ML20071J980

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Revised Hope Creek Event Classification Guide
ML20071J980
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 07/15/1994
From:
Public Service Enterprise Group
To:
References
PROC-940715, NUDOCS 9407290183
Download: ML20071J980 (41)
v • d • e


Text

g PUBLIC SERVICE ELECTRIC & GAS COMPANY 07P23/94 DOCUMENT DISTRIBUTION NOTZCE PAGE 1 OF 1 4

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SHT/

CLASS DOCUMENT ID VOL INST REV STAT TYPE FORMAT OTY PROC ATT. 03 000 008 A HECG H 001 i PROC ATT. 04 000 007 A HECG H 001 '

PROC HECG-TOC 000 035 A HECG H 001 PROC SECT. II 000 002 A HECG H 001 PROC SECT. III 000 007 A HECG H 001 PROC SECT. 01 000 006 A HECG H 001 PROC SECT. 06 000 005 A HECG H 001 PROC SECT. 17 000 006 A HECG H 001 PROC SIG. ATT. 000 030 A HECG H 001  !

PROC SIG. I-18 020 A HECG H 001 l

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'0Jb[0 b

0 PLEASE SIGN AND DATE THIS NOTICE TO ACKNOWLEDGE RECEIPT 'ghI ,

AND RETURN WITHIN 5 WORKING DAYS TO: I PSE&G DDG/MC N04 PO BOX 236 HANCOCKS BRIDGE, NJ 08038 TO CHANGE YOUR DISTRIBUTION STATUS, PLEASE CHECK THE APPROPRIATE SPACE BELOW: '

REMOVE FROM DISTRIBUTION CHANGE COPYHOLDER INFORMATION

__ SEE MY INSTRUCTIONS ABOVE 9407290183 940715 i COPYHOLDER SIGNATURE: - PDR ADOCK 05000354 DATE: I F - PDR {

DDG USE ONLY: DATA ENTRY COMPLETED:

_- 1

4 1

HOPE CREEK GENERATING STATION

/' EVENT CLASSIFICATION GUIDE

' July 15, 1994 CHANGE PAGES FOR REVISION #35 The Table of Contents forms a general guide to the current revision of the Hope Creek ECG. The changes that are made in this TOC Revision #35 are shown below. Please check that your revision packet is complete and remove the outdated material listed below:

ADD REMOVE Pace Descriotion Rev. Pace Descriotion h l Table of 35 All Table of 34 All Contents (TOC) Contents (TOC)

All Sec. Sig. 1-18 21 All Sec. Sig. 1-18 20 All Sec. 11 2 All Sec. 11 1  !

Sec, iii 7 All Sec. iii 6 All Sec. 1 6 All Sec. 1 5 All l

Sec. 6 5 All Sec. 6 4 i All  :

I Sec. 17 6 All Sec. 17 5 All 2

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HC-ECG 1 Of 1 i i

i 4

l HOPE CREEK GENERATING STATION EVENT CLASSIFICATION GUIDE O July 29, 1994 CHANGE PAGES FOR REVISION #36 j The Table of Contents forms a general guide to the current revision of the Hope Creek ECG. The changes that are made in this TOC Revision #36 are shown below. Please check that your revision ,

packet is complete and remove the outdated material listed below: l l

ADD REMOVE Pace pescriotion Rev. Pace Descriotion Rev.

All Table of 36 All Table of 35 Contents (TOC) Contents (TOC)  ;

All Sig. Att. 30 All Sig. Att. 29 All Att. 3 8 All Att. 3 7 i

I All Att. 4 7 All Att. 4 6 O

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CONTROUj$PY 4

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i HOPE CREEK

! 1 EVENT CLASSIFICATION TABLE OF CONTENTSGUIDE 'I July 15, 1994 EFFECTIVE SECTION TITLE REV. PAGES DATES T.O.C. Table of Contents 35 2 July 15, 1994 Sig. 1-18 Section Identification / Signature Page 21 2 July 15, 1994 Sig. Att. ECG Attachments / Signature Page 29 2 June 24, 1994

1. Introduction 2 7 Jan 7, 1994
11. Cross Reference - Event to Requirement 2 10 July 15, 1994 i'ii. Cross Reference - Attachment to Events 7 1 July 15, 1994
1. REACTOR COOLANT LEAKAGE /LOCA 6 1 July 15, 1994
2. STEAM BREAK OR SRV FAILED OPEN O 2 May 26, 1989
3. FAILURE TO SCRAM 2 1 Dec 21, 1992
4. LOSS OF DECAY HEAT REMOVAL -

2 1 Aug 21, 1992 3 2 Dec 21, 1992

[~' FUEL DAMAGE / DEGRADED CORE

\s. FISSION PRODUCT BOUNDARY FAILURE 5 1 July 15, 1994

7. RADIOLOGICAL RELEASES / OCCURRENCES 5 5 Jan 28, 1994
8. NON-RADIOACTIVE LEAK / SPILL 3 2 Jan 7, 1994 (toxic gas, oil spill, hazmat)
9. ELECTRICAL POWER FAILURE 3 2 Jan 7, 1994
10. LOSS OF INSTRUMENTS / ALARMS / COMMUNICATIONS 4 2 May 10 1993
11. CONTROL ROOM EVACUATION O 1 May 26, 1989
12. 4 6 Jan 7, 1994 l QUAKE / STORMS (earthquake, floods, etc ) wind,
13. SITE HAZARDS 1 5 Aug 21, 1992 (aircraft crash, missiles, . explosions, etc.)  :
14. FIRE 3 1 Jan 7, 1994

/

15. PERSONNEL EMERGENCIES / MEDICAL 3 2 Jan 7, 1994 j
16. SECURITY EVENTS /FFD 5 3 Jan 7, 1994
17. PUBLIC INTEREST ITEMS 6 3 July 15, 1994 j
18. TECH SPECS / PLANT STATUS CHANGES 10 5 Jan 7, 1994

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HCGS Rev. 35

ECG T.C.C.

4 Pg. 2 of 2 EOPE CREEK EVENT CLASSIFICATION GUIDE TABLE OF CONTENTS - (Continued)

July 15, 1994 EFFECTIVE ,

TITLE REV. PAGES DATE ATTACHMENT 12 16 May 21, 1994

1. Unusual Event
2. Alert 7 7 May 21, 1994
3. Site Area Emergency 7 7 May 21, 1994
4. General Emergency 6 9 May 21, 1994
5. Reserved
6. CM1 Log (UE/A/SAE) 18 10 May 21, 1994
7. CM1 Log (GE) 18 10 May 21, 1994
8. CM2 Log 13 15 Apr 29, 1994
9. Non-Emergency Notifications Reference 17 3 June 24, 1994 l
10. One Hour Report - NRC/ Region 1 5 July 27, 1990 One Hour Report - NRC/ OPS (Security) Sept 27, 1991

(' 3 5 5 Apr 26, 1991

\sa . One Hour Report - NRC/ OPS 3

13. Reserved l
14. Four Hour Report - NRC/ OPS 2 5 July 27, 1990
15. Environmental Protection Plan 3 3 Sept 27, 1991 l
16. Spill / Discharge Reporting 5 10 Jan 7, 1994
17. Four Hour Report - Fatality / Medical 4 7 Apr 21, 1993
18. Four Hour Report - Transportation Accident 1 6 July 27, 1990
19. Twenty Four Hour Report - FFD 1 3' Sept 27, 1991 l
20. Twenty Four Hour Report - NRC/ OPS '2 5 July 27, 1990
21. Reportable Event - LACT /MOU 0 2 May 26, 1989
22. 'Other/ Engineering 2 3 Sept 27, 1991
23. Written Reports /LERS/Other 2 9 Jan 7, 1994  ;

)

HCGS' Rev. 35

, 3 , c _e . --.-i,y-

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

EC3

ATT 3 99 102.7

' - . UNIHOL C CUPY !!

