ML20024D674

Public Version of Rev 1 to Emergency Plan Implementing Procedure EP-IP-001, Emergency Classification & Rev 1 to Procedure EP-IP-035, Emergency Vent Monitor Sampling.

ML20024D674
Person / Time
Site:	Susquehanna
Issue date:	06/28/1983
From:	PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML17139B660	List: ML20024D667 ML20024D674
References
PROC-830628, NUDOCS 8308050616
Download: ML20024D674 (60)

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PROCECURE COVER SHEET PENNSYLVANIA PC'.dR & LIGHT CO.

SUSCUEHANNA STEAM ELECTRIC STATICN EP-IP-001 EMERGENCY CLASSIFICATICN Revision 1 Page 1 of 44 Ef fective Date (n-@ @3 Expiration Date (0-@-85 Revised Expiration Date i

CONTROLLED .

Dre::ared by & ' . ?cvbs Date C U Reviewed by [' //J Date 4. / 7. f 3

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g PORC Review Re~ ired Y* () No(l) '

Aaproved by fo/21/83

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Fot?. Q" Date ' l Section Head / I / '

• PORC Meeting Number [?d/2 b7w - Ed-/92 Date/ff 13, /? h'/f?, /0/MD . ,

~s N Date 6 -M ;f 7 Superintencent of' Plant I i

FORM AD-QA-101-1, Rev. 1 Page 1 of 1

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• EP-IP-001 Revision 1 Page 2 of da TABLE OF CONTENTS SECTICN . .. PAGE 1.0 PL'RPOSE 3 2.0 SCCPE 3 ,

3.0 REFERENCES

3 4.0 RESPCNSIBILITIES 3 5.0 DEFINITICNS 4 6.0 INSTRUCTICNS 4 ATTACHMENTS ATTACHMENT PAGE A Action Step - EMERGENCY DIRECTOR / SHIFT SUPERVI.SOR 5 .

- Timing of Classification 6 ,

f B Action Step - RADIATION PROTECTION C00RDINATOR 7 C Action Step - RECOVERY MANAGER 8 D Action Steo - RADIATION SUPPORT MANAGER 9 E Classification Matrix Index 10

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EP-IP-001 Revision 1

.. Page 3 of 44 EMERGENCY ?,LASSIFICATICN 1.0 PURPOSE i

The purpose of this instruction is to provide guidance for the classification of abnormal events into EMERGENCY CLASSIFICATICNS (i.e., ,

UNUSUAL EVENT, ALERT, SITE EMERGENCY or GENERAL EMERGENCY). An abnormal event is any occurrence on site or off-site (that could or does have effects.

on-site) that is considered outside the realm of normal operation.

• 2.0 SCOPE _

This procedure should be utilized any time an abnormal event is identified or an existing abnormal event changes significantly. [

l

3.0 REFERENCES

3.1 NUREG-0654, Planning Standards and Evaluation Criteria 3.2 NUREG-0696, Functional Criteria for Emergency _Resconse Facilities 3.3 NUREG-0731, Guidelines for Utility Management Structure and Technical Resources, Sept. 1980. , l 3.4 SSES Emergency Plan 4.0 RESPCNSIEILITIES _

4.1 It is the responsibility of the SHIFT SUPERVISOR to assess available information and data and inttially classify the abnormal event. Until the TSC is manned, the SHIFT SUPERVISOR has the responsibility to upgrade, downgrade or terminate the EMERGENCY as clant conditions warrant. If the TSC is functional, the SHIFT SUPERVISCR shall assess available information and recommend reclassif.jca-ti'on, to the EMERGENCY DIRECTOR as necessary.

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.. Page 4 of 44 4.2 After the accident i s initially classified, it i s the responsibility of the EMERGENCY DIRECTOR to assess available information and to .

recIassify the EMERGENCY as necessary. Until the EOF is manned, the EMERGENCY DIRECTOR has the responsioility to uograde, downgrade or terminate the EMERGENCY as clant conditions warrant. If the EOF is functional, the EMERGENCY DIRECTCR is responsible for assessing plant conditions and advising tne RECOVERY MANAGER to upgrade the EMERGENCY ,

as necessary. The EMERGENCY DIRECTOR can also recommend l declassification or termination of the EMERGENCY to the RECOVERY MANAGER when conditions warrant.

i 4.3 It is the responsibility of the RADIATION PROTECTION COORDINATOR to assess off-site release information anc recommend to the EMERGENCY DIRECTOR to' reclassify the EMERGENCY, as necessary.

i 4.4 It is the responsibility of the RECOVERY MANAGER to assess plant  :

) information and to reclassify the EMERGENCY as necessary. In addition, j the RECOVERY MANAGER is responsible for declassifying or terminating the EMERGENCY when conditions warrant.

4.5 It is the responsibility of the RADIATION SUPPORT MANAGER to assess  !

off-site release information and recommend to the RECOVERY MANAGER to

, reclassify tne EMERGENCY as necessary. . .

~

5.0 DEFINITIONS ,

5.1 EOF - Emergency Operations Facility l 5.2 TSC - Technical Support Center 1

5.3 OSC - Operations Support Center i 5.4 EAL's - Emergency Action.. Levels:

6.0 INSTRUCTIONS

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6.1 The EMERGENCY DIRECTOR /3HIFT SUPERVISOR will follow the instructions in Attachment A, Action Step, EMERGENCY DIRECTOR / SHIFT SUPERVISOR.

J 6.2 The RADIATION PROTECTION COORDINATOR will follow the instructions in Attachment 8, Action Step, RADIATION PROTECTICN COORDINATOR.

6.3 The RECOVERY MANAGER will follow the instructions in Attachment C,

! Action Step, RECOVERY MANAGER.

6.4 The RADIATICN SUPPORT MANAGER will follew the instructions in Attachment D, Action Step, RADIATICN SUPPORT MANAGER.

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Attachment A EP-IP-001

• Revision 1 Page 5 of 44 ACTION STEP

EMERGENCY DIRECTOR / SHIFT SUPERVISOR A.1.0 The EMERGENCY DIRECTOR / SHIFT SUPERVISOR will

NOTE: WHEN AN ABNORMAL CONDITION IS NOTED, EITHER BY ASSESSMENT OF ,

CONTROL ROOM INDICATION OR A CALL TO THE CONTR3L ROOM CONCERNING THE ABNORMAL CONDITIONS, THE SHIFT SUPERVISOR WILL-

BE NOTIFIED AND THEN REPORT TO THE. CONTROL ROOM TO ASSESS THE-SITUATION.

A.1.1 Evaluate available information. 1 A.1.2 Secure additional information if necessary to insure an i accurate assessment.

A.1.3 Classify the existing conditions using the guidance in Attachment E, Classification Matrix.

NOTE: IF MORE THAN ONE ABNORMAL EVENT IS OCCURRING AT THE SAME TIME, CLASSlFY THE EMERGENCY EASED ON THE EVENT APPEARING TO ,

HAVE THE HIGHEST EMERGENCY CLASSIFICATICN. ATTACHMENT E .

SHOULD BE UTILIZED TO GIVE GUIDANCE AS'TO THE RELATIVE SEVERITY OF DIFFERENT CATEGORIES OF EVENTS. .

3 NOTE: THE EMERGENCY SHOULD BE CLASSIFIED WITHIN 15 MINUTES OF

) INDICATION. SEE TIMING OF CLASSIFICATION, SECTION A.2.0, OF j THIS PROCEDURE FOR DETAILED GUIDANCE.

A.1.4 IF the new EMERGENCY classification ts higher than the existing EMERGENCY classification, then go to EP-IP-002, '

Attachment A.

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A.1.5 IF the new EMERGENCY classification is lower than existing emergency classification, THEN, go to EP-IP-028, Attachment A.

NOTE: OTHER ACTIONS AND REPORTS OUTSIDE THE SCOPE OF THE EMERGENCY PLAN MAY BE REQUIRED. SEE NDI 5.1.3 FOR OTHER REPORTING

, REQUIREMENTS.

A.1.6 WHEN existing conditions are less severe than any of the classifications in Attachment E, Classification Matrix, THEN go to EP-IP-028, Attachment A.

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Attachment A EP-;P-001

.. Revision 1 Page 6 of ad A.2.01 TIMING OF CLASSIFICATION A.2.1 UNUSUAL EVENT The EMERGENCY DIRECTOR shall declare an UNUSUAL EVENT as soon as it has been indicated and verified. All reasonaole ,

efforts shall be implemented to make this verification within 15 minutes of the initial indication of the event.

A.2.2 ALERT The EMERGENCY DIRECTOR shall declare an ALERT as soon as the event has ceen indicated and verified. All reasonable efforts shall be imolemented to make this verification within 15 minutes of the initial indication af the event.

