ML20137J392

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Revised Emergency Plan Implementing Procedures,Including Rev 5 to EPIP-1.05, Response to General Emergency, Rev 0 to EPIP-2.04, Transmittal of Plant Status & Core Assessment Data & Rev 0 to EPIP-2.05, Transmittal Core Damage Data
ML20137J392
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/02/1986
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18149A022 List:
References
PROC-860102, NUDOCS 8601220425
Download: ML20137J392 (50)
v • d • e


Text

7

. EMERGENCY PLAN IMPLEMENTING PROCEDURES INDEX LATEST

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V EPIP NUMBER TITLE REVISION DATE EPIP-1.01 Emergency Manager Controlling Procedure 05-21-85 EPIP-1.02 Response to Notification of Unusual Event 02-14-85 EPIP-1.03 Response to Alert 05-21-85 EPIP-1.04 Response to Site Area Emergency 04-16-85 EPIP-1.05 Response to General Emergency 12-31-85 EPIP-2.01 Notification of State and Local Governments 02-14-85 EPIP-2.02 Notification of NRC 01-15-85 EPIP-2.03 Reports of Offsite Agencies 04-16-85 EPIP-2.04 Transmittal of Plant Status and Core Assessment Data 01-02-86 EPIP-2.05 Transmittal of Core Damage Data 01-02-86 EPIP-3.01 Emergency Personnel Notification List 09-26-85 EPIP-3.02 Activation of Technical Support Center 09-18-84

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\, E}IP-3'.03 Activation of Operational Support Center 09-12-84 EPIP-3.04 Activation of Emergency Operations Facility 10-01-85 EPIP-4.01 Radiological Assessment Director Controlling Procedure 08-13-85 EPIP-4.02 Radiation Protection Supervisor Controlling Procedure 10-23-84 EPIP-4.03 Dose Assessment Controlling Procedure 12-03-85 EPIP-4.04 Emergency Personnel Radiation Exposure 12-03-85 EPIP-4.05 Respiratory Protection 05-21-85 EPIP-4.06 Personnel Monitoring and Decontamination 07-29-82 EPIP-4.07 Protective Measures 09-10-85 EPIP-4.08 Initial Offsite Release Assessment 10-01-85 EPIP-4.09 Source Term Assessment 10-01-85 i EPIP-4.10 Determination of X/0 07-29-82 ,

EPIP-4.11 Follow-Up Offsite Release Assessment 10-01-85 EPIP-4.12 Offsite Environmental Monitoring Instructions 09-23-83 8602820425 860116 PDR ADOCK 05000280 <

F PENT )

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. EMERGENCY PLAN IMPLEMENTING PROCEDLTES INDEX s

LATEST EPIP NUMBER TITLE REVISION DATE (U} EPIP-4.13 Offsite Release Assessment with Environmental Data 09-23-83 EPIP-4.14 In-Plant Monitoring 09-26-85 EPIP-4.15 Onsite Monitoring 09-23-83 EPIP-4.16 Offsite Monitoring 09-23-83 EPIP-4.17 Monitoring of OSC and TSC 05-21-85 EPIP-4.18 Monitoring of EOF 05-21-85 EPIP-4.19 Radio Operations for Health Physics Monitoring 10-01-85 EPIP-4.20 Health Physics Actions for Transport of Contami-nated Injured Personnel 09-12-83 EPIP-4.21 Evacuation and Remote Assembly Area Monitoring 08-15-83 EPIP-4.22 Post Accident Sampling of Containment Air 09-29-83 EPIP-4.23 Post Accident Sampling of Reactor Coolant 02-16-84

/N EPIP-4.24 Gaseous Effluent Sampling During an Emergency 05-31-84 NY EPIP-4.25 Liquid Effluent Sampling During an Emergency 07-29-82 EPIP-4.26 High Level Activity Sample Analysis 03-29-84 EPIP-4.27 Dose Control Emergency Response 11-06-84 EPIP-5.01 Transportation of Contaminated Injured Personnel 04-16-85 EPIP-5.02 Search and Rescue 04-16-85 EPIP-5.03 Personnel Accountability 04-16-85 EPIP-5.04 Access Control 12-03-85 EPIP-5.05 Site Evacuation 04-30-85 EPIP-5.06 Emergency Radiation Exposure Authorization 05-21-85 EPIP-5.07 Administration of Radioprotective Drugs 04-16-85 l EPIP-5.08 Damage Centrol Guideline 04-16-85

EPIP-6.01 Re-entry / Recovery Guideline 04-23-85 I

i

. No. 97887230 MTM 22

. . Rev. 8 VIRGINI A POWER SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE l

PROCEDURE TITLE REVISION NUMBER 05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE j

(With 1 Attachment) 1 of 24 PURPOSE

1. To provide guidance to the Station Emergency Manager during the pro-gress of a classified GENERAL energency.

USER Station Emergency Manager ENTRYCONDITIONS

1. ' ntry From EPIP-1.01, Emergency Manager Controlling Procedure.

L DOCUMENT ALTERED TO REMOVE CONFIDENTIAL INFORMATION REVISION RECORO j- REV. 00 PAGE(S): Entire Procedure DATE: 07-29-82 REV. 01 PAGE(S): 1 of 22, 21 of 22 and 22 of 22 DATE: 11-10-83 REV. 02 PAGE(S): Entire Procedure DATE: 03-29-84 REV. 03 PAGE(S): 1, 3, 4, 6, 8, 9, 10, 11, 13, 14, DATE: 06-17-85 23 and 24 of 24 REV. 04 PAGE(S): Entire Procedure DATE: 10-01-85 REV. 05 PAGE(S): Entire Procedure DATE:

EC 31135 APPROVAL RECOMMENDED APPROVED l OATE DEC 311985 GC REhlEw CHAIRMANSTA TION NUCLEAR SAFETY Q _

,,Q AND OPERATING COMMITTEE EPIP <~

Eo., eras 721o 4

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NUMBER PROCEDURE TITLE REVISION 05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 2 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED

1. INITIATE PROCEDURE:

a) Declare position of Station Emergency Manager b) BY:

DATE:

TIME:

NOTE: The Shift Supervisor may be relieved as Station Emergency I

Manager IAW the SPS Emergency Plan.

O -

2. INPLANT NOTIFICATION:

a) From the Control Room, sound the EMERGENCY Alarm b) Make announcement on station Gai-Tronics system as follows:

1) "A GENERAL EMERGENCY has been declared"
2) "All Emergency Response personnel report to their assigned stations"
3) "All other personnel report to their Emer-gency Assembly Areas" c) Repeat Steps 2.a and 2.b, AND )

O l Continue with instructions l

1 I

No,. e7 s snio I

NUMBER PROCEDURE TITLE REVISION

, V 05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 3 of 24

- STEP ACTIONEXPECTED RESPONSE RESPONSE NOT OBTAINED

3. ONSITE ACCOUNTABILITY:

a) Direct Security to initiate Notify Security Shift EPIP-5.03, Personnel Account- Supervisor via PBX-ability b) Direct Security to initiate EPIP-5.04, Access Control

4. CALLOUT OF PERSONNEL:

a) Verify Emergency Response a) Direct Security to initiate Personnel - ONSITE EPIP-3.01, call out of Emergency Response person-nel.