65 4 ATTACHMENT 3 SITE AREA EMERGENCY l 4

l Table of Contents i Page l Emergency Coordinator (EC) Log Sheet 2 I.

Reporting 6 II.

Initial Contact Message Form (ICMF) 7  ;

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HCGS Rev. 8 i

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EC3

' ATT 3 Pg. 2 of 7 ,

O I. EMERGENCY COORDINATOR LOG SHEET Initials ,

INSTRUCTIONS

1. This is a permanent record.
2. Each step shall be initialed or marked N/A as, appropriate. ,
3. Emergency Coordinator (EC) responsibility is fulfilled by:

name

Title:

i (SNSS/EDO/ERM)

Notify the Control Room '

( EC A. Declare a SITE AREA EMERGENCY.

staff and call the communicators to the Control Room.

Initiating ECG Section Condition  !

)'

Declared at hrs on date l time I

NOTE J

If directed to implement this attachment due to a

" Reduction" of the event, proceed to Section "C" and l DO NOT implement Section "B".

l B. NOTIFICATIONS j

1. Check appropriate boxes and provide a brief EC description of the event on the INITIAL CONTACT MESSAGE l FORM (ICMF) (pg 7 of this. attachment). Complete, approve, and provide ICMP to the Designated Communicator

, (CM1).

HCGS Rev. 8

ECB 4 ATT 3 Pg. 3 of 7 O

B. NOTIFICATIONS (cont)

Initials i l

2. Direct the Designated Communicator (CM1) to EC implement Attachment 6 and make the notifications on the Communications Log within the time limits specified.
3. Direct the Secondary Communicator (CM2) to implement EC Attachment 8.
4. Notify the Salem SNSS (NETS X5127; 9-339-5200).

EC Direct the implementation of EPIP 101S, Section 3.2.

C. SUPPORT EC If not done previously, direct the OSC Coordinator to '

activate the OSC in accordance with EPIP 202H. ,

D. EMERGENCY PLAN IMPLEMENTATION ]

EC If the EC is the EQQ or SNSS, implement EPIP 103H, " Site Area O Emergency."

OR If the EC is the EBM, implement EPIP 401 and perform the .

following:

1. Notify the EDO of the change in Emergency Classification Level, the time of declaration, and direct the EDO to implement EPIP 103H, " Site Area Emergency." ,
2. Notify EOF staff of the change in emergency classification.

E. SECURITY ,

i EC For security event, notify the PSE&G Security Supervisor [

(X2222 to implement the Security Contingency Plan and Procedures.

NOTE  !

The Station Status Checklist shall be transmitted every 30 minutes or immediately if a significant change in station status occurs.

HCGS Rev. 8 s > . e. > - -

ECG

' ATT 3 Pg. 4 of 7

<- l s

EC Log Sheet (Cont.) j l

Initials l 1

F. TECHNICAL COMMUNICATIONS l

l 1. Upon receipt of the Station Status checklist (SSCL)

! EC from the CH2, review and approve for transmittal.

l Implement more frequently for significant station status change.

2. Ensure completion and approval of the NRC Data Sheet EC form.

1 a) Obtain the form (both pages) from the CM2 (Att. 8) {

b) Provide the approved form to the CM2 for transmittal i to the NRC as soon as possible, but not to exceed '

ONE HOUR.

NOTE:

(~3 As manpower permits, the Emergency Coordinator may

( ,) assign an additional communicator (preferably an RO or SRO) to provide continuous updates to the NRC. The assignment of an additional communicator should not be made if personnel being considered are required to mitigate the event or to complete high priority Emergency Response functions.

c) Notify the NRC of any significant changes in Plant Status, Emergency Status, or any actions taken in accordance with 10CFR50.54(x).

d) Direct CM2 to log or document (via NRC Data sheet) any additional information provided to the NRC.

This includes, but is not limited to, changes in Plant Status, Emergency Status, or any actions taken in accordance with 10CFR50.54 (x) .

3. When turning over EC duties ensure your communicators EC are directed to turnover notifications responsibilities to the facility being activated.

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HCGS Rev. 8

h. . . >

CC3

  • ATT 3 Pg. 5 of.7 O

EC Log Sheet (Cont.)

i Initials G. PRECAUTIONARY PROTECTIVE ACTION RECOMMENDATION (PAR) i EC 11 a Precautionary PAR is developed with no escalation of the emergency status, THEN complete a new working copy ICMF (PAR Upgrade) for this Attachment and direct the CM1 to make new notifications with a clean copy of Attachment 6.  :,

i H. EMERGENCY ESCALATION EC 11 the event classification escalates above a SAE, THEN exit this attachment and implement a new attachment as directed by.

the classifying section EAL.

I. RELIEF / TURNOVER EC 11 relieved as EC prior to change in event classification, i THEN turnover responsibility for this attachment to the ,

oncoming EC and document your relief below and in EPIP 103H.

assumed EC' duties at hrs.

name time I J

J. REPORTING EC l Ensure that appropriate reports are made IAW Section II (page 1

6) of this Attachment.

K. RECORD 8 EC Ensure that all completed documents related to this Event are forwarded in accordance with reporting requirements of Section II of this Attachment. -

l 1

HCGS Rev. 8 I

I i

ECG

' ATT 3 Pg. 6 of 7

. r'x s,

II. REPORTING Instructions

1. This is a permanent document - all pages of this Attachment.
2. Appropriate documents shall be appended to this form and the package expedited through all steps.
3. Responsible person shall initial each step.

Initialg i

1. Ensure that an Incident Report is prepared.

SNSS

2. Forward this Attachment, the Incident Report, and any SNSS supporting documentation to the Operations Manager (OM) .

Review the Incident Report and any other relevant

( OM 3.

information for correct classification of event and  ;

corrective action taken. .

4. Contact tha LER Coordinator (LERC) and request that OM the required reports be prepared. Provida this Attachment and any other supporting documentation to the LERC.
5. Prepare required reports. ECG Attachment 23 may be LERC used as a guide for reporting requirements.

Report or LEh Number

6. When no longer reqv, red send this attachment and LERC appended documents vs the Emergency Preparedness Manager (EPM). ,
7. Forward this Attachment package to the Central EPM Technical Document Room (CTDR) for microfilming.