A.?.3 SITE EMERGENCY The EMERGENCY DIRECTOR shall declare a SITE EMERGENCY as soon as the event has been indicated and verified; but in no case shall this verification time exceed 15 minutes.

A.2.4 GENERAL EMERGENCY '-

The EMERGENCY DIRECTOR shall declare a GENERAL EMERGENCY as ,

soon as an event or combination of events within this category is indicated and verified. For indications based on radiological effluents, the verification time shall not ,

exceed 15 minutes. For less apparent indciations, the EMERGENCY DIRECTOR shall ensure that an appropriate ALERT or SITE EMERGENCY is in effect and determine the applicacility of a GENERAL EMERGENCY as soon as possible.

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l Attachment B EP-IP-001

.. Revision 1 Page 7 of 44 ACTION STEP RADIATION PROTECTION C00RDINATOR 3.1.0 UNTIL relieved by the RADIATION SUPPORT MANAGER, the RADIATION PROTECTICN CCORDINATOR will:

8.1.1 Evaluate available radiolegical release information.

NOTE: SECURE ADDITIONAL INFORMATION IF NECESSARY TO INSURE AN ACCURATE ASSESSMENT.

3.1.2 Classify the existing radiological release conditions using tse guidance in Attachment E, Classification Matrix.

NOTE: IF MORE THAN ONE RADIOLOGICAL RELEASE OR EVENT IS CCCURRING AT THE SAME TIME, CLASSIFY THE EMERGENCY EASED ON THE EVENT OR COMBINATION OF EVENTS APPEARING TO HAVE THE HIGHEST EMERGENCY CLASSIFICATICN. ATTACHMENT E SHOULD BE UTILIZED TO GIVE GUIDANCE AS TO THE RELATIVE SEVERITY OF DIFFERENT CATEGORIES OF EVENTS.

B.1.3 IF the NEW EMERGENCY classification.is higher tr.an the existing EMERGENCY classification THEN' advise the EMERGENCY DIRECTOR to upgrade to the new classification. .

B.I.4 -IF the new EMERGENCY classification is lower than the xisting classification THEN recommend to the EMERGENCY l

DIRECTOR to. downgrade to the new classification.

l Page 1 of 1 i

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Attachment C EP-IP-001

.. Revision 1 Page 8 of ??

ACTION STEP RECOVERY MANAGER C.1.0 The RECOVERY MANAGER will:

C.1.1 Evaluate availaole information. ,

NOTE: SECURE ADDITICNAL INFORMATION IF NECESSARY TO INSURE AN ACCURATE ASSESSMENT.

C.1.2 Classify the existing conditions using the guidance in Attachment E, Classification Matrix.

NOTE: IF MORE THAN ONE ABNORMAL EVENT IS OCCURRING AT THE SAME TIME, CLASSIFY THE EMERGENCY BASED ON THE EVENT APPEARING TO HAVE THE HIGHEST EMERGENCY CLASSIFICATION. ATTACHMENT E SHOULD BE UTILIZED TO GIVE GUIDANCE AS TO THE RELATIVE SEVERITY OF DIFFERENT CATEGORIES OF EVENTS.

NOTE: THE EMdRGENCY SHOULD BE CLASSIFIED WITH 15 MINUTES OF INDICATION, SEE ATTACHMENT A, PAGE 6, OF THIS PROCEDURE FOR DETAILED GUIDANCE. . .

2 .

C.1.3 IF the new EMERGENCY classification is higher than the .

existing EMERGENCY classification, THEN go to EP-IP-002 i Attachment I, I.2.0.

i C.1.4 IF the new EMERGENCY classification is lower than the existing EMERGENCY classification, THEN GO TO EP-IP-023, Attachment E. .

NOTE: OTHER ACTIONS AND REPORTS OUTSIDE THE SCOPE OF THE EMERGENCY PLAN MAY BE REQUIRED'SEE NDI 5.1.3 FOR OTHER REPORTING REQUIREMENTS.

C.1.5 WHEN exisiting conditions are less severe than any of the classifications in Attachment E, Classif'ication Matrix, THEN go to EP-IP-028, Attachment E.

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Attachment D Es-IP-001

.. Revision i Page 9 of Ja  ;

ACTION STEP RADIATION SUPPORT MANAGER 0.1.0 The RADIATION SUPPORT MANAGER will:

D.1.1 Evaluate available radiological release information. ,

NOTE: SECURE ACDITIONAL INFORMATION IF NECESSARY TO INSURE AN ACCURATE ASSESSMENT. .

D.1.2 Classify the existing radiological release conditions using the guidance in Attachment E, Classification Matrix.

NOTE: IF MORE THAN ONE RADIOLOGICAL RELEASE OR EVENT IS OCCURING AT THE SAME TIME, CLASSIFY THE EMERGENCY BASED ON THE EVENT OR CCMBINATION OF EVENTS APPEARING TO HAVE THE HIGHEST EMERGENCY C ASSIFICATION, ATTACHMENT E SHOULD BE UTILIZED TO GIVE GUIDANCE AS TO THE RELATIVE SEVERITY OF DIFFERENT CATEGORIES OF EVENTS.

D.1.3 IF the new EMERGENCY classification is nicher than the existing EMERGENCY classification THEN acvise the RECOVERY MANAGER to reclassify to the new classtfication.

0.1.4 IF the new Emergency classification is lower than the existing classification THEN recommend to the RECOVERY MANAGER to reclassify to the new classification.

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Page 1 of 1

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Attachment E EP-IP-001

.. Revision 1 Page 10 of 44 CLASSIFICATICN OF EMERGENCY CCNDITICNS (NOTE: Eefore using this matrix, read the note on the next page)

TABLE OF CCNTENTS -

CATEGCRY OF EVENT PAGE ABNORMAL EVENTS REQUIRING PLANT SHUTDOWN 15 ,

A!RCRAFT/ TRAIN ACTIVITY 21 CCNTROL RCCM EVACUATICN 37 FUEL CLADDING DEGRADATION 12-14 GENERAL 44 INJURED /CONTAMINAiED PERSCNNEL 29 INPLANT HIGH RADIATICN 34 LOSS OF AC POWER 32 LCSS OF CONTROL RCCM ALARMS AND ANNUNCIATORS . 40 LOSS CF DC POWER 33 .

1 LOSS OF DELAY HEAT REMOVAL CAPABILITY 38,39 LOSS OF REACTIVITY CONTROL .

13,19 LOSS OF REACTOR VESSEL INkENTORY 16,17 NATURAL PHENOMENA 27,28 CNSITE FIRE /EXPLOSICN 25,26 RADIOLOGICAL EFFLUENT RELEASE 22-24

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SAFETY / RELIEF VALVE FAILURE 30 SECURITY EVENT 31 SPENT FUEL RELATED INCIDENT 35,36 STEAM LINE SREAK 41-43 T0XIC/ FLAMMABLE GASES 20 Page 1 of 35 nme-e-m - - - - - . - , . . - , . ,_.p. -

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J Attachment E EP-IP-001

.. Revision 1 Page 11 of 4' CLASSIFICATICN OF EMERGENCY CCNDITIONS 1 NOTE ON USE OF THIS MATRIX NOTE:

Iceally tnis matrix i s designed to make it possible to classify every abnormal occurrence into the proper emergency classificaticn very precisely cased on the detailed Emergency Action Levels (EAL) described in the matrix. However it is ,

impossible to be exactly precise or entirely complete in anticipating abnormal occurrences. Therefore, before classifying any abnormal occurrence based on the-EALs in this matrix, one should verify that the general conditions prevalent in -

plant and offsite meet the general class description of the emergency classification outlined below. In addition prior to classification, one should be aware of the ramifications in plant and particularly offsite of that classification. Special consideration of offsite consequences should be made j prior to declaring a GENERAL EMERGENCY.

CLASS DESCRIPTIONS UNUSUAL EVENT - Unusual events are in process or have occurred which indicate a

, potential degradatidn of the level of safety of the plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.

ALERT-EventsareinprocessorhaveoccurredwhichirIvolveanactualor potential substantial degradation of the level of safety of the plant. Any releases exoected to be limited to small fractions of the EPA Protection Action ,

Guideline exposure levels.

SITE EMERGENCY - Events are in process or have occurred which involve actual or likely major failures of plant functions needed for protection of the public.

Any releases not expected to exceed EPA Protective Action Guiceline exoosure levels except inside the emergency planning boundary.

GENERAL EMERGENCY - Events are in-process or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity. Rleases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels beyond the emergency planning boundary. - - ~

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Attacn ent E EP-IP-CCI Revis+:n 1 3;;e IC of 44 CATEGORY - FUEL CLACDING DEGRADATICN UNUSUAL EVENT (I)

I. (A CR B CR C)

Signi ficant degradation, as indicated by:

A.

