-23 RHR Hx Arca Corr.

3. Fuel building area radiation monitor (SD-37 or 38) SD-15 Door to HPACA Area

3. Any valid (Confirmed by HP survey) ARM (other > 70 mr/hr. SD-16 Fire Brigade Locker Area j than a Group 1,G. Safe Shutdown ARM) >1000 > 1000 times normal (normal lesels can be l

times normal. (Normal levels can be considered as 4. Report of visual observation ofloss of water level considered as the monitor reading prior to the l

the monitor reading prior to the noticed increase.) resulting in irradiated fuel being uncovered. noticed increase).

l l

• This Initiating Condition is not meant to apply to

• This Initiating Condition is not meant to apply to This Initiati.tg Condition is not meant to apply to anticipated temporary increases due to planned anticipated temporary increases due to planned anticipated temporary increases due to planned events (e.g., incore detector movement, radwaste esents (e.g., incore detector movement, radwaste events (e.g., incere detector movement, radwnste container movement, depleted resin transfers, upper container movement, depleted resin transfers, upper container movement, depleted resin transfers, upper internal movements, etc.) internal movements, etc.) internal movements, etc.)

l Page 2 of 10 ATTACHMENT I r

- - -- - - - - - - ~ ~ - - - - - ~ ~~ ~ ~ ~ ~- ~ - --- - -

EIP-ZZ-00101 Rev.16 EMERGENCY ACTION LEVELS Group 2 FISSION PRODi'CF BARRIERS A. UNUSUAL EVENT B. ALERT C- SITE EMERGENCY D. SITE EMERGFNCY E.GENFRAL EMERGENCY h CONTAINMENT BARRIER Anv RCS BARRIER hicator Anv FUEL CLAD BARRIER A CTMT BARRIER Lc_$s Indicator i Lo__ss Indicator from any two Indicator or bdicator and barners

& FUEL CLAD BARRIER and Any RCS or FUEL CLAD B WRIER and b 6 cator & RCS BARRIER Inicator bdicator /g;lbdicator from the third CONTALMIENT HARRIER RCS BARRIER FL'EL CLAD BARRIER MODES 14 MODES 1 -4 MODES 1-4 less indicaton: less indicaton: less indicaton:

1. Contamment Pressure 1. RCS Leak Rate 1. Cntical Safety Function Status a) A rapid unexplamed less of CTMT pressure following an Safety Injection initiated with a loss of subcoolmg (less than Meet the enty requirements for initial increase in pressure. instrument error) using Anachment 2 or 3 of Emerg. Pmcedure E-0. FRC.1, Red Path for Core cooling.

g 2. SG Tube Rur+ture 2. Primary Coolant Activity Level b) CThff pressure g sump level not increasing wi h a a) h of the following: RCS coolant activity >300 Ci/cc LOCA. 1) GE-RE-92 (Channel 925) >2.0E-5 Ci/cc dose equivalent 1-131.

2. Centainment Isolation Valve Status 2) BM-RE-25 (Channel 256) >l.0E-4 pCi/cc 3. Centainment Radiation Monitonne l bcomplete CniT isolation allowmg a d: rect release to the 3) SJ-RE-02 (Channel 026) >1.0E-4 pCi/cc GT-RE-59/60 (Channels 591/601) environment, following a valid CTMT isolation signal (ClSA, 4) Narrow range lesel m any SG contmues to increase in an reading >3 E+3 R/Fe.

l CISB, CPIS) unconvolled manner

3. SG Release with Pnmarv-Secondan I cakace gnd Potential loss indicator:

a) Pri-to-sec leakage greater than Tech Spec allowable b) either cf the followint 4. Cntical Safety Function Status and 1) The ruptured SG pressure is decreasing in an uncontrolled Meet the entry requirements for b) either of the following- manner er completely depressurized. FRC.2, Orange Path for Core

1) The leaking SG pressure is decreasing in an 2) Manual use of the ruptured SG PORV for cool down Lochng g FRIL1, Red th ' Mr IIcat uncontrolled manner or completely depressurized. 3 Containment Radiation Menitorine Smk.

