ML20050D490

From kanterella
Jump to navigation Jump to search
Public Version of Revised Emergency Plan Procedures, Consisting of Revision 4 to Procedures Book II Re Initiating Conditions & Revision 3 to Procedure IP-1058 Re Earthquake Emergency.Revised Index Encl
ML20050D490
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 03/16/1982
From: Brons J
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML093450361 List:
References
PROC-820316-01, NUDOCS 8204120256
Download: ML20050D490 (11)


Text

. .

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN POINT NO. 3 NUCLEAR POWER PLANT P. C. BOX 215 SUCH AN AN. N. Y.1 C511 TEt.E PM C Pe ts 914-739 8200 8

E.M ICY PLAN PRCCEOUPIS l

Book II REV. 4 PROCEDURE NO. IP-TITI.E: Book II:

Initiating Condf.tions NTE i NOTE: only revised

/ Alert pages have been Site Area replaced.

General (IC-11,16 NUE-1,2) e e

O r

l WRI'ITEN BY: / .. - //fM

. _d(HW-PORC REVIEW /'/h, /,., DATE M/'t 4 2.-

APPROVED BY: ,- h ~ DATE jft/,f72.,

O 9

F204120256 820329 PDR ADOCK 05000286 F PDR (

- - it'i i

3

-m eli

$$E c -1 ul*g.

twl g 23jg n  :=>=

ft #13:

I

, E IW I . 3.

asE 8 7 7 7 l 5 73 78 TR 71 5

"bb' "II' "I' I "II' b$

a u! US US MS a

i A

v 8

=

E

?' 4

f. 5 r

A c j  :

l.* 3 e

i a

)m I" 3

a a 5

1 i  :

i  :

I

= $ .

s-  !-  :

r  :

r .:

r.

r 5 e

: 2

= =

al

1 l!.!![l 3 g

} .I .I .i B 4 4 4 4 1 1 -

e .

! - 8I  ; Ib l 'yI l, l I.1 1 2 : -

2..=a s -

s 3:t -

y3 - q 3.:::.:: -

s

3-

-3 ;r :s 4 1 a3 -218 5::2 .

33 3- 3 -

r . :-

4 :s .gs ,

r- - s a: . 2.- - -

8 el4.- 3 g :3: e r 4 313=:

a v=

l.2 i l

: : .g-  :.14;- ;j3:1;1: L

.1 j e 1-x.

.1 l ;. ; q-- 1:1.s 3:--

, 't 2s

g1:, } 4 -: :

int:2:.:3 -

- al>l 11: s..::::=. :25. 2 1at*f]1;r.

1

is3 1 1 -

1 g 5 ~4 . 3 v; 5g- ;2 3 3 ~.

s<

I

't a

, .52-3I' 11

.g 3:5}] u 12jd]3..1~-

ey -mu 8 *:32 3gg 3 13 *  !? 27 m 4:,01 d

-2842 4 14 id4 214 i J 41 1  ; a 2 2 a

~

b, .

e

'C-il l

  1. 8 =

4

)

TA312 4-1 INSTRATING ODEDITIONS AND EMEleFABeCT ACTE 000 ISVER.S FOSSISLE IIIDICATICIe8 peWEssalCE P1Jue? I'IEFTtITIVE ACTEOet IMITI ATIser*. CTjesugTIOteS TO OPEMA10stS t3eEseGENCT CIASSIFICATIOes see-DCEseCY PelOCEputtE ltEC009eENDATIOstS E8 8. StruaITY

1. Secusity threat. attempte.1 entry or s. Same me initiating conditions blification of thiumeal' Event PEP-ILPC-2 atteng.ted saletage.
b. Bomb threate specifically thseating the 34eysical safety of the Indian Point Station which result in the actual discovery of a tw=de or which requise the use of offeite assistance.
2. Ongoing secusity g romise a. Same se initiating conditions Emergency Alert PEP-sePC-2
3. security thseat involving the teentment a. Same ao lattiating conditions

^

Sits Aree poorgency PEP-serC-2 loss of physical cuntset of the plant.

4. less of phyelcal matrol of the plant. a. Same as initiating conditione Generen h agency REP-prC-2 This may cseate ethes initiating conditions which may marrant peo-tactive action I I eo enseadat ions .

[I F-*

G I

e

%\.

I So

~

f a

4 4

e

l NOTIFICATION OF UNUSUAL EVENT CLASSIFICATION Unusual Events are situations in progress or ones which have occurred which indicate a potential degradation of the level of safety of the

plant. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occur. In this classification, no alteration of the operating status of the plant is anticipated but response may involve support from members of the plant staff and/or local services.

The Shift Supervisor or Senior Reactor Operator will declare an Unusual Event when any of the initiating conditions listed below exist, or at any time in his judgement plant status warrents such a 1

declaration.