Of f gas c a r.e l Pre-treatment Monitor nign radiation alarm annunciatio 10601 or incication on panel 1C600. n on OR 5!

panel OC673 or indication on panel 1C322.Off on on gas Po OR ~

CT than or equal to 2 uCi/cc of I-131 equivalentReactor .

eater ALERT (I)

I.

(A GR B CR C OR D)

Severe degradation, as indicated by: -

A.

Cff gas Pre-treatment monitor High-High radiation alarm annu canel CC651 or indication on panel 1C600.

• nciation on OR 5T Reactor as determined coolant activity by sample greater than 300 uCi/cc of ecuival analysis. ent I-131, OR C-- v -

' 3]_^ ateam Line High radiation +--ip 1C0:2. annunciation or ind< 3.-e < n .,.

v panel OR

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The200 than containment rem. post accident monitor indication on panel 1C601 greater i

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Attachment E EP-IP-001

.. Revision i Page 13 of 14 CATEGORY - FUEL CLACDING CEGRACATION SITE EMERGENCY (I)

I ( A CR S CR C) -

Degraded ore with possible loss of coolable geometry, as indicated by:

A. (1 AND 2 AND 3) ,

1. Failure of control roc (s) to fully insert on a scram or shutdown indication on full core display, panel IC651.

i AND

2. Uoscale readings on LPRM strings (greater than 94 watts /cm) adjacent to not-fully inserted rods as indicated by LPRM upscale alarms"on panel 1C651.

r i

i AND

3. Reactor coolant activity greater than 300 uCi/cc of equivalent I-i . 131 as determined by sample analysis.

OR 5T Reactor coolant activity greater than 1,000 uCi/cc of equivalent I-131 as determined by sample analysis.

OR CT The containment post accident monitor indication on panel 1C601 greater than 400 rem. ,

l l

MORE NEXT PAGE Page 4 of 35

Attachment E EP-IP-001

.. Revision 1 Page la of 44 CATEGORY - FUEL CLADDING DEGRADATICN GENERAL EMERGENCY (I or II)

I. (A CR B) -

Loss of 2 out of 3 fission product barriers (fuel cladding & reactor coolant pressure bouncary) with potential loss of the third barrier (primary containment), as incicatec by:

A. (1 AND 2)

1. Containment post accident monitor indication on panel 1C601 greater than 400 rem.

AND

2. (a CR b OR c)

a. Containment pressure greater than 40.4 PSIG as indicated on panel 1C601.

OR 57 A visual inspection of the containment indicates a cotential for loss of containment (e.g. a crack in containment concrete at tendon and anchorage or penetration failure).

OR -

c! Other indications of potential or actudi' loss of primary containment.

OR 57 (a AND b) .

a. Reactor coolant activity greater than 1,000 aCi/cc of equivalent I-131 as determined by sample analysis.

AND 5T Actual or potential failure of reactor coolant isciation valves to isolate a coolant leak outside containment as determined by valve position indication on canel IC601 or

visual inspection.

I ~

0R . - -

II (A AND B)

A. Core melt as indicated by: Containment ocst accident monitor indication on panel 1C601 greate- than 2000 rem.

AND 57 Containment high pressure indication or annunciaticn on panel 'C601.

Page 5 of 35

,me W

Attachment E EP-IP-001

.. Revision 1 Page 15 of 44 CATEGCRY - AENCRMAL EVENTS RECUIRING PLANT SHUTCC'.sN UNUSUAL EVENT (I)

I. (A CR B CR C) l Abnormal occu ences which result in the operator taking the plant from

! operating status to a hot shutcown condition sucn as:

1 A. Imolementation of a controlled shutdown in response to a Tecn spec Action statement.

CR 5T Indications or alarms on process or effluent carameters not functional in control room to an extent requiring plant shutdown as a result of significant" loss of assessment or communication capability. (e.g.,

plant computer, safety parameter display system, all meteorological instrumentation.)

OR C. Turoine rotating comconent failure causing the operator to rapidly shutcown the plant.

ALERT (I) -

I. Turbine failure causing casing penetration, as indicated by:

Direct observation or notification received by the Control room operator.

SITE EMERGENCY (I)

I. None GENERAL EMERGENCY (I)

~

I. None .

Page 6 of 35

- = . - -

Attachment E EP-IP-C01

.. Revision 1 Cage 16 of 14 CATESCRY - LCSS CF REACTOR VESSEL INVENTORY UNUSUAL EVENT (I)

(A CR B) -

Valid initiation of an ECCS System as indicated by:

1 A. Initiation of an ECCS System AND low, low, low reactor water level (-

129) annunciation or indication on panel 1C651.

D3 .

B. Initiation of an ECCS System AND High Drywell Pressure annunciation or indication on panel 1C601.

ALERT (I)

I (A CR 8)

Reactor coolant sys:em leak rate greater than 50 gpm, as indicated by:

A. Drywell floor drain pump A or B Hi-Hi alarm on panel 1C601 AND 2 or more drywell floor drain pumps continuously running as indicatec on panel 1C601.

CR -

BT Other estimates of Rx coolant system leakage. "-

SITE EMERGENCY (I)

I. Known loss of coolant accident greater than make-up capacity, as indicated by:

' dater level below (and failure to return to) top of active fuel for greater than three minutes as indicated on fuel zone level indicator on panel 1C601.

. . i

-~

MORE NEXT PAGE Page 7 of 35

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Attachment E EP-IP-001

.. Revision 1 Page 17 of 44 CATEGORY - LOSS OF REACTOR VESSEL INVENTORY l

GENERAL EMERGENCY (I or II)

I. Loss of coolant accident with possibility of imminent release of large l, amounts of radioactivity as incicated by:

I Water level below (and failure to return to) top of active fuel for greater than 20 minutes as indicated on Fuel zone level indicator on panel 1C601.

OR II. (A OR B)

Loss of 2 out of 3 fission product barriers (primary containment & reactor coolant pressure boundary) with potential loss of the third barrier fuel cladding, as indicated by:

A. (1 AND 2 AND 3)

1. High drywell pressure annunciation or incication on panel 1C601.

AND 27~ (a OR b OR c)

a. Containment pressure exceeds 40.4 PSIG as indicated on panel 1C601. _

OR bT A visual inspection of the containment indicates a potential or actual loss of containment (e.g. a crack in containment concrete at tendon and anchorage or penetration failure).

s c7 Containment _ isolation valve (s) fail to close as indicated by valve position indication on panel IC601.

AND 3T- Reactor Vessel level drops below (and fails to return to) top of active fuel for' greater than three minutes as indicated on fuel zone level, indicator om panel 1C601.

OR 57 (1 AND 2)

1. Failure of reactor pressure vessel isolation valves to isolate coolant break outside containment as indicated by valve position indication on panel 1C601 or visual inspection.

AND

2. Reactor Vessel level drops below (and fails to return to) too of active fuel for greater than three minutes as indicated on fuel zone level indicator on panel 1C601.

l Page 3 of 35

- - - -e

. ~ . nm3m

r Attachment E EP-IP-001

.. Revision 1 Page IS of 44 CATEGORY - LCSS OF REACTIVITY CONTROL f UNUSUAL EVENT (I)

I. Inadvertent Criticality, as indicated by:

Unexpected increasing neutron flux indication on panel IC651. g ALERT (I)

I. (A AND B AND C)

Failure of the reactor protection system to initiate and complete a scram which brings the reactor subcritical, as indicated by:

l A. Trip of at least one subchannel in each trip system (RPS A and RPS B) as indicated by annunciators and trip status lights on panel IC651.

AND 5T- Failure of control rods to insert as confirmed by the full core display indication on panel 1C651 or process computer indications.

AND CT- Failure to bring the reactor subcritical confirmed by neutron count rate on the neutron monitoring indication on panel IC651.

SITE EMERGENCY (I)

I. (A AND B AND C)

Ltss of functions needed to bring the reactor subcritical and loss of

, ability to bring the reactor to cold shutdown as indicated by:

A. Inability to insert sufficient control rods to bring the reactor succritical as indicated by count rate on the neutron monitoring instrumentation on panel 1C651.

AND .

57- (1 OR 2 OR 3)

Failure of both loops of standby liquid control to inject into the vessel indicated by: -

- -e r

l 1. low pump discharge pressure indication on panel IC601; l OR J 2. Failure of valve C31-F008 position light on panel 1601 to indicate open:

CR 37 Failure of explosive valves IF004 A and B position lights to indicate open (fired);

AND CT- Rx coolant temperature greater than 200 F as indicated on panel 1.C651.