2) Manual use of the leaking SG PORV for cool down. GT-RE-59/60 (Channels 591/60!) readmg >l E+3 R/hr.

5. Core tait Thermocouples Potential less indicaton:

Critica! Safety Function Status Potential 1 is indicators: Core exit TCs >700*F.

4.

4. Cntical Safetv Function Status Meet the entrv requirements for FRZ 1. Red Path Summary Meet the entry requirement for FRIL 1, Red Path Heat Smk or 6. Reactor Ve<sel Water Level l frC M FRP.1, Red Path for Integnty. a) RVLIS (Pumps OtT)less than 1

5. Containment Pressure '

5. RCS Leak Rate 40Y '

a) 112 concentration in containment >4% RCS leakage >50 gpnt. g E )

6. SG Tube Rurture b) RVLIS (Pumps On)less than I b) Less than 1 full train of Ctmt spray grd Ctmt coolm.g a) Any of the followiro:

minimum fans, with Ctmi pressure greater than 27 psig

[ GE-RE-92 (Cimnnel 925) >2.0 E-5 Ci/cc RCPs on Minimum

6. S!cmficant Radioactive Inventerv m Ctmt

2) BM-RE-25 (Channel 256) >10 E-i Ct/cc 4 44 GT-RE-59/60 (Channels 591/601) readmg >l 5 E+3 R/hr

3) SJ-RE-O'(Channel 026) >l.0 E-t pCi/cc 3 30

7. Core Exit Thermocounles

4) Narrow range level in any SG contmues to increase in en 2 20 a) Core exit TCs >l200*F gnd restoration procedures not ,Jolled manner. I 13 effective m 15 minutes.

and E b3e primary-to-secondary leak rate exceeds 50 gpm.

b) Core exit TCs >700*F and RVIls (purnps ofn <40% and restcration procedures not effective in 15 minutes.

I Page 3 of 10 ATTACIBIENT I

EIP-ZZ-00101 Rev.16 EMERGENCY AcrION LEVELS Group 3 HAZARDS AFFECTING PLANT SAFETY Security Esents UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY A. B. C. D.

Confirmed Security Event Which Security Event in the Plant Protected Security Event in a Safe Shutdown Area. Security Event Resulting in a Loss et the Indicates a Potential Degradation in the Area. Ability to Reach and Maintain Cold Level of Safety of the Plant. Shutdowit.

MODES: At AllTimes MODES: At AllTimes MODES: At AllTimes MODES: At AllTimes Indicators Indicators Indicators Indicators Any of the following: Confirr:d report by the Shift Security Any of the following Any of the following:

Supervisor of an mtrusion by a hostile 1. Bomb device discovered within any

1. Bomb device discovered within the force into the plant Protected Area. of the following areas: 1. Occupation of the Control Room by plant Protected Area and outside the a. Area 5 a hostile force.

following Safe Shutdown Areas: b. Containment

c. Aux Feed Pump Rooms 2. Occupation of the Aux Shutdown

a. Area 5 d. Aux Building Panel by a hostile force.

b. Containment c. Diesel Generator Buildmg

c. Aux Feed Pump Rooms f. UHS Cooling Tower

d. Aux Building g. ESW Pumphouse

e. Diesel Generator Building h. Control Building

f. UHS Cooling Tower i. RWST

g. ESW Pumphouse j. Fuel Building

h. Control Building

i. RWST 2. Confirmed report from the Shift

j. Fuct Building Security Supervisor of an intrusion by a hostile force into any of the i 2. Confirmed report from the Shift following areas:

l Security Supervisor of an attempted a. Area 5 entry, sabotage or security threat that b. Containment cannot be properly compensated for c. Aux Feed Pump Rooms within 10 minutes. d. Aux Building

e. Diesel Generator Building

f. UHS Cooi.,g Tower

g. ESW Pumphouse

h. Control Building

i. RWST

i. Fuel Building Page 4 of 10 ATTACHMENT 1 W

EIP-ZZ-00101 Rev.16 EMERGENCY ACTION LEVELS Group 3 IIAZARDS AFFECTLNG PLANT SAFETY Firts Natural Events UNUSUAL EVENT ALERT UNUSUAL EVENT ALERT E. F. G. H.