HCGS Rev. 8

CCG j ATT 3  ;

Pg. 7 cf 7 I i

INITIAL CONTACT MESSAGE FORM r^N

- I. THIS IS , COMMUNICATOR IN THE CONTROL ROOM TECHNICAL SUPPORT CENTER EMERGENCY OPERATIONS CENTER 1

AT THE HOPE CREEK NUCLEAR GENERATING STATION.  !

THIS IS NOTIFICATION OF A SITE AREA EMERGENCY WHICH WAS ,

DECLARED AT ON .

(TIME - 24 HOUR CLOCK) (DATE)

I THIS IS NOTIFICATION OF A PROTECTIVE ACTION RECOMMENDATION UPGRADE WHICH WAS MADE AT ON .

(TIME ~- 24 HOUR CLOCK) (DATE)

II. ECG SECTION INITIATING CONDITION DESCRIPTION OF EVENT:

I l

THERE IS NO RELEASE IN PROGRESS. - see NOTE below for I

l THERE IS A RELEASE IN PROGRESS. ,

release definition 33 FT. LEVEL WIND SPEED: WIND DIRECTION (FROM):

(MPH) (DEGREES)

IV.

NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME ]

Sector (s) Distance-Miles l WE RECOMMEND EVACUATION AS FOLLOWS l

b] WE RECOMMEND SHELTERING AS FOLLOWS l

1 EC Initials Time 1 (EC Approval to Transmit ICMF) l NOTE: Release is defined as: Plant Effluent > Tech Spec Limit of

,_, 1.20E+4 uCi/sec Noble Gas or 1.70E+1 uCi/sec I-131.

Rev. 8 HCGS

i EC3

' ATT 4 Pg. 1 of 9 CONIPOL COPYif ATTACEMENT 4 65  :

i l

GENERAL EMERGENCY f

Table of Contents Page I. Emergency Coordinator (EC) Log Sheet 2 l II. Reporting 6 Predetermined Protective Action 7 Recommendations (flowchart)

Protective Action Recommendation Worksheet 8 Initial Contact Message Form (ICMF) 9 l O L

l l

O HCGS Rev. 7

- - - _ _ - - - - _ - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3

EC3

  • ATT 4 Pg. 2 of 9 0 .

I. EMERGENCY COORDINATOR LOG SHEET Initials INSTRUCTIONS

1. This is a permanent record.
2. Each step shall be initialed or marked N/A as appropriate.
3. Emergency Coordinator (EC) responsibility is fulfilled by: .

name

Title:

(SNSS/EDO/ERM)

A. Declare a GENERAL ENERGENCY. Direct the Communicators to EC be prepared to make notifications.

O ECG Section Initiating Condition Declared at hrs on time date NOTE A Protective Action Recommendation (PAR) shall be made on the Initial contact Message Form (ICMF) .

B. PROTECTIVE ACTION RECOMMENDATION (PAR)

1. Refer to page 7 of this attachment and choose the most EC appropriate Predetermined PAR. The worksheet spage 8) should be used to determine the affected dowr> ind sectors.
2. If immediately available from the SRPT (RAC or RSM),

EC obtain a Radiologically Based PAR for comparison.

3. Compare the Predatermined PAR and the Radiologically EC Based PAR and choose the most conservative for inclusion on the ICMF.

O HCGS Rev. 7

CC3

  • ATT 4 Pg. 3 of 9 i

Initials ,

C. NOTIFICATIONS

1. Check appropriate boxes and provide a brief description EC of the event on the INITIAL CONTACT MESSAGE FORM (ICMF)

(pg 9 of this attachment). Complete, approve, and  ;

provide ICMF to the Designated Communicator (CM1).

2. Direct the Designated Communicator (CM1) to EC implement Attachment 7 and make the notifications on the Communications Log within the time limits specified.
3. Direct the Secondary Communicator (CM2) to implement EC Attachment 8.
4. Notify the Salem SNSS (NETS X5127; 9-339-5200).

EC Direct the implementation of EPIP 101S, Section 3.2.

D. SUPPORT EC - . ,

If not done previously, direct the OSC Coordinator to activate the OSC in accordance with EPIP 202H.

E. EMERGENCY PLAN IMPLEMENTATION EC If the EC is the EQQ or SNSS, implement EPIP 104H, " General ,

Emergency." .

OR If the EC is the EBH, implement EPIP 401 and perform the ,

following:  ;

1. Notify the EDO of the change in Emergency Classification Level, the time of declaration, and direct the EDO to implement EPIP 104H, " General Emergency." ,
2. Notify EOF staff of the change in emergency classification.

F. SECURITY EC ~

For secur3ty event, notify the PSE&G Security Supervisor ,

(X2222) to implement the Security Contingency Plan and Procedures. l i

()

  • fCGS Rev. 7 l

ECJ

' ATT 4 Pg. 4 of 9 k

Initialg NOTE The Station Status Checklist shall be transmitted every 30 minutes or immediately if a significant change in station status occurs.

G. TECHNICAL COMMUNICATIONS

1. Upon receipt of the Station Status checklist (SSCL)

EC from the CM2, review and approve for transmittal.

Implement more frequently for significant station status change.

2. Ensure completion and approval of the NRC Data Sheet EC form. _

a) Obtain the form (both pages) from the CM2 (Att. 8)

(~- Provide the approved form to the CM2 for transmittal

( b) to the NRC as soon as possible, but not to exceed ONE HOUR, NOTE:

As manpower permits, the Emergency coordinator may assign an additional communicator (preferably an RO or SRO) to provide continuous updates to the NRCs The essignment of an additional communicator should not be made if personnel being considered are required to mitigate the event or to complete high priority Emergency Response functions.

c) Notify the NRC of any significant changes in Plant Status, Emergency Status, or any actions taken in accordar.ce with 10CFR50.54(x).

d) Direct CH2 to log or document (via NRC~ Data Sheet) any additional information provided to the NRC.

This includes, but is not limited to, changes in Plant Status, Emergency Status, or any actions taken 73 in accordance with 10CFR50.54(x).

HCGS Rev. 7

EC3 ATT 4 Pg. 5 of 9

[

v Initials

3. When turning over EC duties ensure your EC communicators are directed to turnover notifications responsibilities to the facility being activated.

H. RELIEF / TURNOVER EC If relieved as EC prior to de-escalation of the GE, then, turnover responsibility for this attachment to the oncoming EC and document your relief below and in EPIP 104H.

assumed EC duties at hrs.

name time I. REPORTING EC Ensure that appropriate reports are made IAW Section II (page 6) of this Attachment.

J. RECORDS EC Ensure that all completed documents related to this Event are O forwarded in accordance with reporting requirements of Section II of this Attachment.

O HCGS Rev. 7

CCG

  • ATT 4 Pg. 6 of 9 p

V II. REPORTING Initials Instructions

1. This is a permanent document - all pages of this Attachment.
2. Appropriate documents shall be appended to this form and the package expedited through all steps.
3. Responsible person shall initial each step.
1. Ensure that an Incident Report is prepared.

SNSS

2. Forward this Attachment, the Incident Report, and any

( supporting documentation to the Operations Manager (OM).