MORE NEXT PAGE i Page 9 of 35 1

- . ~ . - - -

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..- -_ - -_- - .. . . -- - = - -- __ .-- . _

i 1

1 Attachment E _

EP-IP-001 i

.. Revision 1

! Page 19 of 44 CATEGCRY - LOSS OF REACTIVITY CONTROL l GENERAL EMERGENCY (I) l I. (A AND 3 AND C ANO~0) i s

), Loss of functions needed to bring the reactor subcritical and transient in

progress that

akes release of large amounts of radioactivity in a short i i j  ::eriac possible. i f

)

i A. Trip of at least one subchannel in each trip system (RPSA and RPSB) as

. indicated by annunciation or trip status lights on panel IC651.

I j AND

! , BT Loss of capability to insert all control rods not fully inserted as 4

indicated by instrumentation on panel IC651.

l AND C Loss of SLC system capability to inject as indicated by instrumentation !

on panel 1C601.

t l AND ,

j U- Reactor power greater than 255 of rated as indicated on panel 1C651.

t I

! l I

. t.

! l l t

l  !

h i

i i

B i l i

l

[ l Page 10 of 35

(

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~_. . . .. _ - . _ .-_ _ _ _

l 1

i Attachment E EP-IP-001

.. Revision 1 Page 20 of 44 CATEGORY - T0XIC/ FLAMMABLE GASES UNUSUAL EVENT (I)

, I. Nearcy or on-site release of potentially harmful quantities of toxic or flammable material, as indicated by:

Visual observation or notification received by the control room operator.

ALERT (I)

I. Entry of toxic or flammable gases into the facility, with subsequent habitability proolem, as indicated by:

Visual observati6n, direct measurement or notification received by the control room operator.

l I

SITE EMERGENCY (I)

I. (A AND B)

Toxic or flammable gases enter vital areas, restricting access, and restricted access constitutes a safety probeim as determined by:

A. Shift Supervisor's evaluation. -

t AND BT~ (1 OR 2)

1. Visual observation, direct measurement or notification received by control room operator.

1 03

2. High chlorine level annunciation or indication on panel OC551 with isolation of primary or alternate air intakes.

l GENERAL EMERGENCY t

l I. None i - - ~

J l

Page 11 of 35

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Attachment E EP-IP-001

.. Revision 1 Page 21 of 44 i

CATEGORY - AIRCRAFT / TRAIN ACTIVITY 7

UNUSUAL EVENT (I)

I. Aircraft crash on-site, unusuai aircraft activity ove facility or train derailment or-site, as indicated by:

Visual observation or notification received by control room operator. ,

ALERT (I)

I. Aircraft or missile strikes a station structure as indicated by:

Direct observation or notification received by control room operator.

SITE EMERGENCY (I)

I. (A AND B AND C)

Severe damage to safe shutdown equipment from aircraft crash or missile impact when not 16 cold shutdown, as determined by:

1 A. Visual observation or notification received by control ' room operator. --

$30 -

B. Shift Supervisor evaluation.

AND CT- Reactor Coolant temperature greater than 200 F as indicated on panel IC651.

G5NERAL EMERGENCY (I)

! I. None

- /

l _

1

~_.- .

Page 12 of 35

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Attachment E EP-IP-001

.. Revision 1 Page 22 of 44 CATEGORY - RADIOLCGICAL E.: FLUENT RELEASE UNUSUAL EVENT (I)

{

I. (A OR 9 CR C OR 0)'

l, Radiciogical effluents exceed Technical Specification limits for l instantaneous release, as indicated by:

t A. Building Vent Stack Monitoring System high radiation alarm annunciation or indication on panel CC669 or 0C677.

CR 5T Service Water Effluent high raciation alarm annunciation on panel IC668 or indicati,on on panel IC6001.

CR CT RHR Service Water Loop A or B Rx effluent high radiation alarm annunciation on panel 1C601 or indication on panel 1C600.

~

OR UT Reoort of radiological effluent technical specification limit being exceeded.

ALERT (I) -

3 .

I. ( A OR 3 OR C OR D)

Radiological effluents exceed 10 times the Technical Specification ,

instantaneous limits, as indicated by:

A. Building Vent Stack Monitoring System indication on panel CC669 or OC677.

OR 57 Service Water Effluent radiation indication on panel IC600.

~

OR CT RHR Service Water Loop A or B Rx effluent radiation indication on panel 1C600.

OR UT Report of radiological effluent release exceeding 10 times technical specifications.

MORE NEXT PAGE Page 13 of 35

. s Attachment E EP-IP-001

.. Revision 1 Page 23 of la CATEGORY - RADIOLOGICAL EFFLUENT RELEASE i

SITE EMERGENCY (I)

I. (A OR B)

A. (1 CR 2)  ;

Radiological effluent release corresponds to greater than 50 arine W.3., i or 250mr/hr thyroid for a half-hour or 500 mr/nr W.S. or 2500 mr/hr tnyroid for 2 minutes at the emergency plant boundary as determined by dose projections based on: .

I

1. Building vent stack monitoring system indications on panel CC669  !

or 0C677.

03 '

2. Field monitoring data on-site or off-site.

OR BT (1 OR 2)

Emergency plan boundary dose is projected to exceed 500 mrem within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as determined by dose projections based on:

1. Building vent stack monitoring system indication on canel CC669 or CC677. -

OR 2T Field monitoring data on-site or off-site.

. e b

l MORENkXTPAGE

! Page 14 of 35 l

l

[

f

e 4 Attachment E EP-IP-001

.. Revision 1 Page 24 of 44 CATEGORY - RADICLOGICAL EFFLUENT RELEASE GENERAL EMERGENCY (I) l I. (A OR B) l A. (1 OR 2 CR 3) '

Radiological effluent release correspends to greatsr than 1 r/hr wnole ,

body or greater tnan 5 r/hr to the child thyroid at the emergency plan boundary as determined by dose projections based on:

1. Building Vent Stack Monitoring System indication on panel 0C669 or OC677.

OR

! ZT Field monitoring data on-site or off-site.

OR 5T In plant conditions.

OR BT (1 OR 2 0.1 3)

Offsite doses are projected to exceed 1 rem whole body or 5 rem tnyroia due to the event as cetermined by case projections cased on:

g

1. Building Vent Stack Monitoring System indication on panel CC669.or 0C677.

t Ca ET Field Monitoring. data on-site or off-site.  !

OR 3T In plant conditions.

' i l l

. . e i i  !

t

(

l l

i 4

Page 15 of 35

e 6 Attachment E EP-IP-001

.. Revision 1 Page 25 of 44 CATEGORY - ON-SITE FIRE / EXPLOSION UNUSUAL EVENT (I) l I. (A OR B) i A. (1 AND 2)

{ Significant Fire within the plant, as indicated by

I

-j 1. Activation of fire brigade by Shift Supervisor.

AND 2T~ Duration of fire longer than 15 minutes after time of notification.

OR BT Explosion inside security protected area; with no significant damage to station facilities. As indicated by:

Visual observation or notification received by control room operator.

l ALERT (I)

I. (A OR B)

A. Fire lasting more than 15 minutes and potentially affecting the safe shutdown of the plant. ' -

OR 8. (1 AND 2)

Explosion damage to facility affecting plant operation as determined t by:

~

1. Direct observation or notification received by control room operator. .

AND

2. Shift Supervisor evaluation.

i f

i MORE NEXT PAGE i

Page 16 of 35 1

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Attachment E EP-IP-001

.. Revision 1 Page 26 of JJ CATEGORY - CN-SITE FIRE /EXPLOSICN SITE EMERGENCY (I)

I. (A AND 3 AND C)

Severe damage to safe shutdown ecuipment from fire or explosion, when plant not in cold shutdown, as determined by:

A. Direct observation or notification received by control room operator.

AND 5T- Shift Supervisor evaluation.

AND CT- Reactor Coolant Temperature greater than 200 F as indicated on panel 1C651.

~

GENERAL EMERGENCY (I)

I. None -

~

. . .i t

I I

s ,

i I.

I Page 17 of 35

-__--x- - --

Attachment E EP-IP-001

.. Revision 1 Page 27 of 44 CATE3 CRY - NATURAL PHENC.vENA UNUSUAL EVENT (I) l I. (A CR 3 CR C)

Natural Phencmenon occurrence, as indicatad by: l A. Tornaco imcact on site.

OR BT Hurricane imcact on site.  !

CR .

CT Earthquake ,cetected by seismic instrumentation systems on panel OC696.

! ALERT (I) ,

i I. (A CR S OR C OR 0)

Natural Phencmenen Occurrence, as indicated by:

~

A. Tornado with reported wind velocities greater than 200moh impacting on

site. ,

OR -

. 37 hurricane or sustained gr.ater than 70 mph winds as indicatec on panel CC653. .

i i

CR I CT EarthQJake With greater than operating basis earthquake (CBE) levels as indicated on panel 0C696.

l 03

0. River level celow 72 inches as indicated on panel GC671.

I  !