Fire Within Protected Area Boundary Fire Affecting the Operability of Plant Natural and Destructive Phenomena Natural and Destructive Phenomena Not Extinguished Within 15 Minutes Safety Systems Required to Establish Affecting the Protected Arca. Affecting a Safe Shutdown Area.

of Verification. or Maintain Safe Shutdown.

MODES: At AllTimes MODES: At All Times MODES: At AllTimes MODES: At AllTimes Indicators Indicators Indicators Indicators

1. Fire in or adiacent to any of the 1. Fire in any of the following Any of the following: An_v of the following:

following: areas:

1. a. Response spectrum recorder

1. a. Operating basis earthquake

a. Area 5 a. Area 5 operating annunciator 98E annunciator 98D alarms in the

b. Containment b. Containment alarms m the Control Room Control Room

c. Aux Feed Pump Rooms c. Aux Feed Pump Rooms and~ Verified to be a real event per nd

d. Aux Building d. Aux Building b

b. hq e gr ter than BE

c. Diesel Generator Building e. Diesel Generator Building OTO-SG-00001.

f. UHS Cooling Tower f. UHS Cooling Tower

2. Report of a turbine rotating , and vertical directions as

g. ESW Pumphouse g. ESW Pumphouse indicated by LIGHT "OSG-AE-1, component failure resultmg m

h. Control Building h. Control Building or LIGHT "OSG-AE-2, casing penetration or major

i. RWST i. RWST damage to seals causing a rapid

j. Fuel Building j. Fuel Buildine 2. a. Report of a tornado, high wind, loss aflubncatmg oil or hydrogen.

and and vehicle crash, explosion, or other

3. Explosion, vehicle crash or tornad natural or destructive phenomena to

2. Not extinguished within 15 2. There is visible damage to m or adiacent to any of the any of the following Safe Shutdown minutes of control room permanent structures or following. areas-verification of a fire. equipment, affecting th Area 5 operability of safety related eqmpment.

{AC taimnent c.

5 Aux Feed Pump Rooms 2.

3.

Containment Aux Feed Pump Rooms

d. Aux Building 4. Aux Building

e. Diesel Generator Building 5. Diesel Generator Building

f. UHS Cooling Tower 6. UHS Cooling Tower

g. ESW Pumphouse 7. ESW Pumphouse

h. Control Building 8. Control Building

i. RWST 9. RWST

j. Fuel Building 10. Fuel Building

b. There is visible damage to permanent structures or equipment, affecting plant operations.

Page 5 of 10 ATTACHMENT 1 l $ _

__ - ---_-- _ _- - -- _E7p,Z7,g., I g 7 - _ _ . -- _ _ _ _- -. ---__ -- _ ---- _ q Rev.16 EMERGENCY ACTION LEVELS Group 3 IIA 7.ARDS AFFECTING PLANT SAFETY Toxic Gas Control Room Evacuation Events UNUSUAL EVENT ALERT ALERT SITE EMERGENCY I. J. K. L.

Release of Toxic or Flammab!: Gases Release of Toxic or Flammable Gases Control Room Evacuation Has Been Centrol Room Eucuation Has Been Decmed Detrimental to Safe Operation Within a Facility Structure Which Initiated. Initiated and Plant Control Cannot Be of the Phnt. Jeopardizes Operation of Systems Established.

Required to Establish or Maintain Cold Shutdown.

MODES: At All Times MODES- At All Times MODES: At All Times MODES: At AllTimes Indicators Indicators Indicators Indicators Any of the following: E of the following:

A Entry into OTO-ZZ-00001, Control 1. Entry into OTO-ZZ-00001, Room evacuation is required. Control Room evacuation is

1. Report or detection of toxic or 1. Report or detection of toxic or flammable gases, not properly requhed.

flammable gases that enter within the Exclusion Area Boundary, that contained, within or adiacent to l and have created a HAZARDOUS any of the following Safe ATMOSPHERE per Shutdown Arcas, that has e created l 2. Control of the Aux Fced System CTP-ZZ-01100. a HAZARDOUS ATMOSPIERE and a SG PORV for cooldoun per CTP-ZZ-01200.