I Initiating Conditions for Notification of an Unusual Event

1. Emergency Core Cooling System (ECCS) initiated and discharged to vessel, with the respect to the following bonafide emergencies:

i l  ? a) loss of reactor coolant to containment r*

b) exceeding primary / secondary, leak rate technical specification l

t c) steam break upstream of the main steam line isolation valves 4

- or feedwater break downstream of check valve d) main steam break downstream of the main steam line isolation valves -

3

2. a) Instantanious radiological effluent technical specification limits exceeded.

b) Accidental release of waste liquid in excess of technical

~

l specification limits.

3. a) Fuel damage indication from RCS activity samples in excess of technical specifications (e.g. chemist sample or failed fuel monitor reading) b) High coolant activity sample (e.g. exceeding) coolant technical specifications for iodine spike.
4. RCS temperature and/or pressure exceedings technical specification limits of the technical specifications 'o r RCS pressure 2735 psig.
5. Exceeding RCS leak rate technical specification of 10 gpa 4
6. Failure of safety or relief valve in a safety related system to close following reduction to applicable pressure.
7. Loss of offsite power or loss of onsite AC power capability e

- -~ ._

NUE-1 L

8. Loss of containment integrity requiring shutdown by technical specifications.
9. Loss of engineered safety feature or fire protection system function requiring shutdown by technical specifications.
10. Fire within the plant not affecting safety systems that lasts greater than 10 minutes.
11. Rod ejection
12. Rapid depressurization of PWR secondary side.
13. Indications or alarms on process or effluent parameters not functional in control room to an extent requiring plant shutdown or other significant loss of assessment or communication ability.
14. Security threat, attempted entry or attempted sabotage. (Bomb threats specifically threatening the physical safety of the Indian Point Station which result in the actual discovery of a bomb or which require use of offsite assistance are included in this classification).
15. Natural phenomenon, beyond usual levels, being experienced or projected (e.g. earthquake detected on station seismic instrumentation, hurricane, tornado, or flood) 3
16. Significant hazzards being experienced' or projected onsite or in close proximity to the site (e.g. aircraft crash, derailment of train onsite, near or onsite toxic or flamable gas release,near or onsite explosion, turbine rotating component failure causing rapid plant shutdown)
17. Other plant conditions exist that warrent increased awareness ~on the part of NRC, State and Local offsite authorities or require plant shutdown under Appendix A technical specification require-ments or involve other than controlled shutdown or Trip.
18. Transportation of a radiologically contaminated injured-individual from the site to an offsite hospital NUE-2 L

1 l

EMERGENCY PLAN PROCEDURES INDEX REV. 11 Procedure # Procedure Title Rev. #

IP-1001 Discussion of Determination of the Magnitude of Release 2 IP-1002 Determination of the Magnitude Release 3 IP-1003 Obtaining Meteorological Data , 2 IP-1004 Midas Computer System, Dose Assessment Models 1 IP-1005 Planned Discharge of Containment Atmosphere During Accident Conditions 2 Environmental Monitoring IP-1010 In-Plant / Site Perimeter Survey 2 IP-1011 Offsite Monitoring Team 2 IP-1015 Airborne Iodine-131 Determination using SAM-2/RD-22 or RM-14/HP-210 2 IP-1017 Recommendation of Protective Actions for Offsite Population 2 IP-1018- Post Accident Environmental Sampling and Counting 1 Personnel Injurv IP-1021 Radiological Medical Emergency (Containment Injured Individual) 4 IP-1022 Transport of Contaminated Injured Personnel Between ,

Unit 3 and 1 0 Damage Assessment ,

IP-1025 Repair and Corrective Action Teams 2 IP-1027 Emergency Personnel Exposure 1 Notification and Communication IP-1030 Emergency Notification and Communications and Staffing 5 IP-1034 Notification and Recommendation to U.S.C.G. and Rail Roads 2 IP-1038 Use of the Emergency Communications Systems 2 (Initial Notification Fact Sheet, County Hot Line & NAWAS) l Procedures Index i Page 1 of 2 i

l ll, i

l i

EMERGENCY PTAN PROCEDURES INDEX REV.11. (PAGE 2)

Procedure # Procedure Title Rev. #

Emergency Operation Facilities IP-1040 Habitability for the Emergency Facilities 3 IP-1041 Personnel Monitoring Devices for EOF, TSC and OSC Personnel 3 IP-1045 Technical Support Center 3 IP-1047 Operations Support Center 4 Accountability and Evacuation IP-1050 Accountability 3 IP-1053 Evacuation of Site 1 IP-1054 Search and Rescue Teams 1 Non-Radiological Emergencies IP-1055 Fire Emergency 1 IP-1056 Directing Fire Fighting Personnel in Controlled Area 1 IP-1057 Tornado (Hurricane) Emergency 0 IP-1058 Earthquake 3 l IP-1059 Air Raid Emergency 0 HP Release Surveys and Decontamination IP-3060 Personnel Radiological Check and Decontamination 2 IP-1063 Vehicle Radiological Check and Decontamination 2 IP-1065 Use of SAM-2/RD-22 to Determine Thyroid Burdens 1 Emergency Equipment and Maintenance IP-1070 ,