1 i

I i

MORE NEXT PAGE Page 15 cf 35

Attachment E E?-I?-001

.. Revision 1 Page 2E of aa CATEGCRY - NATURAL PHENCMENA SITE EMERGENCY (I)

I. (A AND B) '

5evere Natural Phenomenon Occurrence, with plant not in cold shutdown as incicated by:

A. Reactor Coolant Temperature greater than 200 F as indicated on panel IC651. -

AND 5-~ (1 OR 2 CR 3 CR ?)

1. Hurricine or sustained winds greater than 80 mph as indicated on panel DC653.

OR 27 Earthquake with greater than Safe Shutdown Earthquake (SSE) levels as indidated on panel OC696. ,

OR 3T River level below 60 inches as indicated on panel 0C671.

CR IT Tornado vith reported wind velocities greater than 220mch .

impacting on site.

GENERAL EMERGENCY I None i 1

i 1

t Page 19 of 35 i

A::achment E EP-I?-001 Revision 1

?sge 29 of d?

CATEGCRY - INJURED /CCNTAMINATED PERSCNNEL UNUSUAL EVENT (I) .

I I. Transportation of externally contaminated injured irdividual from site to offsite mecical facility, as determined appropriate by Shift Suoervisor.

ALERT (I)

I. None SITE EMERGENCY (I)  !

i I. None GENERAL EMERGENCY (I)

I. None -

t

. *. .r l

t

• 1 l

l I

e 1

Page 20 of 35 l

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._ . . .__ - _ = - . = . - _ - . . _ _ _ . ..

i . .

, l l

Attachment E 1 EP-IP-001

.. Revision 1 Page 30 of ??

i CATEGORY - SAFETY / RELIEF VALVE FAILURE

, UNUSUAL EVENT (I) I

. .. 1 I. (A AND E AND C)

Failure of a safety / relief valve to close following reduction in Rx pressure l as indica ed by:

l )

A. Indication of open safety / relief valve on panel 1C601.

AND 57~ Rx Pressure less than 1000 psig as indicated on panel IC651.

AND W C. The open safety / relief valve is not being held open manually by operator action or the Automatic Depressurization System.

o ALERT (1) i

I. None SITE EMERGENCY (I) I

't s.

! I. None I .

GENERAL EMERGENCY (I) l 1, I. None l

l e

i 1

4 i

4 4,

l I i Page 21 of 35

Attachment E EP-IP-001 Revision 1 Page 31 of al CATEGCRY - SECURITY EVENT UNUSUAL EVENT (I)

~ -

I. Security tnreat cr'attemoted entry or attempted sabotage, if ceemed I, acpropriate by Shift Supervisor.

ALERT (I)

I. (A AND B)

Ongoing Security Compromise as determined by: i i

A. Report frcm Security of security safeguards contingency event that I j

results in adversaries commandering an area of the clant, but not  :

controlling shutcown cacability or any vital area. '

l

, AND

' j B. Shift Supervisor evaluation. i i

SITE EMERGENCY (I) i 4

I. (A AND 8)  !

I An on going adversary event threatens imminent loss of pnysical control of '

the plant, as determined by:

i l A. Report from Security of physical attack on the plant involving imminent occupancy of the control room, auxiliary shutdown panels or other vital  !

j area. ,

I

! I AND 57~ Shif t Suoervisor evaluation.

t

' GENERAL EMERGENCY (I) t

! I. (A AND B)

Loss of physical control of the facility as determined by: l 1

l A. Report from Security that a physical attack on the plant has resultad l in unauthorized personnel occupying the control ro,om or any other vital i j areas. - - l AND i 87 Shift Supervisor evaluation. '

i Page 22 of 35

Attachment E EP-IP-001

.. Revision 1 Page 32 of da CATEGORY - LOSS OF AC POWER UNUSUAL EVENT (I) l, I.

(A GR B)

Loss of all off-site power OR loss of all on-site AC power supplies, as indicated by:

A. Loss of power to Startup Transformer 10 AND 20 annunciation or indication on panel OC653.

OR 57 Failure of all diesel generators to start or synchronize indication or annunciation on panel OC653.

ALERT (I)

I. (A OR B)

Loss of all off-site power AND all on-site AC power supplies, as indicated i by:

A. Loss of power to Startup Transformer 10 and 20 annunciation or indication on panel OC653. -

I i AND 57- Failure of all diesel generators to start or synchronize annunciation or indication on panel OC653.

SITE EMERGENCY (I)

I. (A AND B AND C)

Loss of all off-site power and loss of all on-site AC power supplies for greater than 15 minutes, as indicated by:

A. Loss of power tg startup-Transformer 10 AND 20 annunciation or ,

indication on panel OC653.

I AND 57~ Failure of all diesel generators to startup or syn'chronize indication or annunciation on OC653.

AND CT The above conditions exist for greater than 15 minutes.

, GENERAL EMERGENCY (I)

I. None

/

Page 23 of 35 l

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l Attachment E EP-IP-001

.. Revision 1 Page 33 of aa CATEGDRY - LCSS OF DC PCWER UNUSUAL EVENT l I. None ALERT (I)

I. (A AND B)

Loss of all on-site vital DC power as indicated by:

A. Less than 210 volts on the 250 VDC main distribution panel buses, 10652 AND 10662, as indicated by trouble afarms on panel 1C651. ,

i AND  :

1 BT- Less than 105 volts on the 125 VOC main distribution buses; 1D612,  :

1D622, 10632, AND 10642 as indicated by trouble alarms on panel IC651.  !

I NOTE: Buses are not tripced on undervoltage condition.

SITE EMERGENCY (I)

I. (A AND B AND C)

Loss of all vital on-site DC power sustained for greater tnan 15 -inutes, as

! indicated by: .

l' A. Less than 210 volts on the 250 VDC main distribution canel buses, 10552 AND 10662, as indicated by trouble alarms on panel 1C651.

l' AND 5T~ Less than 105 volts on the 125 VDC main distribution tuses; ID612, i 1D622, 10632, AND 1D642 as indicated by trouble alar?,s on panel IC651. i i

AED l C. The above condition exists for -greater than 15 minutes. l NDTE: Buses are not tripped on undervoltage condition. '

GENERAL EMERGENCY (I) - - ' f

?

I. None  !

x.

Page 24 of 35 y - - --m. w. ,----- ---m---rmmgw' 7-- --e-t'-r--,-- T-- -

Attachment E EP-IP-001

.. Revision 1 Page 34 of 44 CATEGORY - INPLANT HIGH RADIATION UNUSUAL EVENT (I)

I. None -

i ALERT (I)

I. (A GR B) ,

Unexoected in plant high radiation levels or airborne contamination which  !

indicates a severe degradation in the control of radioactive material, as indicated by.

A. Are Radiation Monitor reading 1000 cimes normal annunciation on panel i IC601 or indication on panel 1C600.  !

i

! CR l

! B. Airborne contamination levels reported greater than MPC Limits.

! SITE EMERGENCY (I)

I. None l -

l GENERAL EMERGENCY (I) -

t .

i I. None .

t

. - /

l Page 25 of 35

Attachment E EP-IP-001

.. Revision 1 Page 35 of a CATEGCRY - SPENT FUEL RELATED INCIDENT UNUSUAL EVENT (I)

I. None -

ALERT (I) l I. (A OR B)

Unexpected in plant high radiation levels or air ~ orne c contamination which indicates a severe fuel handling accident as indicated by:

, A. Aefuel floor area radiation monitor reading 1000 times normal annunciation on panel 1C601 or indication on panel 1C600.

OR 87 Airborne Contamination levels on refueling floor repor ed greater than MPC Limit.

j l

\'

t f l

A I I

I i

. *- r i  !

l ,

I

I t

MORE NEXT PAGE Page 26 of 35

Attachment E EP-IP-001

.. Rew ision 1 Page 36 of 44 CATEGCRY - SPENT FUEL RELATED INCIDENT SITE EMERGENCY (I OR II) ..

I (A AND B)

Major camage to irradiatec fuel with actual or clear cotential for ,

significant release of radioactive material to tne environment, as indica ed  !

oy:

Drooping, bumping or otherwise rough handling of a new OR fuel bundle j with irraciated fuel in the pool. I i

AND .

BT- (1 OR 2) i

1. Refuel'ing floor area ractation monitor reading 1;JO times normal annunciation on panel IC601 or indication on IC600. l OR 5T Reactor Building vent stack monitoring system high radiation annunciation or indication on panel 0C669 or OC677.