2. Confirmed report by local, County cannot be established within 15 or State Oflicials of potential minutes

a. Area 5 evacuation of site personnel as b. Containment determined from the DOT c Aux Fced Pump Rooms evacuation tables for selected d. Aux Building

c. Diesci Generator Building  !

hazardous materials in the DOT f. UHS Cooling Tower Emergency Response Guide for g- ESW Pumphouse Hazardous Materials. h. Control Building

i. RWST

j. Fuel Building l

Page 6 of 10 ATTACIBENT 1 s

e h

EIP-ZZ-00101 Rev.16 EMERGENCY ACTION LEVELS Group 4 SYSTEM MALFUNCTIONS Annunciator Esents l'NUSUAL EVENT ALERT SITE EMERGENCY

~

A. B. C.

Unplanned Loss of Most or All Alarms Unplanned Loss of All Annunciators With Either a inability to Monitor a Sigmficant Transient in l (Annunciators) for Greater Than 15 Minutes. Transient In Progress, or the Plant Computer is Progress.

Unavailable.

MODES: 1-4 MODES: 1-4 MODES: 1-4 Indicators Indicators Indicators

1. Either of the following: 1. Either of the following: All of the following:

a. 3 of 4 field power supplies hase failed for a. 3 of 4 field power supplies have failed for greater than 15 minutes (loss of all greater than 15 minutes (loss of all 1. a. Either of the following:

annunciators) and not a result of planned annunciators) and not a result of planned 1) 3 of 4 field power supplies have failed action. action. (loss of all annunciators).

tt All thirteen logic power supplies have failed b. All thirteen logic power supplies hase failed 2) All thirteen logic power supplies have for greater than 15 minutes (loss of all for greater than 15 minutes (loss of all failed (loss of all annunciators).

annunciators) and not a result of planned annunciators) and not a result of planned or action. action. b. Both of the following:

or or 1) Any combination of power supplies All of the following: All of the following: (including Optical isolators) have

c. Any combination of power supplies c. Any combination of power supplies failed.

(including Optical isolators) have failed for (including Optical Isolators) have failed for 2) Any failed power supply's minimum greater than 15 minutes. greater than 15 minutes. compensatory action _s, per

d. Any failed power supply's minimum d. Any failed power supply's minimum OTO-RK-00001, cannot be maintained.

compensatory actions, per OTO-RK-00001, compensatory actions, per OTO-RK-00001, and cannot be maintained. cannot be maintained. 2. The plant computer is unavailable.

c. The loss does not result from planned e. The loss does not result from planned and_

action. action. 3. Either of tne following:

and a. A change in reacter power greater than

2. An_v of the following: 10%.

a. A change in reactor power greater than b. Safety injection initiation.

10%.

b. Safety injection initiation.

c. The plant computer is unavailable.

Page 7 of 10 ATTACILMENT I I

At -

1 I

7 v -

U- U U LU U U. .U- U C EIP-ZZ-00101 Rev.16 EMERGENCY ACTIONLEVELS Group 4 SYSTEM MALFUNCTIONS Electrical Events (Operating) Electrical Events (Shutdown)

GENERAL UNUSUAL EVENT ALERT SITE ESIERGENCY SITE EMERGENCY E%1ERGENCY UNUSUAL EVENT ALERT D. E. F. G. It L J.

Loss of All Offsite Only One AC Source Loss of All Offsite Loss of All Vital DC Prolonged Loss of All Loss of Required DC Loss of All Offsite Power to Essential to Essential Busses Power and Loss of Power Offsite Power and Power During Cold Power and Loss of All Busses for Greater for >l5 Minutes Such All Onsite AC Power Prolonged Loss of All Shutdown or Refueling Onsite AC Power to  !

Than 15 Minutes. That Any Additional to Essential Busses. Onsite AC Power. Mode for Greater Than Essential Busses During Single Failure Would 15 Minutes. Cold Shutdown or Result in Station Refueling. ,

Blackout.