O -

AND GO'TO Step 5 of this instruction b) Direct Security to activate Corporate Emergency Response Team by calling General Office Security IAW Attachment 1, EPIP-3.01, Callout of Emergency Response Personnel NOTE: The notification of General Emergency and an applicable protective action recommendation must be made to the state within 15 minutes following the declaration of General Emergency.

Steps 5 through H determine the of fsite protective actions to be recommended for various General Emergency situations.

The protective action recommendation should be at least sheltering within a 360* radius through Zone 2 and in the downwind and two adjacent sectors (673' 5 total) through Zone

5. Refer to Attachment 1 for affected zones and sectors.

O DOCUMENT ALTERED TO REMOVE CONFIDENTI

u$,s7ssmo NUMBER PROCEDURE TITLE REVISION

(' 05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE l 4 of 24  !

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1

- STEP ACTION /EX*ECTED RESPONSE RESPONSE NOT OBTAINED

5. CORE MELT AND LOCA WITH CONTAINFENT FAILURE IMMINENT OR OCCURRING:

a) Following conditions have a) GO TO Step 6,of this been met: instruction.

1) RCS specific activity -

GREATER THAN 3000 uCi/ gram dose equivalent I-131 EE 5 or more core exit thermNouples - GREATER Q THAN 2000*F V

2). Containment High Range Radiation Monitor 3 -

GREATER THAN 5x10' mR/hr

3) Containment failure imminent as indicated by pressure - GREATER THAN 60 psia NOT DECREASING pR Shif t Supervisor judge-ment that containment failure has occurred b) Determine wind speed and affected sectors
O

f ND. 97887210 p NUMBER PROCEDURE TITLE REVISION V EPIP-1.05 RESPONSE TO GENERAL EMERGENCY 05 PAGE 5 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED

5. (CONTINUED)
1) IF wind speed LESS THAN 2.5 mph, recommend sheltering through Zone 5 of affected sectors AND Recommend evacuation of affected sectors in Zones 6 through 10 AND Recommend evacuation of Og _

unaffected sectors through

- Zone 5

2) E wind speed GREATER THAN 2.5 mph, recommend shel-tering affected sectors through Zone 10 AND Recommend evacuation of unaffected sectors through Zone 5 c) Request Radiological Assessment Director aid in determination of sheltering recommendations IAW EPIP-4.01, Radiological Assessment Director con trolling Procedure, d) GO TO Step 13 a

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m NUMBER PROCEDURE TITLE REVISION 05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 6 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED

6. CORE MELT AND S/G TUBE RUPTURE WITH STEAM BREAK:

a) Following conditions have a) GO TO Step 7 of this been met: instruction.

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1) RCS specific activity-GREATER THAN 3000 pCi/ gram dose equivalent I-131 2

5 or more core exit thermocouples-GREATER THAN 2000*F

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2) S/G tube rupture -

- IDENTIFIED E

Shift Supervisor judge-ment that tube rupture IN PROGRESS

3) Major S/G Secondary depressurization as indicated by MS header to line DP - GREATER THAN 100 psid

! Shif t Supervisor judgement that large steam break -

IN PROGRESS l b) Determine wind speed and I affected sectors O

N),s7sst:10 NUMBER PROCEDURE TITI.E REVISlot.'

x^,) 05 1 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY I PAGE 7 of 24

- STEP ACTIONEXPECTED RESPONSE RESPONSENOTOBTAINED

6. (CONTINUED)
1) Il[ wind speed Less THAN ,

2.5 mph, recommend shel-tering through Zone 5 of affected sectors AND Recommend evacuation of affected sectors in Zones 6 through 10 AND

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Recommend evacuation of

, ( ,) unaffected sectors through Zone 5

2) II[ wind speed GREATER THAN 1 2.5 mph, recommend shel-tering of affected sectors through Zone 10 AND Recommend evacuation of unaffected sectors through Zone 5 l

r c) Request Radiological Assess-( ment Director aid in deter-mination of sheltering recommendations IAW EPIP-4.01, Radiological Assessment Director Controlling Procedure.

d) GO TO Step 13,.

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NUMBER PROCEDURE TITLE REVISION 05 v

EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 8 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

7. CORE MELT AND LOCA WITH CONTAINMENT FAILURE LIKELY:

a) Following conditions have a) GO TO Step 8 of this been met: instruction.

1) RCS specific activity-GREATER THAN 3000 pCi/

gram dose equivalent I-131 0,,R_

5 or more core exit thermocouples-GREATER THAN 2000*F

~ '

2) Containment High Range

. Radiation Monitor -

2 GREATER THAN 5x10

3) Containment failure is likely as indicated by significantly impaired Engineered Safeguards Systems AND pressure -

j GREATER THAN 23.0 psia b) Request Radiological Assess-ment Director aid in deter-mination of evacuation recommendations IAW EPIP-4.01, Radiological Assessment Director Controlling Procedure.

c) Recommend the following:

1) Evacuation within a 360*

l radius through Zone 5 l

2) Evacuation of the downwind and adjacent sectors (67h* total)

(, in Zones 6 through 10 l d) C0 TO Step 1][

l

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NUMBER REVISIGN f"% PROCEDURE TITLE

( 05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 9 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

8. CORE MELT AND LOCA WITH CONTAINMENT FAILURE NOT LIKELY:

a) Following conditions met: a) GO TO Step 9,of this instruction.

1) RCS specific activity-GREATER THAN 3000 pCi/

gram dose equivalent I-131 0,, R, 5 or more core exit thermo-couples-GREATER THAN 2000*F ,

2) Containment High Range

{N g ,) Radiation Monitor ~

2

. GREATER THAN 5x10

3) Containment failure is NOT likely as indicated by pressure - LESS THAN 23.0 psia AND DECREASING b) Request Radiological Assess-ment Director aid in deter-mination of evacuation recommendations IAW EPIP-4.01, Radiological Assessment Director Controlling Procedure, c) Recommend the following:
1) Evacuation within a 360' radius through Zone 2
2) Evacuation of the downwind and adjacent sectors (67h*

total) through Zone 5

3) Sheltering of the downwind and adjacent sectors (67h*

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.s, total) in Zones 6 through 10 d) GO TO Step 13

N).s7as7220 NUMBER I f% PROCEDURE TITI.E REVISION

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05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 10 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

9. CORE MELT AND S/G TUBE RUPTURE WITH MS SAFETY LIFT LIKELY:

a) Following conditions have a) GO TO Step IC[ of this been met: instruction.