O_R_

II ( A AND 5)

Camace to irraciate fuel due to uncontrolled dec ease in the fuel cool levei-to ceiow the level of the fuel, as incicated by:

4 A. (1 OR 2) ,

, 1. (a AND b)

a. Uncovering of irradiated fuel confirmation by low water level  :

annunciation on panel 0C211.

aND -

ST- A hign seal leak flcs alarm annunciated on CC211.

i OR - - -

2T Visual observation of water level below irradiated fuel in the pool.

AND B- (1 OR 2) -

1. Refueling floor area radiation manitor annunciation on panel 1C651 or indication on panel 1C600.

OR l 2T Reactor building vent stack monitoring system high radiation annunciation or indication on panel CC669 or OC677.

GENERAL EMERGENCY (I) s I. None

? age 27 of 35

. .+w

~

Attachment E EP-IP-001 Revision 1 Page 37 of u CATE3 CRY - CCNTROL ROCM EVACUATION UNUSUAL EVENT (I) . -  :

I. None -

ALERT (1)

I. (A AND B)

Control Room evacuation as indicated by. .

.  ?

A. Initiation of control room evacuation procedures. f i

AND  !

3. Estaolishment of control of shutdown systems from local stations. l SITE EMERGENCY (I) ,

I. (A AND 3)

Celayed Control Room Evacuation indicated by:

A. Initiation of control room evacuation procedures. ,

AND -

c5 Shutcown systems control at local stations not established witnin 15 minutes.

i GENERAL EMERGENCY (I) i  !

I. tione t

I l .

l - -

I I

l 6

L Page 28 of 35

i t . .

1 i

l Attachment E j EP-IP-001

+

.. Revision 1 Page 38 of 44 CATEGORY - LOSS OF DECAY HEAT REMOVAL CAPABILITY L'NUSUAL EVENT (I)

I I. None -

ALEN (I)

. I. (A OR B)

, Loss of some of the decay heat removal capability as indicated by: [

1 A. (1 OR 2') f

, Loss of both RdR service water loops as !.1dicated by:

3

1. Low flow indication or annunciation on panel IC601.  !,

! I i, i

CR 2- Other indication. l i ,

OR l B. Loss of RHR loops A AND B as indicated by low flow indication or

' f l.

annunciation on panel 1C601. , _ _

.m, i SITE EMERGENCY (I) -

t ..

I. (A AND 8 AND C)

Loss of capability to achieve cold shutdown, as indicated by:

l

! A. Loss of main condenser system at indicated by closed turbine stop and  !

bypass valve position _ indications on panel 1C651. j i

AND

) 5- (1 OR 2) f

1. Loss of both RHR service sater loops as indicated by low flow I

)

indication or annunciat-iore on panel OC653. j 1 ,

l OR l 2- Loss of both RHR loops as indicated by flow indication or 1 l annunciation on panel 1C601. -

(

! AND--~

C Reactor Coolant temperature greater than 200"F as indicated on panel 1C651.

i i

MORE NEXT PAGE i Page 29 of 35 i

i i,

~ ~ - - - w mpw

Attachment E EP-IP-001

.. Revision 1 Page 39 of 44 CATEGORY - LOSS OF DECAY HEAT REMOVAL CAPABILITY GENERAL EMERGENCY (I)

I. (A AND B AND C)

Loss of cacaDility to achieve cold shutdown, with possibility of release of large amounts of radioactivity as indicated by: I A. Suppression pool temperature greater than 290 F indicated on the  !

computer output (MAT 12,13,14,15 or 16) l i

END \

B. Loss of main condenser system as indicated by closed turbine stop and l bypass valve position indications on panel 1C651.  ;

AND  !

CT- (1 CR 2)  !

1. Loss of both RHR service water loop as indicated by low flow indication or annunciation on panel 1C601.

OR r II Loss of both RHR locos as indicated by flow indication or .

annunciation on panel 1C601.

k j

l i

l _

.e I

l ~

l i

l I

l Page 30 of 35 i---- - -

r- _,_.-._+-m_._ -

p,m_ y ..,,____.,_,____g,,,,._, ,, _., ._.g, .-_ . , _ , _ , -,_,_,, _ ., e

J . .

l Attachment E EP-IP-001

.. Revision 1 l Page t0 of ta i

CATEGORY - LOSS OF CONTROL ROCM ALARMS AND ANNUNCIATORS UNUSUAL EVENT (I)

I. None -

ALERT (I)

I. Loss of most control room annunciators, as determined by control room operator from direct observation.

SITE EMERGENCY (I)

,! I. (A AND B) l Most annunciators lost and plant transient initiated while annunciators are lost, as indicated by:

l A. Direct observation of control room operator that most annunciators are l I lost. i 4

j AND l BT- (1 OR 2 CR 3 OR 4) .

l 1. Low - Low reactor water level indication on canel IC651 followed  ?

, by ECCS initiation incication on canel 1C601. -

e - ,

! CR l 2. Reactor coolant temperature change greater than 100 F per hour , j 1 indication on recorder TR-1R006 on panel ICC07 (Reactor Bldg.

Elevation 683').

i l OR 37 High Rx pressure indication.on panel 1C651 and followec by scram indication on panel IC651.  !

i OR - . <

4. Any indication that transient has occured or is in procress. -

J l , GENERAL EMERGENCY (I) ,

j

, I. None  !

' I I

i I

i

! L 1

i Page 31 of 35 i

4

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l l

Attachment E

, EP-IP-001

.. Revision 1 Page 41 af 44 CATEGORY - STEAM LINE EREAK UNUSUAL EVENT (I)

I. None -

ALERT (I)

I. (A AND B)

MSIV malfunction causing leakage as indicated by:

A. Valid MSIV closure signal or indication on panel IC601.

AND BT (1 GR 2 OR 3)

1. Main Steam Line Flow indication on flow indicators on panel 1C652.

OR 27 Hign Main Steam Line Tunnel temperature annunciation on panel 1C601 or indication on panel IC614.

OR 3! Main Steam Line radiation indication on panel IC600.

i MORE NEXT PAGE Page 32 of 35

- -. .. . - _ ---- - . . =- . . _ --

~

j Attachment E EP-IP-001

.. Revision 1 -

i Page 42 of 44 I C ATEGORY - STEAM LINE BREAK SITE EMERGENCY (I) -

I. (A CR B OR C OR 0)

Steam line creak occurs outside of containment without isolation, as indicated by:

, A. (1 AND 2) i 1. Failure of both MSIV's in the line with the leak to close as indicated by position indication on panel 1C601.

(a OR b OR c) j a. Hi,gh MSL flow annunciation on panel 1C601 or indication on

panel 1C652.

i CR

b. High steam tunnel temperature annunciation on panel 1C601 or

' indication on panel 1C614. .

OR

{ c7 Other indication of main steam leakage outside cotainment.

CR B. (1 AND 2) i

1. Failure of steam isolation valve HV-F008 and HV-007 to close as indicated on panel 1C601. -

AND i

, 2. (a OR b OR c OR d OR e OR f) I

. a. RCIC steamline pipe routing area high temperature , l j annunciation on panel 1C601, or indication on panel 1C614 i E

b. RCIC equipment area high temperature annunciation on panel 1C601 or indication on panel IC614.

OR

! c7 RCIC steamline high flow annunciation on panel 1C601.

OR dT RCIC steamline.tunnek ventilation high delta temperature l annunciation on panel 1C601. '

l OR l e. RCIC turbine exhaust diaphragm high pressure annunciation on l l panel 1C601. - I

!' M

f. Other indi:ation of steam leakage from the RCIC system.  !

Site Emergency Continued Next Page MORE NEXT PAGE

(-

Page 33 of 35 i

l l

.-,-s-. -r.---n-,,rv--.r.-,.- rr-,_s,,, ,,--,-------_.----me,,-y. ,m-mm, . . , , , ,

s-,---, ,,,y.- --

-,-y_w- --,,w-w,,._,ww. v-,.3 ., , , , ,, , ,,,,, ,

] Attachment E EP-IP-001

. . . Revision 1 Page 43 of 44 CATEGORY - STEAM LINE BREAK 1 -

SITE EMERGENCY (Continued) * ~

j OR- ,

C (1 AND 2) - l

1. Failure of steam isolation valve HV-F002 and HV-F003 to close as '

indicated by position indicator on panel 1C601. ,

AND E (a OR b OR c OR d OR e OR f)

a. HPCI steamline pipe routing area high temperature j annunciation on panellC501, or indication on panel IC614.  !

i OR i

b. HPCI equipment area high temperature annunciation on panel 1C601 or indication on panel IC614.

OR

. E HPCI steamline high flow annunciation on panel 1C601. j OR 8- HPCI steamline tunnel ventilation high delta temperature

~

l annunciation on panel 1C601. ,

i OR E HPCI turbine exhaust diaphragm high pressure annunciation on panel 1C601. , l.