MODES: 1-6 MODES: 14 MODES: 14 MODES: 14 MODES: 14 MODES: 5. 6 MODES: 5,6. Defueled Indicators Indicators Indicators Indicators Indicators Indicators Indicators All of the 1. Loss of a_n_y 3 of 1. Loss of a_Il 4 of 1. Loss of all vital All of the following: 1.No operable 1. Loss of all 4 of the following: the following the following DC power as (Division 1 or 2) following power

1. Loss of offsite

1. Loss of offsite power sources: power sources: indicated by Power sources:

power to NB01 power to NB01 a. Offsite a. Offsite less than 106.9 source as indicated by a. Offsite power to and NB02' anjd NB02. power to power to VDC on vital -

< 106.9 VDC on NB01 NB01 NB01 DC busses 2. Loss of both NK01 or NK03 b. Offsite power to

2. NB01 and b. Offsite b. Offsite NK01, NK02, Emergency Diesel (Division 1) NB02 NB02 being power to power to NK03, and Generators NE0i or c. Emergency supplied by NB02 NB02 NK04. and NE02. NK02 o_r NK04 Diesel NE01  ;

NE01 and c. Emergency c. Emergency (Division 2). d. Emergency

~

. a. estorab.on of NE02. Diesel NE01 Diesel and Diesel NE02 at least one

d. Emergency NEPl E Failure to and and The loss of Diesel NE02 d. Emergency restore power to 2. Failure to restore 2. The loss of all 4 has 3.

offsite power Diesel at least one DC

• • 'E "] power to at least occurred for >l5 has occurred and NE02 . bus within 15 g .

one operable minutes.

for >l5 2. The loss of all 3 and minutes' Division of Vital or DC power within minutes. has occurred for

>l5 minutes.

2. The loss of a._Il 4 has occurred for EMd 15 minutes.

>l5 minutes.  ; ,

for FRC.1, Red Path for Core Cooling.

Page 8 of 10 . ATTACHMENT 1

_ _ _ _ _ - - _ _ _ _ _ ___m_---__m__

EIP-ZZ-00101 Rev.16 EMERGENCY ACTION LEVELS Group 4 SYSTEM MALFUNCTIONS Shutdown Capability UNt!StrAL EVENT AI.ERT SITE E31ERGENCY SITE E5fERGENCY K.* L. M. N.

Inability to Perform a Required Inability to Maintain Plant in Cold Loss of Water Level That Has or Will Complete I.oss of Function Needed to Shutdown Within Technical Shutdown. Uncover Fuel in the Reactor Vessel. Achieve or Maintain Hot Shutdown.

Specification Limits.

MODES: 1-4 MOGES: 5. 6 MODES: 5. 6 MODES: 1-4 Indicators Indicators Indicators Indicators l

1. The plant is not brought to a 1. Any of the following: 1. Any of the following: 1. All of the following: I required operating mode within a a. Complete loss of both trains of a. Complete loss of both trains of a. Failure to bring the reactor j Technical Specification LCO action RHR. RHR. subcritical with the control rods I statement time. b. templete loss of both trains of b. Complete loss of both trains of fully inserted. I CCW. CCW. b. Complete loss of all Boron

c. Complete loss of both trains of c. Complete loss of both trains of Injection Flowpaths.

ESW. ESW. o__r and and 2. All of the following:

2. Either of the following: 2. Either of the following: a. All steam generator levels <10%

a. Greater than 200 F on any valid a. Greater than 200 F on anp21id wide range.

incore thermocouple.* incore thermocouple.' b. All steam dump valves to t,. Uncontrolled temperature rise, b. Uncontrolled temperature rise, condenser (AB-UV-34, 35, and l

with no actions available that with no actions available that 36) are NOT responding to i will likely prevent approaching will hkely prevent approaching steam header pressure controller 1 200'F on any valid incore 200oF on any valid incore (AB-Zl-34, 35, or 36).

thermocouple.* thermocouple.* c. All steam generator steam dump

1rt_d valves to atmosphere are NOT

3. a. Water level in the reactor vesse; operating properly (AB-PIC-I A, is less than 2.0 inches on 2A, 3 A and 4 A).