1) RCS specific activity-GREATER THAN 3000 uC1/

gram dose equivalent I-131 0,,R S or more core exit thermocouples -

GREATER THAN 2000*F

2) S/G tube rupture flow

. greater than the capacity of one (1) Charging /SI Pump

3) Shif t Supervisor judgement ,

that lifting of MS safety  !

valve (s) likely b) Request Radiological Assessment Director aid in determination of evacuation recommendations IAW EPIP-4.01 Radiological Director Controlling Procedure.

c) Recommend the following:

1) Evacuation within a 360*

radius through Zone 2

2) Evacuation of the downwind and adjacent sectors (67 total) through Zone 5
3) Sheltering of the downwind and adjacent sectors (67h*

O Total) in Zones 6 througa 10 d) C0 TO Step 13,

N,s.s7ss72to NUMBER PROCE00RE TITLE REVISION

%) EPIP-1.05 RESPONSE TO GENERAL EMERGENCY 00 PAGE 11 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED

10. CORE MELT WITH LOW CONTAINMENT ACTIVITY:

a) Following conditions have a) CO TO Step 11 of this been met: instruction.

1) RCS specific activity-GREATER THAN 3000 pCi/

gram dose equivalent I-131 ER.

5 or more core exit thermocouples-GREATER THAN 2000*F

~ ^

2) Containment High Range Radiation Mogitor -

LESS THAN 10 mR/hr -

3) Containment pressure-LESS THAN 17.7 psia AND NOT INCREASING b) Request Radiological Assessment Director aid in determination of evacuation recommendations IAW EPIP-4.01 Radiological Assessment Director Controlling Procedure c) Recommend evacuation within a 360* radius through Zone 2 d) GO TO Step p

e.,s. s7s s721o NUMBER PROCEDURE TITLE REVISION

( 05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 12 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

11. SIGNIFICANT RELEASE POTENTIAL:

a) Any of the following exist: a) GO TO Step 12,of this instruction.

1) Projected Site Boundary doses exceed 2 Rem whole-body or 12, 2 Rem thyroid exposure 0,,,R,
2) Loss of physical control of the station b) Request Radiological Assessment p Director aid in determination of evacuation recommendations IAW EPIP-4.01, Radiological Assessment Director Controlling Procedure.

c) Recommend evacuation within a 360* radius through Zone 2 d) GO TO Step y i

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NUMBER PROCEDURE TITLE REVISION l x 05 j EPIP-1.05 RESPONSE TO GENERAL EMERGEFCY PAGE 13 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08T INED

12. MISCELLANEOUS EVENTS:

a) A General Emergency has been ,

declared for any reason other than those specifically mentioned above ER Station Emergency Manager judgement indicates actions required to protect the health and safety of the public O b) Request Radiological Assessment Director aid in determination of. sheltering recommendations IAW EPIP-4.01, Radiological Assessment Director Controlling Procedure.

c) Recommend the following:

1) Sheltering within a 360*

radius through Zone 2

2) Sheltering of the downwind and adjacent sectors (67
  • total) through Zone 5 NOTE: Updates to state and local governments should be provided at approximately 30 minute intervals and after significant changes to plant status, radiological data, or meteorological data.
13. STATE AND LOCAL GOVERNMENT NOTIFICATION:

! a) Initiate EPIP-2.01, Notification of State l and Local Governments l

4

ed.e7:s72io NUMBER PRO:EDURE TITLE REVISION (s,_,/ 05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PA GE 14 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

14. NRC NOTIFICATION:

a) Notify NRC Operations Center IAW EPIP-2.02, Notification of NRC

15. EVALUATE STATION CONDITIONS:

a) Unit (s) are NOT affected a) E a unit is affected, eval-by emergency condition uate safe operation of unaf-fected unit.

1) Evaluate safety of any operating unit AND
2) Consider unit shutdown Consider unit shutdown if

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if conditions so conditions so indicate.

. indicate

16. VERIFY EMERGENCY CENTERS / FACILITIES:

a) All emergency centers and a) GO TO Step H of this facilities - ACTIVATED instruction.

b) GO TO Step 20 of this instruction

17. VERIFY TSC ESTABLISHED:

a) Check TSC NOT previously a) GO TO Step M of this in-activated struction.

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hj.e7ss721o p NUMBER PROCEDURE TITLE REVISION

(,,/ 05  !

EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 15 of 24

- STEP ACTION / EXPECTED RES00NSE RESPONSE NOTOBTAINED

17. (CONTINUED) b) Relieve the Shift Supervisor b) Il[ Shift Supervisor relief as Emergency Manager NOT available GO TO Step 18 of this instruction and
1) BY: return to Step lj[ when appropriate.

DATE:

TIME:

c) If desired, relocate Emergency Manager position to TSC d) Announce Station Emergency

(N _

Manager name and location

\ to offsite authorities e) Verify TSC - ACTIVATED e) Initiate activation of TSC

'IAW EPIP-3.02, Activation of Technical Support Center.

18. VERIFY OSC ESTABLISHED:

a) Check OSC NOT previously a) GO TO Step 19[of this in-activated struction.

b) Direct on-duty mechanical foreman to assume position of interim OSC Director c) Direct activation of OSC IAW EPIP-3.03, Activation of Operational Support Center i

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N'3. 978 8721C NUMBER PROCE00RE TITLE REVISION

'O EPIP-1.05 RESPONSE TO GENERAL EMERGENCY 05 PAGE 16 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

19. VERIFY LEOF ESTABLISHED:

a) Check LEOF NOT previously a) GO TO Step 2j) of this in-activated instruction.

b) Direct Security to activate LEOF IAW EPIP-3.04, Activation of Emergency Operations Facility

20. VERIFY EPIP-4.01:

a) Check status of EPIP-4.01, Radiological Assessment Director Controlling

,/ Procedure b) Verify Onsite Monitoring Team - ACTIVATED c) Verify Offsite Monitoring Team (s) - ACTIVATED

21. CHECK RADIOLOGICAL CONDITIONS:

a) Radiological conditions - a) Confer with Radiological STABLE 011 DECREASING Assessment Director and i

Emergency Operations Director.

AND Initiate appropriate miti-gating actions.

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N'p.s7ss7220 NUMBER PROCEDURE TITLE REVISION

'~'

EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 17 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED

22. CHECK UNIT CONDITIONS:
a) Reactor plant (s) - STABLE a) Jg[ TSC activated confer with Emergency Operations Director. ))[NOT, confer with SRO On-Call, AND Initiate appropriate miti-gating actions.
23. DAMAGE CONTROL:

r a) Damage to station equip- a) GO TO Step 24,.

( ,T) ment has been verified b) With Emergency Operations b) jg[ TSC NOT manned confer and Maintenance Directors, Vith senior operations evaluate extent of damage and maintenance personnel onsite c) Evaluate following assist-ance requirements

1) Offsite Technical
2) Additional personnel
3) Material and Equipment d) Direct Emergency Mainte- d) IF Emergency Maintenance nance Director to initiate Director NOT available, EPIP-5.08, Damage Control initiate interim damage control activities.