OR i f. Other indication of steam leakage from the H?CI system.

1 I

OR 5- Any other unisolatable steam line breaks.  !

ml

_. GENERAL {MERGENCY (I)

I. None '

t l

C t _ __ __ _ _ . _ _ _ . . _ . . _ . _ . _ _ ___ _. .

Page 34 of 35

Attachment E EP-IP-001

.. Revision 1 Page 44 of a4 CATEGCRY - GENERAL UNUSUAL EVENT (I)

I. Plant concitions-exist that warrant increased awarene s on the part of plant management or state and/or local offsite authorities.

ALERT (I) ,

I. Plant conditions exist that warrant precautionary activation of Technical -

Suoport Center and placing Emergency Operations Facility personnel and other-key emergency personnel on standby. ,

SITE EMERGENCY (I)

I. Plant conditions exist that warrant activation of all emergency centers and monitoring teams 03 a precautionary notification to the public near the site.

, GENERAL EMERGENCY (I) ,

I. Plant conditions exist that make release of large amounts of radioactivity in a short time periods possible, AND notification of recommended protective action to the puolic near the site snould be considered.

t 1

I .

l i

t I . , _ _

Page 35 of 35 e

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)

1 PROCEDURE COVER SHEET PENNSYLVANIA PC',vER & LIGHT CO. 6 SUSQUEHANNA STEAM ELECTRIC STATION EP-IP-035 Revision 1 EMERGENCY VENT MONITOR SAMPLING Page 1 of 13 Effective Date (n @ R3 Expiration Date (o-as-E Revised Expiration'Date l

% N. M P M fD M

.g 7l: -

' ? :l * 4 ih WM Y 4 '

~ h Q *Q (in'g

• Q ) .

y

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Prepared by W6 ) uML '

Date d - / 7'f _8 Reviewed by f/N h M [ b u d[g- -. - Date 6-2/-97 l

PORC Review Required es (T ' o ;/) '

Approved by c -

Date . ([2] J Section Head' ' / '

/ /'

PORC Meeting Nunber T3-W3 Date 4 T3 Superintendent of Plant b2m Date _ $ 9 T W E

FCRM 20-QA-101-1, Rev. 1 Page 1 of 1

., e >+ --gge-r -- - , , - - . . , , , . - _ , . . - _ _ - . _ _ _ ,, ,_. _ , - . . . . ~ - . _m

EP-IP-035 Revision 1

.. Page 2 of 13 TABLE OF CONTENTS SECTI0tj - -

PAGE 1.0 PURPOSE -

3 2.0 SCOPE 3

3.0 REFERENCES

3

~

4.0 RESPONSIBILITIES 3 5.0 DEFINITIONS 3

6.0 INSTRUCTIONS 3 ATTACHMENTS ATTACHMENT PAGE A Action Step - Emergency Director . 4 OSC Coordinator - -

TSC Coordinator .

B Act. ion Step - Chemistry Sampling Team 5 C Action Step - Sample Preparaticn anc Analysis 9 D Data Sheet (FORM EP-IP-035-1) . 12 E Vent Monitor Samples Data Sheet (EP-IP-035-2) 13

, -. /

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~-- -- - . - - -

w----- -.-g- - e.

4 EP-IP-035 Revision 1

.. Page 3 of 13 1.0 PURPOSE The purpose of this procedure is to outline the steps-required for

collecting grab samples and changing filters from the ventilation exhaust systems.

2.0 SCOPE To provide the Chemistry Department with instructions and guidelines for obtaining grab samples and changing filters from the Reactor Building, Turbine Building, and the Standby Gas Treatment ventilation exhausts during Emergency Conditions.

3.0 REFERENCES

l 3.1 SSES Emergency Plan 3.2 EP-IP-010, In-Plant Emergency Monitoring ,

3.3 EP-IP-033, Oose Assessment and Protective Actions 3.4 EP-IP-042, Chem Lab Emergency Preparation

>e 4.0 RESPONSIBILITIES .

4.1 The EMERGENCY DIRECTOR or designated C00RDINATOR is responsiole for instructing, directing and dispatching CHEMISTRY SAMPLING TEAM.

4.2 The CHEMISTRY SAMPLIN'G TEAM is responsible for obtaining grab samples I

and changing filters.

1 j S.0 DEFINITIONS

+

SCBA - Self - Contaihed Breathing Apparatus 6.0 INSTRUCTIONS ,

6.1 The EMERGENCY DIRECTOR or designated COORDINATORS will follow instructions in Attachment A, Action Step-EMERGENCY DIRECTOR-COORDINATORS.

6.2 The CHEMISTRY SAMPLING TEAM will follow instructions in Attachment 8, Action Step-CHEMISTRY SAMPLING TEAM.

6.3 Chemistry personnel will follow instructions in Attachment C, Action Step, SAMPLE PREPARATION AND ANALYSIS.

- - . . _ _ . _ , _...-.__~__-.-..__m- ._. -_. _ _ _ ._ ..,__ _ _ -..._ _ _ .. _ _ --.- ..-- _ ._...__ _ _ _ __.

! Attachment A EP-IP-035

_ Revision 1 Page 4 of 13 i

. ACTION STEP

. EMERGENCY DIRECTOR -

OSC COORDINATOR j

TSC COORDINATOR I

CHECK i

I A.1.0 The EMERGENCY DIRECTOR or designated COORDINATOR will:

A.1.1 Direct the activities of the CHEMISTRY SAMPLING TEAM A:1.2 Brief TEAM on existing emergency and instruct personnel as to what samples are required.

A.1.3 Appoint a TEAM LEADER.

NOTE: CONSIDER SPECIAL REQUIREMENTS FOR MINIMIZING INTERNAL AND EXTERNAL EXPOSURE i

, PER EP-IP-033, " DOSE ASSESSMENT AND PROTECTIVE ACTION."

A.1.4 Instruct the RADIO COMMUNI'CA70R in TSC (if TSC is activated) to assign code name to TEAM and to .

maintain communications with TEAM LEADER.

A.1.5 Coordinate with the RADIATICN PROTECTION COORDINATOR respiratory prot'ective devices and j protective clothing requirements needed for this l sampling function. Cbtain latest survey results i from Reactor Building S13' (if available) and readings from ARM 14 and ARM 15.

\ . . <

i A .1. 6 ~ Assign additional SAMPLING PERSONNEL to. assist or relieve TEAM as circumstances dictate.

l A.1.7 Advise the EMERGENCY DIRECTCR immediately of any l conditions or survey results that may be of j assistance in evaluating the EMERGENCY.

I i

A.1.3 Inform the EMERGENCY DIRECTOR of the CHEMISTRY SAMPLING TEAM results.

l l

l Page 1 of 1 l

I

9 Attachment B EP-IP-035

.. Revision 1 Page 5 of 13 ACTION STEP CHEMISTRY SAMPLING TEAM - -

CHECK B.1.0 The CHEMISTRY SAMPLING TEAM will:

8.1.1 Upon notification of an Emergency Condition, report immediately where instructed for briefing and assignment.

B.1.2 Obtain from the COORDINATOR:

8.1.2.1 Specific sample requested B.I.2.2 Anticipated area radiation readings

. including the readings from the two ARM's located on the Reactor Building 818' level.

B.1.2.3 Special Instructions including additional protective clothing requirer,ents, respiratory protection requirements, and radiation detection instrument selection.

B.1.3 Ensure Chemistry Lab is prepared per EP-IP-042,

" Chemistry Lab Emergency Preparation" B.1.4 A'ss'emcle or locate the following equipment:

B.1.4.1 Respiratory protective devices and protective clothing as specified by

. . COORDINATOR.

B.1.4.2 Hi-range dosimetry and extremity dosimetry B.1.4.3 Survey meter B.1.4.4 Grab sample apparatus with particulate filter and silver zeolite cartridge installed B.1.4.5 Stopwatch Page 1 of 4

, , - - - - - -g

4 Attachment B EP-IP-035 1

,_ Revision 1 Page 6 of 13 B.1.4.6 Tweezers

~

B.1.4.7 Particulate filters B.1.4.3 Silver :eolite cartridges B.I.4.9 Plastic bags B.1.4.10 Plastic petri dish B.1.5 Perform instrument checks on survey meter.

B:1.6 Don appropriate protective clothing and respiratory protective device as directed by COORDINATOR.

i B.1.7 Assure that TLD and SRD are worn.

B.1.8 Ensure survey meter is operational and on highest scale before leaving chemistry laboratory.

B.1.9 Proceed to Vent Monitor Samoling Station and while enroute continuously monitor radiation levels and

! the status of CAM's and ARM's..

B.1.9.1 If general area radiation levels exceed 1,000 mrem /hr., retreat to a low

background area and notify the COORDINATOR.