BB-LI-0053 A or B. d. Complete loss ofboth RHR l or trains. (A complete loss of ESW l

b. RVLIS (pumps off) <55% or CCW constitutes a compl-te

• If a thermocouple is not available,

• It is not intended to declare an loss of RHR.)

use Wide Range Hot Leg

• If thermocouple is not available, or Unusual Event due to an unknown use Wide Range Hot Leg E All of the following:

condition or failure resulting in temperature indications:

temperature indications.

exceeding the allowable action . BBT1413A - Loop I a. The Ultimate Heat Sink (UHS)

BBTI423A - Loop 2

. T4 A p1 is inoperable as a result oflevel statement time. The allowable .

action statement time is always . RECORDERS P or temperature.

available from the time of the BBTR413 - Loop 1 b. Complete loss of both UHS discovery. BBTR423 - Loop 2 BTR4 - Loop i Cooling Tower trains.

BBTR423 - Loop 2 BBTR433 - Loop 3 BBTR443 - Loop 4 BBTR433 - Loop 3 BBTR443 - Loop 4 Page 9 of 10 ATTACHMENT 1

v -__ _

v y -- - - y EIP-ZZ-CD101 - ~

Rev.16 EMERGENCY .% TION LEVELS Group 4 SYSTEM MALFUNCTIONS Communication Events RCS/ Fuel Esents Reactor Protection System GENERAL UNUSUAL EVENT UNUSUAL EVENT UNUSUA L EVENT ALERT SITE EMERGENCY EMERGENCY O. P. Q. R. S. T.

Unplanned Loss of All Onsite or Fuel Clad Degradation RCS Leakage Failure of Reactor Failure of Reactor Failure of the Reactor OIIsite Communication Protection System Protection System Protection System to Capabilities Instrumentation to Instrumentation to Complete an Automatic Complete or Initiate Complete or Initiate Trip and Manual Trip an Automatic an Automatic Was NOT Successful Reactor Trip Once a Reactor Trip Once a and There Is Indication Reactor Protection Reactor Protection of an Extreme -

System Setpoint Has System Setpoint Has Challenge to the Ability Been Exceeded and Been Exceeded and to Cool the Core.

Manual Trip Was Manual Trip Was l Successful. NOT Successful.

MODES: 1-6 MODES: 1-6 MODES: 1-4 MODES: 1, 2 MODES: 1, 2 MODES: 1, 2 Indicators Indicators Indicators Indicators Indicators Indicators

1. _A_Il of the following: 1. Any of the following: 1. _A_rly of the 1. Failure of 1. Failure of _A_Il of the following:

a. Complete failure of a. >1.0 pCi/ gram Dose following: reactor reactor

1. Failure of reactor Plant telephone systems Equivalent I-131 for a. Unidentified protection protection

b. Complete failue of greater than a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> leakage greater system system pr tection system instunentation to Paging systems continuous period. than 10 gpm. instrumentation instrumentation to initiate an initiate an

c. Complete failure of b. Dose Equivalent b. Pressure boundary to initiate an automatic trip.

Plant radios 1-131 activity leakage greater automatic trip. automatic trip. "

d. Complete failure of exceeding the limits than 10 gpm. 2. Manual reactor trip Plant Emergency ofTech Spec Fig. c. Identified leakage and and is NOT successful Dedicated Phones. 3.4-1. greater than 25 usinc; manual trip o_r c. >100/E bar Ci/ gram gpm. 2. Manual reactor 2. Manual reactor switches

2. All of the following: of gross radioactivity. trip is successful trip is NOT SB-HS-1 on RLOO3

a. Complete failure of ENS using either successful using and (Red Phone)line manual trip manual trip SB-HS-42 on

b. Complete failure of switch, switches RLOO6.

Notification and SB-HS-1 on SB-HS-1 on RLOO3 RLOO3 3. Meet the entry Coordination line (Blue requirernents for Phone) or and FRC.1 o_r FRH.1,

c. Complete failure of SB-HS-42 on SB-HS-42 on RLG06. red path summaries Touch-tone telephone RLOO6 for core cooling and system (EPABX) heat sink.

d. Complete failure of the Sheriffs radio system.

Page 10 of 10 ATTACHMENT 1

_ _ _ _ - _ - - - _ _ _ _ _ _ _ __ _ ______ _ __-__ _ -___-____ __-_