Periodic Check of Emergency Preparedness Equipment 4 IP-1075 Periodic Check of Indian Point Emergency Communication Equipment 2 IP-1076 Beepers 3 IP-1079 Issuance and Use of Radiological Equipment Stored in the Command Guard House 1 Exercises, Drills and Training IP-1080 Conduct of Emergency Drills 2 IP-1085 Emergency Response Training 1 l

l Procedures Index Page 1 of 2 l

POWER AUTHORITY OF THE STATE OF NEW YORK INDIAN PolNT NO. 3 NUCLEAR POWER PLANT P. C. SCX 215 SUCH AN AN. N. Y.10511 I

TatsPMo N Cs 914 739W8200 l

EMERGENCY PIXi PRCCIOURES PRCCEDURE NO. IP- 1058 REV. 3 TITLE: EARTHQUA.E EMERGENCY e

e

/

wa m En _ J - --

REVIE1 BY:

PORC REVIEW ~N ,

. 4[.~ DATE I m./tL APPRCVED BY: DATEM/6f0ft.,

t

! EFFECTIVE CAq 3-t(,91 4

IP-1058 EARTHQUAKE EMERGENCY l 1.0 INTENT & DISCUSSION This procedure highlights the actions which should be followed in the event of an earthquake near or at the Indian Point site.

1. If the earthquake is felt at the site or recorded by station seismic equipment it shall be reported as a Notification of Unusual Event.
2. If the earthquake is within the range of the microseismic monitoring network or reported to us by the public sector, a courtesv notification should be made to offsite authorities.
3. Plant personnel actions are only taken when actual seismic event is experienced at the site.

Emergency Procedure PEP-S-1, Seismic Monitoring Equipment Actuation specifies minimum assessment and responsive action requirements in the event of a seismic monitoring equipment actuation. i l

l It is not the intent of this procedure to substitute for the Radiological Emergency Procedures if the consequences of an earthquake create a radio-logical hazard. Applicable procedures for that type of radiological emergency should be followed in addition to those contained in this procedure.

2.0 ASSESSMENT EQUIPMENT

a. Unit 3 is equipped with a seismic monitoring system that records vibrations caused by strong local earthquakes or similar events. Use of the data received from the system enables operating personnel to determine what course of action to take following an alarm or earthquake.

Briefly, the system consists of two SMA-2 Strong Motion Accelerographs located on the 46 foot and 100 foot elevations in the Vapor Containment, three Peak. Shock Recorders located on the 46 foot elevation and Peak Recording Accelerographs installed on #31 RCP, #31 SG and the Pressurizer.

The Unit 3 Control Room is equipped with the appropriate alarm panel and recording devices.

b. In addition to the installed monitoring system, the National Warning System (NAWAS) telephone installation in the Unit 3 Con' trol Room can also provide earthquake warning information and verifications.
c. If the earthquake is not strong enough to record on site monitoring equipment, the Control Room should be notified by Unit 2 Control Room, NAWAS, Woodward Clyde or another source.as to the magnitude and location of the event.

3 1 of 2 I

. a 3.0 PROCEDURE 3.1 If the earthquake is strong enough to be recorded on seismic monitoring equipment:

a. See PEP-S-1, Seismic Monitoring Equipment Actuation
b. Make appropriate Emergency plan notifications as per IP-1030
c. Assure Con Edison Unit 2 is notified of the magnitude as recorded on IP-3 equipment.

3.2 If the earthquake is experienced in the general area, but not strong enough to record on site monitoring equipment:

a. The Control Room would be notified via the Seismic Consultant (Woodward Clyde), Unit 2 Control Room, NAWAS or some other source.
b. Confirm the notification of an earthquake event by calling Woodward Clyde or the Unit 2 Control Room if the message came from a source other than them.
c. If confirmed, make courtesy notifications to offsite authorities.

(NOTE: This is a courtesy notification for information only, it is not a Notification of an Unusual Event, however, offsite authorities contacted are the same individuals as an NUE would be reported to).

4.0 DISCUSSION OF THE MICROSEISMIC MONITORING NETWORK Indian Point seismic consultants Woodward Clyde, have established within a 15 mile radius surrounding Indian Point a microseismic conitoring network. This networks consist of approximately 15 stations with seismic monitoring instrumentation which transmit data to a central location at their offices. Daily interrogation of this data is accomplished.

The scale used for the Indian Point microseismic network is the Coda scale. It is seismic scale specific to the Northeastern United States.

The Coda range is from 1.5 to 4.5 where 4.5 on the Coda scale is approximately equal to 4.5 on the Richter Scale. A 4.5 reading would be able to be felt by most people but is non-destructive.

l t

l 2 of 2 l

l