B.1.9.2 If.your total quarterly whole-body exposure approaches 2,500 mrem, retreat to a low background area and notify the l . . COORDINATOR.

B.1.10 After reaching the Vent Monitor, check existing area radiation levels and report to the COORDINATOR. ,

B.1.11 Record Stack Flow (CFM) of the Vent Monitor desired.

B.1.12 Secure FAAM by pressing the Vacuum Pump STCP button on the Air Monitor panel. Record Time.

B.1.13 Shut valve V-1.

Page 2 of 4

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• 4 ,

Attachment B EP-IP-035

_ Revision 1 Page 7 of 13 B.1.14 purge noble gases from the system by pressing the

- FLUSH button on the FAAM Observe V2 open and V5

- - close.

B.1.15 Allow the systen to purge for two (2) minutes and then end the purge by pressing the FLUSH button on the FAAM.

B.1.16 Remove the installed charcoal cartridge and particulate filter (place particulate filter in plastic petri dish).

8.1.16.1 Monitor cartridge and filter during removal for potential high radiation levels.

B.1.16.2 If cartridge or filter reads > 25 mrem /hr" on contact, place it in lead porta pig and leave at the Vent Monitor.

B.1.16.3 If cartridge or filter reads < 25 mrem /hr on contact, place it in plastic bag for transport to Chemistry Lab.

B.1.16.4 Record contact dose rates for cartridge and filter.

8.1.17 I.ns. tall new particulate filter and silver zeolite charcoal cartridge in the FAAM. Record time of change-out. .

l B.1.18 Install the Vent Monitor Grab Sample apparatus to the FAAM.by: attaching it to the local sample connections. The particulate side is connected to V-4 and the gas sampling end is connected to V-3.

B.1.19 Ensure the stopcocks on the -Vent Monitor Grab

! Sample apparatus are open.

8.1.20 Open valves V-3 and V-4.

t l

l Page 3 of 4 Tp mgr'---T*--T'- N =' *"

q Attachment B EP-IP-035

._ Revision 1

! Page 8 of 13 B.1.21 Press the Vacuum Pump START button on the Air 3

. -Monitor panel and simultaneously begin timing the sampling period and monitoring the dose rate.

8.1.21.1 Record sample flow rate from sample flow rate gauge.

B.1.22 When reading on contact is approximately 10 mrem /hr. above background or after 5 minutes of sampling, secure sampling by pressing Vacuum Pump "STOP" button on the Air Monitor panel.

8:1.23 Record sample duration, date and time.

B.1.24 Close valves V-3 and V-4, and open valve V-1.

1 B.1.25 Close the stopcocks on the Vent Monitor grab sample apparatus.

B.1.26 Remove the Vent Monitor Grab Sample apparatus from the FAAM and place it in a plastic bag.

I B.1.27 Restart the FAAM by pressing'the Vacuum Pump

" START" Button on the Air Monitor panel. ,

B.1.28 Notify the COORDINATOR that the sample has been taken and the FAAM has been returr.ed to operation.

B.I.29 Tiansport samples to the chemistry laboratory for I analysis.

.c l

t.

i f

Page 4 of 4 l

4 m_--,.m__,__.-___ _____..__,__.,_____..((.____,.___

_ _ _ _ . _ . . . , _ _ , , , , , _ . _ . _ _ , _ . . _ . _ , , , _ . _ _ _ , . . . , _ , , _ _ , _ , , _ , _ . . _ , . _ _. . [

_ _ _ _ . - - _ _ _ _ _ _ _ - _ _ _ _. _____ _ _ _ _ _ _ _ _ _ _ ~ _ __ .__ __

i i

a

Attachment C

! EP-IP-035

! .. Revision 1 Page 9 of 13 i

f ACTION STEP

- SAMPLE PREPARATION AND ANALYS?S CHECK i C.1.0 Chemistry Personnel will:

C.1.1 Place the composite iodine cartridge and e i particulate filter (if returned to the Chem. Lab) {

j and the vent monitor grab sample apparatus in the fume hood in the Low Level Radiochemistry Lab.

I C'.1. 2 Disassemole the grab sample apparatus.

C.1.3 Place the particulate filter in a plastic Petri dish, wrap in clean plastic film, and place in clean plastic bag. Record dose rate on contact.

i C.1.4 Blow instrument air through the iodine cartridge

! for at least 1 minute.

C.1.5 Wrap it in clean plastic film, place in a clean plastic bag, and record dose

• rate on contact.

C.I.6 If contact dose rates on composite cartridge andlor particulate filter are < 25 mrem /hr., wrap in clean plastic film and put in clean plastic bag.

i

. 1 l NOTE: If contact dose rate on the gas grab sample container < .5 mrem /hr then l proceed to step c.1.15.

C . I . 7,, Place a rubber septum en one end of the gas 1 container.

C.1.8 Remove 1 ml of air from a new labelled gas vial ~

using a gas tight syringa.

i C.1.9 Open the stopcock on the end of the gas grab sample j container and transfer 1 ml of gas into the partially evacuated gas vial.

t j C.1.10 Obtain an approximate contact dose rate for the

,' diluted sample.

l i Page 1 of 3

- - . . - - - w -- ..- .

.----r-.,,----,,,- ,.-,w,w--mrm.m .we---.--rwe-s-*++w-w,_+-enwe-s-w-y e-~-

Attachment C EP-IP-035

.. Revisien 1 Page 10 of 13

~~

C.1.11 Using the dose rate from Step C.1.10 and the following table as a guide, cetermine the approximate number of dilutions which will give a gas vial a contact dose rate of less than 0.5 mr/hr.

Sample Vial I mi to 14.7 ml Dilution Vol. of Dose Rate (mr/hr.) Dilutions required Factor Orio. Samole (ml)

<0.5 count as is 14.7 1 0.5 - 8 1 231 6.37E-2 8-12 2 3623 4.06E-3 120-1900 3 5.69E4 2.53E-4 1900-30,000 4 8.93E5 1.65E-5 30,000-500,000 5 1.40E7 1.05E-6 500,000-7,000.C00 6 2.20E3 6.63E-3 C.1.12 Based on the number of dilutions required, remove 1 ml of air from new labeled gas vials using a gas, tight syringe.

C.1.13 Make successive dilutions by transferring 1 ml aliquots of gas into the partially evacuated gas vials.

C.1.14 Circle the numoer of dilutions and record vial identification and contact dose rate of final diluted sample.

C.1.15 Wrap the gas container / vial in clean plastic film j and place in a clean plastic bag.

C.1.16 Take samples to Counting koom for analysis (including comoosite iodine cartridge and particulate filter if < 25 mrem /hr. on contact).

C.1.17 Perform a quantitative isotopic analysis on the samples, decay correcting to the time of sampling.

x Page 2 of 3

Attachment C EP-IP-035

.. Revision 1 Page 11 of 13 C.I.13 Record: count date, time, and geometry on the Data heets and staple together.

1 .

s Page 3 of 3

.._e_. _

o -

Attachment 0

. EP-IP-035 VENT MONITOR SAMPLES DATA SHEET ~

Revision 1 Page 12 of 13 Ref. Steo B.1.2.1 Sample Source Team Members - -

~

B.1.11 Stack Ficw cfm B.1.12 Date/ Time /

B.1.16.4 Dose rate on contact: Cartridge mrem /hr. Filter mrem /hr.

, 8.1.17 Cartridga changed Filter changed l

l B.1.21.1 Grab sample.- Flow rate c fi.-

8.1.23 Date/ Time / Duration Grab. Grab. Grab.  !

Comp. Comp.

Samole Part. Iodine Gas Part. Gas No. .

Oose Rate mrem /nr.

Count Date Count Time By Geometry C.I.13 Samole Dil.1" Dil.I Dil.3 Dil.4 011.5 Dil.6 011.7 Vial ID Dil. Factor 14.7 231 3623 5.69E~4 8.93E5 1.40E7 2.20ES Dose Rate mrem /hr Vol. of Orig. ,

Samele (ml) 1 6.37E-2 4.06E-3 2.58E-4 1.65E-5 1.05E-6 6.68E-S FORM EP-IP-035-1, Rev. O, Page 1 of 1

~ ~~

Attachment E EP-IP-035

.. Revision 1 Page 13 of 13 VENT MONITOR SAMPLES DATA SHEET Sample Source i

Cate/ Time .

Noble Gases Activity at Samole Time (uCi/cc)

Kr-85 KR-S5m

~

Kr-37 Kr-88 Xe-133 Xe-135 Xe-138 Iodine I-131 I-132

! I-133 l .

I-134 I-135 - - e Particulate

~

Rb-88 .

Rb-89 Cs-138 Sa-139 Ba-140 FORM EP-IP-035-2, Rev. O, Page 1 of 1 l

l