D)

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n'o . erasnio NUMBER O

PROCEDURE TITLE REVISION 05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 18 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

24. VERIFY ONSITE CONDITIONS:

a) Conditions indicate limited a) GO TO Step 2_5_ 5 of this in- -

evacuation of buildings or struction.

areas - REQUIRED b) Sound EMERGENCY Alarm and make l appropriate announcement using the plant Gai-Tronics system NOTE: Updates to state and local gevernments should be provided at approximately 30 minute intervals.

[\ .

25.

FOLLOW-UP STATE AND LOCAL

. GOVERNMENT NOTIFICATION:

a) Verify updated Health Physics dose assessments completed b) Verify timely follow-up b) Initiate EPIP-2.01, State and local government Notification of State and notification IAW EPIP-2.01, Local Governments.

Notification of State and Local Governments

26. FOLLOW-UP NRC NOTIFICATION:

a) Verify follow-up NRC a) Initiate EPIP-2.02, notification IAW, EPIP-2.02, Notification of NRC.

Notification of NRC n

v

Ni.97es7210 Q NUMBER PROCEDURE TITLE REVISION h EPIP-1.05 RESPONSE TO GENERAL EMERGENCY _

05 PAGE 19 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

27. ADDITIONAL REPORTING: .

a) Direct the Emergency Administrative Director to evaluate reporting criteria IAW EPIP-2.03, l

Reports to Offsite Agencies b) Initiate reporting require-ments of EPIP-2.03, Reports to Offsite Agencies

28. VERIFY ACCOUNTABILITY:

a) All personnel accounted for a) Direct initiation of O, IAW EPIP-5.03, Personnel Accountability EPIP-5.02, Search and Rescue

29. SITE EVACUATION:

a) Radiological Assessment a) GO TO Step 3 Director reconmends Site evacuation b) Consider the following:

1) Onsite dose greater than 1 Rem whole body OR greater than 5 Rem thyroid exposure
2) Characteristics and direction of the plume
3) Contamination vs. per-sonnel safety and ex-posure O

U

N$.97887210 NUMBER p]

t EPIP-1.05 PROCEDURE TITLE RESPONSE TO GENERAL EMERGENCY REVISION 05 PAGE 20 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

30. INITIATE SITE EVACUATION:

a) Initiate EPIP-5.05, Site Evacuation

31. EVACUATION / RECOMMENDATION NOTIFICATIONS:

a) Notify state and local governments of evacuation IAW EPIP-2.01, Notification of State and Local Governments b) Notify NRC Operations Center of evacuation initiation O. IAW EPIP-2.02, Notification of.NRC

32. EMERGENCY EXPOSURE:

a) Conditions indicates a) GO TO Step 3j3.

authorization of emergency radiation exposure limits should be considered b) Implement EPIP-5.06, Emergency Radiation Exposure Authorization

M,a.s7ss7210 NUMBER PROCEDURE TITLE REVISION Q 05 EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 21 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

33. BLOCKING AGENT:

a) On recommendation of a) GO TO Step 34.

Radiological Assess-ment Director, evaluate issuance of Radioiodide blocking agent to onsite personnel if following exist:

1) Projected onsite total absorbed dose equiva-lent I-131-GREATER THAN 3 Rem O 2) Actual onsite total absorbed dose equiv-alent I-131-GREATER THAN p Rem b) Direct Radiological Assessment Director to implement EPIP-5.07, Administration of Radioprotective Drugs
34. VERIFY EVENTS:

a) Review EPIP-1.01, Attach-ment 1, Emergency Action Levels THEN GO TO Step 34.b b) Insure additional b) Initiate station APs, EPs, events have NOT occurred or EPIPs to address new events.

AND O

Pd&. 97857210 p NUMBER PROCEDURE TITLE REVISION EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 22 of 24

- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED

34. (CONTINUED)

Notify Radiological Assess-ment Director.

AND Insure initiation of EPIP-2.01, Notification of State and Local Governments and EPIP-2.02, Notification of NRC.

c) Verify emergency conditions- c) GO TO Step 5_ to verify CHANGED recommendations.

1) IF condition - IMPROVED -

.C0 TO Step E

2) E condition - DEGRADED -

GO TO Step 5 for reeval-uation of recommendations

35. VERIFY EMERGENCY TERMINATION:

a) Verify EALs - NOT EXCEEDED a) IF EALs are still exceeded, GO TO Step 3 AND b) Verify plant conditions - b) Evaluate conditions and GO TO

' Step SAFE AND STABLE ,5_.

AND c) Onsite and offsite response c) Continue monitoring activi-personnel - NOT REQUIRED ties and GO TO Step M.

d) GO TO Step g to terminate O

No.97187210 NUMBER PROCEDURE TITLE REVISION

%) EPIP-1.05 RESPONSE TO GENERAL EMERGENCY PAGE 23 of 24

- STEP ACTION /EXPEs~TED RESPONSE RESPONSENOTOBTAINED

36. CHECK FOR RECLASSIFICATION:

a) Step M indicates event a) GO TO Step 5 of this in-severity - REDUCED struction. -

b) Reclassify event and GO TO Step E for procedure termination

37. TERMINATE EPIP-1.05:

a) Verify Recovery Manager concurrence IF LEOF

~

activated b) Close out

1) Initiate briefing of off-site authorities at EOF and by phone
2) Written summary initiated (due within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)

BY:

DATE:

TIME:

3) Termination completed BY i

DATE:

TIME:

b G

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no. stesnio NUMBER PROCEDURE TITLE REVISION EPIP-1.05 RESPONSE TO CENERAL EMERGENCY AGE 24 of 24

- STEP ACTIONMXPECTED RESPONSE RESPONSE NOTOBTAINED

37. (continued) c) GO TO EPIP-1.01, Emergency Manager Controlling Pro-cedure Step 5 d) Fe vard completad EPIP-1.05, forms and other applicable records to Secretary SNSOC
38. EMERGENCY TERMINATION:

a) Verify Recovery Manager concurrence IF LEOF

~~~

activated

~

b) Close-Out ,

1) Initiate briefing of ,

offeite authorities at LEOF and by phone

2) Initiate written summary to offsite authorities within 8, hours
3) COMPLETED BY:

DATE:

TIME:

) GO TO EPIP-1.01, Emergency Director Controlling Pro-cedure Step 8 d) Forward Completed EPIP-1.05, forms and other applicable I records to Secretary SNSOC i

END

Peo. 97887220

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NUMBER ATTACHMENT TITLE REVISION EPIP-1.05 05 J SM SECOR M p,gg A TTACHMENT 1 1 f1

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)

J NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.04 TRANSMITTAL OF PLANT STATUS AND PAGE CORE ASSESSMENT DATA (2 Attachments) 1 of 9 PURPOSE

1. To provide Plant, Radiological, and/or Emergency status for Station Emer-gency Manager and/or Recovery Manager.

USER Emergency Communicator OR Station Emergency Manager ENTRY CONDITIONS Any of the following:

1. Emergency classification of ALERT of higher declared; S
2. Directed by another EPIP; E
3. Directed by Station Emergency Manager.

REVISION RECORO REV. 00 PAGE(S): Entire Procedure DATE: JAN O g jgg REV. PAGE(S): DATE:

REV. PAGE(S): DATE:

REV. PAGE(S): DATE:

REV. PAGE(S): DATE:

REV. PAGE(S): DATE:

REV. PAGE(S): DATE:

APPROV R M ENDED APPROVED DA TE acu- .

TX M,,,, NNUccE,RS,,ErV c,a,R.,N S , ,,

s,D, f Q, ANo oPERariNa couuirreE

~

EPIP g

hb 97887210 NUMBER REVISION f% ) PROCEDURE TITLE

>U 00 EPIP-2.04 TRANSMITTAL OF PLANT STATUS AND ##

CORE ASSESSMENT DATA 2 of 9

- STEP ACTIONEXPECTED RESPONSE RESPONSE NOTOBTAINED

1. INITIATE PROCEDURE:

a) INITIATED BY:

TIME:

DATE:

2. OBTAIN " PLANT STATUS" FORM:

a) Attachment 1, Plant Status a) Obtain copy from procedure file form located at back of this procedure

[; . .

\s/ 3. RECORD PRIMARY SYSTEM DATA IF required, request data from IN MAIN CONTROL ROOM: Control Room a) Reactor Coolant System

1) Hot leg temp.
2) Cold leg temp.
3) Diff. Temp. calculated
4) RCS Pressure i 5) Pressurizer Level b) Refueling Water Storage Tank Level c) Reactor Coolant Pumps l

(A, B, C) status l

l d) Core Parameters

1) Core Exit Thermocouples (at least five)
2) Margin to Saturation l (subcooling) l 3) Source Range counts
4) Intermediate Range Amps
5) RVLIS v

4 N3.97887210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.04 TRANSMITTAL OF PLANT STATUS AND PAGE CORE ASSESSMENT DATA

. 3 of 9

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

3. RECORD PRIMARY SYSTEM DATA
  • E required, request data from IN MAIN CONTROL ROOM: (cont) Control Room e) Containment _
1) Temperature
2) Pressure
3) Sump Level '
4) Isolation Phase
5) Hydrogen concentration
4. RECORD SECONDARY SYSTEM DATA
  • E required, request data from IN CONTROL ROOM: Control Room

. a) Heat Sink:

1) Steam Le.el Generator -

A,B,C

2) Steam Generator Feed-water Flow
3) Condensate Storage. Tank Level
4) Aux. Feedwater - 3A, 3B, FW-P-2
5. RECORD ENGINEERED SAFEGUARDS
1) CHG/SI
2) LHSI
3) CS
4) OSRS
5) ISRS b) Emergency Bus (H, J) status c) Emergency Diesel Generator L/ - (1, 2, 3) status i

No.97857210 NUMBER PROCEDURE TITLE REVISION v 00 EPIP-1.04 TRANSMITTAL OF PLANT STATUS AND PAGE CORE ASSESSMENT DATA 4 of 9

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED j l

5. RECORD ENGINEEPS.D SAFEGUARDS
  • E required, request data from IN CONTROL ROOM: (continued) Control Room d) Reserve Station Service (D. E, F) status '
6. RECORD HIGH RANGE EFFLUENT RADIATION MONITORS DATA IN CONTROL ROOM:

a) Vent Vent (RM-VG-131-1, -131-2) b) Process Vent (RM-GW-130-1, -130-2)

,O , c) Main Steam -

d A (RM-RI-MS 124, -224)

B (RM-RI-MS-125. -225)

C (RM-RI-MS-126. -226)

7. RECORD REMARKS:

a) Obtain from Status Board a) Obtain from Station Emergency Manager

8. OBTAIN APPROVAL TO TRANSMIT DATA:

a) Present completed Attach-ment 1 to Station Emergency Manager b) Receive approval to transmit

9. RECORD TIME AND DATE " PLANT STATUS" FCRM SENT" a) Record at bottom of Attachment 1,

Net 97887230

~s. NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.04 TRANSMITTAL OF PLANT STATUS AND PAGE CORE ASSESSMENT DATA 5 of 9

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

10. TRANSMIT " PLANT STATUS" FORM TO RECOVERY MANAGER (LEOF):

a) Use IBM-PC, Attachment 2 a) IF PC NOT operable SR_

IF TSC NOT activated, use PBX phone

11. COMPLETE PLANT STATUS REQUIREMENT:

a) Inform Station Emergency

,T Manager that data sent

[O b) Provide copy to Emergency

. Administrative Director for distribution

12. OBTAIN " REPORT OF RADIOLOGICAL CONDITIONS" FORM:

a) Obtain most recent copy a) Obtain copy from procedure file EPIP-2.01, Attachment 2

13. RECORD REMARKS, IF APPLICABLE:

a) Obtain from Status Board a) Obtain from Station Emergency Manager

14. OBTAIN APPROVAL TO TRANSMIT DATA:

a) Show completed EPIP-2.01, Attachment 2 to Station Emergency Manager

\

b) Receive approval to transmit

Nk 97887210 NUMBER PROCEDURE TITLE REVISION V(~ 00 EPIP-2.04 TRANSM11"iAL OF PLANT STATUS AND PAGE CORE ASSESSMENT DATA 6 of 9

- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED

15. RECORD TIME AND DATE " RADIO-LOGICAL CONDITIONS" FORM SENT:

a) Record at bottom of EPIP-2.01, Attachment 2_

16. TRANSMIT " RADIOLOGICAL CONDITIONS" FORM TO RECOVERY MANAGER (LEOF):

a) Use IBM-PC, Attachment 2_ a) E PC NOT operable EE E TSC NOT activated, O _

use PBX phone

17. COMPLETE " RADIOLOGICAL CONDITIONS" REQUIREMENT:

a) Inform Station Emergency Manager that data sent b) Provide copy to Emergency Administrative Director for distribution

18. OBTAIN " REPORT OF EMERGENCY" FORM:

a) Obtain most recent copy a) Obtain copy from procedure file EPIP-2.01, Attachment 1

19. RECORD REMARKS, IF APPLICABLE:

a) Obtain from Status Board a) Obtain from Station Emergency Manager 3

g

NA 97887210 NUMBER PROCEDURE TITI.E REVISION O

00 EPIP-2.04 TRANSMITTAL OF PLANT STATUS AND PAGE CORE ASSESSMENT DATA 7 of 9

- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED

20. OBTAIN APPROVAL TO TRANSMIT DATA:

a) Show completed EPIP-2.01, Attachment 1 to Station Emergency Manager b) Receive approval to transmit

21. RECORD TIME AND DATE " REPORT OF EMERG3CY" FORM SENT:

a) Record at bottom of EPIP-2.01, Attachment 1

22. TRANSMIT " REPORT OF EMERGENCY" FORM TO RECOVERY MANAGER (LEOF):

a) Use IBM-PC, Attachment 2 a) IF PC NOT operable SR IF TSC NOT activated, use PBX phone

23. COMPLETE " REPORT OF EMERGENCY" -

REQUIREMENT:

a) Inform Station Emergency Manager that data sent b) Provide copy to Emergency Administrative Director for distribution

No,97887210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.04 TRANSMITTAL OF PLANT STATUS AND PAGE CORE ASSESSMENT DATA 8 of 9

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

24. PERFORM RELIEF AS REQUIRED:

a) g relieved, a) IF NOT, GO T0 step 25

1) Brief your relief on current status of emergency
2) Review last completed Attachment 1 AND EPIP-2.01, Attachment 2

_ AND EPIP-2.01, Attachment 1

3) Transfer this procedure and all completed attach-ments to relief b) Record relief:

Relieved by: _

Time:

l .

Date:

25. VERIFY EMERGENCY:

I a) IF NOT terminated, GO TO a) E terminated, GO TO step 22 step M O

No.97847210 NUMBER PROCEDURE TITLE REVISION

/m

() EPIP-2.04 TRANSMITTAL OF PLANT STATUS AND 00 PAGE t

CORE ASSESSMENT DATA 9 of 9

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 'b

26. DETERMINE NEED FOR FOLLOW-UP NOTIFICATION:

a) Status of any data on a) IF NOT changed, wait for request Attachment 1 - CHANGED, from LEOF GO T0 step 2 b) Status of any data on a) IF NOT changed, wait for request EPIP-2.01, Attachment 2_ - from LEOF CHANGED, GO TO step H c) Status of any data on a) IF NOT changed, wait for request EPIP-2.01, Attachment 1,- trom LEOF CHANGED, GO TO step g f%.

s 2h.

TERMINATE EPIP-2.04:

a) Completed by:

Time:

Date:

b) Forward completed EPIP-2.04 forms and other applicable documents to Station Emer-gency Manager END O

l Na.s7ss722o

, NUMBER A TTACHMENT TITLE REVISION O

(, EPIP-2.04 00 l

l A TTACHMENT PAGE .l l

1 1 of 1 l

PRIMARY SYSTEM Unit RZACIOR COOLANT SYSTEM (T = TEMPERATURE)

I - HOT *F T - COLD *F AT *F PRESSURE PSIG PRESSURIZER LEVEL  %

REFUELING WATER STORAGE TANK LEVEL  %

REACIOR C00LANI PUMP A: A. R. OOC B: A. R. 00C C: A. R, OOC CORE PARAMEIERS I CORE EXIT THERMOCOUPLE *F MARGIN TO SATURATION *F SOURCE RANGE COUNTS *F INTERMEDIATE RANGE AMPS *F RVLIS *F CONIAINMENT TEMP. 'F PRESS, PSIA SUMP LEVEL  %

CONT. ISOLATION PHASE I, II, III. HYDROGEN  %

SECONDARY SYSTEM STEAM GENERATOR LEVEL O

A  % B  % C  %

STEAM GENERATOR FIDW CONDENSATE STORAGE TANK LEVEL  %

AUX. FEED h*ER 3As A. R. 00C 3B: A. R, OOC FW-P-2: A. R. 00C ENGINEERED SAFEGUARDS CHG/SI At A. R. 00C B: A. R, OOC C: A. R OOC OSRS A: A. R. OOC B: A. R. 00C LHSI A A. R. 00C B: A. R. 00C ISRS A: A. R 00C B: A. R 00C CS At A. R. OOC B: A. R. 00C ELECIRICAL DISTRIBLTION EMERGENCY BUS H: RSS, DIESEL, DEAD, BACKFEED J: RSS, DIESL, DEAD, BACKFEED 3

EMERGENCY DIESEL GENERATOR (EDG)

1
A, R, OOC 2: A, R, OOC 3: A, R, OOC
RESERVE STATION SERVICE D
HOI DEAD E: HOT. DEAD F: HOT, DEAD HIGH RANGE EFFLUENT RAD MONITORS VENT VENI PROCESS VENT MAIN SIEAM A B C REMARKS Legend: CHG/SI - Charging /S.I. OSRS - Outside Recire. Spray RVLIS - Resetor Vessel Level Indication System ISRS - Inside Recire. Spray LHSI - Low Head S.I. RSS - Reserve Station Service CS - Containment Spray

, (A = Available, R = Running: 000 = Out of Conmission)

Preparer Time: Date:

(24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

N9.97887220 NUMBER A TTACHMENT TITLE REVISION l EPIP-2.04 00 A TTACHMENT PAGE IBM-PC USER INSTRUCTIONS 2 1 of 6

1. COMPUTER STARTUP
1. Call LEOF to notify them that IBM-PC system is ready for operation.
2. Call Richmond to notify them that the IBM-PC system is ready for operation.
3. Insert diskette face up into the "A" drive (left side) AND close disk drive door.
4. Energize IBM-PC by placing power switch (right rear of computer) in the "0N" position.
5. Energize monitor by turning top knob clockwise until a

" click" is hear AND the green light above the knob comes on.

. 6. Verify that program begins automatic startup (approximately A one to two minutes).

V II. COMMUNICATIONS VERIFICATION

1. Prompt message on screen (" Enter the appropriate station designator (S)urry or (N) orth Anna?_.") should be responded to by typing letter "S" and depressing ENTER key (the return /

" elbow" key).

2. Call the LEOF to inform them that a test form is being sent.
3. Send test form to LEOF by performing the following:
a. Depress F-10 key to obtain transmit menu.
b. Depress F-1 key to transmit test form to LEOF.

CAUTION: Do not proceed until the message " DATA WAS RECEIVED IN LEOF" appears on the screen OR the menu returns.

4. Call LEOF to verify receipt of test form.

A 5. Verify that modem is in the TALK mode and that RTS and DTR V lights are lit.

DOrilMFNT AITFRFn TO RFMOVF CONFinFNTIAl INFOD M ATIOM

~

No.97887220 NUMBER A TTACHMENT Tl!LE REVISION EPIP-2.04 00 A TTACHMENT PAGE IBM-PC USER INSTRUCTIONS 2 2 of 6 II. COMMUNICATIONS VERIFICATION (continued)

6. Using Modem telephone, dial (CERC support).
7. After a sustained tone is heard, push modem DATA button AND hang up telephone.
8. Verify that light below DATA button illuminates AND that green Sg lighc appears.
9. Depress F-10 key to display the " FUNCTION KEY TABLE" menu.

NOTE: The modem is now ready to transmit. If the DATA link is broken at any time, it must be re-established prior to the transmission of any data.

III. PROGRAM USAGE NOTE: Information for Plant Status panels is provided by the control room phone talker. Information for the Radiological Status panels is provided by the Radiological Assessment Director (except for meteorological data, which is provided by the control room phone talker). Information for the Emergency Status panels is provided by the Station Emergency Manager AND the Control Room phone talker.