) SNSS

3. Review the Incident Report and any other relevant OM information for correct classification of event and corrective action taken.
4. Contact the LER Coordinator (LERC) and request that OM the required reports be prepared. Provide this Attachment and any other supporting documentation to the LERC.
5. Prepare required reports. ECG Attachment 23 may be LERC used as a guide for reporting requirements.

Report or LER Number

6. When no longer required send this attachment and LERC appended documents to the Emergency Preparedness Manager (EPM). ,
7. Forward this Attachment package to the Central EPM Technical Document Room (CTDR) for microfilming. ,

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Rev. 7 1

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

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. j ECG PREDETERMINED PROTECTIVE ACTION ' RECOMMENDATIONS ( v# of g INITIAL. CONDITIONS: (l l

PAR REQUIRED FOR GENERAL EMERGENCY l

)

OPERATIONAL i OR SECURITY L EVACUATE DOWNWIND il SECTOR 0-5 MILES .

SECURITY r SHELTER ALL REMAINING SECTORS 0-5 M!IIS BASED GE (

? i f

OPERATIONAL l l

l FUEL CLAD NOT LOST L INTEGRITY SHELTER DOWNWIND 1 SECTOR 0-5 MILES l LOST (DEFAULT PAR) F ,

?  :

14SS OF CLADDING 88 F IDSS OF CLAD ONLY L EVACUATE DOWNWIND 11 SECTOR 0-5 MILES MSS [N PROG f BARRIERS F SHELTER ALL REMAINING SECTORS 0-5 MILES  :

LOSS OF ALL 3 f BARI'IERS  ;

V LOSS OF CLAD .\ND EITHER L EVACUATE ALL SECTORS 0-5 MILES  ;

I RCS DB CONTATiMENT F i

EVACUATE ALL SECTORS 0-5 MILES  !

CON MAY NO OR UNCERTAIN L EVACUATE DOWNWIND il SECTOR 5-10 MILES I SHEMR E REMMNG Sm0RS '5-10 MS A

? .

8 0-10 MILES f SHELTER ALL SECTORS NOTE: AFTER PAR IS PROVIDED. EVALUATION t OF PLUME AREAS SHOULD BE PERFORMED TO INITIATE EVACUATIONS I IN ALL RECOMMENDED SHELTER AREAS  !

THAT HAVE SUFFICIENT EVACUATION TIME.  !

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HCGS Rev. 7 1

l i

ECG RECOMMENDED PROTECTIVE ACTIONS WORKSHEET (aorg i O  !

WIND DIRECTION FROM PAR AFFECTED SECTORS DEGREES COMPASS DOWNWIND 11 SECTOR

]

349 - 011 N SSE -

S -

SSW i 011 - 034 NNE S -

SSW -

SW 034 - 056 NE SSW -

SW -

WSW 056 - 079 ENE SW -

WSW -

W .

079 - 101 E WSW -

W -

WNW l 101 - 124 ESE W -

WNW -

NW '

124 - 146 SE. WNW -

NW -

NNW 146 - 169 SSE NW -

NNW -

N 169 - 191 S NNW -

N -

NNE 191 - 214 SSW N -

NNE -

NE 214 - 236 SW NNE -

NE -

ENE i 236 - 259 WSW NE --

ENE -

E 259 - 281 W ENE -

E -

ESE 281 - 304 WNW E -

ESE -

SE  :

304 - 326 NW ESE -

SE --

SSE 326 - 349 NNW SE -

SSE -

S )

O NOTE: CONp! DER ADDING A SECTOR TO THE PAR IF THE WIND DIRECTION (FROM) IS WITHIN 13 0F A SECTOR DIVIDING llNE.

3.g NORTH 333 NNW 32c ms osc ]

NW NE soc ose l

WNW MIb ENE 2er ovr WEST EAST 25g

- 101 WSW / ESE 1

/ 12 (

23g O SW 146' Se 214 SSW SSE 888' HCGS 81 SOUTH p,y, 7 l

ECG

  • ATT 4 Pg. 9 Cf 9 INITIAL CONTACT MESSAGE FORM

,mI

! I. THIS IS , COMMUNICATOR IN THE O (NAME)

CONTROL ROOM TECHNICAL SUPPORT CENTER EMERGENCY OPERATIONS FACILITY AT THE HOPE CREEK NUCLEAR GENERATING STATION.

THIS IS NOTIFICATION OF A GENERAL EMERGENCY WHICH WAS DECLARED AT ON .

(TIME - 24 HOUR CLOCK) (DATE)

THIS IS NOTIFICATION OF A PROTECTIVE ACTION RECOMMENDATION UPGRADE WHICH WAS MADE AT ON .

(TIME - 24 HOUR CLOCK) (DATE)

II. ECG SECTION INITIATING CONDITION DESCRIPTION OF EVENT:

III.

((_-) b3 THERE IS NO RELEASE IN PROGRESS. - see NOTE below for THERE IS A RELEASE IN PROGRESS. release definition 33 FT. LEVEL WIND SPEED: WIND DIRECTION (FROM):

TMPh) (DEGREES)

_-------_ -___--- u_----_--__-------__----_____----_--_-------

IV. Sector (s) Distance-Miles WE RECOMMEND EVACUATION AS FOLLOWS WE RECOMMEND SHELTERING AS FOLLOWS EC Initials Time (EC Approval to Transmit ICMF)

NOTE: Release is defined as: Plant Effluent > Tech Spec Limit of 1.20E+4 uCi/sec Noble Gas or 1.70E+1 uCi/sec I-131.  ;

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i HCGS Rev. 7 i

I ECG

- ATT ii Pg. 1 of 10

,r 3 CONIHOL (X)PY ll

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HOPE CREEK i EVENT CLASSIFICATION ,

CROSS REFERENCE l j  ;

EVENT TO REQUIREMENT DOCUMENT SECTION 11 NOTE This Section is not to be used for Event Classification. Refer to Sections 1 thru 18.

Initiatina Event / Condition Reference *

1. Reactor Coolant Leakage Rate /LOCA A. Exceeding reactor coolant leak rate technical UE5 specification B. Reactor coolant leak rate greater than 50gpm AL5 C. Unisolable RCS leak outside containment . NUMARC, Table 4 D. Loss of coolant accident greater than makeup sal 73 capacity

( )

E. Loss of coolant accident with failure of ECCS GE6b,C systems to perform, or with potential contain-ment failure.  !

2. Steam Break or Safety / Relief Valve Failed Open A. Failure of a safety / relief valve to close UE6 following a reduction of pressure B. Steam line break outside drywell AL4 C. Steam line break outside drywell with con- SA4 tinuing leakage
  • Unless otherwise identified, references are as outlined in Appendix I, NUREG 0654.

Only initiating Event / Condition references for Emergency Classes UE -GE are listed here. Non -emergency references are included in the sections themselves.

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HCGS Rev. 2

EC3

- ATT ii Pg. 2 of 10 O

V NOTE This section is not to be used for Event Classification. Refer to Sections 1 thru 18.

Initiatina Event / Condition Reference *

3. Failure to Scram A. Failure of the reactor protection system to ALll automatically initiate and complete a scram which brings the reactor subcritical.

B. Conditions requiring operation of the standby SAS liquid control system with subsequent failure to reduce power (continued power generation but no core damage evident).

C. Conditions requiring operation of the stand- GE6 by liquid control system with subsequent failure to reduce power (containment failure imminent with significant core damage).

4. Loss of Decay Heat Removal O

\~ /' A. Complete loss of any decay heat removal ALS capability needed for plant cold shutdown. ALLO B. Complete loss of any decay heat removal SA8 capability needed for plant hot shutdown.

C. Continued loss of all conventional means GE6d of decay heat removal with core damage and containment failure possible if cooling not restored.

5. Fuel Damage / Degraded Core A. Fuel damage indications UE3 a,b B. Severe loss of fuel cladding ALla,b I

C. Degraded core with indication of possible SA2 loss of coolable geometry D. Fuel handling accident with radiological AL12 )

release to the Reactor Building from irradiated fuel.

i

('M l (l

HCGS Rev. 2

ECG

- ATT ii Pg. 3 of 10

(~h L/

NOTE This Section is not to be used for Event Classification. Refer to Sections 1 thru 18.

Initiatina Event / Condition Reference

  • E. Major irradiated fuel damage with SAlO '

radiological release exceeding (or projected to exceed) the threshold dose rates at the MEA for a Site Area Emergency.

6. Fission Product Boundary Failures (2/3)

A. Severe loss of fuel cladding GE2

()

^

B. Loss of RPV integrity GE2 C. Loss of primary containment GE2

7. Radiological Releases A. Contaminated injured person transported from UE 1 6 the site to an offsite medical < facility.

B. Loss, theft or diversion of any UE12 special nuclear material onsite 10CFR70.52 C. Increase in measured or calculated A6 dose rates (mR/hr) or airborne activity levels by a factor of e 1000 times (indication of degradation in control of radioactive materials)

D. Liquid release that exceeds T/S limits UE2 for 2 15 minutes.

E. Gaseous release that exceeds T/S limits. UE2 F. Gaseous release that exceeds 10 A15 times T/S limits.

HCGS Rev. 2

i EC3 1

- ATT 11 i Pg. 4 of 10

(-~

\-) ,

l NOTE This Section is not to be used for Event Classification. Refer to Sections 1 thru 18.

Initiatina Event / Condition Reference

  • i G. Dose Rate at Minimum Exclusion Area SAE13 (MEA -0.56 miles from the affected unit) greater than or equal to 500 mR/hr Whole Body (WB) or 2500 mR/hr Thyroid. ,

1 H. Dose Rate at Minimum Exclusion Area gel (MEA) greater than or equal to 1R/hr WB or 5 R/hr thyroid.

8. Nonradioactive Leak / spill A. Toxic or flammable gas release UE14d that threatens plant personnel.

B. Toxic or flammable gas release A18d

( ) entering plant structures. -

C. Toxic or flammable gas release SAE16c entering into vital areas where safe plant operation is compromised.

9. Electrical / Power Failure A. Loss of A.C. Power capability UE7 that requires Unit Shutdown B. Loss of all offsite power UE7 C. Loss of all offsite power and A7 loss of most onsite A.C. Power D. Loss of all offsite power and SAE6 loss of most onsite A.C. Power for an extended period of time.

E. Total loss of all A.C. Power SAE6 F. Loss of all vital onsite D.C. A8

- Power ,

j

[

(. ,

i l

)

HCGS Rev. 2 l

EC3 ATT 11 Pg. 5 of 10 l

A NOTE l This Section is not to be used for Event l Classification. Refer to Sections 1 thru 18.

Initiatina Event / Condition Reference

  • G. Loss of all vital onsite D.C. SAE7 Power for > 15 minutes.
10. Loss of Instruments / Alarms /

Communications A. Indications or alarms on UEll process or effluent parameters not functional in Control Room.

B. Loss of all or most OHAs A14 C. Loss of all or most OHAs SAE12 and plant transient initiated or in progress e

\- 11. Control Room Evacuation A. Evacuation of Control Room A20 anticipated or required. ,

B. Evacuation of Control Room SAE18 completed with control of S/D systems not established at the Remote S/D Panel within 15 minutes.

12. Earthquake / Severe Weather A. Earthquake / seismic event felt UE13a in-plant or instrument detected B. Earthquake / seismic event A17a greater than Operating Basis Earthquake (OBE)

C. Earthquake / seismic event SAE15a greater than Design Basis Earthquake (DBE)

D. Flood: Water level in river UE13b high (m./

HCGS Rev. 2

EC3 -

  • ATT ii  !

Pg. 6 of 10 NOTE This Section is not to be used for Event  !

Classification. Refer to Sections 1 thru 18. I Initiatina Event / Condition Reference

  • l l

E. Flood: Water level in river A17b  :

high; near design basis l F. Flood: Water level in river SAE15b' l high; greater than design basis G. Water level in river low UE13b H. Water level in river low near A17b '

design basis I. Water level in river lower SAE15b than design basis  !

J. Hurricane / unusual wind indicated UE13d i by met tower instrumentation K. Hurricane / unusual wind indicated A17d by met tower instrumentation .

near design basis I t

L. Hurricane / unusual wind indicated SAE15c by met tower instrumentation greater than design basis M. Tornado funnel observed, within MEA UE13c N. Tornado funnel observed within A17c the protected area ,- ,

O. Tornado funnel observed, SAE5c affecting plant structures P. Any major internal or external GE7 event substantially beyond i design basis.

i i

0 1 l

HCGS Rev. 2 l

. _ . _ _ _ . __ _ _ _ _ _ __ __ _l

l

. 1 CC3 ,

- ATT 11 l Pg. 7 of 10 l NOTE This Section is not to be used for Event Classification. Refer to Sections 1 thru 18.

1 Initiatina Event / Condition Enference*

13. site Hazards (explosions, crashes, etc.)

A. Aircraft unusual activity over UE14a l Facility or crash within the _

MEA B. Aircraft crash within the A18a Protected Area C. Aircraft crash affecting SAE16a Plant Structures D. Turbine rotating component UE14e failure E. Turbine rotating component A18e  ;

' failure causing casing  ;

i penetration F. Missile impact onsite A18b from any source within the Protected Area.

G. Missile impact onsite SAE16b damaging a Plant Struc-ture H. Unplanned explosion UE14c affecting plant operations I. Unplanned explosion A18c potentially compromising the function of one or more safety systems or normal operation of the plant i J. Unplanned explosion com- SAE16b i

promising the function of one or more safety systems O ,

HCGS Rev. 2 i

EC3

- ATT ii

- Pg. 8 of 10 O

Q NOTE This Section is not to be used for Event Classification. Refer to Sections 1 thru 18.

Initiatina Event / Condition Reference

  • K. Any major event substantially GE7 ,

beyond design basis.

p

14. Fire A. Fire lasting > 10 min that UElO affects plant operations B. Fire potentially compromis- A13 ing the function of one or ,

more safety systems C. Fire compromising the SAEll function of one or more safety systems D. Any major fire (substantially GE7 beyond design basis) which -

could cause massive common damage to safety systems.