NOTE: If there are any problems with the running of the program, call LEOF and request instructions or assistance.

1. If requested.by the Station Emergency Manager, turn on the Shintron Video Amplifier located on the floor inside the rear of the Emergency Procedure Coordinator's cabinet (which is in front of the Emergency Communicator's desk). Verify that wall-mounted screen has a display.
2. Verify that " Function Key Table" menu is displayed on the computer screen.
3. Depress the F-1 function key to display part one of the Plant Status panel.

O DOCUMENT ALTERED TO REMOVE CONFIDENTIAL INFORMATION

- , ,.-r, , -

Ng.97887220 e

NUMBER A TTACHMENT TITLE REVISION

( ELIP-2.04 00 A57ACNMENT EMERGENCY COMMUNICATOR FAGE IBM-PC USER INSTRUCTIONS 2 3 of 6 III. PROGRAM USAGE (continued)

4. Enter the appropriate data into the data blank and move the cursor to the next data blank by depressing ENTER key.

NOTE: See the Editing Quick Reference Page for an explanation of the edit keys and their usage.

Upon completion of information entry for this screen, depress the F-2 key to display part two of the 'lant Status panel.

6. Upon completion of information entry for this screen, depress i the F-3 key to display part three of the Plant Status panel.
7. To enter information on the Radiological Status Panel or the

_ . Emergency Status Panel, refer to the attachments and depress CI keys F4 - F9 as appropriate.

IV. TRANSMITTING DATA NOTE: Transmit data anytime a change is made to any panel, OR when request is made by emergency personnel.

I 1. Depress the F-10 key to obtain ALTERNATE FUNCTION KEY TABLE menu.

2. Depress the appropriate TRANSMIT function key to transmit the desired status panel.
3. Verify that " Transmitting Data" message appears on the upper left portion of computer screen.
4. Upon successful completion of the data transmittal, the " Data was received in Richmond" message AND/OR " Data.was received in LEOF" message (s) will appear on lower portion of the computer screen.

s_ ,

e , -. . , - . , - - - -- - , - - .

No.97887220 NUMBER A TTAC# MENT TITLE REVISION EPIP-2.04 00 A TTAC# MENT EMERGENCY COMMUNICATOR PAGE IBM-PC USER INSTRUCTIONS 2 4 of 6 I IV. TRANSMITTING DATA (continued)

NOTE: The message or messages that appear depends on the appropri-ate comeunication link being established. If both the LEOF and the CERC (Richmond) have been activated, do not proceed until both messages have been displayed.

5. Depress the F-10 function key to obtain the FUNCTION KEY TABLE.

NOTE: Make printed copies anytime you change information on any status panel, or as requested by SEM or directors.

_ V MAKING HARD COPIES FOR DISTRIBUTION IN TSC
1. Ensure first page of desired Status Panel on computer screen.
2. Align printer print head to point just barely above the perforated page. En50s: 20WER and ON LINE or SEL lights are lit and PAPER light is out.
3. At the computer, depress the " Shift" key and the PrtSc key simultaneously.
4. Verify that information displayed on the computer screen is printed.
5. Depress appropriate function key to display second page of desired Status Panel on computer screen.
6. Repeat steps 3 and 4 of Section V.
7. Depress appropriate function key to display third page of desired Status Panel on computer screen.
8. Repeat steps 3 and 4 of Section V.

O

. = . __

N4.97887220 e

NUMBER A TTACHMENT TITLE REVISION

(~ \ EPIP-2.04 00 EMERGENCY COMMUNICATOR ATTACNMENT PAGE ~I IBM-PC USER INSTRUCTIONS j 2 5 of 6 1 l

I i

l FUNCTION KEY TABLE Key i Function 1 1st Plant Status Panel 2 2nd Plant Status Panel 3 3rd Plant Status Panel 4 1st Radiological Status Panel 5 2nd Radiological Status Panel 6 3rd Radiological Status Panel 7 1st Emergency Status Panel 8 2nd Emergency Status Panel 9 3rd Emergency Status Panel 10 Go to Alternate Function Key Table f'N ALTERNATE FUNCTION KEY TABLE Key # Function 1 Transmits Plant Status Panel 2 Transmits Radiological Status Panel 3 Transmits Emergency Status Panel 10 Go to Function Key Table

NOTES
1. Use the FUNCTION KEY TABLE to enter information on the status panel pages.
2. Use the ALTERNATE FUNCTION KEY TABLE to transmit data to EOF or Richmond.
3. Use Function key F10 to shift between the data entry (FUNCTION KEY) table and the transmit (ALTERNATE FUNCTION KEY) table.
4. DO NOT DEPRESS FUNCTION KEYS IF THE RED DISC DRIVE LIGHT IS ON!
5. When in the data entry mode, you may change to another screen display with the cursor at any location on the screen by using the appropriate function key.

,__ _ , _ _ _ . ~ ,

@ 97887220 l

- 1 I

NUMBER A TTAC# MENT TITLE REVISION l EPIP-2.04 00 EMERGENCY COMMUNICATOR A TTAC# MENT PAGE IBM-PC USER INSTRUCTIONS 2 6 of 6 i

Editing Key Quick Reference Page

  • To advance forward through the fields, press the T.NTER key (the return elbow key).

Y ,

  • To move backward through the fields, press the TAB key.

b

-+i

  • To move the cursor to the right while preserving data, press the CONTROL key and the CURSOR RIGHT key.

6 CTRL +

4

  • To move the cursor to the left while preservirs data, press the CONTROL key and the CURSOR LEFT key.

4 CTRL +  %

  • To erase the rest of the line from the cursor on, press the CONTROL key and the END key.

CTRL + END

  • To delete one character and insert a blank space at the right, press

, the DELETE key.

i

  • DEL
  • To insert a blank and delete the last character, press the INSERT key.

l 0 t l INS t

  • To backspace and destroy the data as the cursor moves, press the l

BACKSPACE key.

l l

l

No.97887230 F..v. 8 "**

VIRGINI A POWER SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE G

V NUMBER PROCEDURE TITLE REVISION l

00 EPIP-2.05 TRANSMITTAL OF CORE DAMAGE DATA PAGE (1 ATTACHMENT) 1 of 6

?URPOSE