15. Personnel Emergencias  ;

A. Contaminated injured person UE16 ,

transported from site to an offsite medical facility.

H. Unplanned explosion UE14c affecting plant operations I. Unplanned explosion A18c potentially compromising the function of one or more '

safety systems or normal operation of the plant J. Unplanned explosion com- SAE16b promising the function of one or more safety systems K. Any major event substantially GE7

()

4 beyond design basis

'HCGS Rev. 2

CC3

. ATT 11 Pg. 9 of 10 Iv NOTE This Section is not to be used for Even't Classification. Refer to Sections 1 thru 18.

Initiatina Event / Condition Reference *

16. Security Events A. Loss, theft or diversion UE12 of any special nuclear 10CFR70.52 material onsite B. Substantiated threat, UE12 attempted entry or dis-covery of a suspected destructive device or evidence of a malicious act.

C. Security Alert UE12 I D. Substantiated threat, A16

\'- attempted entry or dis-covery of a suspected destructive device or evidence of a malicious act with a Security Alert declared.

E. Ongoing security compromise A16 F. Ongoing security compromise SAE14 with imminent loss of physical control of the plant.

G. Ongoing security compromise GE3 with in the loss of physical control of the plant.

17. Publio Interest Items A. Any plant conditions exist UE15 that warrant increased awareness on the part -

of STATE / LOCAL authori-O ties.

(

HCGS Rev. 2

EC3

. ATT 11 Pg. 10 of 10 O

NOTE This Section is not to be used for Event Classification. Refer to Sections 1 thru 18.

Initiatina Event / Condition Reference

  • B. Any plant conditions exist AlS that warrant precautionary standby of STATE / Local authorities. ,

C. Any plant conditions exist SAE17 that warrant precautionary activation of STATE / LOCAL authorities and notification to the general public.

18. Tech. Specs / Plant Status Changes A. Unit shutdown to comply UE3, UE4, with the following T/S UES, UE7, LCO's: UE8
1. Reactor Coolant System (RCS) leakage
2. Specific activity of the Primary Coolant
3. A.C. Electrical power sources
4. RCS pressure / temperature limits .
5. Primary Containment Integrity B. Exceeding any T/S Safety UE4 Limit Tech. Spec 2.1 and 6.7.1 C. Manual or automatic ECCS UEl actuation with discharge to the vessel.

D. Liquid release that exceeds UE2 i

T/S limits for 2 15 mins.

E. Gaseous release that exceeds UE2

. T/S limits.

HCGS Rev. 2

i

  • ECG j Szc. iii  ;
  • Pg. 1 of.1 j CONTT10L COPY #. ] ]

CROSS REFERENCE O 'b . 1 ATTACHMENTS TO EVENTS SECTION iii -~

i  !

i ATTACHMENT EVENT / INITIATING CONDITION 1

1- 1A, 2A, SA, 7A, 7B, 7D, 7E, 8A, 9A, 9B, 10A, 12A, 12D, 12G, 12J, 12M, 13A, 13D, 13H, 14A, ,

15A, 16A, 16B, 16C, 17A, 18A, 18B, 18C, 18D, 18E ,f 2 1B, 2B, 3A, 4A, 5B, SD, 7C, 7F, 8B, 9C, 9F, ,

10B, 11A, 12B, 12E, 12H, 12K, 12N, 13B, 13E, l

-l 13F, 13I, 14B, 16D, 16E, 17B 1C, 1D, 2C, 3B, 4B, SC, SE, 7G, BC, 9D, 9E, 9G, l 3

10C, 11B, 12C, 12F, 12I, 12L, 120, 13C, 13G, 13J, 14C, 16F, 17C i 4 1E, 3C, 4C, 6, 7H, 12P, 13K, 14D, 16G .l 10 7I, 7L, 7M  ;

7I, 7K, 16H 7N (2,4,6) , 8D, 10D, ISB, 17D, 18F, 18G, 18H f 12 18I, 18K ,

14 7N (1,3,5), 15C, 17E, 18L, 18M, 18N, 180 ,

15 17F  ;

16 8D, SE 17 ISD, 15E 18 7J B 19 16I 20 18P, 18Q ,

21 17G l 22 18R, 18S, 18T i

HCGS Rev. 7

. . t

-w +,_

CCNIHut UDPY h {

65 I

Ecc

^

SECTION 1 SECTION 1 REACTOR COOLANT LEAKAGE / LOCA eiai s

L REACTGR CDORANT LEAK 3. REACTOR rnne aart LEAK C, REACTOR CDOLANT B. LOSS OF CDOLANT ACCSENT GEIAft2 TEAM B. LDSS OF COOLANT ACCIDENT WITE PAILURI CF NMMC EICKEDING TEcu srsc BATE CRIATER TEAM LEAK OUTsGE alAER;P CAPACITY EGE SY$TEMS TO PEEFORM. OE WITM FOTOTIAL CON 0tTIONS UMIT RESLinNG UI 50 CFM PRIMARY CUNTADfMENT CONTADiMDT FalLERE UNIT snufacum F- r r r r r

! Shutdo a meated to corns *y Reactw coated lookega t>weasetde Prunery gpy ,,g., w edh 1EOeeCAL $PECTICA"X)N m- ~ e encates a Systern Laoh reaches W 8

l ACTION STAllidENI; leek y a greater greater than 50 GPM 2" M i

f/5 LCO 3 4 3 2 AND g g l

I m . _ ,., _

MN toe % Ct l encates ey w , erd e.esens e.aoe ,

EALS l ' *==:aLa

% =',",,f,,'-*=

l 2. hereasng Reacts / Iwture B% hos termperatwes

! 3. heresang Seector / bhw

% swr, er Finar Lewem

4. Owest Cheenstaan THD4!

I I

l > a l v ECCS

s. - Faa. tite.,

rePv woner tem I coenet te restored g enome W I

I l

uol wl Severe toss of Am6 PftadAitT CCW.AmEh1 l caseeag es subcates 8eue es men.oied by tv (reser to Sectan 6a (refer to Sechen oc g FIS$10N PRCinCT fl$90N Pit'Off L

IOmCdat FatukE) BOUD&At FaituetE)

Mul Mul l

L_

NotrGTON/ ADD 3 ER2 neome em.= i m.EB awmi B : .ne.o i An.EM cmaiA 2

. a= h ptst 4.131 sitt Aa[A Ewa:rwl Gggang gagggiscy

l CU<ilha UDPy it '

65 I-FISSION PRODUCT BOUNDARY FAILURES I

- The tonowing conddians / EALS irdcote Fodure of a fissen proa.ct boundary NOTE ECG SECTION 6 Any two w reaura iin o poienta io= on the thi,4 wnd y represents a CENERAL EWERCENCY CONDITa0N.

SECTION 6 Pg. I of 1 Marutor for these conditons ofter ony sagte boundary Fonare.

A. SEVERE LOSS OF FUEL CLADDING B. LOSS OF RPV INTEGRITY C. LOSS OF PRIMARY CONTAINMENT IN1TiATINC 1. CONTAINMENT 2. RCS ANALYSIS 3. PROCESS WONilVRS 8. RCS / CONT. INDICATIONS OF A LOCA 2. SNSS/EDO ANALYSIS 1. INDICATION OF 2. SNSS/EDO ANALYSIS CONDITIONS HlGH RADIATION SitoWS FA!!ED INDICATIONS THAT RPF INTEGRITY CONTAINMENT BREACH CF CCMT. FAIWRE OR IUEl. IS ISST OR BYPASS IMMINENT FA1WRE l r r r r r r r r l DAPA RCS Sample vano tg21 okum on gar RPv water Level thih of the folioeng SNSS/EDO Mgerrent &T Breach or Bypass of SNSS/EDO judgement -

> 200 R/hr shows00-131 of the fonowing reaches TAF 1. DimrELL PRESSUAE M that RPV integnty is Prrnary Cordomment os that Prunary

> 300 A /g Process Monitars- 2. RPV Water Level lost inecoted by arc Conto amerd foAure, l

WN STM (JNE (C6-82)

" " ~ *"

oR wS (A) @Uncontro4ed Chornber Pressure anddDub l g OFFGAS PRETREAIMENT WOM10R and i (B) h.tr (SRX621/ 9RX622) cont % r* tion HlCH ALAliM in Wou.on Poci i Og Level EALSI (c) unisme erimor, Systern Lack l dtschargeng outs 4 Prrnary Cor.tamrnent.

l

^"

I Ary of the foiiowing l A B C P"*"'**

as a renJt at tr"e obove:**N l 1. Reactor / Turtsne Bidg. Roeotion Levets l 2. Reactor / Turbane sug Area Temperatures

! Any T.o fission Product Bounaanen hae faded:

sug SIoNuor Le.es AWESAWC28WC l

l AND l EC Judgemeat that e reiname Em se

} == me Third m a,.y

. L_ THEN NOTflCATON/

RN RErta To ATTAcudnt 4 HCG,S y CDIEIAL EMEEDCT m

  • Ce;:,+mpye I 1  !

65

)

ECG SECTION 17 PUBLIC INTEREST gcyN, PIANT CONDm0NS EXIST THAT WARRANT TiiE AIERTING OF STATE AND 14 CAL CmCIAIS NTATtf4 L INCREASED AWARENESS B. PRECAUTIONARY STAhDBY C. PRECatmONARY ACTIVATION LND PUBUC NOTIFICATION CONI)iTIONS F- r r r SNSS/EDO jueges plant SNSS/EDO jusges phant SNSS/EDO judges piant a cond. tens sorrent- conditans worront tgith condetmas arrant tJ>o l of the fodoomg actens. of the 4% octions:

tre port of State / Local 1. Precoutenary RTMDON l. Actnoten of einergency I authores of the Technica Support centers and mon.tonng Center (TSC). tearns.

i THEN 2. Puce Emer ncy 2. Precoutecary nottcoton Cperatens oceny (EOF) of tne putic.

and other key emergency l " " '

  • EALSl THEN THEN I

I I e Precautenary l IW6hG of the TSC eda key ,

I **9***9 s4 port personnet i does MI reone ACTNADON of NE l

l l

L_

PEER TO REFER TO RETER 10 NOTmTK)N/ AIIACmdLhi 1 ATIADrwLai 2 AITAOedhi 3 REMTM tmusual EttmT cat snt AaEA EMBfdNCT HCCS

. . REV. t.

ECG SECTION 17 PUBLIC INTEREST gcja,g D. EMERGENCY CONDITIONS L KAJOR LOSS OF EMERGENCY F. UNUSUAL CONDmONS DISCOVERED AITER-THE-FACT. ASSESSMENT CAPAB11JTY. WARRANUhG A NETS Of7 SITE RESPONSE EFIFa%T OR NOTIf1 CATION CAPABI1JTY. CR OF GOVERNMENT AGENCif3 MTING COMMUNICATIONS CAPAB0JTY [toClitSo.72 (bX2Xst)]

CONDITONS [10CFE50.72 (bX1Xv))

w w w

(- SNSS/EDO deternwes that on event (s) ggjgg g, g,c g ,, g j, g g o test u who I that had D evas4 occwed, (em event or sei.oten hos

" occwred M m rWW (event oos not ongoing at the t#me , with on ent to the hooita and safety of.

of escovery) shach esceeded on ,, g,.

Emergency Acten Level (EAL) but Tu k l

=cs not declared as on emergency. 1. Loss of Any of the fosoeing: OR e Emerge Not#cotaon Onste pusonnel System ( ) for > 1 Hr.

MD (Not opplicothie d NRC OR nott.es PSE&G of the loss) Protection of the l There are currently NO odierse Telephone environment e 5,Emerge"?NaS) stem. for > i a EALS l coasewnas ia mess os .

resuM of the event- e Offatte Swens (>10%) for

> 1 Hr. AND l e use of the TSC or EOF.

e SPOS or CROS for > 24 Hrs. * **** **** 's med l e As Meteoro6ogical data for OR

> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. hot;fcobons to other l e Sde access da to Acts of governmerit ogences hos nate (snoe nood etc.) been or edi te mee.

l . control Room habitabuy (SCBA's reped in CR) THEN l . As or most (> 7ss) own for < 15 munutes.

l e A8 phard went Roeoton mtn l 28 1 Concurrent loss of rnvitpe l Accioent er Emergency plant 1

inecotors or mondors ehich I significantly impous essessment capabstaes m3TD MN ----

Refer to EAL 10A if exter.t of loss requwes sfwtdown I NOTE:

h ---- Refer to EAL's 100 or 10C d toes of Ohrs for > 15 mm NOTE:

e Refw to ECG Secten tl 4 Conteca Room evocooted L_ _

REFER TO REFER TO EEFER 10 l ,

. Artacwwwi 14 NOTfGTO,N/ AmcudwT 12 Amcuni 12 HCGS REEN og-wous REPosi cut Hout aE7 cat fcue e aEPos REV. f.

ECG SECTION 17 PUBLIC INTEREST '

sectio" 27 Pg. 3 of 3 G. UhUSUAL OR IMPORTANT ENVIRONMENTAL EVENTS It UNL'SUAL CONDITIONS DIRECTLY Af7ECTINC lHCCS CFERATING LICENSE APPENDG B, IAWER A11DWAYS CREEE TOWNStitP (LACT)

HIRTiNG SECTION 4.8 ENWRONMENTAL PROTECTION PLAN) (FER HIMORAhDUW OF IJNDERSTANDINGl CONDITIONS V~ w w w w w As judged by SNSS/EDO: Protected outs species Any occwrence of on 4a judged by SkSS/EDO. As judged by $N55/EDO impinge on Service unusuoi or snportant I Unusuosy large Igb water stake screens event that indcotes or Antspoted h On- s:te events .Ach 6,1 (es.: seo furtie, could result a sigruf: cont mervemect or epment savo6re cwms swens j sturgeon) os reported enwonmentos impoet or personnes on. cts moy er etwee nose .rucn by 54e personnel cosscpy reioted to phant sagalacentty M rnay be heard off-sde operataan. Such as the local traff c pottems.