1. :To provide core assessment data for Reactor Ana1ysis element of the Techni-cal Support Group.

USER Technical Support Team OR Emergency Technical Director ENTRYCONDITIONS ,

Any of the following:

O 1. Emer$ enc 7 c1assiricatien er i1ert or hi Sher dec1aredi a

2. Directed by another EPIP; gR
3. Directed by Station Emergency Manager.

l DOCUMENT ALTERED TO REMOVE CONFIDENTIAL INFORMATION REVISION RECORD REV. 00 PAGE(S): Entire Procedure DATE: JAN 0 21986 REV. PAGE(S): DATE:

REV. PAGE(S): DATE: l REV. PAGE(S): DATE:

REV. PAGE(S): DATE:

REV. PAGE(S): DATE:

REV. PAGE(S): DATE:

APPRO RECO MENDED APPROVE 0ff y_/ DA TE QC REVIEW Q f5 CHAIRMAN STA TION NUCLEAR SAFETY g Qg AND OPERA TING COMMITTEE JAN 2 1986 i EPIPA CI

f43,97857210 s

NUMBER PROCEDURE TITLE REVISION EPIP-2.05 TRANSMITTAL OF CORE DAMAGE DATA PAGE 2 of 6

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED

1. INITIATE PROCEDURE:

a) Initiated by:

Time:

Date:

2. OBTAIN " CORE DAMAGE ASSESSMENT" FORM:

4 a) Attachment 1, Core Damage a) Obtain copy from procedure file Assessment

> eer^

  • 8 8-CD RADIONUCLIDE DATA:

a) Obtain from Status Board a) Obtain'from Radiological Assess-ment Director b) Sample location c) y liquid sample ONLY, b) IF NOT, proceed to Step h obtain Temperature at sample location d) IF airborne sample ONLY, c) IF NOT, proceed to Step M obtain the following at the time sample taken:

1) Containment temp.

i 2) Containment press.

3) Sample temperature
4) Sample pressure l

i i

O l

l

Nb.e7ss :so o

NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.05 TRANSMITTAL OF CORE DAMAGE DATA PAGE 3 of o

- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED

3. OBTAIN P.A.S.S.

RADIONUCLIDE DATA: [ continued) e) Record Water inventory IF, required, request data from levels data in Control Control Room Room

1) RVLIS
2) RWST
3) PRT
4) Pressurizer
5) Sump
6) Ste c Generators Wide Range - A, B, C
7) Steam Generators Narrow Range - A, B, C
4. RECORD AUXILIARY INDICATORS E required, request data from DATA IN CONTROL ROOM Control Ro'om a) Containment Radiation Monitor (RMS-162, -262) b) Containment Hydrogen Concentration (RMS-160, -260) c) Core Exit Thermocouples (at least five)
5. RECORD REMARKS, IF APPLICABLE:

a) Obtain from Status Board a) Obtain from Station Emergency Manager O

Ho.97887210 NUMBER PROCEDURE TITLE REVISION EPIP-2.05 TRANShITTAL OF CORE DAMAGE DATA -

PAGE 4 of 6 l

- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

6. OBTAIN APPROVAL TO TRANSMIT DATA:

a) Show completed Attachment 2 to Station Emergency Manager b) Receive approval to transmit

7. RECORD TIME AND DATE " CORE ,

ASSESSMENT" FORM SENT:

a) Record at top of form

(~S 8. TRANSMIT " CORE ASSESSMENT" FORM

\

TO CORPORATE EMERGENCY RESPONSE TECHNICAL MANAGER a) Use station phone to call a) IF NOT operable, use available emergency phone

9. COMPLETE CORE ASSESSMENT REQUIREMENT:

a) Inform Station Emergency Manager data transmitted b) Provide copy to Emergency Administrative Director for distribution O

DOCUMENT ALTERED TO REMOVE CONFIDENTIAL INFORMATION L

~

_ . - _ - l ._._ f . . _ _ _ . _ .

fe.97887210 NUMBER PROCEDURE TITLE REVISION C\

EPIP-2.05 TRANSMITTAL OF CORE DAMAGE DATA 1 PAGE 5 of 6

- STEP ACTION / EXPECTED RESPONSE RESPONSENOT OBTAINED l

10. PERFORM RELIEF AS REQUIRED:

a) E relieved, a) IF NOT, GO TO Step H

1) Brief your relief on current status of emergency
2) Review last Attachment I completed
3) Transfer this proce-dure and all completed attachments to relief

. b) Record relief:

Relieved by:

Time:

Date:

11. VERIFY EMERGENCY NOT TERMINATED:

a) IF NOT terminated, a) E terminated, GO TO Step g GO TO Step M l

12. DETERMINE NEED FOR FOLLOW-UP NOTIFICATION:

a) Status of any information a) E NOT changed, wait until on Attachment 1 - CHANGED request is made by Corporate Emergency Response Technical GO TO Step 2 Manager O 9

- - . . . - . - - . -.n,- - - - . - ,-. ----- .,-

,n..

ND 97887210 NUMBER PROCEDURE TITLE REVISION 00 EPIP-2.05 TRANSMITTAL OF CORE DAMAGE DATA PAGE 6 of 6

- STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED

13. TERMINATE EPIP-2.05:

a) Completed by:

Time:

Date:

b) Forward completed EPIP-2.05 forms and other applicable documents to Emergency Technical Director.

9

  • e l

END 1

0

Ng.C7ss7220 NUMBER A TTACHMENT TITLE REVISION 0

(')

1 EPIP-2.05 A TTACHMENT CORE DAMAGE ASSESSMENT DATA SHEET PAGE 00 1 1 of 1 Unit Forward to Corporate Emergency Response Technical Manager, Corporate EOF PASS RADIONUCLIDE DATA: Time of Sample Nuclide SA Nuclide SA Nuclide SA Notes: Give specific activities (SA) in micro-Curies /ml.

Give individual iodine SA's and not dose equivalent I-131.

PASS Sample Location: RCS: Hot Leg Cold Leg Loop

'RHR: before or after heater exchanger Containment Airborne Containment Sump Liquid samples only:

Temperature (des. F) at sampling location Airborne samples only:

Containment temperature (deg. F) at time of sampling Containment pressure (psia) at time of sampling

, Sample temperature (deg. F) at time of measurement Sample pressure (psia) at time of measurement

(* Water inventory levels (in "% of span" unless otherwise noted):

RVLIS: wide range narrow range dynamic range RWST PRI Pressurizer Sump (ft)

Steam generators (wide range): A B C Steam generators (narrow range): A B C AUXILIARY INDICATIONS:

CONTAINMENT RADIATION HONITOR: reading (R/hr)

(manipulator crane) time of reading CONTAINMENT HYDROCEN CONCENTRATION: reading (volume is Hydrogen) recombiner status on off time of reading CORE EXII THERMOCOUPLE READINGS (deg. F): time of readings A08 E0's C01 H11 K08 M11 B05 E10 G02 H13 K11 N04 B10 E12 G06 H15 LO6 N06 C08 E14 G08 J02 LO8 N08 C12 F03 G15 J10 L12 N10 D03 F05 H03 J12 L14 P07 DOS F09 H05 K03 H03 P08 E04 Fil H08 K05 M09 R07 E07 F13 H09 REMARKS:

O Preparer: Time Date:

(24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

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