I fosowieg:

l THEN THEN tYs THEN THEN EALS ii ona vaat - ==d esease outbreats.

Wartokty or u occ.ence o,nusuoi on, i

spaces protected by the Endangered Spaces Act of 1971

) increase in nwsonce i argonerns or conetsons l THEN I

m For unonticipated or ernergency escharge l

o -t. ..., o, -of monces.

refer to ECG Section 8.

1

- - - - - determanobos) of report 1takty ed

)

be mode by Envuorwhente Lxensing L_ os a resJt of im;derrentag Attactwnent 15 REFER 10 NOT'ElCATION/ REsTR TO ggyg AliAandai IS ATTACMaEN121

, M*6AL tsN / LACT PtCT. *LAN "I

HCGS

. REV. L

EC3

  • Sig. Att. 1 - 23 Pg. 1 of 2 LL N i,T L i:!)PY If i f 3

( '

HOPE CREEK 65 EVENT CLASSIFICATION GUIDE ,'

ATTACEMENTS SIGNATURE PAGE July 29, 1994 EFFECTIVE ATTACHMENT TITLE REV. PAGES DATE

1. Unusual Event 12 16 May 21, 1994
2. Alert 7 7 May 21, 1994
3. Site Area Emergency 8 7 July 29, 1994
4. General Emergency 7 9 July 29, 1994
5. Reserved
6. CM1 Log (UE/A/SAE) 18 10 May 21, 1994
7. CM1 Log (GE) 18 10 May 21, 1994
8. CM2 Log 13 15 Apr 29, 1994
9. Non-Emergency Notification 17 3 June 24, 1994 Reference

() 10.

11.

One Hour Report - NRC/ Region One Hour Report - NRC/ OPS 1

3 5

5 July 27, 1990 Sept 27, 1991 (Security)

12. One Hour Report - NRC/ OPS 3 5 Apr 26, 1991
13. Reserved i
14. Four Hour Report - NRC/ OPS 2 5 July 27, 1990
15. Environmental Protection Plan 3 3 Sept 27, 1991 i l
16. Spill / Damage Reporting 5 10 Jan 7, 1994
17. Four Hour Report - Fatality / Medical 4 7 Apr 21, 1993
18. Four Hour Report - Transportation 1 6 July 27, 1990  !

i Accident

't

19. Twenty Four Hour Report - FFD 1 3 Sept 27,
20. Twenty Four Hour Report - NRC/ OPS 2 5 July 27, avv0
21. Reportable Event - LACT /MOU 0 2 May 26, 1989
22. Other/ Engineering 2 3 Sept 27, 1991
23. Written Reports /LERS/Other 2 9 Jan 7, 1994

[b LJ HCGS Rev. 30

EC3

  • Sig. Att. 1 - 23 Pg. 2 of 2 O

SIGNATURE PAGE Prepared By: b a d GJ4.- MJ 19 7/t 9s/

(If Editorial Revisions Only, Last Approved Revision) Date' l

l l

Roviewed By: d/A l Station Qualified Reviewer Date Significant Safety Issue l

( ) Yes ( ) No l Raviewed By: N fik Department Manager Date Reviewed By: d4 hex -7 /( 7/4 'j' Date Emergency peparWiness Manager l l

oviewed By: Yl4 General Manager - Quality Assurance / Safety Review Date (If Applicable) ,

t 80RC Review and Station Approvals i

alA o/ A  ;

Mtg. No. Salem Chairman Mtg. No. Hope Creek Chairman  :

Date Date ,

Ul A- v/A-Gcneral Manage'r - Salem General Manager a Hope Creek Date Date  :

t O l HCGS Rev. 30  ;

I

4 EC3

  • Cig. 003. i - is P 1 ot-t- ~\

i OL CUPT '!

l ]@ _g

/~'\

HOPE CREEK

'N ,/

EVENT CLASSIFICATION GUIDE OOe -

SECTION SIGNATURE PAGES i

~

July 15, 1994 __

EFFECTIVE SECTION TITLE BEV PAGER DATES

1. Introduction 2 7 Jan 7, 1994
11. Cross Reference - Event to Requirement 2 10 July 15, 1994 111. Cross Reference - Attachment to Events 7 1 July 15, 1994
1. REACTOR COOLANT LEAKAGE /LOCA 6 1 July 15, 1994
2. STEAM BREAK OR SRV FAILED OPEN O 2 May 26, 1989
3. FAILURE TO SCRAM 2 1 Dec 21, 1992
4. LOSS OF DECAY HEAT REMOVAL 2 1 Aug 21, 1992
5. FUEL DAMAGE / DEGRADED CORE 3 2 Dec 21, 1992
6. FISSION PRODUCT BOUNDARY FAILURE 5 1 July 15, 1994
7. RADIOLOGICAL RELEASES / OCCURRENCES 5 5 Jan 28, 1994

/~%)

~

8. NON-RADIOACTIVE LEAK / SPILL 3 2 Jan 7, 1994 (toxic gas, oil spill, hazmat)
9. ELECTRICAL POWER FAILURE 3 2 Jan 7, 1994 4 2 May 10, 1993
10. LOSS OF INTRUMENTS/ ALARMS / COMMUNICATIONS
11. CONTROL ROOM EVACUATION O 1 May 26, 1989
12. QUAKE / STORMS (earthquake, wind, floods, 4 6 Jan 7, 1994 etc)
13. SITE HAZARDS 1 5 Aug 21, 1992 (aircraft crash, missiles, explosions, etc.)
14. FIRE 3 1 Jan 7, 1994
15. PERSONNEL EMERGENCIES / MEDICAL 3 2 Jan 7, 1994
16. SECURITY EVENTS /FFD 5 3 Jan 7, 1994
17. PUBLIC INTEREST ITEMS 6 3 July 15, 1994 10 5 Jan 7, 1994
18. TECH SPECS / PLANT STATUS CHANGES (U HCGS Rev. 20 1 1

I

a

  1. EC3  !

' cig. Com. i - is  ;

Pg. 2 of 2 O SIGNATURE PAGE Prepared By: LC AMEM b -/ 2.-9 Date '

I (If Editoria; p isions only, Last Approved Revision)

Reviewed By: N Tcl4fLL Dio8 '

ff //

(off 9Y

~

Station Qualified Reviewer Date Significan ' Safety Issue  !

Revie d By: ., J 484 _

V Department ager Date Reviewed By: m- P.

genc PrepaYedness M&hager 9wr k E

Reviewed By: d/4 , l General Manager - QualitP~ Assurance / Safety Review Date

(

s (If Applicable)- l SORC Review and Station Approvals 4/n 4/A '

Mtg. No. Salem Chairman Mtg. No. Hope Creek Chairman Date Date AlY5 General Manager - Salem h

General AtanapF- Hoph Creek 7/sne Date Date O HCGS Rev. 20

. _ . . . . _ _ _ --. _ ,

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